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:
n as a dose mitigating system. This is a coordinating review function. 6. The movement of heavy loads (i.e., loads heavier than the combined weight of a spent fuel assembly and the fuel handling tool) or of irradiated fuel in the spent fuel pool and over the open reactor vessel is reviewed by ASB under SRP Sections 9.4.1 and 9.4.2. An analysis of the radiologi- cal consequences may be required for such drops of heavy objects if more than one fuel assembly can be damaged. The need for such calculation is determined by ASB who will advise AEB (note: the radiological consequences of a fuel cask drop in which the fuel inside the cask is damaged is reviewed by the AEB under SRP Section 15.7.5). II. ACCEPTANCE CRITERIA The AEB acceptance criteria for this SRP section are based on requirements of 10 CFR Part 100 (Ref. 1) with respect to the calculated radiological conse- quences of a fuel handling accident and General Design Criterion 61 (Ref. 2) with respect to appropriate containment, confinement, and filtering systems. Specific criteria necessary to meet the requirements are: 1. The plant site and dose mitigating ESF systems are acceptable with respect to the radiological consequences of a postulated fuel handling accident if the calculated whole-body and thyroid doses at the exclusion area and low population zone boundaries are well within the exposure guideline values of 10 CFR Part 100, paragraph 11. "Well within" means 25 percent or less of the 10 CFR Part 100 exposure guideline values, i.e., 75 rem for the thyroid and 6 rem for the whole-body doses. 2. The radioactivity control features of the fuel storage and handling systems inside containment and in the fuel building are acceptable if they meet the requirements of General Design Criterion 61, "Fuel Storage and Handling 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