Document: NRC Regulatory Guide
Document ID: 42280809-8d61-4537-929f-69224a044bb5
Document Type: regulatory_guide
Title: Inservice Inspection of Prestressed Concrete Containment Structures with Grouted Tendons (Rev. 3)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1814/ML18142C165.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.90
CFR Part: 
CFR Title: 

Content:
cal tendons only). However, in France, Belgium, South Korea, Canada, and China, the use of grouted tendons in nuclear power plant containment structures has been more common. In addition, at least one U.S. reactor design certification application has proposed grouted tendons, AREVA’s Evolutionary Power Reactor (EPR). Currently there are no license applications requiring use of the guide. Therefore, there is no impact on internal and external stakeholders if RG 1.90 is not updated. 3. What is an estimate of the level of effort needed to address identified issues in terms of full-time equivalent (FTE) and contractor resources? Revision of the guide is estimated to require 0.2 FTE. NOTE: This review was conducted in May 2018 and reflects the staff’s plans as of that date. These plans are tentative and are subject to change. 4. Based on the answers to the questions above, what is the staff action for this guide (Reviewed with no issues identified, Reviewed with issues identified for future consideration, Revise, or Withdraw)? Reviewed with issues identified for future consideration. 5. Provide a conceptual plan and timeframe to address the issues identified during the review. At this moment a conceptual plan or timeframe is not necessary, due the limited applicability and current use of RG 1.90. If NRC’s licensing activities presents a need for revision in future, the NRC staff will perform a complete review analyzing the need from the user office and provide a plan and timeframe to address the issues. REFERENCES 1. American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section III, “Rules for Construction of Nuclear Power Plant Components,” Division 2, “Code for Concrete Reactor Vessels and Containments,” 2001 Edition through 2003 Addenda, American Society of Mechanical Engineers, New York, NY. Also known as ACI Standard 359-01, American Concrete Institute, Farmington Hills, MI. 2. American Society of Mechanical Engineers, Boiler &