Document: NRC Regulatory Guide
Document ID: 0b9a3243-ab39-402c-9f4b-215c6e4f79ab
Document Type: regulatory_guide
Title: Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments (Rev. 3)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0037/ML003740007.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.35
CFR Part: 
CFR Title: 

Content:
g general visual examination of the containment exterior sur face. h. Presence of free water. 8. REPORTING TO THE NRC The reportable conditions listed in Regulatory Positions 7.1.3, 7.1.4, 7.1.5, 7.3, or 7.4 could indi cate a possible abnormal degradation of the contain ment structure (a boundary designed to contain ra dioactive materials). Any such condition should be reported to the NRC in accordance with the recom mended reporting program of Regulatory Guide 1.16, "Reporting of Operating Information-Appendix A Technical Specifications." The NRC staff recognizes that for some contain ment designs, adoption of all provisions of this guide may not be feasible. In those cases, licensees should present alternatives for those provisions of the guide they are unable to implement. D. IMPLEMENTATION The purpose of this section is to provide informa tion to applicants and licensees regarding the NRC staff's plans for using this regulatory guide. Except in those cases in which the applicant or licensee proposes an acceptable alternative method for complying with specified portions of the Commis sion's regulations, the methods described herein will be used in the evaluation of inservice inspection and surveillance programs for the following nuclear power plants using prestressed concrete containments with ungrouted tendons: 1. Plants for which the construction permit or design approval is issued after July 31, 1990. 2. Plants for which the licensee voluntarily commits to the provisions of this guide. 1.35-5 Sample Size Criteria (See Regulatory Position 2) 4% 2% 0 1 5 10 20 30 I I IIII lime after Initial Structural Integrity Testing of Containment, Years (Lift-off Testing Schedule, Containment No. 1) I-I 2 Years (Maximum) 0 1 5 15 25 35 III I Time after Initial Structural Integrity Testing of Containment, Years (Lift-off Testing Schedule, Containment No. 2) Figure 1. Schedule of Lift-off Testing for Two Containments at a Site (See Regulatory Position 1.5) REGULATORY ANALYSIS