Document: NUREG-0800
Document ID: 23a67737-6e7e-4dfc-9090-dca6a186a7dc
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF MAIN STEAM LINE FAILURES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070679.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
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0 CFR Part 100 are applicable to this section because they specify the methodology for calculating radiation exposures at the site boundary for postulated accidents or events such as loss of a reactor coolant pump. For events having a moderate frequency of occurrence, any release of radioactive material must be such that the calculated doses at the site boundary are a small fraction of the 10 CFR Part 100 guidelines. A small fraction is interpreted to be less than 10% of the 10 CFR Part 100 reference values. For the purpose of this review, the radiological consequences of any steam piping failure must include consideration of the containment, confinement, and filtering systems. The applicant's source terms and methodologies with respect to gap release fractions, iodine chemical form, and fission product release timing should reflect NRC-approved source terms and methodologies such as those contained in NUREG-1465. Meeting this requirement provides assurance that, in the event of a main steam piping failure, radiation exposures at the site boundary will not exceed a small fraction of the reference values specified in 10 CFR Part 100.21 III. REVIEW PROCEDURES The reviewer selects and emphasizes specific aspects of this SRP section as are appropriate for the particular plant. The review areas to be given attention and emphasis are determined by the similarity of the information presented in the safety analysis report (SAR) to that recently 22 reviewed on other plants and whether items of special safety significance are involved. DRAFT Rev. 3 - April 1996 15.1.5-4 At the construction permit stage, there is generally insufficient information available to make meaningful radiological consequence calculations for this accident. At this stage, the review is limited to a brief review of the applicant's discussion of the main steam line failure accidents to determine that there are no unusual design features that would preclude the limitation of radiological consequences by