Document: NUREG-0800
Document ID: 6cdd237d-c5b3-4a09-8753-54cfe1fea503
Document Type: srp
Title: REACTOR VESSEL MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190007.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.1
CFR Part: 
CFR Title: 

Content:
e staff positions of GL 88-01 or the recommendations of NUREG-0313, Revision 2 with regard to protection against IGSSC in or near weldment to the reactor vessel. 5. Fracture Toughness. The information submitted by the applicant relative to tests for fracture toughness is reviewed for conformance with the Code, Section III, paragraph NB-2300, and Appendix G of 10 CFR Part 50. These tests include Charpy V-notch impact tests and drop-weight tests. A description of the tests is reviewed, and the location of the test specimens and their orientation are verified. Information regarding calibration of instruments and equipment is reviewed for conformance to Code Section III, paragraph NB-2300. In the event that none of the fracture toughness tests has been performed, the preliminary safety analysis report (PSAR) must contain a statement of the applicant’s intention to perform this work in accordance with Code Section III, NB-2300 and Appendix G of 10 CFR Part 50. Revision 2 - March 2007 5.3.1-15 The final safety analysis report (FSAR) is reviewed to ensure that all the impact tests shown in NB-2300 have been performed. The results of the tests shall be in accordance with the acceptance criteria shown in Subsection II.5 of this SRP section. The reviewer evaluates the initial Charpy upper shelf energy for the reactor vessel materials in accordance with the acceptance criterion specified in 10 CFR Part 50, Appendix G, paragraph IV.A.1.a. Reactor vessel materials that do not meet the specified initial Charpy upper shelf energy acceptance criterion shall be evaluated in accordance with the provisions for additional analysis also specified paragraph in IV.A.1.a. In addition to the ASME Code, RG 1.161 provides an acceptable methodology for the performance of analyses intended to meet the provisions for the additional analysis in paragraph IV.A.1.a. The reviewer also evaluates the end-of-license Charpy upper shelf energy for the reactor vessel materials in accordance with the