Materials, construction, and testing of concrete containments
Book
·
OSTI ID:6836680
General Design Criterion 1, Quality Standards and Records 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 structures, systems, and components important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. This guide describes bases acceptable to the NRC staff for implementing the above requirements with regard to the materials, construction, and testing of concrete containments. With the issuance of this revision to Regulatory Guide 1.136, the following regulatory guides have been withdrawn: 1.10, 1.15, 1.18, 1.19, 1.55, and 1.103.
- OSTI ID:
- 6836680
- Report Number(s):
- REG/G-1.136
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
BUILDING MATERIALS
CONCRETES
CONSTRUCTION
CONTAINMENT
CONTAINMENT SYSTEMS
DOCUMENT TYPES
ENGINEERED SAFETY SYSTEMS
MATERIALS
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
QUALITY ASSURANCE
REGULATORY GUIDES
TESTING
THERMAL POWER PLANTS
US NRC
US ORGANIZATIONS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
BUILDING MATERIALS
CONCRETES
CONSTRUCTION
CONTAINMENT
CONTAINMENT SYSTEMS
DOCUMENT TYPES
ENGINEERED SAFETY SYSTEMS
MATERIALS
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
QUALITY ASSURANCE
REGULATORY GUIDES
TESTING
THERMAL POWER PLANTS
US NRC
US ORGANIZATIONS