Document: NUREG-0800
Document ID: 889e380e-bdb0-4af7-8056-db56551e3a1b
Document Type: srp
Title: UNCONTROLLED CONTROL ROD ASSEMBLY WITHDRAWAL FROM A
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070711.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.1
CFR Part: 
CFR Title: 

Content:
(1) 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 assures that the fuel cladding integrity is not challenged during and uncontrolled control rod assembly withdrawl in conjunction with a loss of onsite or of offsite power. 3. GDC 20 requires that the protective system automatically initiate the operation of the reactivity control system to assure that fuel design limits are not exceeded as a result of anticipated operational occurrences. The withdrawal of a control assembly significantly 15.4.1-3 DRAFT Rev. 3 - April 1996 impacts local fuel pin power, and could lead to cladding failure. Measures are required to assure that an abnormal rod withdrawal be detected and automatically terminated prior to fuel design safety limits being violated. Meeting GDC 20 assures that cladding integrity is not challenged during this anticipated operational occurrence. 4. GDC 25 requires that the reactor protection system be designed to assure 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 reactivity control system that would create an unmitigated withdrawal of a control assembly could lead to cladding failure. Meeting GDC 25 assures that a power transient fostered from a reactivity addition due to a single failure of the reactivity control system will be detected and terminated prior to a challenge of the fuel cladding integrity. III. REVIEW PROCEDURES The reviewer, in determining whether the acceptance criteria are met, considers the following: 1. Peak conditions for the transient are maximized by low initial power; thus, the power level of the reactor should be at the lowest possible value compatible with the control rod configuration used for the