Published July 1976
| Version v1
Report
Quality verification for plate-type uranium-aluminum fuel elements for use in research reactors
Description
Paragraph (a) (7) of 50.34, ''Contents of Applications: Technical Information,'' of 10 CRF Part 50, ''Licensing of Production and Utilization Facilities,'' requires that each applicant for a construction permit to build a production or utilization facility include in its Preliminary Safety Analysis Report (PSAR) a description of the quality assurance program to be applied to the design, fabrication, construction, and testing of the structures, systems, and components of the facility. The Regulatory Guide presented describes a method acceptable to the NRC staff for establishing and executing a quality assurance program for verifying the quality of plate-type uranium-aluminium fuel elements used in research reactors
Additional details
Publishing Information
- Imprint Pagination
- 3 p.
- Report number
- REG/G--2,3(07-76)(Rev.1)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8311308
- Subject category
- S99: GENERAL AND MISCELLANEOUS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- ALUMINIUM; FUEL ELEMENTS; FUEL PLATES; QUALITY ASSURANCE; REGULATORY GUIDES; RESEARCH REACTORS; URANIUM; US NRC
- Descriptors DEC
- ACTINIDES; DOCUMENT TYPES; ELEMENTS; METALS; NATIONAL ORGANIZATIONS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; US ORGANIZATIONS
Optional Information
- Notes
- NUREG.