核电C承压设备-RCCM代码介绍

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Bureau Veritas Presentation _ Date
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1 Historical recall
► First French 900 MW and 1300 MW were manufactured under
Westinghouse licence
Design based on ASME III Code Construction based EDF specifications Issuing of the 1974 Order on Main Primary Systems • Safety margins defined so as to be globally compatible with ASME III provisions Technical specifications issued with adaptations and FRA + EDF approval needed
Nuclear Island Components Materials Examination methods Welding Fabrication
Section III Section II Section V Section IX Various parts of Section III
Section 1 is the key to enter in the RCC-M
Bureau Veritas Presentation _ Date
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1 Integration of PED (section I, subsection Z, appendix ZU)
► ZU 200: hazard analysis ► ZU 300: actions by Notified Bodies and Recognized Third Party
Bureau Veritas Presentation _ Date
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1 Integration of ESPN (section I, subsection Z, appendix ZT)
► ZT 200: hazard analysis ► ZT 300: actions by Notified Bodies, Accepted Bodies, Accepted
In Finland YVL are mandatory In France ESPN is now mandatory for new NPP (ESPN Order 2005) • ESPN is based on European PED (to take account the pressure risk) • ESPN complete PED to take into account the radiological risk
Bureau Veritas Presentation _ Date
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3 Section I
3 RCC M section 1: structure RCC-M Code
SubSection A: SubSection B: SubSection C: SubSection D: SubSection E: Subsection G: Subsection H: Subsection J: Subsection Z: General requirements Class 1 components Class 2 components Class 3 components Small components Reactor internals Supports Storage tanks Technical appendices
Bureau Veritas Presentation _ Date
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1 Why a construction code ?
► To take into account :
Pressure risks Safety concerns
► For a economical interest ► To integrate feed-back experience
Construction code and associated standards (European, ASTM, national standards ) Regulatory requirements Equipment specification
Bureau Veritas Presentation _ Date
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1 RCC M frame
Pressurizer Steam generator
RCC M Code is dedicated to the manufacturing of PWR mechanical components located in the nuclear islands
Primary pump Reactor
Organizations
► ZU 400: service instruction ► ZU 500: identification of equipment items ► ZU 600: equipment items and assemblies ► ZU 700: materials ► ZU 800: small components
► In 1978
30 nuclear plants in operation or under construction
Practices well established and technical performances known
Decision to write the rules corresponding to these practices

General approach
Three barriers • • • Fuel enveloppe Integrity of the cooling system containment
NUCLEAR PRESSURE EQUIPMENT RCC-M Code
R. Palengat Milan June 17th, 2009
Content
Content
1 Generals 2 RCC M structure 3 Section I 4 Section II materials 5 Section III examination methods 6 Section IV welding 7 Quality assurance 8 Conclusions
Organizations and Recognized Third Party Organizations
► ZT 400: service instruction ► ZT 500: identification of equipment items ► ZT 600: equipment items and assemblies ► ZT 700: materials ► ZT 800: small components ► ZT 900: radiological protection
Bureau Veritas Presentation _ Date
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1 Which code for a New Nuclear Power Plant ?
► Example of EPR for Finland, France
and China
EPR Global Application
Class 1: Highest level or guarantees
Class 3: Pressure risk governs
→ Industrial standards
Sect. VIII Annex Z Compliance to PED
Harmonized Standards PED 97/23 EC
National Industrial Standards
ASME Code
NCA NB NC ND None NG NF NC/ND 3800-3900 Appendices
Subsection A is the key to enter in RCC-M Section 1
Bureau Veritas Presentation _ Date
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3 Classification of components : safety requirements
Bureau Veritas Presentation _ Date
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2 Structure of RCC M Code
2 RCC M structure
RCC-M Code
ASME Code
Section 1: Section 2: Section 3: Section 4: Section 5:
NC
ASME VIII Div 1 +
Harmonized standard : EN 13445, EN 13480 National industrial standards : ASME VII, AD-M, CODAP …..
Bureau Veritas Presentation _ Date
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1 Regulatory requirements
► In addition to the RCC-M Code regulatory requirements providing from
the country where the nuclear equipments are installated (if existing)
Bureau Veritas Presentation _ Date
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1 Generals
1 Which requirements for a NPP ?
► A construction code is a part of several requirements applicable to
manufacture a Nuclear Power Plant
ASME III NC +
ASME Sect. III NC
KTA 3211
RCC-M Subs. C
ASME III
Sect. VIII Annex Z Compliance to PED
Class 3
ND +
Байду номын сангаас
Harmonized Standards PED 97/23 EC
National Industrial Standards
Bureau Veritas Presentation _ Date
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1 Regulatory requirements
► RCC M edition 2007 integrates
Standards updating : more and more European Standards are now referenced in the last edition Regulatory evolutions coming from PED and ESPN Order : for example for the procurement of materials Addition of 2 appendices to integrate PED and ESPN • Appendix ZU for PED • Appendix ZT for ESPN
Bureau Veritas Presentation _ Date
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1 Which code for a New Nuclear Power Plant ?
EPR Global Application
ASME III
Class 1
NB +
RCC-M Sect. I Subsection B
Class 2
Specific "Break Preclusion" Equipments
RCC-M Sect. I Subsection B
Class 2: Nuclear risk governs
→ Nuclear standards
ASME Sect. III NC
KTA 3211
RCC-M Subs. C
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