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:
ide 1.154.69 For standard design certification reviews under 10 CFR 52, the procedures above should be followed, as modified by the procedures in SRP Section 14.3 (proposed), to verify that the design set forth in the standard safety analysis report, including inspections, tests, analysis, and acceptance criteria (ITAAC), site interface requirements and combined license action items, meet the acceptance criteria given in subsection II. SRP section 14.3 (proposed) contains procedures for the review of certified design material (CDM) for the standard design, including the site parameters, interface criteria, and ITAAC.70 5.3.2-15 DRAFT Rev. 2 - April 1996 IV. EVALUATION FINDINGS The reviewer verifies that sufficient information has been provided to satisfy the requirements of this SRP section and that the completeness and technical adequacy of histhe evaluation will 71 support the following statement in the staff's safety evaluation report: The pressure-temperature limits imposed on the reactor coolant system for all operating and testing conditions to assure adequate safety margins against nonductile or rapidly propagating failure are in conformance with the fracture toughness criteria of Appendix G of 10 CFR Part 50 and Section III, including Appendix G, "Protection Against Nonductile Failure," of the ASME Boiling and Pressure Vessel Code. The change in fracture toughness requirements of the pressure vessel during operation will be determined by Appendix H of 10 CFR Part 50. Thermal shock events have been adequately addressed in accordance with 10 CFR 50.61 (PWRs only). The use of 72 operating limits, based upon the criteria defined in Standard Review Plan Section 5.3.2, provides reasonable assurance that non-ductile or rapidly propagating failure will not occur, and constitutes an acceptable basis for satisfying the requirements of paragraphSections 50.55a, 50.60, and 50.61 (PWRs only) of 10 CFR Part 50 and 73 74 75 General Design Criteria 1, 14, 31 and 32 of