Document: NUREG-0800
Document ID: 240b218f-0879-4774-a145-71a59b902d69
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF A DESIGN BASIS LOSS-OF-COOLANT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350160.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.5
CFR Part: 
CFR Title: 

Content:
ide 1.7. The atmospheric dispersion characteristics (X/Q values) used in the calculations are those stated in Section 2.3 of this report. The results of the calculation are reported in Table 15. . The .contribution of the ESF leakage doses to the total calculated radio- logical consequences of the LOCA is evaluated in Section 15. V. IMPLEMENTATION The following provides guidance to applicants and licensees regarding the staff's plans for using this SRP section. Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides. VI. REFERENCES 1. Regulatory Guide 1.7, "Control of Combustible Gas Concentrations in Contain- ment Following a Loss-of-Coolant Accident." 2. 10 CFR Part 100. § 100.11, "Determination of Exclusion-Area Low Popula- tion Zone and Population Center Distance." .3. Regulatory Guide 1.3, "Assumptions Used for Evaluating the Potential Radio- logical Consequences of a Loss-of-Coolant Accident for Boiling Water Reactors." 15.6.5-18 Rev. 1 - July 1981 4. Regulatory Guide 1.4, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Pressurized Water Reactors." 5. Regulatory Guide 1.52, "Design, Testing, and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units of Light- Water-Cooled Nuclear Power Plants." 15.6.5- 19 Rev. 1 - July 1981