Technical report on material selection and processing guidelines for BWR coolant pressure boundary piping. Draft report. Revision 2 [electronic resource].
- Published
- Washington, D.C. : U.S. Nuclear Regulatory Commission, 1986.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: 55 : digital, PDF file
- Additional Creators
- U.S. Nuclear Regulatory Commission and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- This report updates and supersedes the technical positions NRC established in NUREG-0313, ''Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping,'' published in July 1977, and its subsequent revision published in July 1980. This report sets forth the NRC staff's revised acceptable methods to control the intergranular stress corrosion cracking susceptibility of BWR ASME Code Class 1, 2, and 3 pressure boundary piping and safe ends. For piping that does not fully comply with the material selection, testing, and processing guideline combinations of this document, varying degrees of augmented inservice inspection will be required, pursuant to 10 CFR 50.55a(g)(6)(ii). This revision also includes guidance regarding crack evaluation and weld overlay repair methods for long term operation or for continuing interim operation of plants until a more permanent solution is implemented.
- Report Numbers
- E 1.99:nureg-0313-rev.2
nureg-0313-rev.2 - Subject(s)
- Other Subject(s)
- Bwr Type Reactors
- Reactor Cooling Systems
- Pipes
- Fabrication
- Specifications
- Cracks
- Stainless Steels
- Stress Corrosion
- Welded Joints
- Alloys
- Chemical Reactions
- Chromium Alloys
- Cooling Systems
- Corrosion
- Corrosion Resistant Alloys
- Energy Systems
- Iron Alloys
- Iron Base Alloys
- Joints
- Reactor Components
- Reactors
- Steels
- Water Cooled Reactors
- Water Moderated Reactors
- Note
- Published through SciTech Connect.
06/01/1986.
"nureg-0313-rev.2"
"TI86901552"
Hazelton, W.S.
View MARC record | catkey: 14461240