Document: NUREG-0800
Document ID: 7ed30441-8f7a-44a4-b42a-6bbe8c5bbff4
Document Type: srp
Title: UNCONTROLLED CONTROL ROD ASSEMBLY WITHDRAWAL AT POWER
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070712.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.2
CFR Part: 
CFR Title: 

Content:
10), which requires that specified acceptable 15 fuel design limits are not to be exceeded during normal operation, including the effects of anticipated operational occurrencesAOOs. b. General Design Criterion 17 (GDC 17), which requires that an onsite electric power system and an offsite electric power system be provided to permit functioning of structures, systems, and components important to safety.16 b.c. General Design Criterion 20 (GDC 20), which requires that the protection 17 system initiate automatically appropriate systems to assureensure that specified 18 acceptable fuel design limits are not exceeded as a result of anticipated operational occurrencesAOOs. c.d. General Design Criterion 25 (GDC 25) , which requires that the reactor 19 protection system be designed to assureensure that specified acceptable fuel 20 design limits are not exceeded in the event of a single malfunction of the reactivity control system. 2. The requirements of GDCGeneral Design Criteria 10, 17, 20, and 25 concerning the 21 22 specified acceptable fuel design limits are assumed to be met for this event when: a. The thermal margin limits (DNBR for PWRs and MCPR 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), do not exceed 1%. 15.4.2-3 DRAFT Rev. 3 - April 1996 Technical Rationale23 The technical rationale for application of these acceptance criteria to reviewing the uncontrolled control rod assembly withdrawal at power is discussed in the following paragraphs:24 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 fuel design limits are not exceeded during any condition of normal operation, including the