PRESENTATION OF THE 2014 REVISIONS TO THE RCC-M CODE

Proceedings of the ASME 2014 Pressure Vessels & Piping Conference PVP2014 July 20-24, 2014, Anaheim, California, USA PVP2014-28501 PRESENTATION OF THE 2014 REVISIONS TO THE RCC-M CODE Philippe Malouines AREVA Senior Expert Chairman of the RCC-M Subcommittee of AFCEN 1, place Jean Millier 92084 Paris La Défense CEDEX-France philippe.malouines@areva.com ABSTRACT The paper describes the general approach followed by AFCEN, the French Society for Codified Rules for Design, Construction and In-Service Inspection of Nuclear Island Components, from the technical and organizational points of view. The RCC-M code, reissued in 2012 and modified with addenda in 2013 and 2014, is presented. The main new topics of activity of the RCC-M Subcommittee are considered: conformity with regulation(s), use of International Standards, equivalence with other codes and harmonization, and new requirements for the quality management system. The paper highlights how industrial experience is currently being integrated into the RCC-M code, and how the code is evolving to take into account the enlargement of the AFCEN Membership, new AFCEN organization rules, and the international environment, and best practices. The processes for dealing with requests for modifications and interpretations are described. INTRODUCTION The creation of AFCEN, the French organization for codifying the design, construction and in-service inspection of nuclear island components, and the publication of first RCC-M code for the design and construction of mechanical components in 1981 is linked to the history of the French Nuclear Industry. In the context of AFCEN s enlargement in February 2010, the first part of this paper describes the evolution of the AFCEN organization based on its new status and internal rules and quality system. The effect of these new rules on the activity of the RCC- M Subcommittee and Working Groups is discussed. The second part of this paper highlights the main changes introduced in the 2012 edition and 2013 addenda leading to the 2014 RCC-M code. HISTORICAL CONTEXT LEADING TO AFCEN When the French government decided to launch a large nuclear program, in the context of the first petroleum crises in the 1970 s, the decision was taken to follow American rules for design and to meet French and European standards for procurement, manufacturing and examination. 1 Copyright 2014 by ASME

The first three loop and four loop (P4) plants were built according to this approach, with many adaptations for practical reasons and as a result of discussions to agree on practice consistent with the French Safety Authority and Utility EDF. This practice was then proposed for overseas applications, in particular the South African Koeberg plant. It appeared that this approach was difficult to justify in front of overseas clients and authorities, and that the elements of this practice should be integrated in a consistent set of codes for further contracts. The leading companies to set the code rules were the Contractors Framatome and Novatome (both since integrated in Areva), and the Utility EDF. Component manufacturers were associated to provide inputs or advice but were not involved in the decision-making process at these times. The first RCC-M code was obtained in 1979 and formed the contractual basis of the second set of four loops plants (called P'4). When all the conditions were met for creating new codes, it was decided to create a specific organization to manage and develop codes for nuclear power plant that was not involved in contractual relationships. Thus AFCEN was created on 19 October, 1980. These arrangements led to Working Groups reviewing actual and current practices and developments with the aim of drafting rules which could be applied without exceptions. The rules needed to be sufficiently precise so as to present no risks of differing interpretations and enable high quality to be achieved at reasonable cost. Groups chaired by a contractor and utility representatives were asked to reach a technical consensus on these grounds. In order to reconcile differences of opinion, a "Resolution" Committee was established. After the creation of AFCEN on October 19, 1980, the Resolution Committee became the RCC-M Sub-Committee. An Editing Committee was soon established to harmonize developments of the further codes to be issued by AFCEN. Following the creation of AFCEN, the RCC-M code rules were developed jointly by EDF and Framatome. They were issued as the 1981 RCC-M edition including the June 1981 addendum, and applied to the Korean Ulchin project. Successive editions of the RCC-M followed: 1983, 1984 (addendum referred to the N4 series contract), 1985 (applied to the Chinese Daya Bay 1 and 2 contracts), 1988, 1993, 1994 (addendum referred to Ling Ao 1 and 2 contracts), 2000, 2002 (addendum applied to the Finland OL3 project), and 2007 applied to the Flamanville 3 and Taishan 1-2 EPR TM projects. DEVELOPMENT OF AFCEN The founders of AFCEN worked together in many applications of the code, but one needed a special agreement: that was the development of EPR TM, for which a specific partnership was established with German nuclear companies and the French/German Authority for the safety assessment of the EPR TM. In 1997 the European Pressure Equipment Directive (PED) n 97/23/EC [1] came into force. Due to the exclusion of nuclear pressure equipment from the scope of the PED, French Regulators completed the enactment of the PED in France [2], by a specific Order dated December 12 th, 2005 called ESPN Order [3]. Later, the French Parliament voted a law in June 2006, to create an independent structure acting as a Nuclear Safety Agency (ASN), and a law that imposes an objective of Transparency in Nuclear Safety. In this context, it was important for AFCEN to demonstrate compliance with the new regulatory framework (ESPN Order [3]) and to propose rules so that any utility or supplier to meet the safety requirements in full transparency. Now, AFCEN has the status, and internal regulations, of an open association of legal entities ( Members under French law). The Members are companies and other entities that have an interest in developing or applying the AFCEN codes, but exclude regulatory authorities. Representatives of Members sit on various committees and subcommittees: see organization chart and subcommittees scope in Table 1. The status of AFCEN and its internal rules were recognized under French Law 1901 concerning 2 Copyright 2014 by ASME

Associations in February 2010. In February 2011, quality management based on NF EN IS0 9001: 1995 was replaced with the requirements of NF EN ISO 9001:2008 and some requirements of Nuclear Management System of IAEA GS-R-3:2006[4]. AFCEN has obtained NF EN ISO 9001 2008 certification in December 2013 from Bureau-Veritas Consulting. AFCEN COMMITTEES Reporting the main Board of Governors of AFCEN are the following committees. The Training Committee determines how training courses on the codes can be delivered and by whom, and the validation of course materials by AFCEN. The Editing Committee coordinates the publication of the AFCEN codes, reviews them, and defines actions or scopes common to all the codes. As an example, quality assurance and safety approach are covered on the same basis for each code. The Quality Manager leads the implementation of quality policy defined by Chairperson and Board of Governors. This policy is presently based on ISO 9001 2008 and main requirements of IAEA GS-R-3 2006[4]. Sub-Committees (see Table 1 enclosed): each Subcommittee is in charge of one set of code rules relating to a specific part of the nuclear island, as indicated in the bottom of Table 1. For example, RCC-M has its own Sub Committee. AFCEN does not codify items or services which are not part of the nuclear island. Working groups are organized by each Sub- Committee on specific technical topics and operate within terms of reference set by the Sub Committee and in the framework of objectives of the common AFCEN quality manual and processes. External User Groups: AFCEN has Framework Agreements with different entities to co-ordinate interactions with Users of the codes who may choose not to become Members. Within Europe by 2014 AFCEN has established three Framework Agreements, including one on RCC-M as well as those signed 4 years ago on RCC-MRx. In UK, AFCEN has a Framework Agreement with The Welding Institute (TWI). TWI convenes a meeting of UK suppliers using the RCC-M code and prepares and communicates to the RCC-M Subcommittee Requests for Modification and Interpretation in adequate form. This facilitates the work of assessment of the RCC-M Subcommittee. In China, AFCEN has signed a Memorandum of Understanding with the China National Nuclear Cooperation and the China Guangdong Nuclear Power Holding Corporation. These companies organize meetings with RCC-M Users in China, with AFCEN experts delegated to transfer to the Sub Committee Modification and Interpretation Requests in French or English, and to ensure that the Sub Committee deals with these in a timely fashion. RCC-M CODE DEVELOPMENT In general, the current process for RCC-M code development and updating remains consistent with the original intentions. The process has evolved to reflect the changes to the AFCEN status and organization, in particular the participation of external experts and new Member s representatives. (a) Requests for modifications Modification Requests (MR) according to industrial needs may be made by any user of the code or by any AFCEN Member. In preparing code modifications the AFCEN committees take account of results from R&D and integrate with feedback from plant experience. The committees take advantage of the centralized organization of the French nuclear industry [5]. Requests for Modification are first analyzed by the dedicated RCC-M Working Group on the topic (design, materials, manufacturing, examination...). A proposal for code modification is defined by an Instruction Sheet drawn up by consensus agreement of the Working Group. This proposal is then approved by the RCC-M Subcommittee, or redebated if significant changes to the code organization or the technical aspects are required. When approval is not reached on the Working Group proposal, a revised Instruction Sheet is drawn up and referred back to the Working Group. 3 Copyright 2014 by ASME

Instruction Sheets approved during the Modification Request process are signed by two AFCEN Members. These signatures testify that a consensus was reached on the decision. A consensus is considered as being reached if no participant expresses an explicit disagreement with the proposal. When approval is obtained in the RCC-M Subcommittee, a Modification Sheet is prepared by the technical secretariat of the Subcommittee. This Sheet is verified by the Working Group leaders and the Subcommittee Chairman, then approved by the President of the Editing Committee, and issued by the General Secretary by delegation of the AFCEN Board of Directors. Discussion by the Board is only needed in cases of significant changes, for example the issuing of a new Section of the code. Some Modification Requests may necessitate an evaluation of their impact. This is in particularly the case when a reference to a new standard is proposed or for a significant change in industrial practice. In such case, a specific enquiry may be addressed to potential suppliers and, where appropriate, an AFCEN development study may be commissioned. Annually, the Modification Sheets are gathered in an Addendum, which is published. The Addendum lists the Modification Sheets and the related chapters of the code. When a new edition of the code is issued, it is strictly the sum of the previous one as modified by the successive addenda (which means by the successive Modification Sheets)..All these activities are conducted according to rules described in the AFCEN Quality Manual. There cannot be a single modification even on details included in RCC-M addenda, unless it has been subjected to the complete process of Modification Request to Modification Sheet. (b) Consistency with French regulation Modification Sheets are sent periodically to the French Safety Authority. There is no more formal regulatory approval of RCC-M code or its modifications. Compliance with the code is not mandatory to comply with French regulations. The French Safety Authority decided in June 2013 to follow the work of some new AFCEN Task Forces. These were formed with the objective of ensuring that the code content was consistent with the Essential Safety Requirements of French Regulation applicable to Nuclear Pressure Equipment. One of the first outcomes concerns the assessment of the degree of heterogeneity in material used for nuclear components. Such an assessment and a maximum level of inhomogeneity is a requirement of French regulation. The code reflects the requirement for a material heterogeneity assessment in Chapters M.140, M160 and M170. One Task Force, where the French Safety Authority is an Observer, has agreed a method to demonstrate that material supply and manufacture complies with the French regulatory requirement. To date four risk assessments of RCC-M material groupings have been undertaken by an independent committee, with Experts independent of AFCEN committees. These Task Forces are very useful for RCC-M code users. They avoid the time spent during a project to demonstrate that the technical basis of the code complies with the regulatory requirement. It is possible that the Task Forces will continue to deal with the particular regulatory requirements of other jurisdictions. (c) Requests for interpretation Another way AFCEN supports the code is by responding to Interpretation Requests (IR).These are discussed by the relevant Working Group which answer directly to the requestor. The answers are periodically presented to the RCC-M Subcommittee. Interpretations are not published, although this may change in future according to Members wishes. (d) Probationary Phase Rules (RPP) New technical or other developments with the possibility of codification may be covered by RCC- M Probationary Phase Rules (RPP). These are in some ways analogous to ASME Code Cases". A RPP is proposed to provide an alternative to an existing rule or practice. 4 Copyright 2014 by ASME

As an example, Chapter A 5000 refers to ISO 9001 and additional quality requirements; the alternative Probationary Phase Rule n 1 (RPP-1) is to use IAEA GS R 3 [4] with specific considerations for PWR equipment construction. This alternative can be used by the supplier, or when the customer requires it, under his own responsibility. AFCEN asks for feedback of experience before incorporating RPPs into the code, Chapter A 5000 in this example. (e) References to other standards RCC-M refers to more than 240 standards (in Table A 1300 of Section I). These standards are mainly European or ISO standards, and it is the policy of AFCEN to refer as far as possible to recognized international standards. Such standards cover materials specifications examination methods, qualification of processes or personnel, competency and qualification etc. In case of a change to a standard, AFCEN evaluates the potential consequences of the change and adapts the code accordingly. For example the new standard for procurement does not have the same scope as the old one. This led to the requirement to prepare selfcontained specifications where a practice is no longer covered by the new standard. In the case of a development in an examination method, it was necessary to adapt the associated criteria so as to maintain an equivalent level of examination quality. RCC-M CONTENT AND STRUCTURE The general structure of the RCC-M has been presented in former communications, and the latest is referenced in [6]. Only the inclusion of the new Probationary Phase Rule n 1 (RPP-1) concerning an alternative to chapter A5000 affects the structure of the Code. This is the first document of the new Section VI. 2012 EDITION As previously indicated the new edition 2012 is the compilation of edition 2007, with the Addenda of 2008, 2009, 2010 and 2011. Some clerical mistakes have been corrected, and specific errata are added to the French and English versions. The errata differ according to the version. It should be noted that French version of the code is the reference one in the event of any questions of interpretation of the translation into English. 2013 ADDENDA The list of Modification Sheets and their scope is given in Table 2 enclosed. Some comments, not exhaustive, on the main changes are given below. Concerning General Parts and Appendices of the code, Table A1300 listing international standards referred to by the code has been updated. Table A1300 includes material standards and welding standards. For example, the latest version of ASTM E 83:2006 for extensometers used in tensile testing is now cited. For the Welding Part (Section IV), the requirements for recording heat input have been tightened from those of the standard NF EN ISO 15614-1 for Welding Process Qualification taking account of experience from welding particular components. The requirements for NDE of welds have been extended in certain situation. It has been clearly stated that surface NDE may replace volumetric NDE, only when the latter is impossible to perform (MS 1197). NF EN 288-3 has been referenced as it is now used for Welding Process Qualification of supports (sub-section H). For Material (Section II), an important modification, is the process to reference new material in the code (MS 1221, paragraph M113). It also considers the possibility of new elaboration mode. New possibility for materials has been open for bolts. Considering Cobalt content, another lessons learn, led to restrict the value in some cases (MS 1195) for welding products. In the contrary, limitation of tantalum for seamless steel has been suppressed. Not feed back in operation has demonstrated any hazards when code rules are correctly implemented. For personnel performing NDE (Section III), it has been added that the analysis of documentation is also in their scope (MC 241), as the practice shown some ambiguity on that purpose. 5 Copyright 2014 by ASME

The Design (Section I) scope of the code has been corrected due to various clerical mistakes in formulae. The consideration of corrosion thickness has been clarified for valves thickness calculation, and dilation ratio has been précised. Various points for nozzle calculation and strength with reinforcement in level 2 have been improved. ADDENDA 2014 The list of Modification Sheets and their scope is given in Table 3 enclosed, and some comments, not exhaustive, are given below. Concerning General Parts of the code (subsections A and Z), the chapter concerning Quality Management System (A5000) has been improved. There is now an explicit requirement for qualification, of scientific software, and calculation modules by Verification and Validation (V&V). As A5000 is based on ISO 9001 plus additional requirements, this requirement is a supplement to Paragraph 6.3. It should be noted that an AFCEN guide is in preparation that will give more detailed recommendations on the process of Verification and Validation (V&V). This guide is expected to be published in mid 2014. Sub-section E, regarding requirements for small components, has been modified for consistency with modern European practice on valve and pump construction. The Tables listing cited standards (A 1300, A 1400) has been updated according to the latest editions of the standards referred to in the chapters on Materials, Welding and Manufacturing. Concerning the Manufacturing and Welding (sections IV and V), the procedure for testing leak tightness of the welds and gaps between the tubes and tube sheets of heat exchangers has now more stringent criteria for leak sensitivity. These criteria have been specified with reference to the ISO standard concerning miscibility of a colored product in demineralized water. In addition, the parts of section IV dealing with receipt of welding filler materials and hardness measurements of welds have also been revised. Concerning Materials (section II), various modifications have been made to material procurement specifications, for example, for steam generator heads and tube sheets. The dimensions of material removed for test specimens have been clarified. The material characteristics of non-pressure retaining parts of primary pumps have been determined. Rewriting of the paragraph on material procurement from stock should facilitate its implementation. Volumetric examination of procured material according to European Standard EN 10160 is now requested in various material specifications through the chapter MC (Examination). This harmonizes the requirements for volumetric examination of ferritic and stainless steels on common basis to assess internal condition of products (not parts). Finally, the code has been improved with regard to the requirements for documentation related to materials (for example, the heat treatment reports or surface defects recordable indications). Concerning NDE (section III), the code now refers to NF EN ISO 9712:2012 for the qualification of personnel performing examination, instead of NF EN 473. Section III has been improved in various other areas: for example, eddy currents reference tubes for NC 30 Fe material of tube bundles, UT examination coverage and procedures, and films used for RT examinations. Concerning Design (section I), the value of S for ferritic steel piping connected to Level 1 valves, has been increased for the calculation of the stress limit P eb in Level 0 criteria. The previous value in the code was applicable to stainless steel and too severe for ferritic steels. Concerning the partial usage factor to be used for fatigue analysis of Level 1 stop valves, a correction for ferritic valves compared to that for stainless steel valves has been demonstrated, and the code has been modified in B 3500.. Stress limit values for Level A criteria for valves have been modified due to a revision of thermal conductivities for ferritic steels. An analysis has shown that former values did note differentiate the nature of the material. 6 Copyright 2014 by ASME

FUTURE WORKS AND CONCLUSION Work in progress in 2014, has not led to major changes in the 2014 Addenda, but will deeply affect the next Addenda in 2015. We can mention: - An AFCEN guidance document separate to the code to help manufacturer to switch from ISO 9001 certification, to RPP-1 (IAEA GS-R-3 recommendation [4]). - An AFCEN guidance document to consider radiological protection in design and construction, - A new flange calculation method in Appendix Z VI, - Modification of material procurement specifications introducing tests for demonstrating any lack of heterogeneity, - A reference to NF EN ISO 3834-2 for quality management of specific welding activities for consistency with chapter A5000//RPP-1/S6000 requirements, - Modification of allowable stress values in Appendix ZI taking account of European standards for pressure equipment design, - Surface examination instead of volumetric examination when justified, - Criteria and sizes of unacceptable defects. All these developments are being discussed with Regulatory Authorities due to new projects and new regulations (mainly European, but not limited to). This is leading to an increase of code activities. The RCC-M Code has been established as a vehicle for the design and construction of the French nuclear fleet and other projects. It has evolved based on this experience, and also integrating German experience used in the EPR project. It evolves continuously, in order to incorporate developments in international industrial practices, the feedback from manufacturing and operational experience, as well as the needs of new projects, and the continuous updating of standards to which RCC-M refers. Recent comparison of construction codes by the international MDEP/SDO groups [7] has revealed areas where harmonization of codes is needed. This can be achieved through exchanges between Utilities, Vendors and Regulatory Authorities. RCC-M is also well adapted to providing spare parts and components for existing PWRs as well as new PWR Projects. Investment to adapt equipment designed to the code to meet each national regulation must lead to an increase of safety, not to an additional administrative layer. Last, the involvement of external Experts and representatives of new AFCEN Members in RCC-M working groups is already giving a new impetus to the codification process, with improvements in technical writing and adoption of new techniques. REFERENCES [1] Directive 97/23/EC of the European Parliament and of the Council of 29 May 1997 on the approximation of the laws of the Member States concerning pressure equipment [2] French Decree n 99-1046 of 13 December 1999 related to pressure equipment; Official Gazette of French Republic, Number 290 of 15 December 1999. [3] French Order of 12 December 2005 related to nuclear pressure equipment (ESPN). J.O. N 19 of 22 January 2006. [4] IAEA Recommendation GS-R-3, The management system for facilities and activities; Safety Requirements» 2006. [5] J.M. Grandemange, D. Kreckel, H.J. Frank "Design and Construction Rules applied to the EPR project: ETC-M". Paper 2488, ICONE 5 Conference May 26-30, 1997, Nice, France. [6] Philippe Malouines, RCC-M: content, working approach and future evolutions, PVP2012-78033 July 15-19, 2012, Toronto, Ontario, Canada. [7] Code Comparison Report STP-NU-051 revision 1, Code Comparison Report for Class 1 Nuclear Power Plant Components, ASME Standards Technology, LLC, 2013 AKNOWLEDGEMENTS The author thanks John Wintle of TWI for his support, and all RCC-M working group leaders for their implication in this work. 7 Copyright 2014 by ASME

TABLE 1: AFCEN Organization Chart- 2014 for Sub Committees PWR reactors : RCC-M Mechanical components RCC-C Nuclear Fuel RCC-E Electrical Equipment ETC-C Civil Works (2010 Ad 2012 Edition) RSE-M In-service surveillance of mechanical components (2010 Edition ad. 2013) ETC-F Fire protection (2010 Edition) FBR and experimental reactors : RCC-MR Mechanical components of FBR reactors (2007) Is replaced by: RCC-MRx Mechanical components for Experimental Reactors (2012 Ad 2013) 8 Copyright 2014 by ASME

TABLE 2 Modification Sheets of 2013 Addenda MS Modification Request TITLE REFERENCE TO RCC-M 1195 T 757 Test per lot Cobalt content of filler materials S 2511 1196 T 758 (T 765) Welding procedure qualification A 1300 - A 1401 - H1 3000 1197 T 773 1198 T 781 1199 M 997 Non destructive examination of full penetration fillet weld Continued validity of qualification Transitional provisions Tab. S 7710.1 (cont. 1) Tab. S 7710.1 (cont. 2) S 1900 Bars for the manufacture of class 1, 2 and 3 Scanning plan and degree M 5110 6.3 of examination 1200 M 1000 Standard updating A 1300 1201 M 1012 Standard updating A 1300 - A 1301 - A 1401 - MC 1212 1202 MC 238 1203 MC 239 1204 MC 240 1205 MC 241 1206 MC 242 Radiographic examination of welds Identification of test areas Case of flush welds which can be clearly located Radiographic examination of steel castings Class of film systems Qualification and of non-destructive examination personnel Liquid penetrant examination Control method 1207 M 1001 Impact test Standard updating 1208 T 783 (+ T 786) 1209 T 787 (+ T 775) 1210 T 788 1211 T 789 Checking of instruments used for measuring welding parameters Welding procedure qualification- Range of approval MC 3313 MC 5232 - MC 5332 Tab. MC 3234 A 1301 - A 1401 - Summary MC MC 2121 MC 3121 MC 4121 - MC 5121 MC 6121 MC 7121 - MC 7131 - MC 7132 MC 8010 Summary MC - MC 4110 - MC 4200 A 1301 - A 1401 - MC 1220 MC 1240 S 7433 S 3200 - Tables S 3203 a) et b) - Tables S 3204 a) et b) List of paragraphs referring to the equipment specification Definitions A 1402 - S 7610 of MPS and MSS Preparation of test plates Base metal 1212 M 1003 Heat treatment Holding time S 2532 A 1502 - M 4102 3.2.3 M 5190 Annex II 9 Copyright 2014 by ASME

MS Modification Request TITLE REFERENCE TO RCC-M 1213 M 1004 1214 C 266 1215 C 268 Minimal diameter for UT performance Valves and fittings Coefficient of expansion Integration in «sizing of valves and piping components» of corrosion requirement A 1502 - M 3308 5/6 Table B 3534 - B 3553.3 B 3541 - B 3552.1 - C 3541 C 3552.1 1216 C 269 Loadings Design loads C 3132.3 - C 3552.2 4) 1217 C 270 1218 C 272 1219 G 150 1220 C 271 1221 M 984 Linear type support Standard support Sizing for pressure - Branch connections requiring reinforcement List of the paragraphs referring to the agreement of the manufacturer Design rules for linear type supports - Nomenclature Introduction of new materials into the RCC-M H 3282.2 Table H 3282.2 C 3643.3 A 1403 ZVI 1200 c) Summary B, C, D, G et M 1 st part B 2200 - C 2210 D 2210 - G 2200 M 113 - M 114 - M 115 1222 M 1007 Normative evolution of bend tests A 1300 - M 334 - M 1131 1 1223 T 793 Designation - Normalization A 1300 - A 1401 - S 2200 1224 C 263 1225 M 941 Body contours at weld ends Particular case of extended weld C 3544.5) ends Removal of the dosage of tantalum on stainless steels 1226 M 1005 Normative evolution 1227 T 791 1228 1229 G 153 M 987 (+ M 939, M 980) M 221.2 - M 221.3 A 1300 - A 1301 - A 1401 - ZI 1.3 (following) - ZI 1.6 (cont. 1) E 2110 J 2110 Special cases of chemical analyses of dissimilar-metal joints - Number S 7861 3) - S 7862.1 3) of samples Bolting following STR M 2311 et M 2312 Miscellaneous modification sheet of 1 er addendum 2012 (June 2013) A 1502 - ZI 1.3 - ZI 2.1-Tab. B 2200 - M 2311 4/5/tab II et III - M 2312 A 1300 - Tab. ZY 210 - Tab. B 3531. d and e - B 3235.3 - Tab. B 6113 B 6534 - C 3531 - J 2210 10 Copyright 2014 by ASME

TABLE 3: Modifications Sheets of 2014 Addenda MS Modification Request TITLE REFERENCE TO RCC-M 1230 C 250 Improvement of the determination of T Adequacy of indices C5 and C 5 with the ASME code 1231 M 967 General provisions RCC-M stocks procurement M 111 Table B 3534 - B 3553.2 - Fig 3553.2.d and 3553.4 1232 M 1011 Scope of Procurement Specification M 3308 Table A 1502 - ZI 1.2 - M 3308 0 1233 TS 001 1234 M 983 1235 M 1014 1236 M 1016 1237 MC 247 Adequacy of the code with the current French nuclear installations Consideration of security requirements for workers and environmental requirements of hydrazine discharges Characteristics applicable to water used for testing and wet layup Primary pumps - Non pressure retaining parts- Applicable procurement specifications Primary pumps - Non pressure retaining parts- Applicable procurement specifications Surface defects Recordable conditions and examination criteria Liquid penetrant examination documents Liquid penetrant products Table F 6610 Table B 2200 Table B 2200 M 2133 6 - M 2133 Bis 6 Table A 1401 - MC 4122 - MC 4200 1238 T 794 Procedure qualification test Gap leak tightness test Table A 1401 - F 4423.2 1239 G 141 Material subjected to pressure - Classification of small components 1240 G 155 General requirements for qualification of computer codes A5230 1241 M 1019 1242 M 1021 Class 1, 2 and 3 carbon steel forgings niv. Clarification Heat treatment report Final manufacture of bolting elements of class 1, 2 and 3. Improvement of the consistency between the procurement specifications of section II Table A 1401 - A 4250 - ZY 900 - ZZ 900 - Table of contents E - E 1110 - E 1310 E 3110 - E 3400 Table A 1502 - M 1122 0 Table A 1502 - M 5140 0/2/4.3.1/6 11 Copyright 2014 by ASME

MS Modification Request TITLE REFERENCE TO RCC-M 1243 MC 244 1244 MC 245 1245 MC 246 1246 MC 250 1247 MC 251 1248 M 975 1249 M 998 1250 M 1015 1251 M 1029 Reference tube for eddy current examinations Modification requirements of the reflectors positioning in he reference tubes used for EC cexamination Radiographic examination Film examination Harmonization of the different paragraphs concerning the shifting of one range of wire penetrameter and a hole penetrameter Qualification and certification of non-destructive examination personnel Updating of the standard EN 473 replaced by the standard ISO 9712:2012 Liquid penetrant examination - Control method Updating of the standard NF EN 571-1 replaced by the standard NF EN ISO 3452-1 Ultrasonic examination Scope and examination conditions Prescription on reference blocs used for buttered ferritic steels Arrangement and integration of heads obtained by forging Arrangement and integration of tube sheet with integrated crown on primary side Volumetric examination Reference to MC 2400 Introduction of a reference to MC 2400 in the procurement specification, précising the conditions of application of UT examination standards Impact tests Dimension of specimens Introduction of reduced samples specimen test and corresponding criteria MC 6134 - M 4105 8 MC 3162 - MC 3312 MC 7121 - MC 7131 - MC 7132 - MC 8010 - MC 8020 Table A 1300 Table A 1401 - MC 4200 MC 2710 - MC 2735 M 2143 - M 2143 Bis A 1502 - M 2115 - M 2115 bis A 1502 - M 335 - M 1131 8.6 - M 1132 6 - M 1134 3.6 - M 2121 6 - M 2122 6 M 2125 7 M 2126 7 - M 2126 Bis 7 M 2127 6 - M 2128 6 MC 1221 1252 C 280 Stress limits Peb modification for ferritic piping B 3552.2b)2) 1253 C 281 Level A criteria Analysis of fatigue behavior Correction of Young s modulus in the computation of the S stress for the analysis of fatigue behavior B 3553.5a) - B 3553.5b)5) 12 Copyright 2014 by ASME

MS Modification Request TITLE REFERENCE TO RCC-M 1254 M 981 1255 M 1026 1256 M 1027 1257 MC 249 rev1 1258 T 795 Determination and harmonization of temperature RTNDT- Results Manufacturing-Delivery state-heat Treatment Deletion of quenching by sprinkling (or by spraying) of large forged parts Tensile test- Standardization-Updating of the new edition of standards about calibration of extensometers Magnetic particles (MT) examination-surfaces preparation Introduction of the processing instruction of paint or coating in case of magnetic particle examination Acceptance of filler material Alloyed steels with Mn and Cr content. M2117 Annex1 M 2111 3.4 M 2112 3.4 M 2113 3.4 - M 2114 3.4 M 2116 3.4 M 2122 3.2.2 M 2131 3.4 M 2131bis 3.4 M 2133 3.4 - M 2133bis 3.4 - A 1300 - MC1210 MC 5143 S 2910 - S2940 1259 T 799 Hardness measurements S 3633 - S 3733 - SI 500 13 Copyright 2014 by ASME