Document: NUREG-0800
Document ID: 1877a6e5-f5a2-4394-bd63-c323831e96d0
Document Type: srp
Title: INTRODUCTION - TRANSIENT AND ACCIDENT ANALYSES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML2231/ML22319A149.pdf
Revision Date: 2023-07
Chapter: 15
Section ID: 15.0
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ts for the principal design criteria for water- cooled nuclear power plants similar in design and location to plants for which construction permits have been issued by the Commission when the GDC were promulgated. For some water-cooled nuclear power plants, the GDC may not be sufficient and additional criteria must be identified and satisfied in the interest of public safety. In particular, it is expected that additional or different criteria will be needed to take into account unusual sites and environmental conditions, and for water-cooled nuclear power units of advanced design. Also, there may be water-cooled nuclear power units for which fulfillment of some of the GDC may not be necessary or appropriate. For plants such as these, departures from the GDC must be identified and justified. The following are examples of AOOs considered in previous licensing reviews for operating 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) 15.0-3 Draft Revision 4 – July 2023 • Depressurization by spurious operation of an active element, such as a relief valve (PWR and BWR) • Reactor-turbine load mismatch, including loss of load and turbine trip (PWR and BWR) • Blowdown of reactor coolant through a safety valve (PWR and BWR) • Control rod drop (inadvertent addition of absorber) (PWR) • Loss of normal feedwater (PWR and BWR) • Loss of condenser cooling (PWR and BWR) • Single error of an operator (PWR and BWR) • Failure of a control component (PWR and BWR) • Failure in the electrical system (PWR and BWR) • Minor reactor coolant system (RCS) leak or loss of reactor coolant such as from a ruptured small pipe or from a crack in a large pipe (PWR and BWR) • Minor secondary system break