Document: NUREG-0800
Document ID: c674c9e0-9f79-481c-9349-461015e181cb
Document Type: srp
Title: INADVERTENT LOADING AND OPERATION OF A FUEL ASSEMBLY IN AN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070719.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.7
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CFR Title: 

Content:
o offsite consequences resulting from reactor 6 operations with an undetected misloaded fuel assembly. 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 are necessary to cover the event of operation with misloaded fuel caused by loading errors: a. 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. b. 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 small fraction of the 10 CFR Part 100 guidelines. Technical Rationale7 The technical rationale for application of these acceptance criteria to reviewing the applicant's analysis of potential fuel-loading errors is discussed in the following paragraphs:8 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 appropriate use 15.4.7-3