Document: NUREG-0800
Document ID: 882f88fc-1752-4866-882f-5680abb93523
Document Type: srp
Title: INADVERTENT LOADING AND OPERATION OF A FUEL ASSEMBLY IN AN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550013.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.7
CFR Part: 
CFR Title: 

Content:
: 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. The specific acceptance criteria and review procedures are contained in the reference SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. General Design Criterion 13 (GDC 13), as it relates to providing instrumentation to monitor variables over anticipated ranges for normal operations, for anticipated operational occurrences, and for accident conditions. 2. 10 CFR Part 100, as it relates to offsite consequences resulting from reactor operations with an undetected misloaded fuel assembly. 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. The primary safeguards against fuel-loading errors are procedures and design features to minimize the likelihood of the event. Additional safeguards include incore instrumentation systems which would detect errors. However, should an error be made and go undetected, it is possible in some reactor designs for fuel rod failure limits to be exceeded. Therefore, the following acceptance criteria cover the event of operation with misloaded fuel caused by loading errors: 1. To meet the requirements of GDC 13, plant operating procedures