Chapter 33
History of the Code Rules for Accreditation, Certification, and Related Issues


In Chapter 33, Marcus N. Bressler discusses the rules for accreditation and certification and similar issues. This chapter has been revised to address the current 2004 Code revisions as well update several accompanying graphics. Since this chapter is intended to provide an overview of the history of the ASME B&PV Code from its inception through the incorporation of nuclear components to the present. Accordingly the Title of the Chapter has also been revised to reflect the scope of the discussions contained in the chapter. From earlier coverage of boilers and pressure vessels, the nuclear initiative required coverage for piping, pumps, valves, storage tanks, vessel internals, and component and piping supports. Rules for repairs and replacements of nuclear components and the use of newer Codes are discussed, including the need for Code reconciliation and commercial grade dedication. The development of certification and accreditation is covered, with emphasis on the new requirements for organizations seeking ASME accreditation. The globalization of the ASME certificates and stamps is described thoroughly.

Marcus, based on his experience working with many Code Committees, is justly the right person to provide in-depth coverage of the various aspects of the Code and connecting these with the topic of this chapter. A discussion is provided regarding the role of regulators, and the commentary includes accreditation for nuclear construction, Code stamping, the role of the Registered Professional Engineer and Authorized Nuclear Inspector (ANI), and the related Mandatory and Nonmandatory Appendices in the Code. Marcus details two examples of the use of Code reconciliation: repair of steam-generator feedwater-nozzle cracks at a 1970s nuclear plant and the support material requirements of an Example Nuclear Plant (ENP).

Marcus Bressler has provided in this revised script his thoughts on Future Developments in the ASME Boiler & Pressure Vessel Code, as well as ASME's emphasis on Globalization of its Codes and Standards. In addition, applicable Code references, description of a typical nuclear survey, and an annotated bibliography are also provided.

  • 33.1 Introduction
  • 33.2 Historical Background
  • 33.3 Nuclear Energy
  • 33.4 Piping, Vessels, Pumps, and Valves in the 1950s
  • 33.5 ASME Section III, Nuclear Vessels, in the 1960s
  • 33.6 Piping, Pumps, and Valves in the 1960s
  • 33.7 Accreditation for Nuclear Construction
  • 33.8 Developments of the 1970s
  • 33.9 The Registered Professional Engineer
  • 33.10 Authorized Inspection
  • 33.11 Quality Assurance
  • 33.12 Inservice Inspection
  • 33.13 Construction Code-Section XI Interfaces
  • 33.14 Repairs and Replacements
  • 33.15 Backfitting of New Code Requirements on Operating Plants
  • 33.16 Careful Preparation of Work Plans
  • 33.17 Code Reconciliation
  • 33.18 Example A: Repair of Steam-Generator Feedwater-Nozzle Cracks at a Nuclear Plant in the 1970s
  • 33.19 Example B: ENP-Support Material Requirements
  • 33.20 Materials Procurement
  • 33.21 Materials Documentation
  • 33.22 Component Procurement for Replacements
  • 33.23 Use of Specific Provisions of Later Editions and Addenda
  • 33.24 Nuclear Accreditation Programs
  • 33.25 Globalization
  • 33.26 Future Developments in the ASME B & PV Code
  • 33.27 Summary
  • 33.28 References

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