Document: NRC Regulatory Guide
Document ID: 91c1459d-4ae6-4802-8c6d-e805db860e10
Document Type: regulatory_guide
Title: Post-tensioned Prestressing Systems for Concrete Reactor and Containment (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1221/ML12216A010.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.103
CFR Part: 
CFR Title: 

Content:
nstruction permit applications until this guide is revised as a result of suggestions from the public or additional staff review. This guide reflects current NRC staff practice. There- fore, except in those cases in which the applicant proposes an acceptable alternative method for comply- TABLE A STATUS OF POSTTENSIONED PRESTRESSING SYSTEMS AS OF MAY 1976 Submitted For Licensing Review Reviewed For Licensing Acceptabii, .v Approved By the NRC Staff Used In U.S. Nuclear Power Plants To Date System BBRV 90, 169, 170, 186 Wires (1/4 in 0) 163 Wires (7 mm i) VSL (55 strands) Stressteel S/H (54 strands) Freyssinet (strand) SEEE (strand) Stressteel (6 1-3/8 in. bars) PCRV Strand- Wrap X X X X X X X X X X X X X X X X X X X X X 1.103-4