Document: NUREG-0800
Document ID: 2133c57c-1767-4769-89e9-ceb528fb7c2b
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF STEAM GENERATOR TUBE FAILURE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350149.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.3
CFR Part: 
CFR Title: 

Content:
med accident initiated iodine spike, the calculated doses should not exceed a small fraction of the above guideline values, i.e., 10 percent or 2.5 rem and 30 rem, respectively, for the whole-body and thyroid doses. The methodology and assumptions for calculating the radiological consequences should reflect the regulatory positions of Regulatory Guide 1.4 (Ref. 2) except for the atmospheric dispersion factors which are reviewed under SRP Section 2.3.4. Plant technical specifications are required for iodine activity in the'primary and secondary coolant systems. These specifications are accept- able if the calculated potential radiological consequences from the steam generator tube failure accident are within the exposure guidelines for the above two cases. III. REVIEW PROCEDURES The reviewer selects and emphasizes specific aspects of this SRP section as appropriate for a particular plant. The judgment which areas need to be given attention and emphasis during the review is based on a determination if the material presented is similar to that recently reviewed on other plants and whether items of special safety significance are involved. At the construction permit (CP) stage, the review i's limited to a brief survey of the pertinent portions of the SAR regarding .the plant design and the appli- cant's accident evaluation to determine that there are no unusual features which would prevent limitation of radiological consequences to acceptable levels by appropriate limits on coolant activity concentrations. The detailed review of the radiological consequences of a steam generator tube failure is done at the operating license (OL) stage when system parameters and accident analyses are fully developed. Standard technical specifications for each of the three PWR vendors' NSSS include limits on the primary and secondary coolant activities which are used in the staff's independent dose calculations (Ref. 3, 4, and 5). If the appli- cant proposes to use these standard limits