Document: NUREG-0800
Document ID: 4d7d277e-c006-45d6-94df-c84845dd68d0
Document Type: srp
Title: INADVERTENT OPENING OF A PWR PRESSURIZER PRESSURE RELIEF VALVE OR A BWR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350144.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.1
CFR Part: 
CFR Title: 

Content:
ow are used during both the construction permit (CP) and operating license (OL) reviews. During the CP review, the values of system parameters and setpoints used in the analysis will be preliminary in nature and subject to change. At the OL review, final values should be used in the analysis, and the reviewer should compare these to the limiting safety system settings included in the proposed technical specifications. The applicant's description of the inadvertent pressure relief valve opening transient is reviewed by RSB regarding the occurrences leading to the initiat- ing event. The sequence of events from initiation until a stabilized condition is reached 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 operation of engineered safety systems that is required. 5. The extent to which operator actions are required. 6. The following TMI Action Plan (Ref. 11 and 12) items are reviewed to assume compliance with the acceptance criteria: a. II.K.2.8. For Babcock and Wilcox designs, the reviewer evaluates the auxiliary feedwater system upgrade and automatic.auxiliary 15.6.1-4 Rev. 1 - July 1981 feedwater initiation as they relate to determining the auxiliary feedwater performance requirements for this event, if the applicant's evaluation of this transient indicate that the system will be required' to function. b. II.K.3.1. If, as a result of the-evaluations performed as required by II.K.3.2, or if the applicant has in the design, an automatic power-operated relief valve isolation system, the reviewer confirms it has been properly accounted for in the analyses. c. II.K.3.5. The reviewer evaluates the assumption made regarding reactor coolant pump trip to assure that they are consistent and conservatively modeled with respect to