Determining prestressing forces for inspection of prestressed concrete containments
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 permit (1) periodic inspection of all important areas and (2) an appropriate surveillance program. Regulatory Guide 1.35, Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containment Structures,'' describes a basis acceptable to the NRC staff for developing an appropriate inservice inspection and surveillance program for ungrouted tendons in prestressed concrete containment structures of light-water-cooled reactors. This guide expands and clarifies the NRC staff position on determining prestressing forces to be used for inservice inspections of prestressed concrete containment structures.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research
- Sponsoring Organization:
- NRC
- OSTI ID:
- 6751027
- Report Number(s):
- REG/G-1.35.1; ON: TI90015186
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210700* -- Nuclear Power Plants-- Regulation & Licensing
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360603 -- Materials-- Properties
ADVISORY COMMITTEES
BUILDING MATERIALS
BUILDINGS
CONCRETES
CONTAINMENT
CONTAINMENT BUILDINGS
CONTAINMENT SHELLS
DOCUMENT TYPES
IN-SERVICE INSPECTION
INSPECTION
LICENSING
MATERIALS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PRESTRESSED CONCRETE
REACTOR LICENSING
REGULATORY GUIDES
STRAINS
STRESSES
THERMAL POWER PLANTS