Document: NUREG-0800
Document ID: 96cbc2a1-0072-44c5-ae86-aadfa416183c
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF MAIN STEAM LINE FAILURES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350118.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
CFR Part: 
CFR Title: 

Content:
adiological consequences of a postulated MSLB outside containment of a PWR facility if the calculated whole-body and thyroid doses at the exclusion area and the low population zone outer boundaries do not exceed the following exposure guidelines: 1. for an MSLB with an assumed preaccident iodine spike and for an MSLB with the highest worth control rod stuck out of the core, the calculated doses should not exceed the guideline values of 10 CFR Part 100, Section 11 (Ref. 1), and 2. for an MSLB with the equilibrium iodine concentration for continued full power operation in combination with an assumed 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. 8) except for the atmospheric 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). These specifications are acceptable if the calculated potential radiological consequences from the MSLB 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 are appropriate for the particular plant. The review areas to be tiven atten- tion and emphasis are determined by the similarity of the information presented in the SAR to that recently reviewed on other plants and whether items of special safety significance are involved. At the construction permit stage, there is generally insufficient information available to make meaningful radiological consequence calculations for this 15.1.5-11 Rev. 2 - July 1981