Document: NUREG-0800
Document ID: 6e757273-b12b-4603-aace-b01e49e5a6da
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF FUEL HANDLING ACCIDENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350313.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.7.4
CFR Part: 
CFR Title: 

Content:
radiological consequences will be reduced by the 'degree of mixing and dilution occurring prior to containment isolation. 5. The atmospheric dispersion factors; X/Q values, to be used in analyzing the consequences of the accident are provided by the assigned meteorologist. I 15.7.4-4 Rev. 1 - July 1981 6. The doses calculated by the applicant and independently by the staff are compared to the acceptance criteria in subsection II. If the results of the dose calculations indicate the dose guideline values may be exceeded, alternatives which would reduce the doses to an acceptable level are examined and explored with the applicant (e.g., increased distance, better filters). IV. EVALUATION FINDINGS The reviewer verifies that sufficient information has been provided by the applicant and the staff independent dose calculations support conclusions of the following type, to be included in the staff's safety evaluation report: The staff finds that the applicant has provided an adequate system to mitigate the radiological, consequences of a postulated fuel handling accident inside the containment and in the fuel building. The staff concludes that the fuel handling system meets the relevant requirements of General Design Criterion 61. The staff further concludes that the distance to the exclusion area and to the low population zone boundaries for the (INSERT PLANT NAME) site, in conjunction with the operation of dose mitigating ESF and implementation of plant procedures, are sufficient to provide reasonable assurance that the calculated offsite radiological consequences of a postulated fuel handling accident are well within the 10 CFR Part 100 exposure guidelines. The staff's conclusion is based on (1) the staff's determination that the design features and plant procedures at the (INSERT PLANT NAME) facility meet the requirements of General Design Criterion 61 with respect to radioactivity control; (2) the staff review of the applicant's assumptions and analyses of the