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:
the review and their methods of application are contained in the referenced SRP section of the corresponding review branch. II. ACCEPTANCE CRITERIA The RSB acceptance criteria are based on meeting the relevant requirements of the following regulations: A. General Design Criterion (GDC) 10 (Reference 2), as it relates to the reactor coolant system being designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during normal operations including anticipated operational occurrences.. B. General Design Criterion 15 (Reference 3), as it relates to the reactor coolant system and its associated auxiliaries being designed with app ro- priate margin to assure that the pressure boundary will not be breeched during normal operations including anticipated operational occurrences. C. General Design Criterion 26 (Reference 4) as it relates to the reactivity control system to provide adequate control of reactivity changes during manual operations and anticipated transients to assure that the acceptable fuel design limits are not exceeded. 15.6.1-2 Rev. 1 - July 1981 D. TMI Action Plan requirements items No's. II.K.2.8, II.K.3.1, II.K.3.5, II.K.3.16, II.K.3.25 and II.K.3.40 of NUREGs-0718 and -0737 (Ref. 11 and 12). The general objective in the review of inadvertent primary pressure relief valve opening events is to confirm-that the following criteria are met: 1. The consequences of the transient are less severe than the consequences of another transient that results in a decrease of reactor coolant inventory and has the same anticipated frequency classification. 2. The plant responds to the pressure relief valve opening transient in such a way that the criteria regarding fuel damage and system pressure are met. The specific criteria necessary to meet the requirements of GDC 10, 15 and 26 for incidents of moderate frequency* are: I a. Pressure in the reactor coolant and main steam systems should be maintained below 110% of the design