Document: NUREG-0800
Document ID: a650b8f2-b0fa-4f0f-bc8f-55bb3f6ec603
Document Type: srp
Title: INADVERTENT OPENING OF A PWR PRESSURIZER PRESSURE RELIEF VALVE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0708/ML070820094.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.1
CFR Part: 
CFR Title: 

Content:
adequate, timely protection. GDC 26 requirements provide assurance of appropriate margins to accommodate malfunctions of the reactivity control system, including stuck rods, minimizing the possibility that specified acceptable fuel design limits would be exceeded. 5. 10 CFR 50.34(f), “Additional TMI-Related Requirements,” applies to this section because the TMI incident involved a stuck open power-operated relief valve. For plants licensed under 10 CFR Part 52, the requirements of 10 CFR 50.34 are incorporated under 10 CFR 52.47 and 10 CFR 52.79. III. REVIEW PROCEDURES The reviewer will select material from the procedures described below, as may be appropriate for a particular case. These review procedures are based on the identified SRP acceptance criteria. For deviations from these acceptance criteria, the staff should review the applicant’s evaluation of how the proposed alternatives provide an acceptable method of complying with the relevant NRC requirements identified in Subsection II. 15.6.1-7 Revision 2 - March 2007 The procedures are used during both the construction permit (CP) and operating license (OL) reviews. During the CP review, the values of system parameters and setpoints in the analysis are preliminary and subject to change. At the OL review, final values should be in the analysis, and the reviewer should compare these to the limiting safety system settings in the proposed technical specifications. The applicant's description of the inadvertent pressure relief valve opening transient is reviewed for the occurrences leading to the initiating event. The sequence of events from initiation until stabilization is reviewed to ascertain: 1. The extent to which normally operating plant instrumentation and controls are assumed to function. 2. The extent to which plant and reactor protection systems are required to function. 3. The credit taken for the functioning of normally operating plant systems. 4. The extent to which the operation of engineered