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:
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 July 11, 1990 REGULATORY GUIDE DISTRIBUTION LIST (Division 1) SUBJECT: REVISION 3 OF REGULATORY GUIDE 1.35, "INSERVICE INSPECTION OF UNGROUTED TENDONS IN PRESTRESSED CONCRETE CONTAINMENTS," AND REGULATORY GUIDE 1.35.1, "DETERMINING PRESTRESSING FORCES FOR INSERVICE INSPECTION OF PRESTRESSED CONCRETE CONTAINMENTS" The subject regulatory guides have been revised to reflect (1) public comments, (2) insights gained by the survey and study of actual inservice inspections (NUREG/CR-2719), and (3) consideration of Subsection IWL, "Requirements for Class CC Concrete Components of Light-Water Cooled Power Plants," of Section XI of the ASME B&PV Code, published January 1989. The NRC staff will use the provisions of the guides as indicated in Section D, "Implementation," of the guides. A sample technical specification incorporating the provisions of the regulatory guides is under development and will be available after August 1990. A copy of the sample technical specification will be available upon request from the plant project managers in the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555. Eric S. Beckjord, 0Dector Office of Nuclear Re ulatory Research U.S. NUCLEAR REGULATORY COMMISSION REGULATORY Revision 3 July 1990 GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.35 (TASK SC 810-4) INSERVICE INSPECTION OF UNGROUTED TENDONS IN PRESTRESSED CONCRETE CONTAINMENTS A. INTRODUCTION General Design Criterion 53, "Provisions for Containment Testing and Inspection," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," requires, in part, that the reactor containment be designed to per mit (1) periodic inspection of all important areas and (2) an appropriate surveillance program. This guide describes a basis acceptable to the NRC staff for developing an