Document: NUREG-0800
Document ID: 4e1c316a-99c2-4fd3-9d9b-323791bd85f8
Document Type: srp
Title: SHORT-TERM ATMOSPHERIC DISPERSION ESTIMATES FOR ACCIDENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070730398.pdf
Revision Date: 2023-06
Chapter: 2
Section ID: 2.3.4
CFR Part: 
CFR Title: 

Content:
ing the requirements of this criterion provides assurance that those personnel needed to monitor and control an accident will be able to function effectively. 2. 10 CFR 100.11(a) specifies for reactor applications before January 10, 1997, that determination of an EAB, LPZ, and population center distance be based on a set of assumptions involving the release of fission products from the reactor core, an expected leak rate from containment, and pertinent meteorological conditions. Identification of an EAB, LPZ, and population center distance is an integral aspect of the siting criteria for a new nuclear power plant. Specified radiation dose guidelines are associated with the EAB and LPZ. Verification that the proposed nuclear plant design meets these radiation dose guidelines is accomplished by calculating expected offsite radiation doses using (a) an assumed inventory of fission products available for release from the containment building, (b) the expected containment leak rate, and (c) site atmospheric dispersion characteristics. Atmospheric dispersion characteristics are determined from meteorological measurements taken at the proposed plant site. Guidance on the onsite meteorological program needed to obtain meteorological data is provided in Regulatory Guide 1.23, and models for calculating the atmospheric dispersion for the EAB and LPZ are provided in Regulatory Guide 1.145. 3. Compliance with 10 CFR 50.34(a)(1)(ii)(D) (for CP and OL applications on or after January 10, 1997), 10 CFR 52.17(a)(1)(ix) (for ESP applications), 10 CFR 52.47(a)(2)(iv) (for DC applications), 10 CFR 52.79(a)(1)(vi) (for COL applications), and 10 CFR 100.21(c)(2) (for reactor applications on or after January 10, 1997) requires an assessment demonstrating that the safety features that are to be engineered into the facility, including the plant design features intended to mitigate the radiological consequences of accidents, are adequate to ensure that the offsite radiological consequences