Document: NUREG-0800
Document ID: feb81401-32fe-404e-84da-ff4b36e788bf
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF MAIN STEAM LINE FAILURE OUTSIDE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350151.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.4
CFR Part: 
CFR Title: 

Content:
ch fuel failure, a dose analysis will be performed with the corresponding iodine activity. No decontami- nation factor or other reductions in the concentrations are assumed in the staff's analysis. c. The appropriate atmospheric dispersion factors (X/Q values) for the staff's independent dose analysis will be determined by the assigned meteorologist in accordance with SRP Section 2.3.4. 3. Comparison of the doses calculated by the applicant and the staff for the two iodine concentrations discussed above with the appropriate acceptance criteria in subsection II of this SRP section. If the doses calculated by the staff exceed those of the exposure guidelines, then the staff will reduce the primary coolant iodine concentration limits in the plant specific technical specification accordingly. IV. EVALUATION FINDINGS The reviewer verifies that sufficient information has been provided by the applicant and that the-app7icant's analysis and the staff's independent calcula- tions support conclusions of the following type, to be included in the staff's safety evaluation report at the operating license stage: The staff concludes that the distances to the exclusion area and low population zone outer boundaries for the (insert PLANT NAME) site, in conjunction with the operation of the dose mitigating ESF systems, are sufficient to provide reasonable assurance that the calculated radio- logical consequences of a postulated main steam line failure outside the containment of the (insert PLANT NAME) station do not exceed (a) the exposure guidelines as set forth in 10 CFR Part 100 para- graph 11 for the case that the failure occurs with a preaccident iodine spike, and (b) 10 percent of these exposure guidelines for the 15.6.4-3 Rev. 2 - July 1981 case that the failure occurs with a primary coolant activity correspond- ing to the maximum equilibrium concentration for continued full power operation as stated in the standard technical specifications for the (insert NSSS VENDOR) design.