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:
REVIEW RESPONSIBILITIES Primary - Materials Engineering Branch (MTEB) Materials and Chemical Engineering Branch (EMCB)2 Secondary - None I. AREAS OF REVIEW 1. Pressure-Temperature Limits The regulations requiring the imposition of pressure-temperature limits on the reactor coolant pressure boundary are the following: ParagraphSection 50.55a of 10 CFR Part 50, "Codes and Standards," requires that 3 structures, systems, and components (SSC) be designed, fabricated, erected, constructed, 4 tested, and inspected to quality standards commensurate with the importance of the safety function to be performed. In addition, General Design Criterion 1 of Appendix A of 10 CFR Part 50, "Quality Standards and Records," requires that the codes and standards used to assure quality products in keeping with the safety function be identified and evaluated to determine their adequacy. General Design Criterion 14 of Appendix A of 10 CFR Part 50, "Reactor Coolant Pressure Boundary," requires that the reactor coolant pressure boundary be designed, fabricated, erected, and tested in order to have an extremely low probability of abnormal leakage, of rapid failure, and of gross rupture. Likewise, General Design Criterion 31, "Fracture Prevention of Reactor Coolant Pressure Boundary," requires, in part, that the DRAFT Rev. 2 - April 1996 5.3.2-2 reactor coolant pressure boundary be designed with sufficient margin to assure that when stressed under operating, maintenance and testing, the boundary behaves in a non-brittle5 manner and the probability of rapidly propagating fracture is minimized. Further, in order to assess the structural integrity of the reactor vessel, General Design Criterion 32, "Inspection of Reactor Coolant Pressure Boundary," requires, in part, an appropriate materials surveillance program for the reactor vessel beltline region. The reactor vessel beltline materials for Pressurized Water Reactors (PWRs) are evaluated for susceptibility to pressurized thermal shock (PTS)