Document: NUREG-0800
Document ID: 7ed30441-8f7a-44a4-b42a-6bbe8c5bbff4
Document Type: srp
Title: UNCONTROLLED CONTROL ROD ASSEMBLY WITHDRAWAL AT POWER
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070712.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.2
CFR Part: 
CFR Title: 

Content:
ant, control, and protection systems be designed with appropriate margin to ensure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences. GDC 10 is applicable to this section because the reviewer evaluates the effects and consequences of an uncontrolled control rod assembly withdrawal (a bank for a PWR; a single rod with current control modes for a BWR) at power to ensure that specified acceptable fuel design limits are not exceeded during normal operation, including the effects of AOOs. SRP Section 15.4.2 as well as SRP Sections 4.2, 4.3, and 4.4 provide guidance for ensuring that instrument setpoints are initially within and remain within the technical specification limits. Meeting the requirements of GDC 10 provides assurance that specified acceptable fuel design limits are not exceeded for AOOs caused by an uncontrolled control rod assembly withdrawal at power.25 2. Compliance with GDC 17 requires (in part) that an onsite and an offsite electric power system be provided to permit functioning of structures, systems, and components important to safety. The safety function for each system (assuming the other system is not functioning) shall be to provide sufficient capacity and capability to ensure that (1) specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded as a result of AOOs and (2) the core is cooled and containment and other vital functions are maintained. GDC 17 is applicable to SRP Section 15.4.2 because this section reviews an anticipated operational occurrence to which the GDC should be applied. Meeting the requirements of GDC 17 provides assurance that an uncontrolled control rod assembly withdrawal at power, in combination with a LOOP will not result in a reactor transient that could cause the reactor coolant pressure boundary design conditions or the fuel design limits to be