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:
ety for Testing and Materials, 1916 Race Street, Philadelphia, Pennsylvania 19103. Comments should be gent to the Secretary of the Commission. U.S. Nuclear Regulatory Guides awe issued to describe and make available to the purlicico section. methods acceptable to the NRC sauff of Implementing specific peas of the Commission's regulations. to delineate techniques used by the staff In evalu- The guides arc slauad In the following ten broad divisons: ating specific problems or postulated acckdents, or to provide guidance to appli- cants. Regulatory Guides ere not substltutes for regulations, and compliance 1. Power Reactors . Products with them Is not required. Methods and solutions different from those set out in Z Research and Test Reactors 7. Transportation the guides will be acceptable if they provide a badis for the findings requisite to 3. Fuels and Materials Facilities S. Occupational Health the issuance or continuance of a permit or icense by the Commisslon. 4. Environmental and Siting S. Antitrust Review Comments and suggestions for Improvments In those guides are encouraged 5. Materials and Plant Protection 10. General at all times. and guides will be revised, as appropriate, to accommodate com- ments and to reflect new information or experience. This guide was revwid as a Copies of published guldes may be obtained by written request Indicating the result of subetantive comments received from the public and edditional staff divisions desired to the U.S. Nuclear Regulatory Commission, Weshington. D.C. review. 2M. Attention: Director. Office of Standards Development. containments built in the United States. The main feature of this system is the use of cold-formed buttonheads for direct bearing at each end of the wire. The prestressed concrete reactor vessel (PCRV) of the Fort St. Vrain station in Colorado uses the BBRV system with 169-wire tendons developing approximately 2000 kips capacity each. A number of containments using the BBRV system with 90, 163,