Document: NUREG-0800
Document ID: dc7fdaed-8abd-4b49-b5df-dcf64a9b93b0
Document Type: srp
Title: SHORT-TERM DISPERSION ESTIMATES FOR ACCIDENTAL ATMOSPHERIC
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070235.pdf
Revision Date: 2023-06
Chapter: 2
Section ID: 2.3.4
CFR Part: 
CFR Title: 

Content:
ident will be able to perform these functions without concern for their personal health and safety. Guidance on evaluation of control room habitability during accidents is provided in Regulatory Guide 1.78, Regulatory Position C.6, and in Standard Review Plan (SRP) Section 6.4, "Control Room Habitability System." Meeting the requirements of this criterion provides assurance that those personnel needed to monitor and control an accident will be able to function effectively. 13 2. 10 CFR 100.11(a) specifies that determination of an exclusion area, low population zone, 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 exclusion area, low population zone, 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 exclusion area and low population zone. Verification that the proposed nuclear plant design meets these radiation dose guidelines is accomplished by calculating expected offsite radiation doses using (a) an assumed DRAFT Rev. 2 - April 1996 2.3.4-4 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 the raw data is provided in Regulatory Guide 1.23, and models for calculating the atmospheric dispersion are provided in Regulatory Guide 1.145. Meeting the siting criteria provides assurance that offsite radiation doses from postulated accidents will not exceed the guideline radiation doses specified in 10 CFR Part 100.14 III. REVIEW PROCEDURES 1. Atmospheric Dispersion Models