Document: NUREG-0800
Document ID: 061b3f99-1bfd-4e65-be97-7e9affac9aef
Document Type: srp
Title: UNCONTROLLED CONTROL ROD ASSEMBLY WITHDRAWAL AT POWER
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0636/ML063600414.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.2
CFR Part: 
CFR Title: 

Content:
sure that specified acceptable fuel design limits are not exceeded as a result of AOOs. 5. General Design Criterion 25 (GDC 25), which 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 systems, such as accidental withdrawal (not ejection or dropout) of control rods. SRP Acceptance Criteria Specific SRP acceptance criteria acceptable to meet the relevant requirements of the NRC’s regulations identified above are as follows for the review described in this SRP section. The SRP is not a substitute for the NRC’s regulations, and compliance with it is not required. However, an applicant is required to identify differences between the design features, analytical techniques, and procedural measures proposed for its facility and the SRP acceptance criteria and evaluate how the proposed alternatives to the SRP acceptance criteria provide acceptable methods of compliance with the NRC regulations. 1. The requirements of General Design Criteria 10, 17, 20, and 25 concerning the specified acceptable fuel design limits are assumed to be met for this event when: A. The thermal margin limits departure from nucleate boiling ratio for PWRs and maximum critical power ratio for BWRs as specified in SRP Section 4.4, subsection II.1, are met. B. Fuel centerline temperatures (for PWRs) as specified in SRP Section 4.2, subsection II.A.2(a) and (b), do not exceed the melting point. C. Uniform cladding strain (for BWRs) as specified in SRP Section 4.2, subsection II.A.2(b), does not exceed 1%. Technical Rationale The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: 1. Compliance with GDC 10 requires that the reactor core and associated coolant, control, and protection systems be designed with appropriate margin to ensure that specified acceptable