Control of ferrite content in stainless steel weld metal - Revision 3, April 1978

Book · Thu Jan 01 04:00:00 EST 1981

OSTI ID:6986811

General Design Criterion 1, Quality Standards and Records, of Appendix A, General Design Criteria for Nuclear Power Plants, to 10 CFR Part 50 requires that components important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety function to be performed. Criterion 14, Reactor Coolant Pressure Boundary, of Appendix A requires that the reactor coolant pressure boundary be designed, fabricated, erected, and tested so as to have an extremely low probability of abnormal leakage, of rapidly propagating failure, and of gross rupture. This guide describes a method acceptable to the NRC staff for implementing these requirements with regard to the control of welding in fabricating and joining safety-related austenitic stainless steel components and systems in light-water-cooled nuclear power plants.

• OSTI ID: 6986811
• Report Number(s): REG/G-1.31
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210700* -- Nuclear Power Plants-- Regulation & Licensing
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900 -- Nuclear Reactor Technology-- Reactor Safety
ALLOYS
AUSTENITIC STEELS
CARBON ADDITIONS
CHROMIUM ALLOYS
COOLING SYSTEMS
CORROSION RESISTANT ALLOYS
DOCUMENT TYPES
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
FABRICATION
FERRITE
IRON ALLOYS
IRON BASE ALLOYS
JOINING
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REGULATORY GUIDES
STAINLESS STEELS
STANDARDS
STEELS
THERMAL POWER PLANTS
US NRC
US ORGANIZATIONS
WELDING