2010 ASME Boiler and Pressure Vessel Code BPVC Section XI - Rules for Inservice Inspection of Nuclear Power Plant Components

2010 ASME Boiler and Pressure Vessel Code BPVC Section XI - Rules for Inservice Inspection of Nuclear Power Plant Components contains Divisions 1 and 3, in one volume and provides rules for the examination, inservice testing and inspection, and repair and replacement of components and systems in light water cooled and liquid metal cooled nuclear power plants. The Division 2 rules for inspection and testing of components of gas cooled nuclear power plants have been deleted in the 1995 Edition. With the decommissioning of the only gas cooled reactor to which these rules apply, there is no apparent need to continue publication of Division 2. Application of this Section of the Code begins when the requirements of the Construction Code have been satisfied. The rules of this Section constitute requirements to maintain the nuclear power plant while in activities. The rules require a mandatory program of scheduled examinations, testing, and inspections to evidence adequate safety. The method of nondestructive examination to be used and flaw size characterization are also contained within this Section.

Summary of changes:

• 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.
• The factor "Y" for defining allowable sizes for subsurface flaws has been revised and the acceptance standard on a/t for subsurfaces flaws was limited to ~15%.
• Clarified "isolable by means of valves."
• Provided guidelines for evaluating non-destructive examination coverage percentages.
• Revised the submittal of the inspection summary.
• Clarified acceptance criteria for leakage.
• Deleted the requirement for applicable Manufacturer's Data Reports to be attached to the NIS-2 form.
• Added a new paragraph to address the Owner's responsibility for requiring the contracted Repair/Replacement Organizations to provide a report documenting their repair/replacement activities.
• Added a new paragraph to establish the contracted Repair/Replacement Organizations responsibility to prepare a report, acceptable to the Owner, documenting their repair/replacement activities.
• Added a new Nonmandatory Appendix to provide Report Form RRA-1 that may be used for documenting contracted repair/replacement activities and will assist the Owner in completing and filing the NIS-2. * Revised the flaw Acceptance Standards for Class 1 ferritic and austenitic piping.
• Added new paragraphs to require additional examinations when new flaws or significant changes in flaw characteristics resulted in necessary corrective actions.
• Revised the membrane plus bending stress limit load cutoff for circumferential flaws.
• 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.
• Revised to clarify requirements for mechanical clamping devices.
• Revisions provide alternative wording to correct imprecise language and ambiguity.
• 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.

BPVC-XI-2010