Document: NUREG-0800
Document ID: 061b3f99-1bfd-4e65-be97-7e9affac9aef
Document Type: srp
Title: UNCONTROLLED CONTROL ROD ASSEMBLY WITHDRAWAL AT POWER
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0636/ML063600414.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.2
CFR Part: 
CFR Title: 

Content:
c 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 integrity and other vital functions are maintained in the event of postulated accidents. GDC 17 is applicable to SRP Section 15.4.2 because this section reviews an anticipated operational occurrence to which the GDC is applicable. Meeting the requirements of GDC 17 provides reasonable 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 exceeded. 4. Compliance with GDC 20 requires that the protection system be designed (1) to initiate automatically the operation of appropriate systems, including the reactivity control systems, to assure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences and (2) to sense accident conditions and to initiate the operation of systems and components important to safety. GDC 20 is applicable to this section because the reviewer evaluates the effects and consequences of an uncontrolled control rod assembly withdrawal at power (i.e., a bank for a PWR; a single rod with current control modes for a BWR). The reactor protection system (RPS) automatically initiates the operation of appropriate systems, including the reactivity control system (RCS), to terminate the AOOs analyzed in this SRP section. The AOOs are terminated in a timely manner so that acceptable specified fuel design limits are not exceeded for either a PWR or a BWR. SRP Section 15.4.2 as