The 2010 Boiler & Pressure Vessel Code ASME Boiler & Pressure ...

2010년도 대한전기협회 KEPIC-Week 발표자료 MN1-5 

The 2010 Boiler & Pressure Vessel Code 

'Handling the Pressure' of Safety, Efficiency, Reliability, and Compliance 

KEPIC Week Conference 

September 1, 2010 

John Bendo 

Nuclear Energy Business Manager 

ASME 

ASME Boiler & Pressure 

Vessel Code 

A Historical Perspective 

Helped solve a major safety problem of the late 19 th and 

early 20 th century… 

• Throughout the 1800’s, both boiler size and operating 

pressure continued to increase 

• The number of explosions tripled between 1879 and 

1899 (383 – more than one per day) 

• Steam boiler explosions were costing thousands of 

lives 

Examples: 

• Steam boat Sultana - The ship’s boiler(s) exploded on 

April 27, 1865 killing 1800 people 

• The Grover Shoe Factory boiler explosion on March 

20, 1905 in Brockton, Massachusetts 

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R. B. Grover & Company Shoe Factory 

Before Boiler Explosion 

R. B. Grover & Company Shoe Factory 

After Boiler Explosion 

… 58 people were killed and 150 were injured. 

- 45 -

ASME Boiler & Pressure Vessel Code 

A Historical Perspective 

• Following a number of explosions of this type states 

began to develop their own boiler laws. 

• This led to the development of different laws among the 

states. 

• An ASME Committee developed the Boiler Code 

between 1911 and 1914. 

• Provided for safe construction and promoted commerce 

through consistency of requirements. 

The methodology used in creating the 

Boiler Code “set the standard” for 

modern code-development. 

Trend for Boiler Explosions in the U.S. 

5000 psi 

1600 psi 

400 psi 

650 psi 

500 psi 

PRESSURE LEVEL 

- 46 -


• Comprehensive and practical: 

• Evolved from 114 pages to today’s 14,000+ pages 

• Covers industrial and residential boilers, pressure 

vessels, nuclear facility components, and transport 

tanks 

• Reflects industry best-practices, offering real-world 

solutions developed by experts in the field 

• Worldwide influence: 

• Adopted in whole or in part by all U.S. states and 

Canadian provinces 

• Accepted as a possible means to meet local 

pressure equipment regulations by more than 100 

nations 

Global Growth 

Certified Boiler & Pressure Vessel Manufacturers (Non-Nuclear) 

5,000 

Certified Manufacturers 

4,000 

3,000 

2,000 

1,000 

0 

74 76 78 80 82 84 86 88 90 92 94 96 98 00 02 04 06 08 

U.S. & Canada International Total 

Data as of 2009-06-30 

- 47 -

ASME Section III Nuclear Certificates by Company 

600 

500 

Number of Companies Holding Certificates 

400 

300 

200 

Total 

North America 

International 

100 

0 

1980 1985 1990 1995 2000 2005 2010 

Year [Data through July 31, 2010] 

Total Number of ASME Nuclear Certificates 

400 

350 

US Nuclear 

Component 

Certificates 

International Nuclear 

Component Certificates 

Total US 

Certificates 

Total International 

Certificates 

300 

Number of Certificates 

250 

200 

150 

100 

50 

US Nuclear Materials 

Certificates 

International Nuclear 

Materials Certificates 

0 

Data through July 31, 2010 

- 48 -

ASME Develops Codes and Standards for Many Industries 

Authorized Inspections 

Automotive 

Bioprocess 

Blanks 

Boiler 

Certification & Accreditation (C&S) 

Chains 

Chemical/Process 

Compressors 

Computational/Analysis 

Computing/Information Science in Engineering 

Controls 

Conveyors 

Cranes and Hoists 

Design 

Elevators and Escalators 

Energy Efficiency 

Engineering Drawing & Related Practices 

Environmental 

Fasteners 

Fitness-For-Service 

Fittings, Flanges & Gaskets 

Fossil 

Gauges/Gaging 

Geometric Dimensioning & Tolerancing (GD&T) 

Heating, Ventilating and Air-Conditioning 

High Pressure Vessels/Systems 

Industrial Gas 

Internal Combustion Engine 

Keys & Keyseats 

Limits & Fits 

Materials 

Measurement 

Medical/Health 

Metal Products Sizes 

Metric System 

Noise Control and Acoustics 

Non-Personnel & Personnel Lifting Devices 

Nondestructive Evaluation/Examination 

Nuclear 

Operator Qualification and Certification 

Performance Test Codes 

Piping & Pipelines 

Plant Operations 

Plumbing 

Post Construction 

Pressure Vessels 

Pumps 

Rail Transportation 

Reinforced Thermo, Plastic Corrosion 

Resistance 

Renewable/Alternative Energy 

Risk Analysis 

Screw Threads 

Steam Table 

Steel Stacks 

Surface Quality 

Testing 

Textile Engineering 

Tools 

Turbines 

Valves 

Waste 

Water Management 

Welding & Brazing 

ASME Code Products 

Boiler and Pressure Vessel Code 

• Section I - Power Boilers 

• Section II - Materials 

• Section III - Rules for Construction of 

Nuclear Facility Components 

• Section IV - Heating Boilers 

• Section V - Nondestructive Examination 

• Section VI - Recommended Rules for the 

Care and Operation of Heating Boilers 

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Boiler and Pressure Vessel Code 

• Section VII - Recommended Guidelines for 

the Care of Power Boilers 

• Section VIII - Pressure Vessels 

• Section IX - Welding and Brazing 

Qualifications 

• Section X - Fiber-Reinforced Plastic 


• Section XI - Rules for Inservice Inspection 

of Nuclear Power Plant Components 

• Section XII - Rules for the Construction and 

Continued Service of Transport Tanks 

Complementary 


B31 Piping and Pipeline Codes 

• B31.1 Power Piping 

• B31.3 Process Piping 

• B31.4 Pipeline Transportation Systems for Liquid 

Hydrocarbons and Other Liquids 

• B31.8 Gas Transmission & Distribution Piping 

Systems 

• B31.8S Managing System Integrity of Gas 

Pipelines 

• B31Q Pipeline Personnel Qualification 

• B31.12 Hydrogen Piping & Pipelines (In 

Development) 

- 50 -

Complementary 


• 33 B16 Standards covering valves, flanges, 

gaskets and fittings 

• Post Construction: 

• PCC-1 Guidelines for Pressure Boundary 

Bolted Flange Joint Assembly 

• PCC-2 Repair of Pressure Equipment and 

Piping 

• PCC-3 Risk-Based Inspection 

• Reinforced Thermoset Plastic Corrosion 

Resistant Equipment (RTP-1) 

• Fitness for Service (API-579/ASME FFS-1) 

Complementary 

ASME Nuclear Codes & Standards 

•AG-1 - Code on Nuclear Air and Gas Treatment 

•N509 - Nuclear Power Plant Air-Cleaning Units and 

Components 

•N510 - Testing of Nuclear Air-Treatment Systems 

•N511 - In-Service Testing of Nuclear Air Treatment, 

Heating, Ventilating, and Air-Conditioning Systems 

•NQA-1 - Quality Assurance Requirements for Nuclear 

Facility Applications (QA) 

•RA-S - Probabilistic Risk Assessment for Nuclear 

Power Plant Applications (PRA) 

- 51 -

Complementary 

ASME Nuclear Codes & Standards 

•NOG-1 - Rules for Construction of Overhead and 

Gantry Cranes (Top Running Bridge, Multiple Girder) 

•NUM-1 - Rules for Construction of Cranes, Monorails, 

and Hoists (with Bridge or Trolley or Hoist of the 

Underhung Type) 

•OM - Code for Operation and Maintenance of Nuclear 

Power Plants 

•PTC 32.1 - Nuclear Steam Supply Systems 

•QME-1 - Qualification of Active Mechanical 

Equipment used in Nuclear Power Plants 


2010 Edition – Highlights & Changes 

- 52 -



Section I – Power Boilers 

• Added heat recovery steam generators to 

the list of equipment covered 

• Revised to enable the use of alternative 

design methods when details of design are 

not given in the Code 

• Revisions to permit inclusion of clad 

thickness in the calculated strength of 

boiler tubes 

• Impose Weld Joint Strength Reduction 

Factors on certain welds 



Section II - Materials 

• Part A: Ferrous Material Specifications - Updated 

more than 90 ferrous specifications 

• Part B: Nonferrous Material Specifications - 

Updated more than 50 nonferrous specifications 

• Part C: Specifications for Welding Rods, 

Electrodes and Filler Metals - Updated 7 welding 

material specifications 

• Part D: Properties (Customary) - More than 15 

stress lines added; more than 25 stress lines 

revised; new Table covering Poisson’s ratio and 

density 

- 53 -



Section III – Rules for Construction of Nuclear Facility Components 

• Division 1 

• Subsection NCA General Requirements (Divisions 1 & 2) 

• Subsection NB-Class 1 Components (Division 1) 

• Subsection NC-Class 2 Components (Division 1) 

• Subsection ND-Class 3 Components (Division 1) 

• Subsection NE-Class MC Components (Division 1) 

• Subsection NF-Supports (Division 1) 

• Subsection NG-Core Support Structures (Division 1) 

• Subsection NB-Class 1 Components in Elevated Temperature 

Service (Division 1) 

• Appendices (Division 1) 

• Division 2 – Code for Concrete Reactor Vessels and Containments 

• Division 3 – Containments for Transportation & Storage of Spent 

Nuclear Fuel & High Level Radioactive Material and Waste 



Section III – Rules for Construction of Nuclear 

Facility Components 

• Clarified requirements for standard impact test 

specimen material for Charpy V-Notch test 

machine calibration 

• Updated and consolidated reference standards 

into Article NCA-7000 

• Appendix F revised to provide requirements for 

support fillet welds. 

• Consolidated common requirements in NB-4622 

and provided specific requirements for base metal 

repairs, cladding repairs and repairs to dissimilar 

joints 

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• Revised NF-1132 to clarify jurisdiction boundary 

for bolts to building structure 

• Revised NCA to update references to NQA-1 2008 

and/or NQA-1a 2009 addenda 

• Revised NCA to address PE (polyethylene) source 

material and piping material and provide rules for 

qualification of Polyethylene Material Suppliers 

• Revised NCA-5125 (b) to require ANI Supervisor 

Audit to include N and NV Certificate Holders 



Section IV – Heating Boilers 

• Added requirements to allow the stamping of cast 

aluminum boilers 

• Added new Aluminum materials to the Table of 

allowed materials. 

• Nonmandatory Appendix I was updated 

- 55 -



Section V – Nondestructive Examination 

• Clarified requirements for radiography 

using phosphor imaging plates 

• Updated or revised over 15 ASTM 

specifications related to NDE 

• Added or revised various definitions to 

clarify the use of NDE terms 

• Clarified the requirements for ultrasonic 

performance demonstration criteria. 



Section VIII – Pressure Vessels 

Division 1 

• Added requirements for pressure vessels 

constructed of impregnated graphite 

• Revised UG-90(c)(2) and added Mandatory 

Appendix 35 addressing Rules for Mass 

Production of Pressure Vessels 

• Added Rules for Bolting Pads, Qualification of 

Nondestructive Examination Personnel and 

Requirements for Split Reinforcing Pads for 

Nozzles. 

• Revised Appendix 26 to limit the design 

temperature to 800 F and permit use of the 

operating temperature properties for the fatigue 

analysis. 

- 56 -




Division 2 – Alternative Rules 

• Added guidance to accommodate loadings 

produced by deflagration 

• Made tubesheet requirements consistent with 

Part UHX of Section VIII, Division 1 

• Added requirements for Qualification of 

Nondestructive Examination Personnel 

• Added PWHT requirements for some materials 




Division 3 - Alternative Rules for the 

Construction of High Pressure Vessels 

• Incorporated the structural stress method for 

fatigue analysis of welded joints from Division 2 

• Added requirements for Qualification of 

Nondestructive Examination Personnel 

• Added wording for performance of UT in lieu of 

RT 

• Incorporated structural stress method for fatigue 

analysis of welded joints from Division 2 

• Incorporated Elastic-Plastic Analysis from 

Division 2 

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Section IX – Welding and Brazing 

Qualifications 

• Reassigned S-Numbers as P-Numbers for 

welding and brazing procedure qualification 

purposes (including updating tables) 

• Revised welding forms to reflect current welding 

variables and terminology 

• Revised QW/QB-422 to indicate the assigned 

ISO/TR 15608 Material Grouping Number 



Section X – Fiber-Reinforced Plastic 


• Revised to allow acceptance test of vessels 

designed to operate at elevated temperature to be 

conducted at ambient temperature 

• Revised requirement for frequency of volumetric 

expansion tests. 

• Removed requirements for the assembly of the 

UV stamp, which are outside the scope of Section 

X. 

• Revised some thickness formulas to simplify and 

make them similar to ASME RTP-1 

• Deleted word "vacuum" throughout the code. 

• Revised to require attaching the partial data 

reports to the primary data report to provide 

traceability 

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Section XI – Rules for Inservice Inspection of 

Nuclear Power Plant Components 

• Revised to require additional examinations when 

new flaws or significant changes in flaw 

characteristics resulted in necessary corrective 

actions 

• Incorporated guidance for pressure testing of 

open-ended discharge piping 

• Made revisions to permit the Owner to use the 

personnel qualifications, methods, and acceptance 

criteria for repair/replacement activities 

• Provided guidelines for evaluating non-destructive 

examination coverage percentages 

• Added new paragraphs and a form addressing the 

Owner's and Repair/Replacement Organizations 

responsibility in preparation of reports 

documenting repair/replacement activities 





• Revised the flaw Acceptance Standards for Class 1 

ferritic and austenitic piping 

• Revised to clarify that the examination 

requirements do not apply to atmospheric or 0 to 

15 psig (0 kPa to 100 kPa) storage tanks 

• Incorporated analytical procedures and material 

properties for evaluation of flaws in piping and 

welds fabricated of Alloy 600/82/182/132 in both 

PWR and BWR environments 

• Added a new article to include IGSCC growth rate 

equations for unirradiated, austenitic stainless 

steels exposed to BWR reactor water 

environments 

• Revised the examination requirements for cladding 

to be consistent with Section III 

- 59 -



Section XII – Rules for Construction and 

Continued Service of Transport Tanks 

• Added rules covering local thin areas in transport 

tanks 

• Added an appendix covering ton containers 

• Added guidelines for the design of supports and 

safety devices for cargo tanks 

Developments in Nuclear Codes and Standards 



• Division 4 – Magnetic Confinement Fusion Energy 

Devices 

• Division 5 – High Temperature Reactors 

_______________________________________________ 



• Division 2 - Gas-cooled Nuclear Power Plants 

• Division 3 - Liquid-metal-cooled Nuclear Power Plants 

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The 2010 Boiler & Pressure Vessel Code ASME Boiler & Pressure ...

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