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:
dling and Radioactivity Control," (Ref. 2) with respect to appropriate containment, confinement and filtering systems. 3. The model for calculating the whole-body and thyroid doses is acceptable if it incorporates the appropriate conservative assumptions in Regulatory Guide 1.25 (Ref. 3) with the exception of the guidelines for the atmos- pheric dispersion factors (X/Q values). The acceptability of the X/Q values is determined under SRP Section 2.3.4. 4. An ESF grade atmosphere clean-up system is required for the spent fuel storage area to reduce the potential radiological consequences. 15.7.4-2 Rev. 1 - July 1981 5. The containment design is acceptable with respect to a postulated fuel handling accident if it possesses the capability for prompt radiation detection by use of redundant radiation monitors and automatic isolation if fuel handling operations inside containment occur when the containment is open to the environment (i.e., with a containment purge exhaust system). An acceptable alternative approach is containment venting through an ESF atmosphere cleanup system or containment isolation during fuel handling operations. III. REVIEW PROCEDURES The reviewer selects and emphasizes specific aspects of this SRP section as are appropriate for the particular plant. The judgment on which areas need to be given attention and emphasis are determined by the similarity of the infor- mation presented by the applicant to that recently reviewed on other plants and whether items of special safety significance are involved. 1. The relevant portion of Chapter 15 of the applicant's safety analysis report (SAR) are reviewed to determine the values of those fuel parameters which affect fission product release and fuel pool iodine decontamination factors, including the maximum fuel rod pressurization, peak linear power density for the highest power assembly, maximum centerline operating fuel temperature for the peak assembly, average burnup for the peak assembly, and minimum