Committee Pages - BPV Committee on Nuclear Inservice Inspection (XI)

BPV COMMITTEE ON NUCLEAR INSERVICE INSPECTION (XI)


	Meetings
		Future BPVC Code Week Meetings
		Boiler Code Event Website (Registration & Hotel Info)
		Boiler Code Meeting Schedule
		Future Meeting Hotel & Travel Information
	This Committee Please LOGIN to Reveal Members-Only Features
		Mgmt & Ops Manual
		Risk Management Strategic Plan
		Procedure Supplements
		BNCS Forms
		Nuclear C&S PowerPoint Presentations
		BPV XI Project Initiation Forms
		BPV XI Jurisdictions
		Single Mark FAQ
		Special Errata
		BPV XI Priority List
		BPV XI Committee Records
	Codes & Standards Resources
		Participation
		Volunteer Recruiting Toolbox
		ASME C&S Policies, Procedures, and Guidelines
		S&C Successful Practices for ASME Standards Development Committees
		S&C Training Modules
		S&C Vision and Mission Statement
		Committee Handbook
		Submit an Interpretation Request
	Publication Information
		Project Initiation Notices
		Public Review Drafts
		Proposed Changes
		ASME BPVC Section XI - Public Review Items
		ASME BPVC Section XI - Public Review Items
		Continuous Maintenance/Document Maintenance Cycle
		Code Cases
		Errata
		Special Notices

Approved Code Cases yet to be published

Code Case #	Code Case Name
	Alternative Requirements to Stress-Based Selection Criteria for Category B-J Welds
	Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic Pipe
	Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping for Raw Water Service
	Analytical Evaluation of Metal Loss in Class 2 and 3 Metallic Piping Buried in a Back-Filled Trench
	Clarification of NDE Practical Examination Requirements
	Evaluation Criteria for Temporary Acceptance of Flaws in Class 2 or 3 Piping
	Examination Requirements for the Core Makeup Tanks
	Temporary Acceptance of Leakage Through Brazed Joints of Class 3 Copper, Copper-Nickel, and Nickel-Copper Moderate Energy Piping
	Alternative Classification and Examination Requirements
	Reference Stress Corrosion Crack Growth Rate Curves for Irradiated Austenitic Stainless Steel in Light-Water Reactor Environments
	Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping and Gate Valves
	Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe

Minimum Site Requirements: IE 6.0+ • Firefox 2.0+ • Chrome 4.0+