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General Assembly ASME Section France November 25, 2014
Section France Following Participation to meetings & workshops
Presented by Claude FAIDY ASME member ASME Contributor to B&PVC Consultant [email protected] +33 6 1410 1119
Content
Introduction
ASME BPVC- Section III Nuclear Components
ASME BPVC- Section XI In-service Inspection
ASME Nuclear Code for 2025
NQA-1
NSQ-100 alternative (for information)
RCCM-ASME III Div. 1 short presentation
USNRC approved editions / other points
Harmonization
Conclusion
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ASME Codes & Standards
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ASME Board of Nuclear Codes & Standards
35 members, chairman Ralph HILL
7 Codes Boilers & Pressure Vessel Codes
o Construction of Nuclear Facility Components (III)
o Nuclear In-service Inspection (XI)
o Other connected section: II Material, V Control, IX Welding
Cranes for Nuclear Facilities (CRANE)
Nuclear Risk Management (CNRM)
Nuclear Air and Gas Treatment (CONAGT)
Nuclear Quality Assurance (NQA)
Operations and Maintenance of Nuclear Power Plants (O&M)
Qualification of Mechanical Equipment Used in Nuclear Facilities (QME)
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B&PV Code Section III: Construction of Nuclear Equipments
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From ASME presentation at Nuclear Codes & Standards Workshop – Prague July 2014
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Comparison ASME III – RCCM for Class 1 Vessels
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Article A1-sameA2-
equ.Total A
B1-diff.
Scope
B2-diff.
techn.Total B Total
NB 1000 0 4 4 3 2 5 9
NB 2000 0 18 18 8 77 85 103
NB 3000 11 8 19 9 19 28 47
NB 4000 0 13 13 16 59 75 88
NB 5000 0 6 6 14 30 44 50
NB 6000 0 9 9 20 22 42 51
NB 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
USNRC Code Approval
BPVC – Section III Nuclear Components 2008 (2009, 2011, 2013, 2015)
BPVC – Section XI In-service Inspection 2008 (2009, 2011, 2013, 2015)
O&M Operation & Maintenance (2009, 2011, 2012, 2015)
For Code Cases Reg Guide 1.84 Rev 36 Design / Fabrication / Material
Reg Guide 1.147 Rev 17 In-Service Inspection
Reg Guide 1.192 Rev 1 O & M
Reg Guide 1.193 Rev 4 Code Cases not approved
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USNRC general information
Vendor Inspections and QA Implementation
Commercial grade dedication: components / computer codes
Counterfeit, fraudulent and suspect items
Reactor Licensing To date: ABWR, System 80+, AP600, AP1000
On going: EPR (AREVA), US-APWR (MHI), ESBWR (GE-HITACHI), APR1400 (KHNP)
New reactors in USA: 14 planned (9 COL)
License Renewal 75 plants + 3 in 2015
Over 60 years: discussion on-going
Plants beyond 40 years 37 plants + 2 in 2015
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Codes & Standards Harmonization
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Multinational Design Evaluation Program
MDEP = 10 regulators + guests CSWG: Codes & Standards WG
VICWG: Vendor Inspect. Coop. WG www.oecd-nea.org
Cooperation in Reactor Design Evaluation and Licensing
CORDEL = All the world Nuclear Industry + Utilities Mechanical codes convergence Pilot Project
www.world-nuclear.org
SDO Convergence Board
Proposed in Paris CSWG meeting 2011-12-04; with some disagreements of SDO partners
in Houston on 2012-02-05 New proposal after Washington on 2012-08-05
• Minimize future Code Divergence • Facilitate Areas of Convergence Standard Development Organizations: ASME-JSME-AFCEN-KEPIC-CSA-NIKIET
NDE personal qualification SNT TC1A / ISO9712
Non Linear Design Rules: limit load, elastic plastic analysis Monotonic / Cyclic
Fatigue Roadmap
HDPE pipe (class 3)
Leak Before Break
High temperature Flaw Evaluation (R5 / RCCMRx-A16)
Stress Intensity Factor Handbooks
Welding – Welder qualification ASME ST LLC
Cyclic stress-strain curves ASME ST LLC
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Codes & Standards Harmonization : Topics
Conclusion
7 different nuclear codes, extremely active; as examples:
Section III: Div 1: LWR Nuclear Components will be re-written before 2015
Section V: Examination will be re-written soon
Section IX: Welding
will be compared again in the next 2 years
Section XI: In-service inspection draft re-write Div 2
NQA-1: quality assurance under re-write process
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