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:
or other corrective actions to prevent potential PTS related failure of the reactor vessel if continued plant operation beyond the screening criteria is planned.34 Technical Rationale:35 The technical rationale for application of the above acceptance criteria to the reactor coolant pressure boundary pressure-temperature limits is discussed in the following paragraphs. 1. GDC 1 and 10 CFR 50.55a establish quality assurance requirements for the design, fabrication, erection, and testing of structures, systems and components (SSC) important to safety. GDC 1 establishes that the quality standards to be applied to SSC shall be commensurate with the importance of the safety functions to be performed. 10 CFR 50.55a, in relevant part, establishes those provisions of the ASME Boiler and Pressure Vessel Code that must be complied with to ensure that SSCs are designed, fabricated, erected, tested, and inspected to quality standards commensurate with the importance of the safety function to be performed. The primary safety functions of the RCPB are to prevent a loss of reactor coolant through leakage or gross failure of RCPB piping or components, and to act as a containment barrier to the release of fission products in the event of an accident resulting in fuel damage. Pressure-temperature limits are established for the reactor coolant pressure boundary (RCPB) in accordance with Section III of the ASME Boiler and Pressure Vessel Code, Appendix G, to ensure that the RCPB material fracture toughness requirements are satisfied. Compliance with GDC 1 and 10 CFR 50.55a provides assurance that the RCPB meets the appropriate quality standards of the 5.3.2-7 DRAFT Rev. 2 - April 1996 ASME Code and thus the probability of RCPB material failure and the subsequent effects on reactor core cooling and confinement are minimized. 2. GDC 14 establishes that the RCPB be designed, fabricated, erected, and tested so as to have an extremely low probability of abnormal leakage, of rapidly