Document: NUREG-0800
Document ID: 26aca061-b0de-4983-bbca-3fccb00afc2f
Document Type: srp
Title: PRESSURE-TEMPERATURE LIMITS AND PRESSURIZED THERMAL SHOCK1
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070431.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.2
CFR Part: 
CFR Title: 

Content:
increase significantly above the point referred to as the nil-ductility transition temperature. This temperature is established for the RCPB material in accordance with Section III of the ASME Code as supplemented by the requirements of 10 CFR 50, Appendix G. Pressure-temperature limits established in accordance with the ASME Code and Appendix G, are used to establish operating parameters that provide assurance that the RCPB will act in a non-brittle manner when subjected to stresses associated with normal operations, maintenance, testing and anticipated operational occurrences. The pressure-temperature limits must be monitored and adjusted to account for the effects of radiation embrittlement of the RCPB materials over the life of the plant, particularly the materials in the reactor vessel beltline. This is facilitated by a material surveillance program consistent with 10 CFR 50, Appendix H. Compliance with the requirements of Appendix G provides a method of satisfying the requirements of GDCs 14 and 31 with regard to assuring that the RCPB acts in a non- brittle manner and that the probability of rapidly propagating failure and gross rupture of the RCPB is extremely low. III. REVIEW PROCEDURES The reviewer will select and emphasize material from the procedures described below, as may be appropriate for a particular case. 5.3.2-9 DRAFT Rev. 2 - April 1996 1. Preliminary Safety Analysis Report (PSAR)Construction Permit/Design Certification Reviews36 Information in the Preliminary Safety Analysis Report (PSAR)/Standard Safety Analysis Report (SSAR) is reviewed for a commitment that the fracture toughness of the ferritic 37 materials in the reactor coolant pressure boundary will comply with the requirements of Appendix G of 10 CFR Part 50, as detailed in Section III of the ASME Boiler and Pressure Vessel Code and that the materials in the beltline region of the reactor vessel will comply with the requirements of 10 CFR 50.60 and associated Appendices G and 38 H of 10