Document: NUREG-0800
Document ID: c75a9de4-9927-49e4-b078-7f5dadd37acd
Document Type: srp
Title: DESIGN BASIS ACCIDENT RADIOLOGICAL CONSEQUENCE ANALYSES FOR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0702/ML070230012.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0.3
CFR Part: 
CFR Title: 

Content:
i. The isotopic quantities of fission products released in curies to the environment from the site. ii. Rates of fission product release to the environment from the site as a function of time. C. The staff reviews the following information if available: (1) the timing and rate of fission product release from the fuel and (2) the isotopic quantities and the chemical forms of fission products released from the fuel, following selected bounding DBAs. This information will help the staff determine whether the proposed PPE values are not unreasonable. The fission product release rates should be fractions of fission product inventory in the reactor core at the ultimate maximum power level. D. In the evaluation using Section 2.3.4 of this standard review plan, the staff reviews the site-specific short-term χ/Q values determined by the applicant and performs an independent evaluation of atmospheric dispersion. E. The staff performs independent confirmatory radiological consequence analyses using the docketed PPE values and the site-specific short-term χ/Q values provided in the ESP application to determine whether the proposed site meets the radiological consequence evaluation factors identified in 10 CFR 50.34(a)(1) at the nearest EAB and LPZ outer boundary as described in Chapter 2 of the site safety assessment. F. For the methodology and assumptions for calculating the radiological consequences of postulated accidents, the staff will use, where applicable, the regulatory positions stated in Regulatory Guide 1.183, “Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors”. NOTE: If a COL application references a certified design and an ESP that referenced a PPE, the staff reviews (at the COL stage) the site-specific short-term χ/Q values specified in the ESP to confirm that the site-specific short-term χ/Q values are bounded by those short-term χ/Q values postulated in the reactor design certification based on the