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:
eviewed under SRP Section 15.0.3. 3. Fuel centerline temperatures (for PWRs) are reviewed under SRP Section 4.2, subsections II.A.2(a) and (b). 4. Uniform cladding strain (for BWRs) are reviewed under SRP Section 4.2, subsection II.A.2(b). 5. Reactivity coefficients and control rod worths are reviewed under SRP Section 4.3 6. The thermal margin limits (departure from nucleate boiling ratio (DNBR) for PWRs and minimum critical power ratio (MCPR) for BWRs) are reviewed under SRP Section 4.4. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. 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 margin to assure that specified acceptable fuel design limits are not to be exceeded during any condition of normal operation, including the effects of AOOs. 2. General Design Criterion 13 (GDC 13), which requires that the availability of instrumentation to monitor variables and systems over their anticipated ranges to assure adequate safety, and of appropriate controls to maintain these variables and systems within prescribed operating ranges. 3. General Design Criterion 17 (GDC 17), which requires, in part, 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. 4. General Design Criterion 20 (GDC 20), which requires, in part, that the protection system shall be designed to initiate automatically the operation of appropriate systems 15.4.2-3 Revision 3 - March 2007 to ensure 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