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:
tribution), 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 DRAFT Rev. 2 - April 1996 of instrumentation (e.g., the incore instruments used to detect fuel-loading errors after fueling operations) is a principal objective of GDC 13. Meeting the requirements of GDC 13 provides assurance that fuel-loading errors will be detected before they can affect power distribution or core integrity or could produce unacceptable stress on the reactor coolant pressure boundary.9 2. To establish the suitability of a nuclear power plant site, 10 CFR Part 100, specifies how the exclusion area, low population zone, and population center distance should be determined. Further, radiation exposure criteria stipulated in 10 CFR Part 100 provide reference values to be used in the site suitability determination based on postulated fission product releases associated with accidental events. 10 CFR Part 100 is applicable to SRP Section 15.4.7 because it specifies the methodology for calculating radiation exposures at the site boundary for postulated accidents or events that might be caused by a fuel-loading error. For events having a moderate-frequency of occurrence, any release of radioactive material must be such that the calculated doses at the site boundary are a small fraction of the 10 CFR Part 100 guidelines. 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 must 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. Meeting this requirement provides assurance that, in the event of an undetected