Document: NUREG-0800
Document ID: 126ade1c-f71d-4438-bb61-4fb69648889d
Document Type: srp
Title: CONTROL ROD MISOPERATION (SYSTEM MALFUNCTION OR OPERATOR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070714.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.3
CFR Part: 
CFR Title: 

Content:
ign limits are not exceeded as a result of AOOs. Meeting the requirements of GDC 25 provides assurance that a single malfunction of the reactivity control system, together with anticipated operational occurrences caused by the initiating event of a control rod misoperation due to system malfunction or operator error 15.4.3-5 DRAFT Rev. 3 - April 1996 during either normal operation or an AOO, will not cause specified acceptable fuel design limits to be exceeded.23 III. REVIEW PROCEDURES The reviewer, in determining whether the criteria are met, must determine the transientsAOOs that should be considered for this event. Generally, the list of errors should include: (1) inadvertently withdrawing one or several rods, (2) leaving one or several rods behind during bank withdrawal, and (3) inserting one or several rods with power compensation in other portions of the core. In addition to these events, the reviewer must also decide, by postulating single failures in equipment or errors in operation, whether additional single rod malfunctions can be created. Once the list of transientsAOOs has been established, the reviewer must determine acceptability in accordance with the criteria of subsection II of this SRP section.24 1. For each failure event analyzed, the cases which result in a limiting fuel rod condition should be presented. Initial conditions and parameter values selected for these cases should be justified with a sensitivity analysis or discussion. Conditions of first-order importance for any time in cycle are initial power level and distribution, initial rod configuration, reactivity addition rate, moderator temperature, fuel temperature, and void reactivity coefficients. 2. For each event, the analytical methods used by the applicant are reviewed. Those steady-state and transientAOO methods that are primarily based on reactor physics considerations are the responsibility of CPBSRXB. Where thermal-hydraulic methods 25 are involved, review assistance may be