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:
o 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 should include a provision requiring that reactor instrumentation be used to search for potential fuel-loading errors after fueling operations. 2. In the event the error is not detectable by the instrumentation system and fuel rod failure limits could be exceeded during normal operation, the offsite consequences should be a 15.4.7-3 Revision 2 - March 2007 small fraction of the 10 CFR Part 100 criteria. A small fraction is interpreted to be less than 10% of the 10 CFR Part 100 reference values. For the purpose of this review, the radiological consequences of any fuel-loading error should include consideration of the containment, confinement, and filtering systems. The applicant's source terms and methodologies with respect to gap release fractions, iodine chemical form, and fission product release timing should reflect NRC-approved source terms and methodologies. 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 13 requires that instrumentation be provided to monitor variables and systems (including those that can affect the fission process, the integrity of the reactor core, the reactor coolant pressure boundary, and the containment and its associated systems) over their anticipated ranges for normal operation, for anticipated operational occurrences, and for accident conditions. GDC 13 is applicable to this section because the reviewer evaluates the potential for fuel-loading errors that could adversely affect the fission process (power distribution), the integrity of the reactor core, and the reactor coolant pressure boundary. Each of these concerns is specifically addressed in GDC 13. In addition, ensuring the