Document: NUREG-0800
Document ID: b085cd1c-2d74-4547-b757-d8513d0cb353
Document Type: srp
Title: OVERPRESSURE PROTECTION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070419.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.2
CFR Part: 
CFR Title: 

Content:
ill have an extremely low probability of failure during transients. 2. GDC 31 requires that the reactor coolant pressure boundary be designed with sufficient margin to preclude brittle fracture during expected operational, maintenance, testing, and 5.2.2-5 DRAFT Rev. 3 - April 1996 accident conditions. During certain conditions in which the reactor coolant pressure boundary might behave in a brittle manner, the overpressure protection system is relied upon to maintain the reactor coolant system pressure below brittle fracture limits. Meeting GDC 31 will ensure that the reactor coolant pressure boundary is not subject to failure by brittle fracture. III. REVIEW PROCEDURES The procedures below are used during the construction permit (CP) review to assure that the design criteria and bases and the preliminary design as set forth in the preliminary safety analysis report meet the acceptance criteria given in subsection II of this SRP section. For operating license (OL) applications, the procedures are used to verify that the initial design criteria and bases have been appropriately implemented in the final design as set forth in the final safety analysis report and in the report on overpressure protection. The latter report is required by the ASME Code and is used as the basis for many of the individual review steps outlined below during the OL review. The OL review also includes the proposed technical specifications, to assure that they are adequate in regard to limiting conditions of operation and periodic surveillance testing. The following steps are taken by the SRXB reviewer in determining that the acceptance criteria of subsection II have been met. These steps should be applied to CP and OL reviews as appropriate. Previously reviewed designs may be used as a guide; however, the reviewer must verify that any changes are justified. 1. The piping and instrumentation diagrams are examined to determine the number, type, and location of the safety and relief valves in