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:
, General Design Criterion 1, "Quality Standards and Records," as it relates to quality standards for design, fabrication, erection and testing; B. 10 CFR Part 50, Appendix A, General Design Criterion 14, "Reactor Coolant Pressure Boundary," as it relates to assuring an extremely low probability of abnormal leakage, rapidly propagating failure and gross rupture of the reactor coolant pressure boundary; C. 10 CFR Part 50, Appendix A, General Design Criterion 31, "Fracture Prevention of Reactor Coolant Pressure Boundary," as it relates to assuring that the reactor coolant pressure boundary will behave in a non-brittle manner and the probability of rapidly propagating fracture is minimized; 5.3.2-3 DRAFT Rev. 2 - April 1996 D. 10 CFR Part 50, Appendix A, General Design Criterion 32, "Inspection of Reactor Coolant Pressure Boundary," as it relates to the reactor vessel materials surveillance program; E. 10 CFR Part 50, §50.55a, "Codes and Standards", as it relates to quality standards for design, and determination and monitoring of material fracture toughness; F. 10 CFR Part 50, §50.60, "Acceptance Criteria for Fracture Prevention Measures for Lightwater Nuclear Power Reactors for Normal Operation," as it relates to compliance with the requirements of 10 CFR 50, Appendices G and H;11 G. 10 CFR Part 50, §50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," as it relates to fracture toughness criteria for PWRs relevant to pressurized thermal shock events; and12 H. 10 CFR Part 50, Appendix G, "Fracture Toughness Requirements," as it relates to material testing and fracture toughness. The requirements of paragraph 50.55a and General Design Criteria 1, 14, 31 and 32 of Appendix A of 10 CFR Part 50 are met by the assurance that material of the reactor coolant pressure boundary possess adequate fracture toughness properties to resist rapidly propagating failure and act in a nonbrittle manner when stressed under operating,