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:
REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of transient and accident analyses for PWRs/BWRs Secondary - None I. AREAS OF REVIEW The specific areas of reviews are as follows: 1. The organization responsible for reactor systems evaluates the effects and consequences of an uncontrolled control rod assembly withdrawal (a bank for a pressurized water reactor (PWR); a single rod with current control modes for a boiling water reactor (BWR)) at power to ensure conformance with the requirements of General Design Criteria 10, 13, 17, 20, and 25 under this Standard Review Plan (SRP) section. The review under this SRP section covers the description of the causes of the anticipated operational occurrence (AOO) and of the AOO itself, the initial conditions, the reactor parameters used in the analysis, the analytical methods and computer codes used, and the consequences of the AOOs as compared with the acceptance criteria. 2. COL Action Items and Certification Requirements and Restrictions. For a DC application, the review will also address COL action items and requirements and restrictions (e.g., interface requirements and site parameters). 15.4.2-2 Revision 3 - March 2007 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. 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