Document: NUREG-0800
Document ID: 18897384-49d0-41ca-b285-0b1201052b03
Document Type: srp
Title: CONTROL ROD MISOPERATION (SYSTEM MALFUNCTION OR OPERATOR ERROR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350372.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.3
CFR Part: 
CFR Title: 

Content:
result of anticipated operational occurrences. c. Criterion 25, which requires that the reactor protection system be designed to assure that specified acceptable fuel design limits are not exceeded in the event of a single malfunction of the reactivity control system. 2. The requirements of GDC 10, 20, and 25 concerning the specified acceptable fuel design limits are assumed to be met for this event when: a. The thermal margin limits (DNBR for PWRs) as specified in SRP Section 4.4, subsection II.1 are met. b. Fuel centerline temperatures as specified in SRP Section 4.2, sub- section II.A.2(a) and (b) do not exceed the melting point. c. Uniform cladding strain as specified in SRP Section 4.2, subsection II.A.2(b) do not exceed 1%. III. REVIEW PROCEDURES The reviewer, in determining whether the criteria are met, must determine the transients that should be considered for this event. Generally, the list of errors should include: inadvertently withdrawing one or several rods; leaving one or several rods behind during bank withdrawal; and 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 transients has been established, the reviewer must determine acceptability in accordance with the criteria of subsection II of this SRP. 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 15.4.3-2 Rev. 2 - July 1981 configuration, reactivity addition rate, moderator temperature,. fuel temperature, and void reactivity coefficients. 2. For each event, the