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Forward AllianceProducts, Services and Solutions

AREVA Initiative for Nuclear Power Plant Long-Term Operation

As carbon and greenhouse gas reduction programs are launched across the globe, utilities need to keep clean installed baseload energy sources online.

With a large majority of reactors over 25 years old and only 45 units connected to the grid between 2000 and 2011 (OECD), it is key to maintain a high level of existing nuclear power plants in operation as a complement to intermittent wind and solar energy on the grid.

Depending on local regulations, the Plant Life Extension process can be implemented though License Renewal, Periodic Safety Reviews and/or Long-Term Operation (LTO) projects.

To support nuclear utilities in managing such projects, AREVA has launched the Forward Alliance Initiative, proposing a catalog of the most advanced and efficient products, services and solutions.

The catalog is structured according to IAEA recommendations for LTO and provides the AREVA response to the different phases of the process, as well as integrated solutions for a number of systems and equipment. It contains three main parts:

Safe used fuel management strategy is also presented as are the knowledge and com-petencies aspects of life extension.

The second part proposes an integrated approach by major NPP component, focusing on Aging Management Reviews and implementation.

The third part gives a detailed description of AREVA tools, products and services available to optimize the overall costs of implementing a safe LTO project.

Based on solid experience in supporting utilities for the operation of over 360 reactors, the catalog consolidates AREVA state-of-the-art know-how, practices, products and services, as well as recommendations for optimizing CAPEX utilization across the LTO project.

Catalog Introduction

AREVA Forward Alliance

The fi rst part describes AREVA services related to the major phases of the LTO process

Feasibility Scoping Screening ImplementationAMR & TLAA

Road-MapPlant Programs

CollectionQuestionnaires

Investment study

Experience in IAEA

methodology implementationSafety Analysis

Experience in AMR for all major

componentsExisting Models

for TLAA

COMSY toolExpertise onDegradation

Experience in IAEA

methodologyimplementation

Aging Management

Program optimization

Monitoring tools & Services of ISI Repair and Replacement

Table of Contents – June 2013

Integrated Plant Assessment• Preparatory Study for LTO• Scoping and Screening for Aging Management Review• Aging Management Review• Used Fuel Management Scoping Study• Long-Term Solutions for Competences Management• AREVA US Experience: From License Renewal to Beyond 60

Aging Management by ComponentReactor Pressure Vessel (RPV)• RPV Inspections• RPV Integrity Assessment • RPV Surveillance Program• Measures for Reducing RPV Irradiation Fluence• Aging Management Strategies for Alloy 600

Internals• Integrated RPV Internals Assessment• RPV Baffle Bolts and Barrel Bolts Assessment• RPV Control Rod Guide Assembly (CRGA) Assessment

Pressurizer (PZR)• PZR Aging Management Review• PZR Repair & Replacement

Steam Generator• Replacement Steam Generator

Reactor Coolant Pump (RCP)• Revamping of RCP Internals• RCP Stator Replacement

Control Rod Drive Mechanisms (CRDM)• Upgraded CRDM

Concrete Aging• Concrete and Civil Works Aging Management Reviews

Instrumentation & Control• Diversified Non-Computerized I&C Solution• I&C Systems Upgrade for LTO• Based Modular Safety I&C Modernization

Supporting Products & Solutions• Fatigue Monitoring System – FAMOSi • Integrated Procurement Solutions

Version 1 - Status June 2013

• Preparatory Study for Long-Term Operation (LTO)• Scoping and Screening for Aging Management Review • Aging Management Review• Used Fuel Management Scoping Study• Long-term Solutions for Competences Management• AREVA US Experience: From License Renewal to Beyond 60

Integrated Plant Assessment


Preparatory Study for Long-Term Operation (LTO)

Assessing the feasibility of long-term operation

of the NPP to support investors’ decisions

The challenge

The decision to pursue long-term operation is based upon an evaluation that includes an eco-nomic and a technical assessment of the physical condition of the NPP, particularly identifi cations of enhancements or modifi cations that may be nec-essary.

This assessment should cover both the safety aspects required by the safety authorities and the future performance of the plant required to ensure the long-term profi tability of the asset.

The solution

Using its manufacturer’s expertise, AREVA devel-oped a structured preparatory analysis aligned with IAEA’s long-term operation feasibility requirements. This simplifi ed, short-time implementation approach helps identify plant-wide preventive measures to enhance the current technical condition of the plant and recommend time frames for implementation. The assessment can also include a preliminary evaluation of key cost elements to support invest-ment decisions. In total, it provides the utility with the road map to long-term operation.

By combining the experience of both manufactur-ing and site experts from the utility, it is possible to evaluate optimally the current state of an NPP. The preparatory LTO study also provides the basis for optimizing the plant programs required to manage the aging of the components.

Key features

A structured approach

• Preparation of plant-specifi c questionnaire

• Performance of interviews between senior plant experts and AREVA

• Performance of site walk downs

• Evaluation of plant experience,

• Preparation of a roadmap to LTO considering regulator requirements

• Joint review and fi nalization of implementation road map, budget estimate and time schedule for LTO

Main topics covered

• Mechanical

• Electrical

• I&C

• Civil / Structural disciplines

Working together. A joint assessment of utility and AREVA experts

Your benefi ts at a glance

• Elaboration of a reliable roadmap to LTO with fi rst level technical and fi nancial evaluation

• A common vision shared between the operator’s and the manufacturer’s experts

• AREVA’s experience in aging management and license renewals in many plants with diff erent regulators

• A split of assessment works between utility and manufacturer optimized depending on the technologies and resources of the utility.

Preparatory Study for Long-Term Operation (LTO)

AREVA References:

• Brokdorf

• Borssele

• Brunsbüttel

• Emsland

• Grafenrheinfeld

• Isar 1

• Isar 2

• Krümmel

• Unterweser

• Grohnde

• Angra 2

Expertise:

• Experts on the fi eld of materials, mechanical equipment, manufacturing, piping, electrical systems, cables, civil structures

• AREVA Laboratory dedicated to material aging, corrosion and qualifi cation of equipment

The statements contained in this document are for information purpose only and shall under no circumstances be considered as a binding off er or an off er to contract. In no event this document and any information included herein shall be construed as providing any warranties or performance guarantees either express or implied, including without limitation warranties of merchantability and fi tness for a particular purpose. Subject to any applicable law, AREVA and any AREVA group companies disclaim all responsibility in case of error or omission and assume no responsibility to update any statements contained herein.

F-001-V1-13-FA-ENGPB

LTO

40 60 Year0

Scoping and Screening for Aging Management Review

The fi rst step towards long-term operation

or license renewal

The challenge

The Aging management review is an important step within the frame of license renewal and long-term operation. However, among the thousands of Sys-tems, Structures & Components (SSC) important to safety (typically 30. 000 SSCs), only a part of them are subject to aging degradation.

It is therefore necessary to select effi ciently those SSCs that will require a detailed assessment. This selection is customized depending on technologies, safety authorities requirements and specifi c utilities expectations.

The solution

In line with IAEA recommendations, AREVA devel-oped a large experience in diff erent countries and with diff erent safety authorities to optimize the selec-tion of relevant SSCs.

This task is supported by AREVA expertise in the fi eld of nuclear safety engineering.The implementation of an Aging Management Program concerns passive, long-lived SSCs while active SSCs are covered by the periodic mainte-nance programs.

Due to the complexity of this labor intensive pro-cess, this systematic activity can be effi ciently sup-ported by a dedicated software tool (COMSY).

Key features:

Scoping

• Selection of the systems that are important to safety

• Integration of national regulations or specifi c requirements by the utilities.

• Safety experts judgment

Screening

• Detailed Identifi cation of SSCs important to safety on commodity group level and categorization into Aging Management Groups

• Collection of aging-relevant parameters for in-scope SSCs

• Main SSCs subject to evaluation

– Reactor vessel

– RCP pressure boundary

– Steam generator, pressurizer

– Pipes, pump casings, valve bodies

– Electric cables, cable trays, cabinet

– Heat exchangers, ventilation ducts

– Containment and containment liner

– Other SSCs


Typical classifi cation of SSCs

Scoping & Screening

Aging Management Review of SSCs in Scope

Mechanicalclass 1 (A)components(e.g. RPV, MCL,MCP, etc.)

Mechanicalnon-class 1 (B)components(e.g. valves,piping, etc.)

Electrical(and I&C)components(e.g. cables,buses, etc.)

Structuralcomponents(e.g. buildings,supports, etc.)


• Systematic and optimized selection of key SSCs that should be subject to aging analysis

• Safety experts support

• Experience with diff erent safety authorities worldwide

• Highly eff ective process using AREVA COMSY tool (shared methodology, structured screening, effi cient collection of data)

• Optimal work-split between the customer and AREVA

Scoping and Screening for Aging Management Review


AREVA References:

Europe:

• Borssele

• Isar 1

• Isar 2

USA:

• Scoping and screening in view of license renewal

• Calvert Cliff s, HB Robinson, Oconee, Mc Guire, Catawba, Columbia, Susquehanna, VC Summer

IAEA diagram for scope setting


All plant SSCs(identify applicable information sources,process the SCCs through each part).

Is the SSCimportant to safety?

Yes No

Yes

Yes

No

No

Is the SC replaced or

refurbished on a specifi ed time

period?

SC subject to LTOevaluation

Not subject to LTO evaluation.

Could failure of SC not

important to safety impact a safety

function?

2

1 3

Aging Management Review

The detailed demonstration that the effects of

aging degradation are adequately managed

The challenge

In the frame of preparation for lifetime extension or license renewal, all the systems, structures and components (SSCs) selected through the scop-ing and screening process should be subject to long-term operative (LTO) evaluation. Based on the current status of the plant and the multiple aging eff ects, the assessment should demonstrate that all the eff ects of aging degradation are adequately managed.

The solution

Based on the expertise developed in aging deg-radation mechanism through the years combined with its manufacturer’s knowledge of the nuclear plants, AREVA supported many customers in their aging management reviews.

The review demonstrates that the handling of aging mechanisms is compatible with the remaining ex-tended life of the plant. In case aging requirements are not covered, it identifi es additional inspection methods, adaptation of maintenance programs or components replacements that may be required. Costs for managing aging are optimized.

The COMSY tool effi ciently supports the system-atic assessment of the many components subject to LTO. Sophisticated degradation assessment functions that comply with the international state of the knowledge on corrosion and degradation mechanisms for mechanical components, electrical equipment and I&C components are embedded in the software. The systematic collection of data and automatic computing of degradation rate and remaining life allows experts to focus on high-value activities.

Key features

• Systematic assessment of relevant aging mechanisms for all relevant SSCs:

– Mechanical

– Thermal

– Chemical

• Identifi cation of SSCs that require mitigation measures

• Review and adjustment of maintenance and inspection programs

• Detailed Time Limited Aging Analysis for major components

– Vessel, vessel head, internals

– Pressurizer, steam generator

• Degradation assessment included in the COMSY tool

• Systematic and structured review supporting team alignment


Typical degradation mechanisms

General corrosion

• uniform corrosion• shallow pitting

Microbiologi-cal corrosion

• MIC

Localized corrosion

• pitting

• crevice corrosion

Stress corro-sion cracking

• IGSCC• TGSCC• Ni-SCC

Corrosion fatigue

• strain induced corrosion• crackin

Fatigue • thermal transient fatigue• thermal cycling fatigue• thermal stratifi cation fatigue

Flow- in-duced corro-sion

• FAC-fl ow-accelerated corrosion• cavitation erosion• liquid droplet impingement (LDI)• solid particle erosion

Tribology • abrasion and wear


• Accurate evaluation of the aging eff ects through state-of-the-art models

• Optimized mitigation solutions to cover the aging requirements with maintenance and inspection programs

• Implementation eff ort reduced through the use of COMSY database

• 30 years of experience in the fi eld of degradation assessment for NPPs

• COMSY tool provides a strong basis for the surveillance of the aging of numerous components for the rest of the plant life and the possibility to integrate easily new aging models.

Aging Management Review


Europe

• Biblis A, B • Grafenrheinfeld• Brokdorf• Isar • Unterweser• Grohnde• Khmelnitski• Krümmel• Philippsburg• Beznau

AREVA References:Asia

• Tomari

South America• Atucha 1 +2 • Embalse• Angra 1 + 2 + 3

US

• DC Cook, Calvert Cliff , Oconee, Mc Guire, Catawba, Columbia, Turkey Point, Monticello, Susquehanna, VC Summer

• Gösgen • Leibstadt• Borssele• Paks• Oskarshamn• Forsmark• Loviisa• Cofrentes • St. Maria de Garona• Rowno • Kozloduy

Typical COMSY window supporting effi cient aging management review

Inspection /maintenance manual

NDE examination records

Technical documentation

Load cycle catalogue

Thermal hydraulicoperating data

Material as-build data

Material specifi cations

Safety and availability requirements

Design and geometry data


Used Fuel Management Scoping Study

A study to determine requirements regard-

ing used fuel management in line with NPP

lifetime extension, and identify the options

going forward

The challenge

Operators seeking a renewal of their operation license will have to go through a comprehensive evaluation that encompasses an economic and technical assessment of the physical condition of the nuclear power plant, including used fuel evolu-tions.

This evaluation should take into account future core management options (increased fuel burn-up and enrichment, various used fuel management op-tions), new applicable safety standards and environ-mental conditions (seismic, corrosion…). It should also demonstrate the adequacy of exist-ing and planned storage capacities (onsite and/or centralized) with existing used fuel backlogs and future unloadings.

The utility must ensure safe used fuel management beyond the original licensed life time while accom-modating changes in capacity and increase in heat-loads, enrichment and burn-up.

The solution

Based on a half century of R&D and successful design, Implementation and Industrial operating experience in the fi eld of used fuel management, AREVA has developed methods and tools pack-aged together in a simplifi ed, structured, quick to implement set of analyses. This set will help the NPP operator identify and assess all possible sce-narios to ensure safe management of used fuel.The scoping Review will list information and data collected and present the results including esti-mated costs of options, time scheduling, needs addressed, compliance requirements met and potential issues.

The Utility will thus have a clear vision of the diff er-ent options guaranteeing safe used fuel manage-ment beyond the original licensed NPP’s lifetime. This vision will support future investment or opera-tion decisions as well as a life extension application to the Safety Authorities.

Key Features

A structured approach

• Preparation of plant-specifi c questionnaire

• Performance of interviews between AREVA and Operator’s experts and managers

• Preparation of a roadmap taking into account regulator requirements

• List of technical solutions available for each scenario

• Estimated cost and time scheduling for each option

• Joint Review of various options’ study and scoping

• Multi-disciplinary team of experienced specialists and experts

Deliverables of a scoping study for opti-mized and safe used fuel management

• Scenarios and options based on Operators’ needs, national safety authorities’ requirements, stakeholders’ constraints and international rules and regulations.

• Estimated project cost

• Implementation planning estimation


Handling operation at used fuel


• A common vision shared by the operator’s and AREVA’s experts

• A clear vision of the diff erent scenarios and options for optimized and safe used fuel management that will secure future operation and investment decisions

• A necessary assessment to support extension of license application from a used fuel management perspective

• AREVA’s leading and lasting industrial experience inused fuel management

Used Fuel Management Scoping Study


AREVA References:

• United States• Japan• China• Korea • Taiwan • Europe (Belgium, Germany, Netherlands, Slovenia, Spain, Switzerland, United Kingdom)

Expertise: • Waste and Used Fuel Management• Safety and Security• Radiation protection• Handling and Transportation• Costing, Economics & Finances• Aging management • Retrievability and Packaging• Public acceptance


Long-Term Solutions for Competences Management

A comprehensive series of services cover-

ing staff assessment, defi nition of training

paths, implementation of training courses

and On the Job Training using AREVA world-

class infrastructures and equipment

The challenge

Operators that are seeking renewal and confi rma-tion of their operation license will have to demon-strate their ability to ensure the permanent develop-ment of the competences of their staff to achieve the required level of safety, security and perfor-mance of the plants.

Competences shall be developed in accordance with the regulation and the actual confi guration of the plant.

They have to go through demonstration of the complete process for competences management, including:• Identifi cation of key competences over the long run • Assessment of staff members regarding key competences• Implementation of appropriate training/recruiting plans to secure the competences• Continuous monitoring of competences and vocational training to maintain these competences at the appropriate level

The solution

Based on more than 10 years of experience in developing the competences of its staff , and also providing training services to its partners and customers, AREVA has developed and implements a wide range of services for the development of competences.

The frame of these services cover:• Defi nition of Human resources Development Plans • Establishment of competences management system, including defi nition of training equipment • Training engineers and managers in technology for engineering activities • Training managers in project and people management • Training technicians an workers for the safety and quality of their interventions on site

AREVA is using its experts, facilities, simulators, and its network of partners to achieve a recognized

A structured approach • Gap analysis and defi nition of needs for human resources • Competences assessment, defi nition and evaluation of training paths • Development/adaptation/implementation of training programs • Identifi cation of support requirements (simulators, equipment…) • Train the trainers

Organization and means• Network of worldwide training centers.• Multi-disciplinary team of experienced specialists and experts • Access to AREVA industrial facilities • Specifi c equipment and simulators • Access to the AREVA international network of partners• Systematic Approach to Training (SAT) methodology


Training session on an operation analysis simulator in Paris, France

record of training experiences, addressing some of the largest utilities.

The solutions are available across the globe with strongest footprint in France, Germany, and the US.


• The expertise of a nuclear operator

• The recognized experience of AREVA in competences development for nuclear energy activities

• Access to AREVA capabilities: – Industrial facilities – Specifi c equipment, mock-ups, simulators – Network of international experts

Long-Term Solutions for Competences Management


AREVA References:

• EDF

• GDF SUEZ

• CNNC

• Europe (France, Germany, United Kingdom, Belgium…)

• United States

• Middle East (Saudi Arabia, Jordan, United Arab Emirates)

• Africa (South Africa)

• Far East (China, Japan)

Contribution of Competences Management to AREVA Action 2016 program


AREVA US ExperienceFrom License Renewal to Beyond 60

Proactive aging management for 60 years

and beyond thanks to AREVA’s unique ex-

perience in license renewal, from application

to implementation and support

Unique Experience in License Renewal

AREVA’s License Renewal (LR) services have helped US utilities extend the safe operating life of their PWR and BWR nuclear power plants by 20 years, while ensuring continued return on invest-ment to their shareholders.• Active Involvement in all key industry working groups : NEI, NRC, EPRI

• LR guidance including: – Mechanical Tools – Rev. 4 (EPRI 1010639) – Electrical Tools – Rev. 1 (EPRI 1013475) – Structural Tools – Rev. 2 (EPRI 1015078)

• Comprehensive procedures and guidelines: – NSSS Generic License Renewal Program – Four generic NRC-approved Aging Manage- ment Reviews: RCS Piping, Pressurizer, Reactor Vessel, Reactor Vessel Internal

• Unique regulatory environment experience: reconstitution and/or revision of Design Bases (DB) documents to meet Current Licensing Bases (CLB) of operating plants

• Experience with all technologies (PWRs, BWRs) and manufacturers

Beyond 60

The AREVA roadmap for safe operation beyond 60 aims at preparing solutions for the safe long-term operation of US nuclear power plants beyond 60 years of operation. It addresses specifi c technical challenges such as:

• Cable aging technology development

• Concrete inspection and NDE development

• Monitoring technology development


Key US regulatory guidelines regarding License Renewal

Post-Application Aging Management Assessment & Activities

Following a successful license renewal the focus shifts to implementing LR commitments, perform-ing the inspections and meeting the commitments: • Evaluate degradation scenarios• Perform NUREG 1801, “GALL” comparisons for existing and/or newly-identifi ed degradations • Identify required inspections • Identify monitoring programs• Prepare implementing procedures • Perform inspections and assess results• Implement recommendations including preventive maintenance optimization, new inspections, and related procedure changes

Related Service-Integrated Plant Assessments

• Aging Management Review • Aging Management Program Development and Enhancement• Fatigue Monitoring, Fire Protection, High Voltage Porcelain Insulators, Concrete Inspections, Reactor Vessel Inspections

NRC GuidanceRG 1.188RG 4.2

NRC ReportsNUREG-1800NUREG-1801NUREG-1555

NEI GuidanceNEI 95-10NEI 98-06

NRC Rules

10CFR5410CFR51

Industry GuidanceEPRI 1015078-structuralEPRI 1010639-mechanicalEPRI 1013475-electricalOwners Groups


AREVA’s unparalleled experience in over 50% of US license renewals allows for:

• Proven License Renewal process experience that reduces overall project risks

• Lower total project costs and faster project execution for License Renewal

• Proven lessons learned from previous License Renewal projects

• Optimized utilization of client staff

AREVA US ExperienceFrom License Renewal to Beyond 60


AREVA References in the US:

A dedicated License Renewal team has been involved in over 50% of License Renewal eff orts in the US since the mid 1990s:

• DC Cook Units 1 & 2

• Calvert Cliff s Units 1 & 2

• H.B. Robinson Unit 2

• Ginna Unit 1

• Oconee Units 1, 2 & 3

• McGuire Units 1 & 2

• Catawba Units 1 & 2

• Three Mile Island

• Turkey Point Units 1, 2 & 3

• Beaver Valley Units 1 & 2

• Davis Bessie Unit 1

• Monticello Unit 1

• Cooper Unit 1

• Browns Ferry Units 1, 2 & 3

• Arkansas Nuclear One Unit 1

• Indian Point Units 2 & 3

• Columbia

• Susquehanna Units 1 & 2

• Crystal River 3

• V.C. Summer Unit 1

Other US LR Applications reviewed by AREVA:

Palo Verde, North Anna, Surry, Kewaunee, Point Beach, Prairie Island, D. Arnold, Harris, Brunswick, Hatch

Our License Renewal team was also involved in international LR eff orts in Angra (Brazil) and Krsko (Slovenia).

Overview of the US situation regarding License Renewal


Aging Management by Component

Reactor Pressure Vessel (RPV)• RPV Inspections• RPV Integrity Assessment • RPV Surveillance Program• Measures for Reducing RPV Irradiation Fluence• Aging Management Strategies for Alloy 600








RPV Inspections

Perform your full 10-year, intermediate and

follow-up surveillance inspections with mini-

mal disruption of outage activity in support to

your Aging Management Reviews

The challenge

The Reactor Pressure Vessel (RPV) is a critical, irre-placeable, and potentially life-limiting component of the Nuclear Steam Supply System. Within the scope of long-term operation and license renewal, RPV surveillance and in-service inspections are vital for Aging Management Programs. As they are carried out during outages, inspections must also minimize vessel occupation time.

The solutionAREVA’s global business entity, “AREVA NDE-Solutions” brings innovation, reliability and effi ciency to RPV inspection thanks to its long standing expe-rience in automated non-destructive examination of nuclear reactor primary components.

Thanks to extensive qualifi cations under various national codes, AREVA has built the broadest global perspective and know-how to this challeng-ing examination worldwide.

AREVA off ers tailored inspection solutions for:• Shell and bottom-dome welds • Core-belt & under-clad defects• Nozzles including inner radius (NIR) and Dissimilar Metal Welds (DMWs)• Radial Support Lugs (including wear)• Threaded area of fl ange plus studs and nuts• Bottom Mounted Nozzles (BMN)

Consequently, AREVA is ideally positioned to provide responsive solutions as new degradation concerns arise in aging components.

AREVA’s Manipulators

TWS

• Meets all ASME PDI regulatory requirements thanks to the most complete range of qualifi cations

• Enhanced inspection accuracy on complex surfaces thanks to dedicated UT analysis features

MIS

• Sole inspection solution to provide full set of RSEM and ASME (Belgium) RPV qualifi cations

• High inspection versatility since enabling immersion focused UT, ET, VT and RT techniques

• Unmatched, demonstrated sensitivity and position repeatability in characterizing large number of indications.

CMM

• Large qualifi cation sets on German, Nordic and European national codes

• Very high accuracy with UT phased array technology

Nozzle Manipulator

• Enables independent inspection of RPV nozzles and associated welds

• Short inspection time compared to full manipulator deployment

Aging Management by Component Reactor Pressure Vessel

AREVA MIS Inspection


• Global and long-standing experience in RPV inspection

• Field-proven tools and techniques reliability and repeatability

• Optimized solutions for minimization of vessel occupation time

• Easy set-up & rigging considering safety and ALARA practice

• Adaptable solutions to your unique plant criteria

RPV Inspections


AREVA References:

Unique experience

“AREVA NDE Solutions” has performed hun-dreds of RPV, RPVH (Reactor Pressure Vessel Head) and BMN inspections worldwide.

Today, “AREVA NDE-Solutions” leverages its global experience and resources to deliver long-term standard or customized inspection solu-tions to local codes and inspection criteria in:• Europe: Belgium, Finland, France, Germany, Slovenia, Sweden, Switzerland, United Kingdom • Americas: Brazil, United States • South Africa• China

Safe, predictable, and fast RPV inspection capa-bilities

Highly skilled personnel, wide qualification set of methods according to various codes and robust though accurate equipment and techniques.

Maintenance of extensive mockups for validation and qualification of new techniques associated with training facilities and resources for inspection personnel.

AREVA Trans-World System (TWS)


RPV Integrity Assessment

Comprehensive assessment of RPV

behavior depending on time of operation,

neutron irradiation and accident loadings

The challenge

The Reactor Pressure Vessel (RPV) is safety relevant for maintaining the core cooling and as one barrier for safe inclusion of fi ssion products. Because it is a non breakable, irreplaceable part of a nuclear reactor, it constitutes a critical life-limiting component. In the frame of long-term operations and license renewal, a proper RPV integrity assess-ment is therefore critical for both the utilities and safety authorities.

In particular, it has to be proven that a postulated fl aw in the wall of an embrittled pressure vessel can not propagate through the vessel in case of certain accident scenarios or pressurized thermal shock (PTS) transients.

The solution

AREVA applies approved and validated analytical and numerical tools and testing methods which al-low state-of-the-art integrity assessments related to • RPV wall fl uence determination, • RPV material properties determination,• Thermo-hydraulic calculation, • Mechanical calculation and PTS integrity analysis

Typical scope of RPV integrity assessment

RPV fl uence calculation

Determination of material properties

• Execution of all necessary experimental work in accredited and certifi ed in-house laboratories

Thermo-hydraulic calculations

• NOS model, RELAP5

• Computational fl uid dynamics (CFD)

Mechanical calculation and structural integrity analysis

• Numerical Finite Element Method (FEM) calculations for complex geometrical shapes and loadings

• Safety-related assessment of postulated or detected fl aws

• Crack growth calculations for lifetime evaluation

• Application of advanced calculation and simulation systems in the fi eld of brittle and ductile fracture including WPS (Warm Pre-Stress) tool for mechanical studies

Final assessment of results

Documentation of the entire project and compilation of the necessary documents for license applications


Door of a building with special requirements

RPV Integrity Assessment


Simulation of a reactor pressure vessel during a coolant loss incident

3D defect modeled for mechanical integrity analysis

Examinations of surveillance program specimens in our hot-lab in Erlangen, Germany

AREVA References:

• RPV safety assessments for commercial nuclear power plants – French 1300 MWe VD3 RPV Integrity Analysis – French 900 MWe VD4 RPV Integrity Analysis – All German plants – Atucha (Argentina), Angra 2 (Brazil), Beznau, Leibstadt, Mühleberg, Gösgen (Switzerland), Borssele (Netherlands), Ringhals (Sweden), Santa Maria de Garoña and Trillo (Spain)• National and international R&D programs on RPV aging: – French tri-partite (EDF-AREVA-CEA) Irradiation Aging programs related to the RPV steel of the French PWR fleet – German CARISMA and CARINA fracture toughness programs – European Programs on Irradiation and Fracture Toughness (PERFECT, PEFORM60, NULIFE, LONGLIFE, … )

AREVA Capabilities:

• Strong partner with extensive experience in the field of aging management of nuclear components• Integrated solution competence from one single source• State-of-the-art facilities and highly skilled and experienced staff • Manufacturing and testing activities on site in certified and accredited laboratories including material testing, hot cells and radiochemistry• Good knowledge of requirements of inspection bodies and nuclear authorities• Assessment and implementation of mitigation measures


• Extensive knowledge and broad experience related to studies of materials under irradiation

• Benefi t from synergies between AREVA experts worldwide related to RPV aging (surveillance program, inspection, fl uence, thermo-hydraulics, mechanics)

• State-of-the-art fracture mechanical and thermo-hydraulic calculations of complex structure and load confi guration by means of analytical and numerical methods


Reactor Pressure Vessel

RPV Surveillance Program

Irradiation surveillance program to support

the RPV materials assessment

The challenge

The irradiation by fast neutrons (E > 1 MeV) has a signifi cant eff ect on the microstructure of the RPV material in the RPV beltline region resulting in material property changes for neutron fl uence > 1017 n/cm2. In particular, the strength of the mate-rial increases and fracture toughness decreases with increasing neutron fl uence. Neutron-induced embrittlement of vessel materials is mainly meas-ured by increase in nil ductility transition reference temperature (RTNDT). The basis for demonstrating an absence of brittle fracture risk is predicting the allowable end of life RTNDT under irradiation. This requirement is ensured by the RPV irradiation sur-veillance program.

The solution

The objective of a surveillance program is to measure the strength and toughness properties of the RPV materials in the core beltline region as a function of neutron irradiation. For this purpose capsules containing specimens are placed between core and inner RPV wall for accelerated irradiation.

AREVA provides the full scope of services for RPV irradiation surveillance programs in light water

Turnkey irradiation surveillance programs for RPV in LWRs

• Consultation, planning, coordination, execution

• Close collaboration with independent experts and authorities

• Manufacturing of specimens and capsules

• Baseline testing

• Delivery of capsules to the power plant

• Withdrawal of capsules from the RPV

• Post-examination of irradiation capsules – Transport to the hot cells test lab – Dismantling of capsules, specimen testing – Examination of temperature and fl uence monitors – Fluence calculations – Safety results assessment – Documentation of the entire project and compilation of the necessary documents in licensable form.

Additional specifi c services such as

• Sampling and analysis of the RPV stainless steel cladding after cladding for experimental fl uence determination

• Conceptual consulting for plant life extension and mitigation measures

• Qualifi ed manufacturing of new specimens from irradiated specimen already tested (reconstitution technique)


RPV: Change of material behavior under irradiation

reactors (LWR). This allows to experimentally verify the tensile and fracture toughness properties of the RPV material at assessment fl uence (neutron fl uence used in the assessment against brittle fracture) and to provide reference temperatures required for RPV integrity assessment.


• Comprehensive monitoring of RPV materials behavior depending on time of operation and neutron irradiation

• Customized irradiation surveillance programs for all types of RPVs up to the end of operating life

• State-of-the-art facilities and highly skilled and experienced staff

• Provision of supplementary capsules for extended surveillance programs

RPV Surveillance Program


Surveillance programs in line with the latest safety standards:

• Germany: KTA 3203 “Surveillance of the Irradiation Behaviour of Reactor Pressure Vessel Materials of LWR Facilities”

• US: ASME III and XI code, ASTM E-185 “Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels” and NRC RG 1.99, 10 CFR 50 Appendices G and H

• France: RCC-M and RSE-M code

AREVA Capabilities:

• Strong partner with extensive experience in the field of aging management of nuclear components

• Capsule manufacturing facilities

• Integrated solution competence from one single source

• State-of-the-art facilities and highly skilled and experienced staff

• Manufacturing and testing activities on site in certified and accredited laboratories including material testing, hot cells and radiochemistry.

• Good knowledge of requirements of inspection bodies and nuclear authorities

Hot and semi-hot cells work


Measures for Reducing RPV Irradiation Fluence

Mitigate the aging under irradiation of your

Reactor Pressure Vessel material thanks to

low leakage technologies

The challenge

The Reactor Pressure Vessel (RPV) has a role to play with regard to safety as it maintains core coo-ing and is one of the barriers for containing fi ssion products. Because it is a non-breakable, irreplace-able part of a nuclear reactor, it constitutes a critical life-limiting component.

Irradiation by fast neutrons (typically E > 1 MeV) has a major eff ect on the microstructure of the RPV material in the beltline region resulting in material property changes for high neutron fl uence. Within the scope of long-term operation and licence renewal, mitigation strategies can be put in place to keep the fl uence of the RPV wall at the lowest possible level.

The solutionThanks to its wide expertise in fuel fabrication, fuel management and fl uence calculations, AREVA has acquired signifi cant know-how in the deployment of core loading strategies to lower fl uence on the RPV materials thanks to a lower exposure to fast neutrons.

In addition to its consulting expertise, AREVA can also support utilities in the implementation of diff er-ent mitigation strategies, including the insertion of specifi cally optimized fuel assemblies in the core.

Fluence Minimization and Mitigation Strategies

• Development of low leakage loading patterns

– Overall fuel management strategy optimization

– Core loading optimization

• Insertion of specifi cally optimized fuel assemblies in the core periphery (example of possible options)

– Extreme low leakage core loading with the highest burn up fuel assemblies in the azimuthal region of the fl uence maximum

– Insertion of optimized shielding fuel assemblies with steel rods replacing some of the fuel rods at the core edge in the azimuthal region of the fl uence maximum

– nsertion of fuel assemblies with high burn up and inserted absorber rods (AgInCd) at the core edge in the azimuthal region of the fl uence maximum

– Insertion of special steel elements at the core edge in the azimuthal region of the fl uence maximum


Reactor Core with 12 specifi cally optimized fuel assemblies at the core edge for low RPV fl uence

Azimuthal region to be optimized RPV

Core BarrelThermal Shield


• Limit the fl uence on the RPV wall to insure Long-Term Operation of your reactor and facilitate the preparation of justifi cation fi les

• Benefi t from synergies between AREVA experts worldwide relating to

– fl uence calculations and understanding how radiation materials interact

– fuel management strategy optimization and core loading pattern optimization

– standard fuel, MOX fuel and shielding fuel assembly manufacturing and related services

Measures for Reducing RPV Irradiation Fluence


AREVA References: AREVA Capabilities:

Working closely with customers in several coun-tries across the world, AREVA has developed various design solutions to improve fuel eco-nomics while reducing RPV fluence.

For example, for 900 MWe reactors in France, a low fluence loading pattern has been selected with high burn up fuel assemblies at the core edge in the azimuthal region of the fluence maximum. Solutions have also been provided for 1300 and 1450 MWe reactors.

In other countries, an In-Out very low leakage loading pattern has replaced an Out-In load-ing pattern. AREVA has brought solutions to its customers for several reactor designs.

AREVA does not exclude any option. Studies can be performed on a case-by -case basis in order to reach the optimal situation in terms of balancing fuel economics, peaking factor limits and RPV fluence reduction according to the par-ticular requirements of each individual customer.

AREVA is also developing and continuously improving RPV fluence calculation methodolo-gies to better predict results and minimize the uncertainty associated with RPV fluence.

Fuel assembly being loaded into the reactor


Aging Management Strategies for Alloy 600

Perform an analysis of the risk of Primary

Water Stress Corrosion Cracking and opti-

mize your Aging Management Program

The challenge

Primary water stress corrosion cracking (PWSCC) phenomena aff ect Alloy 600 base material as well as Alloy 182/82 welds. Depending on design, Alloy 600 zones can be found in the following areas:• Bottom Mounted Nozzles (BMN) • Reactor Pressure Vessel Head (RPVH) penetrations and radial guides • Dissimilar Metal weld (DMW) on the reactor pressure vessel (RPV) pressurizer nozzles

The condition of these zones with respect to PWSCC needs to be assessed within the scope of Periodic Safety Reviews and license renewal processes for PWR plants, and adequate Aging Management Programs must be implemented.

The solution

AREVA can propose solutions for every step of the Aging Management Program, in line with the regu-latory framework:• Evaluation of risks and life prediction• In-service inspections• Repair, replacement or mitigation strategies

Focus on Risk Determination Studies

• Evaluation of the PWSCC sensitivity of the Alloy 600 base metal and 182 weld metal

• Evaluation of the residual stress level in the base and weld metal of the BMN using leading-edge measurement technologies and welding numerical simulation

• Assessment of the PWSCC risk, and of the time to initiation or of crack propagation

• These assessments allow a solution to be implemented in an optimized time frame, according to customer constraints

Possible Scope for Inspection

• High performance volumetric and surface inspection of RPVH penetrations, BMN base metal and of base metal/weld interface

• Advanced surface inspection of RPVH and BMN J-Welds (volumetric under development)

• Volumetric inspection of the DMW

• Volumetric inspection of radial guides welds

Focus on Component Replacement

• Reactor Pressure Vessel Closure Head (RVCH). We tailor RVCH installation services for each customer’s plant confi guration. Specialized options include modify- ing the containment hatch and performing ingress/egress studies.

• Pressurizer replacement as well as a full range of associated services can be of- fered and adapted to specifi c requirements and depending on reactor type.

Aging Management by Component Reactor Pressure Vessel Pressurizer

RPV Nozzle Inspection using the TWS In-Service Inspection tool


• Competencies to assess the condition of your RPV alloy 600 zones, predict their evolution, and propose repair solutions

• Support to help you select the optimized scenario adapted to your constraints

• Engineering, NDE mitigation, repair and replacement

Aging Management Strategies for Alloy 600


AREVA Technical Tools and Solutions:AREVA References:

• Risk assessment based on materials analysis and residual stresses evaluation for the BMN or the RPVH • Mitigation and surface remediation techniques include: – Primary water chemistry optimization – Surface remediation (abrasive water jet, roto-peening, cavitation peening) – Cavitation peening tools are adapted to BMN geometries• A wide range of NDE inspection techniques and associated robotics – Manual or automated conventional or phased array UT of DMW – UT TOFD techniques for CRDM nozzles or BMNs – ET array techniques for RPVH penetrations and BMN J-welds – Nozzle-only or full RPV scope manipulators• Different repair technologies have been developed by AREVA for each zone: – CRDM and pressurizer heater nozzles: ID ambient temper bead or weld overlay – BMN and pressurizer nozzle: half nozzle repair – DMW: Weld Overlay (full structural or preventive), full removal and reweld, or local repair Dissimilar Narrow Gap Weld with patented pure intermediate layer• Depending on the repaired zone, Alloy 690/52/152 or 316SS is usually used

Zone risk assessment for the French fleet for all Alloy 600 zones of the RPV• Evaluation of the PWSCC sensitivity of the 600 Alloy and 182 weld metal• Evaluation of the residual stress level in the weld metal of the BMN weldsReactor Pressure Vessel Head Replacements90 Reactor Vessel Head Replacements (RVHR) including nearly 80 in the United States for sev-eral designs.DMW repair: Goesgen (Switzerland) PZR spray nozzle repairBMN repair: South Texas (half nozzle repair)RVH nozzle penetration repairs: 133 of the 169 head repairs in the US have been performed by AREVA using ID ambient temper bead, weld overlay or other technologies.

Full structural weld overlay principleReplacement closure head

81/82 BUTTER

81/82 WELD 82 BARRIERLAYER

309L BARRIERLAYER

WOL (52M)

NOZZLE SS SAFE END SS WELD FITING


RPV Internals

Integrated RPV Internals Assessment

Optimize the integrity assessment of RPV

internals

The challenge

In the frame of their long-term operations strategy, utilities have to conform to several regulatory procedures and provide the necessary studies, inspections, component repairs & replacements to support their license renewal or periodic safety review eff orts as well as their Aging Management Program (AMP) commitments.

RPV internals aging eff ects have to be managed by utilities through Aging Management Programs (AMP) which have to take into account observed wear and degradation of components like Control Rod Guide Tube Assemblies and baffl e bolts.

The solution

AREVA has developed several tools and methods to allow for state-of-the-art full scope internals assess-ments and upgrades:• Aging Management Plans and studies• Diverse Inspection solutions (eg. SUSI …)• Engineering Evaluation / Analysis and models• Component Repair and Replacement


Flexible multi-role underwater robot SUSI

Key features

Inspection

• SUSI: this fl exible multi-role underwater system allows for extremely time-effi cient UT observation of activities and components inside the cavity. SUSI can also be used as a carrier of the UT transducer for performing Baffl e Bolts inspection. SUSI has a 5cm positioning accuracy which eradicates any potential bolt ident-i fi cation errors

• Additional inspection systems have been developed specifi cally to measure the eff ects of wear on the Control Rod Guide Assemblies thanks to high precision cameras

Justifi cation fi les

Using state-of-the-art models, AREVA can provide

• Baffl e bolt aging justifi cation analysis

• Upper and lower core grid alignment analysis

• Control Rod Guide Assembly justifi cation fi les

• Stainless steel neutron embrittlement analysis

Component repair & replacement

• An optimized component replacement strategy and its implementation can be performed by AREVA for your baffl e bolts, Control Rod Guide Assemblies and split pins, your stellited inserts and also for your complete upper or lower internals


• Benefi t from the integrated approach off ered by AREVA which combines inspection, justifi cation fi les setup and component repair or replacement

• Obtain an accurate vision of the condition of your internals thanks to our state-of- the-art inspection systems

• Optimize repair and replacement analysis for your baffl e bolts and your Control Rod Guide Assemblies (CRGA) by using our custom-designed analysis models

Integrated RPV Internals Assessment

AREVA masters existing regulatory guidelines to support utilities:

• US EPRI MRP-227 / MRP-228 related to :

– Screening for degradation mechanisms

– Evaluation of functional impact of degradation

– Inspection recommendations supporting license extension


Example of PWR Internals confi guration 3D models can be used for baffl e bolt justifi cation fi les

• AREVA is the fi rst company to provide full MRP227 inspection capabilities

• Along with EPRI, the CEA, EDF and Tractebel, AREVA is a member of the international GONDOLE program which aims at collaborative R&D programs on internals swelling under irradiation

• AREVA also participates in alternative scientifi c programs like the JOBB and CIR (with EPRI) eff orts


RPV Internals

RPV Baffl e Bolts and Barrel Bolts Assessment

Optimize the condition assessment of your

RPV baffl e bolts

The challenge

In the frame of their long-term operations strategy, utilities have to conform to several regulatory procedures and provide the necessary studies, inspections, component repairs & replacements to support their License Renewal or Periodic Safety Review eff orts as well as their Aging Management Program (AMP) commitments.

RPV internals aging eff ects have to be managed by utilities through AMP which have to take into account observed wear and degradation of compo-nents like baffl e bolts.

The solution

AREVA developed several specifi cally designed tools and methods to allow for state-of-the-art barrel and baffl e bolt condition assessments and upgrades:• Aging management plans and studies• Specifi cally designed inspection systems• Engineering evaluation / analyses and models• Bolt replacement tools and services

Following inspections, AREVA can prepare the jus-tifi cation fi les that review baffl e bolt and core barrel bolt cracking characteristics. This is used to assess if the mechanical characteristics, the number and location of the bolts ensure fi t and safe long-term operations. When necessary, AREVA can also pro-vide bolt replacements.


Key features

Inspection

• The fl exible multi-role underwater system SUSI allows for extremely time-effi cient UT observation of activities and components inside the cavity. SUSI can also be used as a carrier of the UT transducer for performing Baffl e Bolt inspections. SUSI has a 5 cm positioning accuracy which eradicates any potential bolt identifi cation errors.

Baffl e bolt cracking justifi cation analysis

• Determination of the maximum accept- able use extension of bolts considering current observed bolt degradation,

• Determination of the minimum number of bolts needed and the corresponding locations, for baffl e plate securing

• Leading edge expertise in baffl e assembly stress analysis and state of the art modeling capabilities

• 1D and 3D predictive model for baffl e assembly aging using fi nite

Replacements

• In the context of justifi cation fi les preparation, consequence analysis is being used to develop minimum bolt patterns to minimize scope of baffl e bolt replacements

• Required replacement can be performed on all types of bolts using specifi cally developed tools like the dual mast tool.

SUSI Inspection 3D models can be used for justifi cation fi les


• Benefi t from the integrated approach off ered by AREVA which combines inspection, justifi cation fi le setup and bolt replacements

• Improve the accuracy of the condition assessment of your baffl e bolts thanks to the specifi cally designed AREVA inspection systems like our underwater system SUSI

• Optimize the aging management of your internals thanks to state-of-the art modeling approaches that help you minimize your bolt replacements thanks to consequence analysis used to develop minimum bolt patterns

RPV Baffl e Bolts and Barrel Bolts Assessment


Barrel bolts exchange Baffl e bolts exchangeAREVA mast system and tools

AREVA References:

• AREVA has inspected and exchanged over 7000 baffle bolts and core barrel bolts worldwide

• Recent references include baffle bolts inspections at Surry, Angra, North Anna, Oconee, DC Cook and Ginna


RPV Internals

RPV Control Rod Guide Assembly (CRGA) Assessment

Optimize the assessment of your RPV

Control Rod Guide Assembly (CRGA) and

split pins

The challenge

In the frame of their long-term operations strategy, utilities have to conform to several regulatory procedures and provide the necessary studies, inspections, component repairs & replacements to support their license renewal or periodic safety review eff orts as well as their Aging Management Program (AMP) commitments.

RPV internals aging eff ects have to be managed by utilities through AMP which have to insure that the RPV Control Rod Guide Assembly are perfectly fi t for purpose. The wear eff ects on the guides and is-sues with cracked or ruptured pins need to be fully assessed as well


Upper Internals Assembly with Guide tubes and support pins assemblies

Key features

Inspection

• Diff erent tools have been developed to address specifi c requirements of utilities in terms of accuracy for CRGA inspection. When required, high camera accuracy of ± 0,06 mm as well as digital image analy sis w / pattern recognition can be provided on our underwater remotely controlled inspection systems.

CRGA wear studies

• Measurements are analyzed by our experts to help you build your justifi cation fi les and advise on your CRGA overall strategy.

• Effi cient justifi cation fi les can also be built to justify the use of existing split pins.

CRGA replacement & repair

• Alternative CRGA can also be installed at your plant if necessary

• Replacement generation 4 split pins can be off ered by AREVA to replace your older generation split pins

The solution

AREVA has developed several tools and methods to allow for state-of-the-art full scope RPV Control Rod Guide Assembly assessments and upgrades • Aging Management Plans and Studies• Inspection tools• Engineering Evaluation / Analysis• Component Repair and Replacement

Thanks to dedicated inspection tools designed by Areva, utilities can improve their assessment of the wear condition and evolution and also bring the ob-jective and factual data to support their justifi cation for the long-term operations of their CRGA


• Benefi t from the integrated approach off ered by AREVA which combines inspection, justifi cation fi le setup and component repairs or replacements for a an easier Aging Management Program preparation project.

• Improve the accuracy of the assessment of the CRGA condition evolution thanks to our specifi cally designed inspection tools and adaptable analysis models to optimize your AMP strategy accordingly

RPV Control Rod Guide Assembly (CRGA) Assessment


AREVA has designed specifi c tools for CRGA inspection which have already been deployed in several countries

AREVA References:

Control Rod Guide Assembly (CRGA) inspections have been performed in Europe and in the United States on several reactors using different tools developed by Areva.

New Generation NG89 PIN Replacement Solutions:

NG89 Pins have been Installed on ∼ 50 % of the Guide Tubes in French 900 and 1300 MW Plants and on nearly 10 Foreign Plants in Europe (e.g Tihange, Belgium) and in the United States (Ginna).


PZR Aging Management Review

Comprehensive assessment of pressurizer

condition and development of inspection

and maintenance strategy

The challenge

Within the scope of long-term operation and license renewal, aging phenomena in the pressurizer have to be analyzed in the Aging Management Review. Important aspects such as fatigue of the spray and surge nozzles as well as the heater sleeves need to be addressed in order to prepare justifi cation fi les for license renewal applications for long-term opera-tion. Some pressurizer designs also encompass specifi c Dissimilar Metal Welds (DMW) in alloy 182 or 82 which is known to be sensitive to Pressurized Water Stress Corrosion Cracking (PWSCC).

The solutionAREVA applies approved and validated analytical and numerical tools and testing methods which al-low state-of-the-art integrity assessments related to: AREVA off ers tailored inspection solutions for:• Pressurizer (PZR) material properties determination• Thermo-hydraulic calculations • Mechanical calculations

Based on this assessment, a review of existing inspection and maintenance programs can be conducted by AREVA and optimized strategies developed for long-term operations.

AREVA also proposes dedicated solutions for issues related to alloy 182/82.

PZR Integrity AssessmentTypical Scope

Determination of material properties

Thermo-hydraulic calculations

• Computational fl uid dynamics (CFD)

Mechanical calculations and structural integrity analysis

• Numerical Finite Element Method (FEM) calculations for complex geometrical shapes and loadings

• Safety-related assessment of postulated or detected fl aws

• Crack initiation and growth calculations for lifetime evaluation

Final assessment of results and documenta-tion of the entire project and compilation of the necessary documents for license applica-tions

Aging Management by Component Pressurizer

3D model of the pressurizer internals used for CFD calculations


• Extensive knowledge and broad experience related to aging phenomena modeling and analysis based on leading-edge fracture mechanical and thermo-hydraulic calculations of complex structures using analytical and numerical methods

• Integrated approach combines expertise in inspection, justifi cation fi les setup and component repair and replacement

PZR Aging Management Review


AREVA References: AREVA Capabilities:

• PZR safety assessments for commercial nuclear power plants: – French fleet: 900 and 1300 MW – Borsselle NPP (The Netherlands)

• As a major pressurizer designer and manufacturer, AREVA has drawn on its expertise in the aging phenomena impact on materials to develop state-of-the-art pressurizer assessments

• Strong partner with extensive experience in the field of aging management of nuclear components• Integrated solution competencies from one single source• State-of-the-art facilities and highly skilled and experienced staff • Manufacturing and testing activities on site in certified and accredited laboratories including materials testing, hot cells and radiochemistry• Excellent knowledge of the requirements of inspection bodies and nuclear authorities• Assessment and implementation of mitigation measures

Stress Analysis in the vicinity of the heater sleeve weld


Pressurizer

PZR Repair & Replacement

Improve the condition of your pressurizer

for safe long-term operation

The challenge

Primary Water Stress Corrosion Cracking (PWSCC) phenomena aff ect Alloy 600 base material as well as Alloy 182/82 welds that can be found on pres-surizers. Depending on designs, these issues can be found in locations such as: • Upper spray, relief and safety nozzles• Instrument nozzles• Surge nozzles• Heater sleeves

The pressurizer heaters can also suff er from dif-ferent aging-related failures such as sheath stress corrosion cracking and electrical malfunctions.

Following the condition assessment of these com-ponents, a repair or replacement strategy needs to be put in place in order to justify the long-term operation of pressurizers.


Full Structural Weld Overlay (FSWOL) principle

AREVA Technical Tools and Solutions

Upper Nozzles

• Full replacement of susceptible material (Alloy 600)

• Full Structural Weld Overlay (FSWOL)

• Optimized Weld Overlay (OWOL)

• Replacement of thermal sleeves

Instrumentation Nozzles


• Half nozzle repair with Outside Diameter (OD) pad

• J Groove weld replacement

• Thermocouple removal and replacement

Heater Penetration

• Susceptible material when required

• Half nozzle repair with OD pad

• Half nozzle repair with Inside Diameter (ID) weld

Surge Nozzles


• FSWOL

• OWOL

The solution

AREVA can propose mitigation, repair and replace-ment solutions to address both Alloy 600 and heater-related issues:• Nozzle and heater penetration repairs• Pressurizer replacement• Heater replacement

STAINLESS STEEL

CLADDING

CARBON STEEL

STAINLESS STEEL

309L

ALLOY 600

ALLOY 52M

ALLOY 82


• Recognized expertise to support your pressurizer mitigation, repair and replacement optimization decision-making process

• A leading-edge portfolio of techniques adapted to all pressurizer repair and replacement needs

PZR Repair & Replacement


AREVA References:

Examples of full pressurizer replacement• Ringhals 4, Sweden (2011)• Millstone 2, United States (2006)• St Lucie-1, United States (2005)

AREVA is involved in pressurizer repairs dur-ing almost every outage season.

AREVA Technical Tools and Solutions (ctd.)

Heater• Heater element removal, replacement• Penetration plugging• Machining of heater support

Full Pressurizer Replacement • Turnkey integrated projects including supply, engineering and installation

Pressurizer Replacement


Steam Generator

Replacement Steam Generator

Reliable and optimized steam generators

for Long-Term Operation (LTO)

The challenge

The fi rst generations of Steam Generators (SG) using Inconel 600 alloys (particularly alloys with-out thermal treatment) have been confronted by corrosion issues leading to the necessity to plug damaged tubes. The corrosion of the tubes varied considerably from one plant to the other and was highly impacted by chemistry management in the early days of the plant.

In order to ensure the safety and reliability of the plant in the longer term the Inconel 600 SG must be replaced especially when LTO is envisaged.

Utilities can take advantage of such replacements to uprate the plant.

The solution

With 340 Steam Generators designed and manu-factured including 100 Replacement Steam Gen-erators, AREVA has gained extensive experience that supports its capability to supply highly reliable steam generators. AREVA products also benefi t from operating experi-ence: improvements have been implemented to reduce the deposits and performance has been improved.

Combined with optimized chemistry management, steam generator replacement can consequently contribute to improve the performance of the plant for long-term operation.

Additionally the axial economizer technology can effi ciently support Power uprates.


Anti vibration bars on Steam Generator

Key features

• Capability of supply for all models

• Conventional design or axial economizer designs

• Improved corrosion resistance:

– Alloy 690 TT tubing

– Stress relief heat treatment of small U-bends

• Loose parts trapping system

• Anti-stratifi cation design

• High-effi ciency primary separators

• Stainless Steel Tube Support Plates with fl at lands


• A high level of reliability supported by AREVA’s experience gained in designing and delivering 100 RSGs and 240 for New build

• Steam generators that will cover the remaining lifetime of the plant

• Large manufacturing capabilities guaranteeing optimization of on-time delivery

• Option to replace existing conventional SGs by axial economizer SGs in the case of power uprate

• Capability to provide support supply and installation packages to facilitate interface management for the customer

Replacement Steam Generator


AREVA References:

• Belgium: 6 Replacement of Steam Generators (RSG) at Doel 4 and Tihange 3• Brazil: 2 RSG at Angra 1• France: EDF 1300MW and 900 MW fleet: 84 RSG• Sweden: 6 RSG at Ringhals 3&4• Switzerland: 2 RSG at Beznau 2• USA: 18 RSG at Prairie Island 1&2, Callaway, ANO1, Salem 2, St Lucie 2, TMI • 240 Steam Generators for New Build projects

Steam generator transport


Reactor Coolant Pump

Revamping of RCP Internals

Prepare reliable operation of the Reactor

Coolant Pump for LTO at an optimal cost

based on a customized assessment and

worldwide experience

The challenge

The Reactor Coolant Pump (RCP) is located be-tween the Steam Generator and the Reactor Vessel. It ensures the circulation of the coolant fl uid of the primary circuit. Originally designed for 40 years, the internals have to operate permanently in a demand-ing environment (pressure and temperature) to en-sure a fl ow rate of up to 28,000 m3/h. Thus, intents to pursue long time operation (LTO) require a closer assessment of aging mechanisms such as thermal fatigue, fretting, cavitation to make appropriate deci-sions regarding the heavy maintenance strategy for the LTO of RCP internals.

The solution

Some 250 AREVA-designed and manufactured RCPs are currently in operation worldwide and AREVA has more than 40 years of valuable main-tenance experience with over 400 RCPs. Thus, after having carried out a dedicated Life Cycle Management study, AREVA can off er revamping solutions that will support reliable operation of the internals during the remaining plant life. This can be achieved at a competitive cost thanks to the op-timized combination of plant-specifi c repair opera-tions and replacement of parts. Customers can also take advantage of the required revamp modifi cations to improve the robustness of the design and effi ciency of the pump.


Refurbishment of RCP internals

Key Features

Dedicated Life Cycle Management Study

• Assessment: examination of the utility’s own Operation & Maintenance experience combined with international lessons learned

• Elaboration of maintenance scenario: (A) Minor parts replacement, (B) Fit, Form & Function, (C) Upgrade, (D) Upgrade and effi ciency improvement

• Costs/benefi ts analysis including risk and NPV analysis

• Recommendations

Integrated Revamping Solutions

• On-site assembly/disassembly

• Design upgrades or repairs to cope with fretting, cracking, cavitation, thermal fatigue and stress concentra- tion issues

• Match-machining of existing parts with new components

• Scope of work: thermal barriers, shafts, diff user labyrinths, etc.

• Support for the justifi cation to Safety Authorities

• Full fl ow tests

Integrated Revamping Solutions


• Integrated solutions combining decontamination, repair, and upgrades to reinforce equipment reliability for Long-Term Operation

• Use of experience feedback from RCPs of similar design

• Dedicated Life Cycle Management study to take into account utility-specifi c parameters and formulate recommendations

• Availability of appropriate engineering skills, expertise capabilities and hot shop facilities

• Full Flow Test Center to validate calculation hypothesis of upgrades and bring justifi cations to Safety Authorities

Revamping of RCP Internals

Supporting Capabilities:

In addition to a Full Flow Test Center dedicated to RCP, AREVA has engineering skills, expertise capabilities on hot components, and hot shop facilities based in France and in the USA.

AREVA Maintenance Experience:

• Model 70 & 93D

• Model 93/93AS/93ANS/93A/93A1

• Model 100A, 100D, N4

Examples of RCP Internal Revamping Programs

• RCP Model 100: reinforcement of shaft – impeller fi tting to cope with fretting and cracking

• RCP Model 93D: repair or replacement and upgrading of shafts, thermal barriers, diff user labyrinths, etc. to reduce thermal fatigue or improve resistance of parts

• Replacement of shafts with match-machining of the reused old impeller


Section of RCP internals SOMANU hot shop (France) performs decontamination, repairs and upgrades of contaminated components


Reactor Coolant Pump

RCP Stator Replacement

Know-how and experience at the service of

motor robustness and lifetime

The challenge

Reactor Coolant Pump (RCP) motors power the RCP for primary circuit circulation and core cooling. The stator is one of the most sensitive parts, as it has to withstand aggressive environment, start-up conditions, and power supply irregularities.

Expectations on RCP motors are greater than ever due to reliability requirements and economic impact of failure (plant shutdown). Utilities have thus to implement appropriate maintenance strategies to cope with RCP motor aging and ensure their robustness for the remaining life of the reactor.

The solution

Backed by a robust design, demanding qualifi ca-tions and a specifi c manufacturing process, 250 AREVA RCP stators have operated worldwide with no failure, no repair and no power plant outage to date.This proven experience and know-how enables AREVA motors to operate up to 40 years, i.e. on average 30% longer than other motors. Such a reli-ability represents an opportunity for plants reaching 30 or 40 years of operation to carry out only one single heavy maintenance activity for their RCP mo-tors and consider long-term operation.

In addition, the replacement by stators of recent design increases the effi ciency of the motor.

AREVA off ers an integrated solution of motor disassembly, decontamination & refurbishment in hot shop with a stator replacement, and on-site re-assembly.


The RCP motors are fundamental to the safety and effi ciency of power plants. Their reliability, in particular when restarting, is critical for the availability of the reactor.

Key Features

A robust design of RCP motor stators

• Improved and qualifi ed insulation system

• Nuclear qualifi cations: aging irradiation tests and accident irradiation tests performed in CEA Cadarache & Saclay (France) in collaboration with EDF

• Each First-Of-A-Kind motor has been submitted to 1,500 successive starts in uninterrupted sequence

• Strategic improvements to improve overall robustness and decrease electrical con- sumption (effi ciency gains)

Associated maintenance services

• Assembly/Disassembly

• Decontamination of RCP motors and replacement with new stators


• A robust and proven design worldwide: no additional heavy maintenance required till end of plant life after having replaced the aged stator with a new one

• Self-funded new stator thanks to effi ciency gains

• AREVA replacement stators mitigate the risk coming with repairing old stators (rewinding process) such as damage of the core, increase of losses, non-compliance with electrical test requirements, etc…

• Optimized plant availability during the Extended Period of Operation

• Integrated solutions combining on-site services, decontamination, repairs, upgrades and stator replacement

RCP Stator Replacement

Insulation of the stator, a century of unique know-how

Our insulation system has been designed to be able to withstand extreme demands: overheating (due to the Joule eff ect), overvoltage (due to direct online startup and stops), intense electric fi elds, environ-ment aggressions (humidity, dust, radiations, etc.) and mechanical constraints (due to direct online startup, operation vibrations, electromagnetic forces, etc.)

Strategic improvements over time to improve overall reliability & effi ciency

Step 1: Improvement of end winding mechanical robustness Step 2: Increasing of insulation thermal class B to F+ 20 °C Step 3: Decreasing of electrical stresses Step 4: Decreasing of operation temperature rise

Supporting capabilities

AREVA has hot shop facilities based in France and in the USA, to serve utilities worldwide. In addition, its skilled engineering workforce is able to perform reverse engineering activities to supply interchange-able replacement stators for RCP motors made by other OEMs without supplementary adaptations. Compared with origin stators, the supplied replace-ment stators have at least the same effi ciency with improved insulation quality.


Up to 25 RCP motors can be decontaminated and refurbished every year in the SOMANU hot shop



AREVAForward Alliance









Control Rod Drive Mechanisms

Upgraded CRDM

Ensuring reliable long-term operation for

plants operating in load follow

The challenge

The Control Rod Drive Mechanisms (CRDM) are located above the reactor vessel. They are used to insert, hold or lift the control rods and to stop the nuclear reaction in the event of an emergency.

In deregulated markets subjected to price tensions exerted by non-nuclear electricity during off -peak periods, nuclear energy profi tability is no longer en-sured. Utilities may be led to operate in load-follow, and manage wear and heat & mechanical fatigue issues : very much in demand, CRDM ensuring permanent regulation can be requested to achieve up to 230,000 steps in a single 18 month cycle. Such CRDM will need to be replaced to operate till the end of the extended life of the plant.

In case of Vessel Head replacement, the plants pursuing LTO also need a complete CRDM replace-ment.

The solution

Backed by its experience of the French market – where nuclear electricity share in the energy mix leads power plants to operate in load follow – AREVA has been working for decades on the


CRDM

Key Features

Longer components lifetime

• 7 million (1300 MW) and 8 million (900 MW) step latches to increase component lifetime by 2 to 3.

• CRDM lifetime tested and qualifi ed in representative load conditions

• Demanding and accurate manufacturing process of Coil Stack to ensure inductance characteristics on the long-term (0 electrical failure reported so far)

Improved design reliability

• Cap design evolution to avoid leakage through the vent device, and to eliminate the upper OMEGA Seal

• Integrated Latch Housing to eliminate the lower CANOPY Seal Weld and take out the risk of leakage due to stress corrosion cracking (in case of RRVCH supply)

Associated services

• Dedicated tools and services for punctual cut and replacement of targeted CRDM to optimize wear phenomena

• Ability to supply “drop-in” closure heads, already equipped with CRDM assembled directly in the factory

stakes related to CRDM lifetime, reliability and raw material requirements in such conditions. CRDM latches qualifi ed for up to 8 million steps can oper-ate without replacement till the end of the extended life of the plant, even in the case of intense opera-tion due to load follow. The risk of leakage will at the same time be reduced thanks to the elimination of some seals.


• CRDM proven service life, increased 2 to 3 times allowing reliable operation of CRDM till the end of extended life, even in case of load follow

• Design upgrades to eliminate critical seal welds and prevent leakage & corrosion risks and high-dosimetry repairs

• Dedicated tools for punctual cut and replacement on-site of used CRDM having operated in load-follow

• Reduced outage schedule when replacing the reactor vessel head thanks to the delivery of a Closure Head already equipped with improved design CRDM

Upgraded CRDM

AREVA References:

In addition to more than 6000 CRDMs manufactured and installed since 1973 with no interruption, AREVA Jeumont site has maintenance experience on over 110 reactors and has performed over 3000 CRDM disassembly/reassembly operations.

“Drop-in RRVCH” with Integrated Latch Housing (ILH)

In case of vessel head replacement with the supply of new closure head, the lower CANOPY seal weld can be removed in order to eliminate the risk of leakage due to stress corrosion cracking. CRDM are assembled directly in the factory on the closure head, and delivered to the plant “ready to install”, reducing drastically the outage duration.

CRDM lifetime tested and qualifi ed in representative conditions

In order to demonstrate the eff ective lifetime of its CRDM’s, AREVA has performed extensive tests on both 900 MW and 1300 MW designs on the CEA test loop (French Atomic Energy Commission) in Cadarache, France. Those tests were performed in conditions that were representative of loads (fl uid dynamic, etc).



Concrete Aging

Concrete and Civil Works Aging Management Reviews

Comprehensive chemical and mechanical

assessments of your concrete structures

The challenge

The aging degradation mechanisms of concrete structures can lead to failings in the integrity of the containment and other civil engineering structures of a nuclear power plant (NPP). Chemical degrada-tion mechanisms can appear with time and weaken concrete structures. Creep and shrinkage can also lead to the relaxation of the pre-stress cables embedded in the structure, increasing the risk of damage over time during pressure tests. Because the primary containment is the key safety-related concrete structure in NPPs and with respect to long-term operation, a precise assessment of the chemical and mechanical properties of this con-crete structure is compulsory in order to prepare the required justifi cation fi les and implement required mitigation strategies.

The solution

Drawing from its experience on its own facilities and in support to utilities, AREVA has developed internal expertise and a network of partners that allow for:• Chemical assessment of concrete structures• Mechanical assessment of concrete structures including calculations of a pre-stressed containment building and prediction of the evolution of the liner geometry supported by liner model test results• Setting-up of surveillance programs for concrete aging • Implementation of mitigation strategies

In addition to studies, AREVA can support utilities from walkdowns to mitigation strategy implementation.


3D Stochastic generated concrete under external species penetration

Evaluation of creep and shrinkage eff ects on the dome can be evaluated using specifi c codes and models developed by AREVA

Concrete Aging Management Typical Program Scope

• Plant walk-down & regeneration of input data • Review of environmental conditions of Structures, Systems & Components (SSCs) • Evaluation of aging mechanisms and eff ects (see details below)• Confrontation of inspection sets and aging eff ects identifi ed• Proposal for mitigation strategies • Implementation of mitigation strategies• Aging Management Review preparation

Focus on the Assessment and Mitigation of Concrete Aging Phenomenon

• Setting up of a surveillance program• Sampling and testing to evaluate the condition of the structure and support diagnosis studies• Defi nition of criteria for each degradation and prognosis of the residual life with respect to the criteria using dedicated models and software• Proposing and implementing eventual mitigation and repair programs: protection by paint, protection against corrosion of rebars by corrosion inhibitors or by cathodic protection, dechlorination• Assessment of creep and shrinkage of the concrete and evolution of the pre-stressing. Life time calculation in pressure test situations• Time of incipient buckling of the liner


• Our expertise in chemical and mechanical aging mechanisms assessments for reinforced concrete structures, particularly in the fi eld of pre-stressed concrete

• Our practical experience on our own nuclear facilities in France and in several nuclear power plants in Europe to support their concrete and civil works aging management strategy

Concrete and Civil Works Aging Management Reviews


AREVA References:

AREVA performed the concrete and civil works Aging Management Review of the Borssele NPP (The Netherlands) and provided support for several civil structure assessment projects in Germany:• Plant walkdown and exchange of knowledge with plant personnel• Regeneration and structuring of input data• Assessment of the environmental conditions of SSCs • Generic nuclear industry experience (by other utilities)• Evaluation of aging mechanisms and effects summarized in a table for confrontation• Study and review of the applied measures to assess aging of SSCs• Confrontation of inspection sets and identi- fied aging effects • Conclusion and advice for further operation period

As an operator in the nuclear fuel cycle, AREVA has carried out several concrete and civil works aging management assessments in its own facilities in La Hague and in Pierrelatte (France): • Setting-up a surveillance plan for selected buildings• Studies to demonstrate durability up to 100 years (or even 300 years in some cases)• Repair of concrete or of reinforcement (corroded rebars)

AREVA has a broad experience in the use of state-of-the-art models and tools:• AREVA and the French Commissariat à l’énergie atomique et aux énergies alternatives (CEAEA) collaborate on concrete & civil works aging issues within the scope of several projects• Aging phenomena are also investigated and modeled within the scope of several programs such as the Nugenia project in Europe which brings together utilities, research labs and AREVA.


Instrumentation & Control

Diversifi ed Non-Computerized I&C Solution

The easy-to-license solution to meet safety

requirements in case of I&C upgrade or

replacement in the frame of LTO

The challenge

Any utility wishing to extend the lifetime of its plant for a signifi cant period faces the issue of the obso-lescence of its existing I&C modules as well as the necessity to adapt its safety requirements to the latest standards.

Whether it selects a computerized safety I&C system and is requested by its safety authorities to develop some back-up non-computerized function-alities or wants to complement an analog system with additional safety features, the utility will usually need to implement a modern non-computerized solution.

The solution

Based on the specifi cations required by some utilities for future new build projects, AREVA has developed a state-of-the-art non-computerized plat-form using technologies that will be supported for at least 30 years. This platform is fully developed in accordance with nuclear industry requirements.

In the case of LTO, it is perfectly adapted to provide the diversifi ed back-up system that may be required to obtain the licensing of a new digital I&C.

It is also designed to complement existing or refur-bished analog systems with the new functionalities required to meet the latest safety regulations.

AREVA can provide a complete solution covering safety requirements analysis, detailed design, inter-faces with other systems, supply and installation of cabinets and system commissioning. AREVA’s non computerized platform also enables interfacing with modern digital man-machine inter-faces.


Prototype of “2 out of 4” voting module

Key Features

Use of fail-safe magnetic logic:

• Operational experience since 1970s in Nuclear Protection Systems

• De-energized to actuate logic

• No complex electronic component – only discrete elements (transistors, transformers…), logic gates or operational amplifi ers to perform safety functions

Available functions:

• Simple AND/OR/NOT logic gates

• Threshold

• Switch-on/Switch-off delays

• 2-out-of-4 voting logic

• Pulse and fl ip-fl op blocks

• Alarm Management

• PID/Digital Step Controller

• Analog selection [Max/2nd max/Min/2nd Min]

• Confi gurable interface with digital HMI systems (MODBUS TCP/IP...)

Compliant with nuclear Codes & Standards:

• Class 1 for IEC 61513

• Qualifi ed according to IEC 60780 and RCC-E (including seismic resistance)


• Capability to provide a reliable back-up system and provide new functions to meet the latest safety requirements from safety authorities

• Simple solution designed in accordance with nuclear specifi cations and therefore easy to license

• Modern platform which will be used for future new plants that will remain maintained for more than 30 years

• Integration of NPP operation requirements thanks to cooperation with EDF in the development

• Optimization and validation of the design thanks to simulation platform

Diversifi ed Non-Computerized I&C Solution


AREVA References:

• This product has been selected by AREVA & EDF for the Non Computerized Safety System to be implemented on Hinkley Point EPRTM plants (UK)• This technology has been used by AREVA for over 40 years in Nuclear Submarines Protec- tion Systems

Typical I&C function implementation Simulation platform screenshot



I&C Systems Upgrade for LTO

The optimized I&C upgrade package

designed to secure safety and outage

duration

The challenge

There are limits to economically extending the life of an I&C system through spare parts management or retro-engineering of obsolete cards. Incorporating the latest safety requirements can also be challeng-ing with an aging system.

Therefore, if LTO is planned, the most economical approach is often to consider a refurbishment or replacement of the upper layers of the instrumenta-tion and control chain. Depending on the complexity of the functional evolutions the utility has to achieve, it can opt for a complete digital system, an analog system or an optimized combination of both.

This renovation should guarantee the safety of the plant during and after the migration to the new system and the work should be completed in the timeframe allocated to the I&C upgrade during the outage. The new system must also be duly inter-faced with existing systems.

The solution

Based on its NPP manufacturer experience in safety and as a developer/integrator of I&C systems, AREVA can provide full system packages that include designing the most suitable solution in accordance with customer and safety authorities latest requirements, supply and integration of the adequate architecture and equipment that will meet the customer’s expectations and constraints, instal-lation and commissioning.

AREVA’s expertise is fully dedicated to ensuring the highest level of safety at all stages of the project during the replacement of the existing system until the new system is fully operational in line with the specifi cations.

The replacement of the I&C is also an opportunity to reduce maintenance costs and avoid the unavail-ability that can result from an out of date system.


I&C modifi cation and tests

Key Features

Design

• Existing I&C assessment

• NPP safety requirements assessment

• Defi nition of the most suitable solution

• Process and architecture defi nition (digital, non-digital, back-up systems)

• Regulatory and licensing fi les

• Integration in existing NPP

Supply

• Equipment supply

• Secure outage through extensive factory acceptance tests

Installation and commissioning

• Optimized installation aligned with outage teams to secure outage duration

• Commissioning

• Optimization of radiation protection

Option: long-term services

• Availability management

• Obsolescence surveillance

• Long-term maintenance program


• Integration of the overall project from design to commissioning including interface management

• AREVA’s multi-disciplinary expertise in nuclear and I&C

• Ensure the highest level of safety during and after the migration to the new system

• Support in the interaction with safety authorities

• Implementation of the upgrade during the outage period

• Select and implement the most suitable products and technologies based on the existing design and the new safety requirements

• Knowledge of the most up-to-date technologies and architectures from new build projects

I&C Systems Upgrade for LTO


AREVA References:

• M2C program: digital I&C upgrade for the 1300 MWe French fleet• Transition from analog to digital I&C technology: scenario studies for the 900 MWe French fleet

• I&C renovation for DUKOVANY NPP: I&C replacement• US, Duke Energy: Oconee 1-3 modernization project• VVER I&C modernization projects

EDF example of I&C architecture



TELEPERM® XS Based Modular Safety I&C Modernization

Tailored approach to securely prepare the

I&C for long-term plant operation

The challenge

For long-term operation, nuclear operators need to secure the safe operability of I&C systems to the end of the plant life. Modernization drivers:• Limited support from analog I&C suppliers• Obsolescence • Safety/reliability/availability issues• System maintainability and O&M costs• Safety improvements• Demand for extended I&C performance.Especially in case of plant life extension, this typically requires the replacement of I&C systems. The transition to digital technology provides many advantages, provided some challenges can be mastered:• Regulatory compliance/licensability• Available technology transition expertise• Secured long-term support

The solution

AREVA’s approach to digital safety I&C moderniza-tion is based on applying elements of its market-leading TELEPERM® XS digital safety I&C platform. Modular structures and standardized interfaces ensure the link-up to remaining equipment. Licens-ability has been proven in various countries to diff er-ent codes/standards.

I&C systems are often upgraded in a modular and phased approach. TELEPERM® XS fi ts to anything from a stand-alone small system up to a comprehen-sive modernization approach. After the fi rst system installation, the infrastructure can be used and extended for additional systems to be modernized. Each system upgrade follows a phased approach, typically starting with a study and concept phase. AREVA applies its broad expertise in I&C and nuclear engineering.


Key Features

• AREVA’s I&C competence and experience – Interface and integration management – Licensing support – Requirements specifi cation and design – Manufacture and testing – Installation and commissioning

• AREVA’s nuclear engineering expertise

• Easy implementation of process optimiza- tions and overall performance improvements

• Allows modular and scalable I&C modernization – from single cabinet to multi-cabinet solutions

• TELEPERM® XS is designed for all kind of safety applications and can be a pre- ferred solution for non-safety applications.

• Customized application solutions – hardware architecture, – software functionality, – redundancy

• Ready to fulfi ll plant-specifi c requirements – Functionality – Response time – Failure assumptions – Space availability – Power supply


• Use of market-leading TELEPERM® XS digital safety I&C platform (reliable, validated, versatile, compatible, economical)

• Use of AREVA’s broad I&C and nuclear expertise

• Worldwide proven licensability

• Modular and scalable approach fi ts plant needs

• Comprehensive training modules

• Comprehensive after-sales support options

• Secured investment to future oriented technology for the long-term and to secure plant life

• Reliable and proven successful safety I&C modernization

TELEPERM® XS Based Modular Safety I&C Modernization


Modernization examples of diff erent sizes:

TELEPERM® XS References

Small applications:• Sizewell B (UK): I&C for continuous boron measurement (COMBO) for fuel storage pools (2 cabinets) • Atucha 2 (Argentina): Reactor Control System (4 cabinets)

Medium sized, combined applications:• Qinshan 1 (China): RPS, Neutron Flux Excore Measurement (21 cabinets; ∼1300 signals)• Oconee 1-3 (USA): RPS+ESFAS; emergency power turbine safety governor control system (18 cabinets per unit)

Comprehensive I&C modernizations:• Ringhals 1 (Sweden): Comprehensive I&C modernization of various I&C systems in a modular approach: diverse RPS, neutron flux power range monitoring, residual heat removal system, safety ventilation system (35 cabinets; ∼5400 signals)• Paks 1-4 (Hungary): Comprehensive I&C modernization of various I&C systems: Reactor Protection System, Reactor Limitation System, Neutron Flux Measurement, Diesel Load Sequencer

Status: 06/2013* VVER and Chinese designs merged


• Fatigue Monitoring System – FAMOSi • Integrated Procurement Solutions

Supporting Products & Solutions

Fatigue Monitoring System – FAMOSi

Local measurement and computation of

thermal loads allow realistic evaluation of

fatigue relevant components

The challenge

Key components of the primary circuit such as noz-zles and pipes are subjected to transient thermal loads that cause material fatigue and jeopardize their structural integrity.

As standards are becoming more stringent to take into account environmentally assisted fatigue or stratifi cation eff ects, utilities need to assess more accurately the current cumulated fatigue of the most sensitive components.

In case of long-term operation (LTO), it is necessary to demonstrate the capability of the equipment to withstand thermal fatigue for the extended operat-ing time.

The solution

By analyzing continuously-recorded local thermal loads, AREVA Fatigue Monitoring System (FAMOSi) provides an accurate evaluation of the cycle count-ing and stress analysis. This helps to reduce the conservative factors that were computed in the original design.

It can therefore demonstrate that the components fatigue is compatible with LTO or suggest solutions to mitigate the fatigue risk by enhancing the operat-ing modes. Unnecessary and costly replacement of components can be avoided.


Key features

FAMOSi hardware

• Heat range: 0 to 400°

• Normal instrumentation with up to 300 or more thermocouples

• Assembled to sections with 2 or 7 thermocouples

• Thermal load monitoring at: Feedwater Nozzle, Surge Line, Spray System, Volume Control System (PWR), Feedwater lines with connecting systems (BWR)

• “Fast Connect System” ensures short installation time in areas with high radiation

• Integration of data to existing I&C environment

• Qualifi ed Instrumentation and data acquisition

FAMOSi software

• Fast Fatigue Evaluation (FFE) for direct processing of measured data and time dependant cumulative usage factor

• Consideration of environmentally assisted fatigue (EAF) according to NUREG / CR-6909 and stratifi cation eff ects

Options

• Reassessment of past history based on existing I&C or recorded data combined with actual recording through FAMOSi measurements

Feedwater nozzle charging. Determination of temperature and stress distribution based on FAMOSi measurements

FAMOSi data acquisition unit

Temperature

Stress


• Accurate computation of fatigue thanks to local measurements

• Avoids replacement of costly components or helps to identify and optimize operating mechanisms that are unfavorable to fatigue sensitive locations

• Integration of the latest codes & standards into the computation methods to take into account stratifi cation or environmental assisted fatigue eff ects

• Easy real time assessment of stress and cumulated usage factor by using the Fast Fatigue Evaluation method of the FAMOSi software

• Possibility to re-evaluate the load history with reduced conservatism based on recorded data with the FAMOSi system

Fatigue Monitoring System – FAMOSi


FAMOSi software calculates the inner temperature and the stress history (green color) based on measured temperature (blue curve) to assess the cumulative usage factor

Typical local measurements points

AREVA References:

• FAMOSi is in operation at different types of reactors: PWR, HPWR, WER-PWR, BWR• Argentina, Belgium, Bulgaria, China, Finland, France, Germany, Netherlands, Russia, Slovakia, Spain, Switzerland


Integrated Procurement Solutions

Introducing AREVA’s New “Integrated Procurement Solutions” consisting of four

modules that can be provided separately or

as a total integrated solution for your sup-

ply chain demands. The scope of these four

modules will be customized based on the

customer needs and will include:

Risk-Informed Procurement• Perform all necessary PRA analysis (initial or confi rmatory) as required to implement a Graded Quality Assurance (GQA) program• Conduct customer inventory reviews based on criticality, usage, and Emergency Response (ER)• Provide Regulatory documentation (analysis and transmittals) for Licensee Application as required by 10CFR50.69. This scope of work includes SME and licensing support as requested• Identify all testing and/or analysis requirements needed to implement a Risk-Informed GQA program and procurement process• Monitor eff ectiveness of the implemented GQA program

Inventory Optimization and Warehousing• Provide consolidation and standardization program for customer inventory optimization• Provide Replacement Parts Equivalency Evalua- tions (RPEs) for safety-related or important to safety applications due to equipment obsolescence or model change• Create an “optimized inventory” based on 1) consolidation analysis 2) historical usage reviews 3) ER categorization 4) Critical Spare analysis 5) GQA program elements• Provide “targeted inventory services” – AREVA’s Nuclear Parts Center (NPC) provides warehousing services for selected equipment based on customer carrying costs and business needs. These services would include equipment storage, required instorage maintenance, records management and Quality Inspection problem resolution

Commercial Grade Dedication• Develop Commercial Grade Dedication (CGD) plans• Defi ne critical characteristics required to provide reasonable assurance• Approve and oversee tests/inspections/ analysis of critical characteristics• Create QA data package/dedication report and documentation of the results• Deliver dedication documentation and any components/equipment/specimens to the requesting project or customer

Component Testing and Qualifi cation (Technical Center)• Conduct all equipment qualifi cation and commercial grade dedication testing activities utilizing AREVA’s state-of-the-art Technical Center. The U.S. Technical Center off ers the following capabilities: 1) Tri-axial seismic test facility (shaker table) 2) Accelerated aging chamber(s) 3) Environmental test chamber(s) 4) Material property testing 5) Reverse engineering• Other AREVA facilities include – Richland Test facilities, Chemistry and Materials Center (with electron scanning microscope), Center for Advanced Engineering Research (collaborative arrangement), Cranberry Electrical Testing Center, the Mill Ridge Road Training Center and European Testing Facilities


Integrated Procurement Solutions


Why AREVA?

• Highly trained, experienced and qualified staff in Probabilistic Risk Analysis, Commercial Grade Dedication and Testing, Inventory Management and Control, Equipment Reliability, Purchasing and Quality Assurance• State-of-the-art testing and research facilities with plans for future growth• The U.S. Technical Center will directly apply their experience and database gained in supplying commercial-grade dedication and environmental qualification services for New Builds and other on-going major U.S. projects for the benefit of our customers• Dedicated core team of individuals focused on providing high-quality supply chain solutions in a cost-effective manner• AREVA is building this new product line from the ground up focused on customer value, scalability and process efficiency• Flexibility to quickly adapt to new regulations and post-Fukushima requirements

How will Integrated Procurement Solutions contribute to our customers’ drive for excellence?

• Increased site focus on risk significant Systems, Structures, and Components (SSCs)• Improved site safety culture• Reduced procurement costs due to SSC safety re-classifications/GQA program• Reduced carrying costs for SSCs through inventory optimization and targeted inventory services• Minimized use of multiple vendors and site staff to perform needed CGD, Environmental Quali- fication and associated testing – trusted, single Integrated solution provider• Reduced CGD costs associated with testing and analysis as a result of using industry-enveloping criteria, as opposed to site- or customer-specific criteria• Minimized impact of fraudulent/suspect pro- curements• Reduced Engineering time and costs associated with Replacement Parts Equivalency evaluations through economies of scale• Reduced potential for forced outages, delayed restarts or forced power reductions due to SSC availability or qualification issues• Program is modular and scalable – customer can move in finite steps, at their own pace and priority from CGD and testing to satisfying obsolescence and reliability issues to a fully implemented Risk-Informed Graded QA program


AREVA supplies solutions for power generation with less carbon. Its expertise and unwavering insistence on safety, security, transparency and ethics are setting the standard, and its responsible development is anchored in a process of continuous improvement.

Ranked fi rst in the global nuclear power industry, AREVA’s unique integrated off ering to utilities covers every stage of the fuel cycle, nuclear reactor design and construction, and related services. The group is also expanding its operations to renew-able energies – wind, solar, bioenergy, energy storage – to be one of the leaders in this sector worldwide.

With these two major off ers, AREVA’s 47,000 employees are helping to supply ever safer, cleaner and more economical energy to the greatest number of people.

www.areva.com

Copyright AREVA 2013

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