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:
ing. Regulatory Guide 1.99 provides methods for predicting irradiation effects on fracture toughness properties that are applicable to compliance with the requirements of GDC 31. Application of GDC 31 assures that the pressure-temperature limits for the RCPB are appropriately determined and provide sufficient margin to account for uncertainties associated with flaws and the effects of service and operating conditions, and thereby provide a minimum probability of brittle material behavior leading to rapidly propagating failure. The probability of substantial reduction in capability to contain reactor coolant inventory, reduction in capability to confine fission products, and interference with core cooling is thereby minimized. 4. GDC 32 requires a material surveillance program for the reactor pressure vessel. Changes in the fracture-toughness properties of materials in the reactor pressure vessel beltline region, resulting from neutron irradiation and the thermal environment, are monitored by a surveillance program in compliance with the requirements of Appendix H of 10 CFR Part 50. Surveillance program compliance with GDC 32 and Appendix H is reviewed under SRP Section 5.3.1. Compliance with GDC 32 provides assurance that pressure-temperature limits continue to provide sufficient margin to minimize the probability of rapidly propagating failure of the RPV throughout the plant lifetime (see Technical Rationale for GDC 31). 5. 10 CFR 50.60 requires that all light-water nuclear power reactors must meet the fracture toughness requirements, including pressure-temperature limits, as set forth in 10 CFR 50, DRAFT Rev. 2 - April 1996 5.3.2-8 Appendix G. Compliance with the requirements of this rule and Appendix G provides assurance regarding the structural integrity of the RCPB and specifically the reactor vessel. The Technical Rationale for this rule is established under the Technical Rationale discussion for 10 CFR 50, Appendix G, below. 6. 10 CFR 50.61, establishes