Document: NUREG-0800
Document ID: 1734e678-943d-4e2c-a9a5-1e89a00a9865
Document Type: srp
Title: UNCONTROLLED CONTROL ROD ASSEMBLY WITHDRAWAL FROM A
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0636/ML063600413.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.1
CFR Part: 
CFR Title: 

Content:
operating ranges. GDC 13 applies to this section because the reviewer evaluates the sequence of events, including automatic actuations of protection systems, and manual actions, and determines whether the sequence of events justified, based upon the expected values of the relevant monitored parameters and instrument indications. 3. GDC 17 requires that an onsite electric power system and an offsite electric power system be provided to permit functioning of structures, systems, and components 15.4.1-4 Revision 3 - March 2007 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 specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded as a result of anticipated operational occurrences. This section reviews an anticipated operational occurrence. Meeting GDC 17 ensures that the fuel cladding integrity is not challenged during an uncontrolled control rod assembly withdrawal in conjunction with a loss of onsite or of offsite power. 4. GDC 20 requires that the protective system automatically initiate the operation of the reactivity control system to ensure that fuel design limits are not exceeded as a result of anticipated operational occurrences. The withdrawal of a control assembly significantly impacts local fuel pin power, and could lead to cladding failure. Measures are required to ensure that an abnormal rod withdrawal is detected and automatically terminated prior to fuel design safety limits being violated. Meeting GDC 20 ensures that cladding integrity is not challenged during this anticipated operational occurrence. 5. GDC 25 requires that the reactor protection system be designed to ensure that specified acceptable fuel design limits are not exceeded for any single malfunction of the reactivity control system, such as accidental withdrawal of control rods. A failure of the