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
CFR Part: 
CFR Title: 

Content:
ated iodine spike, the calculated doses should not exceed a small fraction of the above guideline values, i.e., 10 percent% or 25 mSv (2.5 rem) and 0.3 Sv (30 rem), respectively, for the whole-body 14 15 16 and thyroid doses. 15.1.5-3 DRAFT Rev. 3 - April 1996 The methodology and assumptions for calculating the radiological consequences should reflect the regulatory positions of Regulatory Guide 1.4, (Ref. 8) except for the atmospheric 17 dispersion factors which are reviewed under SRP Section 2.3.4. Plant technical specifications are required for the iodine activity in the primary and secondary coolant system and for the leak rate from the primary to the secondary coolant system in the steam generator(s). Plant technical specifications include limits for the maximum concentration of radioactive iodine permitted in the primary and secondary coolant systems and the permissible leak rate from the primary to the secondary coolant system in the steam generator(s). These 18 specifications are acceptable if the calculated potential radiological consequences from the MSLB accident are within the exposure guidelines for the above two cases. Technical Rationale19 The technical rationale for application of these acceptance criteria to reviewing the applicant's analyses of transients initiated by steam system piping failures is discussed in the following paragraphs:20 Compliance with 10 CFR Part 100 requires that a suitable exclusion area, low population zone, and population center distance be determined for each nuclear power plant site. Further, radiation exposure criteria stipulated in 10 CFR Part 100 provide reference values to be used in the site suitability determination based on postulated fission product releases associated with accidental events. The requirements of 10 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