Document: NUREG-0800
Document ID: a1ba9094-2225-4b8b-aadf-92e70968c29a
Document Type: srp
Title: REACTOR VESSEL INTEGRITY
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070432.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.3
CFR Part: 
CFR Title: 

Content:
Vessel Code, Section III. The stringent fracture toughness requirements of the regulations and ASME Code Section III will be met, including requirements for surveillance of vessel material properties throughout service life, in accordance with Appendix H of 10 CFR Part 50. Also, operating limitations on temperature and pressure will be established for this plant in accordance with Appendix G, "Protection Against Non-ductile Failure," of ASME Code Section III, and Appendix G, 10 CFR Part 50, and 10 CFR 50.61 (for PWRs) . 35 The integrity of the reactor vessel is assured because the vessel (1) will be designed and fabricated to the high standards of quality required by the ASME Boiler and Pressure Vessel Code and any pertinent Code Cases; (2) will be made from materials of controlled and demonstrated high quality; (3) will be subjected to extensive preservice inspection and testing to provide assurance that the vessel will not fail because of material or fabrication deficiencies; DRAFT Rev. 2 - April 1996 5.3.3-8 (4) will be operated under conditions and procedures and with protective devices that provide assurance that the reactor vessel design conditions will not be exceeded during normal reactor operation, maintenance, testing, and anticipated transientsoperational occurrences ; 36 (5) will be subjected to periodic inspection to demonstrate that the high initial quality of the reactor vessel has not deteriorated significantly under service conditions; (6) may be annealed to restore the material toughness properties if this becomes necessary; and (7) will be subjected to surveillance to account for neutron irradiation damage so that the operating limitations may be adjusted. For design certification reviews, the findings will also summarize, to the extent that the review is not discussed in other safety evaluation report sections, the staff's evaluation of inspections, tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC),