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:
REVIEW RESPONSIBILITIES Primary - Reactor Systems Branch (SRXB) Secondary - None I. AREAS OF REVIEW A. Overpressure protection for the reactor coolant pressure boundary (RCPB), during power operation of the reactor, is ensured by application of relief and safety valves and the reactor protection system. For boiling water reactors (BWRs), the area of review includes relief and safety valves on the main steam lines and piping from these valves to the suppression pool. For pressurized water reactors (PWRs), the area of review includes pressurizer relief and safety valves and the piping from these valves to the quench tank, on the primary, and steam generator relief and safety valves on the secondary. 1 The adequacy of the proposed preoperational and initial startup test programs is examined as a part of this review. The reviewer also evaluates the proposed technical specifications to assure that they are adequate with regard to limiting conditions of operation and periodic surveillance testing. B. Overpressure protection for the RCPB, during low temperature operation of the plant (startup, shutdown), is ensured by the application of pressure relieving systems that function during the low temperature operation. For PWRs the area of review includes relief valves with piping to the quench tank, the makeup and letdown system, and the RHR system which may be operating when the primary system is water solid. For DRAFT Rev. 3 - April 1996 5.2.2-2 BWRs, no special area of review is required since BWRs never operate in water-solid conditions. Review Interfaces:2 SRXB also performs the following review under the SRP section indicated: 1. Reviews the reactor coolant depressurization system for PWRs as part of its primary review responsibility for SRP Section 6.8 (proposed).3 2. The SRXB also reviews the design of systems that interface with the reactor coolant system with regard to the capability of the interfacing system to withstand full RCS pressure as part of its primary