Document: NUREG-0800
Document ID: 58e96831-02fa-4fe0-9367-ac30b1da435a
Document Type: srp
Title: CONTROL ROD MISOPERATION (SYSTEM MALFUNCTION OR OPERATOR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0636/ML063600415.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.3
CFR Part: 
CFR Title: 

Content:
OL action items and requirements and restrictions (e.g., interface requirements and site parameters). For a COL application referencing a DC, a COL applicant must address COL action items (referred to as COL license information in certain DCs) included in the referenced DC. Additionally, a COL applicant must address requirements and restrictions (e.g., interface requirements and site parameters) included in the referenced DC. Review Interfaces Other SRP sections interface with this section as follows: 1. General information on transient and accident analyses is provided in SRP Section 15.0. 2. Design basis radiological consequence analyses associated with design basis accidents are reviewed under SRP Section 15.0.3. 3. Review of the limiting anomalies for a boiling water reactor (BWR) with current modes of control rod operation is performed under Standard Review Plan (SRP) Sections 15.4.1 and 15.4.2, and no additional areas are considered under SRP Section 15.4.3. 4. Uniform cladding strain (for BWRs) and fuel centerline temperatures (for PWRs) are reviewed under SRP Section 4.2. 5. Reactivity coefficients and control rod worths are reviewed under SRP Section 4.3 6. Thermal margin limits are reviewed under SRP Section 4.4. 7. Safety systems required to prevent misoperations, as required by General Design Criterion 25, as well as the control rod system are reviewed under SRP Sections 7.2 and 7.7. The purpose of the review is to determine the events that are to be included as single error malfunctions (e.g., single rod withdrawal). The specific acceptance criteria and review procedures are contained in the referenced SRP sections. 15.4.3-3 Revision 3 - March 2007 II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. General Design Criterion 10 (GDC 10), which requires that the reactor core and associated coolant, control and protection systems be designed with appropriate