Document: NUREG-0800
Document ID: 9738c583-ac33-4836-b8f1-580dc98eb7f0
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF THE FAILURE OF SMALL LINES CARRYING
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350147.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.2
CFR Part: 
CFR Title: 

Content:
the staff and by the applicant are compared with the acceptance criteria stated in subsection II of this SRP section. If the doses calculated by the staff are not within the exposure guidelines (i.e., they are not less than 10 percent of 10 CFR Part 100, §100.11), then the staff will pursue alternatives with the applicant to reduce the doses to within the guideline values. IV. EVALUATION FINDINGS The reviewer verifies in the Safety Evaluaton Report'(SER) that sufficient information has been provided in the SAR. The applicant's analysis and the staff's independent calculations are summarized. The SER should'identify the specific small line failure that was analyzed by the staff and the calculated doses, including the assumptions and unique system and operation provisions. The evaluation should support conclusions of the following type to be included in the SER: The staff concludes'that the distances.to the exclusion area and to the low population zone outer boundaries for the (insert PLANT NAME) site, In conjunction with the operation of the dose mitigating ESF 15.6.2-4 Rev. 2 - July 1981 systems, are sufficient to provide reasonable assurance that the calculated radiological consequences of a postulated small line failure outside the containment, assuming the primary coolant equilibrium iodine concentrations permitted by the standard technical specifications, in combination-with an accident generated iodine spike, do not exceed a small fraction of the exposure guidelines as set forth in 10 CFR Part 100, §100.11. The results of the staff's calculations are listed in Table 15. The staff's conclusion is based on (1) the staff review of the applicant's classification and identification of small lines in accordance with General Design Criterion 55, "Reactor Coolant Pressure Boundary Penetrating Containment," and Regulatory Guide 1.11, "Instrument Lines Penetrating Containment," (2) the staff review of the applicant's analysis of radiological consequences, (3) the