Document: NUREG-0800
Document ID: 866c6ef6-2f4a-45c7-9e71-43e1f66a8422
Document Type: srp
Title: Draft Revision 3– July 2018
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1807/ML18071A066.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5
CFR Part: 
CFR Title: 

Content:
0.61 at the EOL. 4.2 Alternative Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events For PWRs for which a construction permit was issued under 10 CFR Part 50 before February 3, 2010, and whose reactor vessel was designed and fabricated to the 1998 Edition or earlier of the ASME Code, the requirements of 10 CFR 50.61a may be applied in lieu of 10 CFR 50.61. To apply 10 CFR 50.61a, the license holder must apply for and receive approval, via license amendment, from the NRR Director. The following is a summary of the requirements in 10 CFR 50.61a: (1) Each licensee is to project values of RTMAX-X for each reactor vessel beltline material for the EOL fluence of the material, where the subscript “X” could be axial weld (AX), plate (PL), forging (FO), or circumferential weld (CW). (2) Each licensee shall perform an examination and assessment of flaws in the reactor vessel beltline as required by 10 CFR 50.61a(e). BTP 5-3-9 Draft Revision 3 – July 2018 (3) Each licensee shall compare the projected RTMAX-X values for plates, forgings, axial welds, and circumferential welds to the PTS screening criteria of Table 1 of 10 CFR 50.61a. C. REFERENCES 1. American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Section III, including Appendix G, “Fracture Toughness Criteria for Protection Against Failure.” 2. American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Section XI, Appendix K, “Assessment of Reactor Vessels with Low Upper Shelf Charpy Impact Energy Levels.” 3. American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Section XI, Appendix G, “Fracture Toughness Criteria for Protection Against Failure.” 4. American Society for Testing and Materials, ASTM E-185-82, “Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels.” 5. U.S. Code of Federal Regulations, “Domestic Licensing of Production