Document: NUREG-0800
Document ID: c9c204f0-a162-491c-8c25-ee0418212f29
Document Type: srp
Title: PRESSURE-TEMPERATURE LIMITS, UPPER-SHELF ENERGY, AND PRESSURIZED
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0703/ML070380185.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.2
CFR Part: 
CFR Title: 

Content:
THERMAL SHOCK REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of component integrity issues related to reactor vessels Secondary - None I. AREAS OF REVIEW The staff will review the application with respect to the regulations concerning, (a) pressure-temperature (P-T) limits on maintaining the reactor coolant pressure boundary (RCPB), (b) reactor vessel beltline Charpy upper-shelf energy (USE), and (c) assessment of potential pressurized thermal shock (PTS) (pressurized-water reactor (PWR) only). The specific areas of review are as follows: 1. Pressure-Temperature Limits/Upper-Shelf Energy/Pressurized Thermal Shock A. Pressure-Temperature Limits. The staff will review the P-T limits imposed on the RCPB during any condition of normal operation, including anticipated operational occurrences and hydrostatic tests, under this section of the SRP to ensure adequate safety margins of structural integrity for the ferritic components of the RCPB. 5.3.2-2 Revision 2 - March 2007 The regulations in 10 CFR 50.60 and associated Appendix G to 10 CFR Part 50 describe the conditions that require P-T limits and provide the general basis for these limits. B. Upper-Shelf Energy. The staff will review reactor vessel beltline materials, which must have Charpy USE values of no less than 102 joules (J) (75 foot-pounds (ft-lb)) initially and must maintain USE values throughout the life of the vessel of no less than 68 J (50 ft-lb). If a material’s USE values are projected to be less than 68 J, a safety analysis must be performed that will provide margins of safety against fracture equivalent to those described by Appendix G to Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (hereinafter referred to as the ASME Code). Reactor vessel beltline Charpy USE drop may be estimated using Regulatory Guide 1.99 when surveillance data are not available or are not applicable. C. Pressurized Thermal Shock. The staff will