Coduri RCC-M Mai Pe Larg

Association Française pour les règles de conception, de construction

et de surveillance en exploitation des matériels des Chaudières Electro-Nucléaires

www.afcen.comFrench Association for Design, Construction and Surveillance Rules

of Nuclear Power Plant Components

AFCEN RCC/ETC and RSEA French set of consistent

Nuclear Codes & StandardsPh. MALOUINES Chairman of the RCC-M SubcommitteeJM. HAURE Chairman of the RCC-E SubcommitteeB. GAUTIER Chairman of the RCC-I SubcommitteeG. CHAIGNE Chairman of the RCC-C SubcommitteeC. PETESCH Chairman of the RCC-MRx SubcommitteeC. DUVAL Chairman of the RCC-G SubcommitteeM. CLEURENNEC Chairman of the RSE-M Subcommittee

Presentation prepared by : C. FAIDY - AFCEN – EDF – [email protected] of RCC-M, RSE-M and RCC-MRx Subcommittees

KEPIC – Week Conference on Codes & StandardsAugust 31- September 2, 2011, Jeju, Korea

Rev 1

KEPIC - Week Conference - August 31, September 2, 2011, Jeju, Korea 2

Content

ü Introduction to AFCENüScope and general overview

ØRCC-E electrical componentsØRCC-I / ETC-F fire protectionØRCC-C fuel assembliesØRCC-G / ETC-C civil worksØRCC-M design/ construction mechanical componentsØRCC-MRx high temperature & experimental reactorsØRSE-M operation for mechanical components

üConclusion


RCC : Design and ConstructionETC: EPR version of RCC

started with French-German cooperationRSE : Surveillance-Inspection in operation

RCC-MRxHT/Irr. Mechanical

Components

RCC-C Fuel Assemblies

ETC-CCivil Engineering

Structures

RCC-E Electrical – I&C

Systems and components

RCC-MPWR Mechanical

components

ETC-FFire protection

RSE-MPWR Mechanical

componentsBOARD &

Executive Committee

Editorial committeeTraining committee

General Assembly of AFCEN Members

AFCEN

www.afcen.com


Structure of Afcen BOARD

RCC-C Subcommittee

RCC-M Subcommittee

Design

Materials

Technology

Examination

RCC-E Subcommittee

General

Design

Software

Qualification

Examination

Installations

RCC-MR Subcommittee

General

Design

Materials

Fabrication

RCC-I Subcommittee

General

RCC-G Subcommittee

Geotechnics soils and

buried struct.

Concrete

Containment & Pools liners

Metal frames

Test and monitoring

General

Executive Committee

Editorial committeeTraining committee

7 Subcommittees

26 WG's

RSE-M Subcommittee

Flaw Analysis

NDE

Inspection

Repair

General


Procedure for code improvements

Modification request from any user or AFCEN SC/WG members

Instruction by dedicated WG

Approval by RCC/ETC-RSE subcommittee

Approval by Editorial Committee

Approval by General Secretary by delegation of the Board

Annual issuing of RCC/ETC-RSE Addendum

Possible request for complementary instruction

Preparation of Modification Sheet by RCC/ETC-RSE Technical Secretary

New initiative:Code Case possibilities


Working methods

üCommittee membersØHistory

• From 1980: Experts from founding members : AREVA and EDF• Since 2008 : + CEA• Since 2009: + Experts from independent notified bodies• Since 2010: + AFCEN company members

ØEach member can contribute to particular WGs + Invited experts

üThe "consensus" approachØ"Consensus" rule

• A consensus is considered as being reached : if no SC official member expresses an explicit disagreement with corresponding justification and, if it's possible, the modification proposed

ØConsensus is recognized by the signature of two SC representative members (Manufacturer/Utility)

Quality Management and Safety

ü AFCEN Organization was operated with EN ISO 9001:1995 principles of Quality Assurance

ü Now AFCEN has switched to ISO 9001 2008 and main requirements of AIEA GS-R-3 2006 «The Management System for Facilities and Activities »

ü Each RCC of AFCEN is based on a common approach of Quality Management System imposes to manufacturers, with variations considering nature of material: mechanical, electrical, civil works, in-service

ü AFCEN wants to provide in RCCs an practical achievement of the link between Quality Management imposed by RCC and Safety requirements recommended by AIEA, as recognized by many Safety Authorities in their regulations.


AFCEN and French Safety Authorities

ü 2 sets of French Safety Authorities for NPPs (DCN and DEP): Ø 1 nuclear law for all Nuclear Installation: TSN law (to be published soon)Ø Safety Analysis in accordance with Safety Analysis ReportØ Pressure Equipments: classified/not classified, nuclear/non-nuclear

• Manufacturer responsibility to be in accordance with law, decrees, orders• Conformity assessment by Nuclear or Non-Nuclear Notified bodies

Ø Utility is responsible of Safety and OperationØ No formal agreements of French C&S by Safety Authorities

• Only partial and "unformal" C&S evaluations versus RegulationØ No "strict" licensing procedure è pre-design analyses and PSAR

ü Nuclear PE have to fulfill 1st non-nuclear PE requirements (PED)Ø Hazard analysis, design, justification of design, fabrication, examination,

pressure test, overpressure protection, instruction notice, conformity assessment, including ageing and operation (radioprotection)

Ø All hypotheses from Utilities needed by Manufacturer, to be transferredKEPIC - Week Conference - August 31, September 2, 2011, Jeju, Korea 8

AFCEN certified training courses


[email protected]

AIB-Vinçotte [email protected]

[email protected]

MJG consulting,

[email protected]

[email protected]

[email protected]

Subcommittee [email protected]


New context è new needsü International cooperation for new reactor development

ØEPRTM in French German context in the 90s ® ETC-MØATMEA developed between AREVA and MHI ® under French SA review

ü Changes in European and French regulationsØIssuing of an European PED (Pressure Equipment Directive for non-nuclear)ØIssuing of new French Nuclear Pressure Equipment Order in December 2005ØA "global" updated French nuclear law is in preparation: TSN law, including "transparence"

ü Information exchange initiatives between Regulators for harmonizationØMDEP: Multinational Design Evaluation ProgramØSDO group: Standards Development Organization

ü New needsØNeed for part procurement compatible with various applications in different countriesØSome convergence between nuclear and non nuclear practicesØEvolutions of practices and tools (construction, examination, analyses)ØNew manufacturers, new designers, new surveillance people, new utility engineers…

ü International usersØNew users : India, China and many EC countries (like UK, Germany, Finland… and EC

Research centers)ØFrench, English, Chinese official version (Russian of a previous edition)ØDifferent regulations are considered





RCC-EDesign and Construction Rules for

Electrical Components of PWR Nuclear Islands

ICONE 18-30369

JM Haure – AFCEN [email protected]


RCC-E General

ü Relationships between Safety Analyses Report and:Ø system and installation engineeringØ off-site and on-site sources

requirements Ø periodic tests and permanent

monitoring requirements to guarantee the safety function availability

Ø I&C architecture and Human Machine Interfaces ,

Ø digital I&C systems requirements

ü Establishing qualification to ambience conditions: normal and mild conditions and harsh and severe accident conditions Ø based on set of ambience defined as

a combination of equipment mission time, and normal and abnormal conditions

Ø High and Low frequencies disturbances protections (Lightning, GSM, DECT, WiFi)

Ø Project data used by any supplier or designer, separation requirements and isolation and decoupling design solutions

Ø Electrical enclosures design requirements.





RCC-I / ETC-FDesign and Construction Rules

for Fire Protection of PWR Nuclear Islands

B. Gautier– AFCEN [email protected]


RCC-I GeneralüScope : requirements to protect against internal fire technical

buildingsØEnsure safety of people/ personalØEnsure protection of safety functions/ systemsØLimit deterioration of equipments which may result in long term un-availability

(all rooms with more than 400 MJ/m2)

üBasis for Design, Construction and InstallationØPreventionØDetectionØFire fighting

üFrench applicationØapplied in France to PWR 1400 MW N4 NPPs (1997) and approved by Safety AuthorityØretrofitted application to all French plants

ü 4 parts :ØPrincipal definitions of the terms used in the RCC-IØFundamental basic rules applicableØFire protection of buildings and equipmentsØQuality Assurance

RCC-I historyü 1977 First rules for CPY

ü 1980 Upgraded for P4

ü 1982 first RCC-I rev A for P ’4, approved by SA

ü 1983 RCC-I rev B, applicable to Daya Bay

ü 1987 RCC-I (rev2) for N4 approved by SA

ü 1993 RCC-I (rev3)

ü 1997 RCC-I (rev4) applicable to N4

ü 1997 ETC-F applicable for EPR



. Mechanical Friction (17%)

. Electrical Short Cut (50%). During Welding (20%). Human Errors(13%)

Solids : . Electrical cables

. Electrical components. . Motors/filters

. Coton (clothes), papers Liquids :

. Oil, fuel, solventsGaz :

. Hydrogen

Energy

CombustibleCombustiveOxygen content in air

(50%)

(2%)

(24%)(24%)

% : starting fire contribution on NPPs

RCC-I : Fire Events

RCC-I: Periodic tests (as an example)

ü Doors:Ø Operation + inspection of components providing fire resistance

ü Penetrations: Ø Visual inspection

ü Dampers: Ø Visual inspection + operation

ü Envelope: Ø Visual inspection

ü Fire station: Ø Visual inspection + operation

ü Fixed spray water fire extinguishing system: Ø Visual inspection + operation of active devices other than sprinklers ;

Measurement of flowrate-pressureü Detection system:

Ø Visual inspection + operation by simulated fireKEPIC - Week Conference - August 31, September 2, 2011, Jeju, Korea 17





RCC-CDesign and Construction Rules

for PWR Fuel Assemblies

G. CHAIGNE – AFCEN [email protected]


RCC-C: Scope / ContentüFuel assemblies and core components

(fuel, RCCA, absorber rods…)

üTechnical rules for design, manufacturing and inspection

üApply by all fuel assembly suppliers for all French NPPs

üContent :ØGeneral provisionsØProduct and part characteristicsØFabrication and related testing and inspectionØTables of inspection requirementsØInspection methodsØFuel system design


RCC-C : Chapter 1 General Provision

ü Purposeü Responsibilitiesü Documentsü Equipments subjected

Ø Fuel assembliesØ Core components, like: rod cluster control

assemblies, burnable poison rod assemblies, source assemblies and thimble plug assemblies

ü QA requirements


RCC-C Chapter 2 : Product and Parts characteristics

ü General requirementsØ QualificationØ Lot definition (Zr tubes, fuel pellets,

strip)

ü Requirements for products and partsØ ElaborationØ Chemical compositionØ CorrosionØ Physical propertiesØ SoundnessØ Dimensional

ü Requirements applicability

Ø Semi-finished components• Zr alloys products (bar stock, strip)• SS long and flat products• Ni-Cr-Fe alloys products

Ø Finished components• Zr tubes• SS tubes and castings• Fissile materials (UO2, MOX…)• Poisons and sources :

– Ag-In-Cd bars, – borosilicates glass tubes, – Sb-Be pellets


RCC-C: Fabrication - Examination

ü Chapter 3 : Fabrication, testing, inspection

ü Special processØ PelletizingØ WeldingØ BrazingØ CleanlinessØ Handling, shipment, storage

ü Chapter 4 : Table of inspectionsü Items :

Ø Fuel rodsØ GridsØ Bottom and top fittingsØ Skeleton assembliesØ Fuel assembliesØ Rod cluster control assembliesØ Burnable poison assembliesØ Neutron source assembliesØ Fuel assemblies with core

components


RCC-C Examination Methods

ü Chapter 5 : Inspection methodsü Inspection methods are:

Ø RadiographicØ UltrasonicØ Sipping testsØ Helium leak testØ Fuel rod inspectionØ Fuel pellet hydrogen and moisture

contentsØ Statistical inspectionØ Appendix : inspector certification

RCC-C Design rulesü Chapter 6 : Designü Requirements

Ø Description of fuel systemØ In-reactor operating environment

• Coolant pressure, temp, flow rate, chemistry

• Neutron flux• Compatibility with core internals

Ø General design and safety bases• Operating conditions: normal, upset,

emergency, faulted• Under normal operating conditions

– Integrity – Fuel array geometry

• Under accidental conditions– No loss of functions: control rods insertion,

fuel array coolability

Ø Fuel assembly• Functional requirements

– Axial and radial fuel geometry– Coolant flowrate– Leaktigthness– Axial and radial expansion

• Loads– Non operational loads (shipment,

handling…)– Operational loads– Accidental loads

Ø Fuel rod• Design and safety basis

– Rod integrity, critical heat flux, melting…• Design requirements

– Clad overheating, fuel melting– Buckling, internal pressure– Corrosion, hydriding…

Ø Core component: different rodsØ Design justification methods

• Analytical predictions• Experimental checks

Ø AppendicesKEPIC - Week Conference - August 31, September 2, 2011, Jeju, Korea 24

Last version published in 2005





RCC-G / ETC-C

Design and Construction Rules for Civil Works

of PWR Nuclear Islands

C. DUVAL – AFCEN [email protected]

SMIRT20-2943


ETC-C Background

ü « ETC » codes = EPR Technical CodesØ Before EPR: RCC-GØ Specific Nuclear design codes initially developed by EDF and German Utilities

Ø Assessed by French and UK Safety Authorities

ü ETC-C Objectives Ø ETC-C describes the principles and requirements for safety, serviceability and

durability conditions of concrete and steelworks structures, together with specific provisions for safety-classified buildings of EPR

Ø Specific design code for EPR

ü Historical basis of ETC-CØ ETC-C inherits the experience of RCC-G (French design & construction code)

Ø ETC-C collects the design experience feedback of a number of pre-stressed containments and structures which were erected using the same or very similar safety concept

ETC-C Background and Eurocodes

ü ETC-C characteristicsØ All the safety requirements are considered at the design level for each

building of the Nuclear Island : actions and combination of actionsØ ETC-C is based on the limit state concept as developed in EUROCODES

(EN1990, EN1991, EN1992 and EN1993) and adapted to our needsØ Design situations are distinguished in compliance with Eurocode Safety

Concept• Partial safety factors for normal operation• EPR requirements for accidental situations



ETC-C - Safety objectives


ETC-C – From safety objectivesto design conditions

ETC-C – Functional Capabilityof structures

ü AB: serviceability of concrete structures – behavior not modifiedü RB: capacity of the concrete structure to withstand applied loading

(permanent deformation with stability fulfillment) and integrity of connected equipments

ü AM: serviceability of steel structures, including integrity- no tearing of cladding but without associated leak criteria

ü RM: structural capacity of penetrations in accidental conditions-permanent deformation but penetration functionality assured

ü C: capacity to contain radioactive products: mainly inner containment and associated to leak criteria

ü E: leaktigthness of fluid containers- integrity with possible permanent deformation


ETC-C: Application to Reactor Building



ETC-C- Severe accidentdesign implications


ETC-C : Current Content1 Part I : DESIGN CRITERIA 2 Part II : CONSTRUCTION

1.1 SCOPE 2.0 GENERAL PRINCIPLES

1.2 DEFINITION OF ACTIONS AND LOAD COMBINATION

2.1 EARTHWORKS AND SOIL TREATMENTS

1.3 GENERAL RULES FOR THE SAFETY RELATED CONCRETE STRUCTURES

2.2 CONCRETES

1.4 METAL PARTS INVOLVED IN CONTAINMENT LEAKTIGHTNESS

2.3 FACING AND FORMS

1.5 STEEL LINER FOR POOL 2.4 REINFORCEMENTS FOR REINFORCED CONCRETE1.6 STRUCTURAL STEEL WORKS 2.5 PRESTRESSING SYSTEM

1.7 INTERFACE EQUIPMENTS BETWEEN ANCHORS AND CONCRETE

2.6 PREFABRICATION

2.7 LEAKTIGHT METAL PARTS ON CONTAINMENTS

2.8 METAL ELEMENTS INCORPORATED INTO THE CONCRETE

1.A SEISMIC ANALYSIS 2.9 WATERTIGHT METAL LINER

1.B CREEP AND SHRINKAGE STRAIN FOR CONTAINMENT

2.10 STRUCTURAL STEEL WORK

1.C SIMPLIFY METHOD FOR AIRCRAFT IMPACT VERIFICATION

2.11 BURIED SAFETY-CLASSIFIED CONDUITS

1.D PENETRATIONS OF REINFORCED AND PRESTRESSED CONCRETE SLABS

2.12 FILLING OF JOINTS

1.E ANALYSIS TERMS FOR CONTAINMENT PENETRATION SLEEVES

2.13 TOPOGRAPHY, TOLERANCES AND SOUNDING

1.FCALCULATION OF STATIC EQUIVALENT FORCES TO CERTAIN ACCIDENTAL ACTIONS

Appendix 1 TOLERANCES

Addendum AD1

ADDITIONAL DOCUMENTS REFERED IN PART I

Addendum AD2 APPLICABLE DOCUMENTS TO PART 2

3 Part III : LEAK AND RESISTANCE TESTS AND CONTAINMENT MONITORING

3.1 TERMINOLOGY3.2 GENERAL PROVISION3.3 LEAK TESTS3.4 RESISTANCE TESTS

Appendices

ETC-C Future developments

ü Incorporate modificationsü Associate a lot of industrial companiesü Promote the ETC-C

ü Last version : 2010(include FA3 experience)






RCC-M

Design and Construction Rules for Mechanical Components of PWR

Nuclear Islands

P. Malouines– AFCEN [email protected]

C. FAIDY – AFCEN [email protected] 18-29773

PVP2011-57069PVP2011-58061


RCC-M: How the RCC-M was initiated

US regulations, codes and standards, industry practices for

the general design/fabrication of systems and components

Initial pragmatic approach for RCC-M setting

French and European regulations and industrial practices

for the general design/fabrication of systems and components

PWR technology progressively adapted/

improved to French industrial and regulatory

context

RCC-M "photography" of 1980 practices

-1st PWR plant in operation 1977- 1980 : 20 more to be constructed

- in fact 58 plants from 1977 to 2000

RCC-M: How the RCC-M was initiated

ü ConsequentlyØ RCC-M is "prescriptive" for LWR application, mainly PWRs

• Limited number of materials• More detailed fatigue rules• Limited fabrication and welding possibilities• Cleanliness consideration• More stringent examination acceptance criteria• More precise appendices

Ø But in any case, alternative proposals can be proposed with equivalency justifications

Ø Mainly tables B-C-D 2000 need to be adapted to new project: Material and Technical Specification for each components



Section 1 Nuclear Island Section IIIComponents

A General requirements NCAB Class 1 components NBC Class 2 components NCD Class 3 components NDE Small components NoneG Core support structures NGH Supports NFJ Storage tanks NC/ND 3800-3900P Containment penetrations NEZ Technical appendices Appendices

Section 2 Materials Section IISection 3 Examination methods Section VSection 4 Welding Section IX : qualificationsSection 5 Fabrication Various parts of Section III

Content and Structure (1/2)

RCC-M Code ASME Code


Content and Structure (2/2)

1000 General. Scope. Documentation. Identification

2000 Materials. Prevention of corrosion. Applicable procurement specification

3000 Design. Sizing. Analysis

4000 Fabrication. Manufacturing and

examination

5000 Pressure tests6000 Overpressure protection

Subsection A General

Section II Materials

Subsection Z Appendices

Section III Examination

Section IV Welding

Section V Fabrication

Subs. B, C, D for RCC-M 1-2-3

04 3 2

0

18

8

77

118 9

19

0

1316

59

0

6

14

30

0

9

2022

1

30

22

34

0

10

20

30

40

50

60

70

80

90

A1-same A2-equ. B1-diff. Scope B2-diff. techn.

Num

ber o

f par

agra

phs

Comparison ASME III NB - RCCM I B

NB 1000

NB 2000

NB 3000

NB 4000

NB 5000

NB 6000

NB 7000


Article A1-same A2-equ. Total A B1-diff. Scope

B2-diff. techn. Total B Total

NB 1000 0 4 4 3 2 5 9NB 2000 0 18 18 8 77 85 103NB 3000 11 8 19 9 19 28 47NB 4000 0 13 13 16 59 75 88NB 5000 0 6 6 14 30 44 50NB 6000 0 9 9 20 22 42 51NB 7000 1 30 31 22 34 56 87

Total 12 88 100 92 243 335 435% 2,8 20,2 23,0 21,1 55,9 77,0 100,0

A1 sameA2 equivalent

B1 different scopeB2 technical difference


Examples of Technical evolutions (1/2)

ü Design and analysisØ Clarification of the relations between plant and component conditions

associated to criteria levelsØ Improvement of stress classification for dynamic loadsØ Updating of fast fracture and fatigue prevention rules

Ø Updating of pressure test conditions: similar to ASME CodeØ Introduction of new chapters 6000 on overpressure protection

• Scope similar to ASME corresponding sections• Reference to EN ISO 4126 for design specifications and tests• Determination of relief capacity according to ASME or EN ISO 4126

Ø Improvement on appendix Z.II on experimental analyses

Ø Change on class2/3 allowable stresses determination• Su/4 replaced by Su/3.5


Example of Technical evolutions (2/2)

ü Fabrication and examinationØ Self-contained RCC-M prescriptions replaced by a reference to ISO and EN

standards with complements• Except for aspects not currently covered by standards

Ø S.8000 on hard-facing revised to cover Cobalt-free processes• Self-contained provisions in the code

Ø Consideration of standards evolutions• Grouping of low-alloy steel grades• Range of validity of welders qualifications for nozzles welds

Ø Updating following construction experience• Flexibility on Iron content for hard-facing, subject to Contractor approval• Repair of automatic welds (root passes may be kept)

Ø NDE techniques, standards and criteria adapted• Introduction of "Tandem" US technique• Conditions of radiographic examination of large thickness


RCC-M Future evolutions

ü Code conformance with different regulation under evaluationØ Possible modification sheets on ZZ and ZY

ü Integration of French (RCCM) – German (KTA) discussionsØ Design aspects not yet fully integrated

ü Integration of technical developmentsØ New integrated parts definitionØ Examination tools and criteria

• Multi-elements and TOFD techniques• Numerical radiography

ü Integration of R&D resultsØ Consideration of environment effects in fatigue evaluations

• Non-mandatory appendix ZL under evaluation

ü Need for convergence of some practices• Between different nuclear and non-nuclear codes• At the international level





RCC-MR / RCC-MRx

Design and Construction Rules for Mechanical Components of

High Temperature Reactors and Fusion Reactor

C. Petesch – AFCEN [email protected]

C. FAIDY – AFCEN [email protected]

PVP2011-57614


RCC-MRx: history and scope

ü RCC-MRx : RCC-MR + RCC-MX to cover High Temperature, Experimental and Fusion Reactors ØRCC-MR : AFCEN + CEA since 1978 for LMFBR

ØRCC-MX : CEA + AREVA since 1988 for experimental reactors

Ø2010 draft edition available and under improvement at EC level (8 different countries sign CWA)

Ø1st published edition planned for end 2012ü Scope : mechanical components of HT/HI reactors

ØImportant for safety and availability

Øwith particular leak tightness requirements, partitioning and baffles, guidance and support functions

Øas vessels, pumps, valves, piping, bellows, box structures or heat exchangers and their supports, generally low pressure and thin shells, but not only…

ü RCC-MRx single document : design and construction of reactor components and the associated auxiliaries, examination and handling mechanisms and irradiation devices.

ü 3 classes of design and construction proposed : N1MRx, N2MRx and N3MRx correspond to decreasing levels of analysis complexity with larger safety factors and less verification

Where RCCMRx has been used ?

ü In FranceØ PhenixØ SuperphenixØ CEA experimental reactorsØ RJH (Jules Horowitz experimental reactor)Ø For all spare parts and replaced componentsØ For ASTRID GEN4 projectØ For ITERØ Continuously used since end of 1980

ü On international projectsØ European Fast Breeder Reactor (EFR)Ø European experimental reactorsØ European GEN4 reactorsØ Indian HTR



RCC-MRx table of contentRCC-MRx AFCEN RCC-MRx Code ASME Nuclear Boiler and

Pressure Vessel Code

Section I General provisions Section III Subsection NCA

Section II Additional requirements and special instructions

Section III Rules for nuclear installation mechanical components Section III Division 1

Section III Tome 1 Design and construction rules Section III Division 1

Subsection A General provisions for Section III Subsection NA

Subsection B Class 1 reactor components, its auxiliary systems and supports Subsection NB + NF + NG + NH

Subsection C Class 2 reactor components, its auxiliary systems and supports Subsection NC + NF + NG + NH

Subsection D Class 3 reactor components, its auxiliary systems and supports Subsection ND + NF

Subsection K Examination, handling or drive mechanisms

Subsection L Irradiation devices

Technical appendices

- A3 / A9 : Properties groups for base metal and welded joints

- A16 : guide for prevention of fast rupture, LBB and defect assessment

- Other technical appendicies

Section III Tome 2 Part and product procurement specifications Section II ( Nx 2000 )

Section III Tome 3 Destructive tests and non-destructive examination methods Section V ( Nx 5000 )

Section III Tome 4 Welding Section IX ( Nx 4000 )

Section III Tome 5 Manufacturing operations other than welding ( Nx 4000 )

Subsection Z

RCC-MRx: An original aspects


Negligible creep Significant creep

Negligible irradiation

RB 3251.1 (Type P damages)

RB 3252.1(Type P damages)

RB 3261.1 (type S damages)

RB 3262.1 (Type S damages)

Significant irradiation

RB 3251.2 (Type P damages)

RB 3252.2(Type P damages)




RCC-MRx : Other examplesof original aspects

ü Cover mechanical structures close to neutron sources with significant thermal load under creep conditions

ü Consequently rules for irradiated devices are proposedü A broad choice of materials, such as aluminum or zirconiumü Class 2 rules are closed to class 1 rules (included creep),

class 3 rules are closed to non-nuclear rules (no creep)ü A section for examination and handling mechanisms

(subsection K)ü Use a maximum of international standards : EN or ISOü Particular rules are proposed for ITER Vacuum Vesselü Has been selected recently as the European Code for HT

reactors (GEN 4) è CWA: CEN Workshop Agreementü Is used to-day for Indian HT reactors





RSE-M

In Service Inspection Rules for Mechanical Components of PWR Nuclear Islands

M. CLEURENNEC – AFCEN EDF [email protected]

C. FAIDY – AFCEN [email protected]


RSE-M : scope / content

ü 5 sectionsØ General rules Section

AØ Particular rules for class 1 Section

BØ Particular rules for class 2 Section

CØ Particular rules for class 3 Section

DØ Mandatory and non-mandatory

Appendices

ü Each section A-B-C-DØ General and scopeØ Qualification renewal – Hydrostatic

testsØ In-service inspectionØ Non-destructive examinationsØ Indication and flaw evaluationØ Surveillance in operationØ Maintenance operationsØ Quality System

ü ScopeØ Rules for ISI , NDE, qualification renewal and hydrostatic testsØ Rules for indication and flaw assessmentØ Rules for surveillance in operationØ Rules for maintenance : repairs, replacements, modifications


RSE-M : General content

Tome I Volume AGeneral rulesVolume BParticular rules for class 1 equipmentsVolume CParticular rules for class 2 equipmentsVolume D Particular rules for class 3 equipments

Tome IIAnnexe 1.0 Annex statusAnnexe 1.1GlossaryAnnexe 1.2List of systems with nuclear pressure equipments

(outside of Primary and Secondary systems)

Annexe 1.3Supplementary list of Codes and StandardsAnnexe 1.4How to apply RCC-MAnnexe 1.5Consistent group of equipments or situationsAnnexe 1.6 Documents- Typical drawingsAnnexe 1.7Check sample equipmentsAnnexe 1.8Risk category for regulated equipments

Annexe 1.9Classification of Nuclear Pressure Equipments

Annexe 1.10Supplement concerningPrimary and Secondary Systems limits

Annexe 2.1Protection and Mitigation of ISI personal during hydrostatic test pressure

Annexe 3.1Tables of visits and associated figures (ref. to Tome III)

Annexe 3.2 How to implement Inspection plan for Nuclear Pressure Equipments (ref. to Tome III)

Annexe 4.1 Surface finish arrangementsAnnexe 4.2 Products and Materials usable on NPPAnnexe 4.3 Qualification methodologyAnnexe 4.4 NDE, surveillance and inspection methodesAnnexe 5.1 Defect geometry for analysisAnnexe 5.2 Acceptable standardsAnnexe 5.3 Fatigue and Plastic instability analysisAnnexe 5.4 Analytical Methodes for K and J evaluation

Annexe 5.5 Allowable plan defect- Mechanical acceptability criteria

Annexe 5.6 Material PropertiesAnnexe 5.7 Specific analysis of volumetrical defectAnnexe 5.8 General principles to develop partial safety

factorsAnnexe 6 not usedAnnexe 7 not used

Annexe 8.1 Corrective maintenance methodesAnnexe 8.2 NDE Qualification for repair

Annexe 9 not usedTome III

Annexe 3.1 Tables of visits and associated figuresAnnexe 3.2 How to implement Inspection plan for

Nuclear Pressure Equipments

RSEM: flaw evaluation handbook

ü Extremely large and validated by more than 200 FEAü K and J evaluation schemesü For K

Ø crack depth to thickness ratio: a/t = 0 ; 0.1 ; 0.2 ; 0.4 ; 0.6 ; 0.8Ø crack depth versus crack length aspect ratio a/c = 1 ; 1/2 ; 1/4 ; 1/8 ; 1/16 ; 0Ø crack depth versus crack length aspect ratioØ thickness to radius ratio of the cylinder

t/ri = 1 ; 1/2 ; 1/5 ; 1/10 ; 1/20 ; 1/40 ; 1/80 ; 0

ü For J through reference stress methodesØ Plate, pipe, elbow, thickness variationØ Mechanical, thermal, thermal + mechanical loadsØ Detailed handbook of limit load formulae

ü All the material properties needed, including ageing effects



RSEM : future plan

ü RSE-M must change in the long termØ More internationalØ Rules independent of country national regulationØ Usable by different plant operatorsØ Including rules under operator responsibility

ü RSE-M subcommittee are working on these new directionsØ Component classificationØ ISI / Modification / Repair rules

ü RSEM publicationØ Last one: 2010Ø New international version available within 3 to 4 years


Conclusions (1/2)

ü RCC/ETC-RSE are continuously improved with experience of users and R&D results, including ageing considerations from design level

ü RCC/ETC-RSE are important tool to fulfill the regulatory requirements of different countries

ü RCC/ETC-RSE will continue a modernization process in accordance with State of the Art and Projects needs (EPR – HTR – Experimental Reactors)

ü RCC/ETC-RSE are open for harmonization process with other international Codes and Standards (MDEP – CSWG – SDOs or direct MOU)

ü RCC/ETC-RSE are important tools for new generation of nuclear engineers, they have to continuously improve their scope, their usability and background documents.


Conclusions (2/2)

ü A complete set of consistent RCC/ETC and RSE is available for :ØDesign and Construction of PWRs and HT reactorsØOperation of PWRs

ü AFCEN certified training courses are now availableü New actors will be associated to the development of these Codes,

as French industry and notified bodies, but also international organizations and companies, including UK, China, India…

ü Now, all potential users are welcome to improve RCC-ETC through:ØContribution to the different AFCEN-RCCM working groupsØModification / Interpretation inquiries (sheet available on AFCEN website)

ØA new website is in progress: www.afcen.comü Reference RCC-ETC and RSE are to-day available in French, English

and Chinese


www.afcen.com