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Summary - This article assists engineers in selecting ASME XI options for the repair of ASME III nuclear components. In summary, the repair options in ASME XI are dispersed throughout Section XI and Code Cases, while, in contrast, the ASME PCC-2 repair standard (for non-safety related components) lists repair options in a well-structured manner. So, we are going to use the structure of ASME PCC-2 as a road map to cross-correlate the equivalent ASME XI repair, where it exists. Therefore, the Table can be used as a checklist to remind engineers of the many repair options.
On one hand …. ASME XI: The repair of safety-related Class 1, 2, and 3 nuclear components is addressed in ASME Boiler & Pressure Vessel Code Section XI and in a series of ASME XI Code Cases. The use of ASME XI and its Code Cases to select a repair technique poses two challenges:
On the other hand … ASME PCC-2: The repair techniques for non-safety related pressure equipment and piping is addressed in several codes, standards, and guides; for example, those published by the National Board, EPRI, API, STP, etc. Of particular interest is ASME PCC-2 “Repair of Pressure Equipment and Piping”. One of the strengths of PCC-2 is its clear structure: The repair techniques are listed sequentially, each article (chapter) of PCC-2 being a repair technique. As such, the PCC-2 Table of Contents can be used as a checklist, to quickly go down the repair options listed.
Following the introductory Chapter, ASME PCC-2 is divided into the three general groups of repair methods:
Finally, PCC-2 Part 5 addresses the general question of pressure or leak testing a repair.
Note that, technically, PCC-2 has benefited from the work done in the nuclear industry, within Section XI. Some of the PCC-2 repairs were first drafted by nuclear power plant engineers.
This article is meant to use the strength of PCC-2, its clear and logical structure, to list the PCC-2 repair options and weave-through the corresponding ASME XI repair techniques. In this roadmap, the statement “No explicit ASME XI equivalent” is not a criticism, it simply reflects that some of the repair techniques are either not practical for a safety-related component (for example, pipeline welded sleeves), or have not yet been brought forward to Section XI.
ASME PCC-2 Part 2 Welded Repairs
Article 2.1 Butt-Welded Insert Plates in Pressure Components
No explicit ASME XI equivalent
Article 2.2 External Weld Overlay to Repair Internal thinning
ASME XI CC N-504
Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping
Inquiry: Under the rules of IWA-4120, in Editions and Addenda up to and including the 1989 Edition with the 1990 Addenda, in IWA-4170(b) in the 1989 Edition with the 1991 Addenda up to and including the 1995 Edition, and in IWA-4410 in the 1995 Edition with the 1995 Addenda and later Editions and Addenda, a defect may be reduced to an acceptable flaw in accordance with the provisions of either the Construction Code or Section XI.
As an alternative, is it permissible to reduce a defect to a flaw of acceptable size by increasing the pipe wall thickness by deposition of weld reinforcement material on the outside surface of the pipe?
Article 2.4 Welded Leak Box Repair
ASME XI IWA-4340MITIGATION OF DEFECTS BY MODIFICATION
Article 2.6 Full Encirclement Steel Reinforcing Sleeves for Piping
Article 2.7 Fillet Welded Patches with Reinforcing Plug Welds
Article 2.9 Alternatives to Postweld Heat Treatment
ASME XI CC N-432Repair Welding Using Automatic or Machine Gas Tungsten-Arc Welding (GTAW) Temper Bead Technique
Inquiry: May the automatic or machine GTAW process be used as an alternative to the SMAW process for performing the temper bead technique on Class 1 components?
ASME XI CC N-606Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW Temper Bead Technique for BWR CRD Housing/Stub Tube Repairs.
Inquiry: May the automatic or machine GTAW temper bead technique be used without use of preheat or postweld heat treatment on Class 1, BWR CRD housing or stub tube repairs?
ASME XI CC N-762Temper Bead Procedure Qualification Requirements for Repair/Replacement Activities Without Postweld Heat Treatment.
Inquiry: Under what conditions may the provisions for procedure qualification of temper bead welding of QW-290 be used in lieu of the procedure qualification requirements of IWA-4600, when postweld heat treatment will not be performed?
ASME XI CC N-740Full Structural Dissimilar Metal Weld Overlay for Repair or Mitigation of Class 1, 2, and 3 Items
Reply: It is the opinion of the Committee that, in lieu of the requirements of IWA-4410 and IWA-4611, a defect in austenitic stainless steel or austenitic nickel alloy piping, components, or associated welds may be reduced to a flaw of acceptable size in accordance with IWB-3640 by addition of a repair weld overlay. In addition, for these materials, in lieu of IWA-4410, a mitigative weld overlay may be applied. All Section XI references are to the 2007 Edition with the 2008 Addenda. For the use of this Case with other editions and addenda, refer to Table 1. The weld overlay shall be applied by deposition of weld reinforcement (weld overlay) on the outside surface of the piping, component, or associated weld, including ferritic materials when necessary, provided the following requirements are met.
ASME XI CC N-576Repair of Classes 1 and 2 SB-163, UNS N06600 Steam Generator Tubing
Inquiry: In lieu of meeting the requirements of the Construction Code, as required by IWA-4411,1 may SB-163, UNS N06600, steam generator tubing be repaired by applying a laser beam weld (LBW) deposit on the inside surface of the steam generator tubing?
ASME XI Appendix QWeld Overlay Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping Weldments
This Nonmandatory Appendix provides an alternative to the requirements of IWA-4420, IWA-4520, IWA-4530, and IWA-4600 for making repairs to, and subsequent examination of Class 1, 2, and 3 austenitic stainless steel pipe weldments [with an internal ID flaw] by deposition of weld reinforcement (weld overlay) on the outside surface of the pipe.
Article 2.12 Fillet Welded Patches
ASME PCC-2 Part 3 Mechanical Repairs
IWA-4000 Repair Replacement Activities
Article 3.2 Freeze Plugs
ASME XI IWA-4420 DEFECT REMOVAL REQUIREMENTSIWA-4421 General RequirementsDefects shall be removed or mitigated in accordance with the following requirements:(a) Defect removal by mechanical processing shall bein accordance with IWA-4462.(b) Defect removal by thermal methods shall be in accordance with IWA-4461.(c) Defect removal or mitigation by welding or brazingshall be in accordance with IWA-4411.(d) Defect removal or mitigation by modification shallbe in accordance with IWA-4340.
Article 3.6 Mechanical Clamp Repair
IWA-4700 Heat Exchanger Tubing [repair]IWA-4710 PluggingIWA-4720 Sleeving
ASME PCC-2 Part 4 Nonmetallic and Bonded Repairs
Section XI Code Case possibly later.
Article 4.2 Nonmetallic Composite Repair Systems: Low-Risk Applications
ASME PCC-2 Part 5 Examination and Testing
See response to Article 5.2
Article 5.2 Nondestructive Examination in Lieu of Pressure Testing for Repairs and Alterations
ASME XI IWA-4540 PRESSURE TESTING OF CLASSES 1, 2, AND 3 ITEMS(a) Unless exempted by (b), repair/replacement activities performed by welding or brazing on a pressure retaining boundary shall include a hydrostatic or system leakage test in accordance with Article IWA-5000, prior to, or as part of, returning to service. Only brazed joints and welds made in the course of a repair/replacement activity require pressurization and VT‐2 visual examination during the test.(b) The following are exempt from any pressure test:(1) cladding(2) heat exchanger tube plugging and sleeving(3) welding or brazing that does not penetrate through the pressure boundary(4) flange seating surface when less than half the flange axial thickness is removed and replaced(5) components or connections NPS 1 (DN 25) and smaller(6) tube‐to‐tubesheet welds when such welds are made on the cladding(7) seal welds(8) welded or brazed joints between non-pressure retaining items and the pressure‐retaining portion ofthe components(9) valve discs or seat
ASME XI CC N-416Alternative Pressure Test Requirement for Welded or Brazed Repairs, Fabrication Welds or Brazed Joints for Replacement Parts and Piping Subassemblies, or Installation of Replacement Items by Welding or Brazing, Classes 1, 2, and 3.Inquiry: What pressure test may be performed in lieu ofa hydrostatic pressure test for welded or brazed repairs, fabrication welds or brazed joints for replacement parts and piping subassemblies, or installation of replacement items by welding or brazing?
ASME XI CC N-843Alternative Pressure Testing Requirements Following Repairs or Replacements for Class 1 Piping Between the First and Second Inspection Isolation Valves.Inquiry: What alternative rules to the test pressure required by IWB-5221 may be applied following repair or replacement activities for that portion of Class 1 boundary between the first and second isolation valves in the injection path of Class 2 safety systems?
ASME XI CC N-795Alternative Requirements for BWR Class 1 System Leakage Test Pressure Following Repair/Replacement ActivitiesInquiry: What alternative to the pressure correspondingto 100% rated reactor power, of IWB-5221(a), maybe used during a BWR Class 1 system leakage test following repair/replacement activities?
ASME XI Repair techniques that have no equivalent in PCC-2
ASME XI CC N-569Alternative Rules for Repair by Electrochemical Deposition of Classes 1 and 2 Steam Generator TubingInquiry: As an alternative to IWA-4000, is it permissible to establish the acceptability of steam generator tubing by electrochemical deposition of material on the inside surface of the tube?
ASME XI CC N-666Weld Overlay of Class 1, 2, and 3 Socket Welded ConnectionsInquiry: As an alternative to the defect removal provisions of IWA-4420,1 may the structural integrity of a cracked or leaking socket weld, if the failure is a result of vibration fatigue, be restored by installation of weld overlay on the outside surface of the pipe, weld, fitting, or flange?
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George Antaki, Fellow ASME, has over 40 years of experience in nuclear power plants and process facilities, in the areas of design, safety analysis, startup, operation support, inspection, fitness for services and integrity analysis, retrofits and repairs. George has held engineering and management positions at Westinghouse and Washington Group International, where he has performed work at power and process plants, and consulted for the Department of Energy (DOE), the Nuclear Regulatory Commission (NRC) and the Electric Power Research Institute (EPRI).
Thank you George for the wonderful post on ASME XI Repairs. I deal with Pressure Vessel Equipment repair. Recently, I have been doing internship at a nuclear power plant. I just stumbled upon this one and found many more in your arsenal.
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