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
CFR Part: 
CFR Title: 

Content:
ns, iodine chemical form, and fission product release timing should reflect NRC-approved source terms and methodologies. Meeting this requirement provides assurance that, in the event of an undetected fuel-loading error, radiation exposures at the site boundary will not exceed a small fraction of the reference values specified in 10 CFR Part 100.10 III. REVIEW PROCEDURES The review procedures for fuel-loading errors are as follows: 1. The reviewer verifies that the various cases of misloaded fuel assemblies outlined in subsection I above have been analyzed by the applicant and the worst case determined. For each case, the effect on the reactor power distribution should be given. 2. The reviewer determines that the effect each postulated error has on reactor instrumentation has been ascertained. For limiting events (where fuel rod failure limits are exceeded), the reviewer verifies that acceptable techniques (see SRP Section 4.4) have been used to calculate the fuel temperature conditions. 3. The reviewer assuresensures compliance with acceptance criterion a of subsection II 11 above by reviewing the plant operating procedures to verify that they contain provisions requiring that incore instrumentation be used to search for misloaded fuel after each fueling operation. Since low-power mapping is typically done, searching for misloading can be accomplished by the usual low-power maps. DRAFT Rev. 2 - April 1996 15.4.7-4 4. When it is determined that fuel rod failure limits can be exceeded, the appropriate technical review branchPERB is requested to perform dose calculations to 12 assureensure that acceptable criterion b of subsection II above is met. 13 For standard design certification reviews under 10 CFR Part 52, the procedures above should be followed, as modified by the procedures in SRP Section 14.3 (proposed), to verify that the design set forth in the standard safety analysis report, including inspections, tests, analysis, and acceptance criteria (ITAAC), site