Document: NUREG-0800
Document ID: 25cb3efc-9642-430d-a72f-52decd59b34f
Document Type: srp
Title: INTRODUCTION - TRANSIENT AND ACCIDENT ANALYSES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070710376.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0
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CFR Title: 

Content:
nit. The SRP uses the term AOOs to refer to the events that are categorized in Regulatory Guide 1.70 and in Regulatory Guide 1.206 as incidents of moderate frequency (i.e., events that are expected to occur several times during the plant’s lifetime) and infrequent events (i.e., events that may occur during the lifetime of the plant). Incidents of moderate frequency and infrequent events are also known as Condition II and Condition III events, respectively, in the commonly used, oft- cited but unofficial American Nuclear Society (ANS) standards. The reviewer will continue to evaluate applications, according to the categorizations and acceptance criteria of References 4 and 5, for licensees that have these categorizations in their licensing bases, or if they wish, according to the categorizations and acceptance criteria of this SRP section. The reviewer will evaluate new applications (i.e., those pertaining to plants that are not yet constructed) according to the categorizations and acceptance criteria of this SRP section. The following are some examples of AOOs in pressurized-water reactor (PWR) and boiling-water reactor (BWR) designs: • Inadvertent control rod or rod group withdrawal (PWR and BWR) • Loss or interruption of core coolant flow, excluding reactor coolant pump locked rotor (PWR) • Inadvertent moderator cooldown (PWR and BWR) • Inadvertent chemical shim dilution (PWR) • Depressurization by spurious operation of an active element, such as a relief valve (PWR and BWR) • Blowdown of reactor coolant through a safety valve (PWR and BWR) • Loss of normal feedwater (PWR and BWR) • Loss of condenser cooling (PWR and BWR) • Steam generator tube leaks (PWR) 15.0-3 Revision 3 - March 2007 • Reactor-turbine load mismatch, including loss of load and turbine trip (PWR and BWR) • Control rod drop (inadvertent addition of absorber) (PWR) • Single error of an operator (PWR and BWR) • Single failure of a control component (PWR and BWR) •