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:
e- mitigating ESF engineered safety feature systems, are sufficient to provide reasonable 40 assurance that the calculated radiological consequences of a postulated main steam line failure outside the containment do not exceed (1) the exposure guidelines as set forth in 10 CFR Part 100 §100.11 for an MSLB with an assumed preaccident iodine spike or for an MSLB with the 41 highest worth control rod stuck out of the core and (2) 10 percent% of these exposure 42 guidelines for an MSLB with an equilibrium iodine concentration in combination with an assumed accident-generated iodine spike. The results of the staff's calculations are listed in Table 15. 15.1.5-7 DRAFT Rev. 3 - April 1996 The staff's conclusion is based on (1) the staff review of the applicant's analysis of the radiological consequences; (2) the independent dose calculation by the staff using conservative assumptions, including atmospheric dispersion factors as discussed in Chapter 2 of this report; and (3) the (INSERT NSSS VENDOR) standard technical specifications for the iodine concentration in the primary and secondary coolant system and for the primary-to-secondary leakage in the steam generators. The staff will review the (PLANT NAME)-specific technical specifications to assureensure that the dose guidelines stated above are not exceeded. At the construction permit stage, the following paragraph is included in the staff's safety evaluation report (SER):43 On the basis of our experience with the evaluation of steam line and steam generator tube failure accidents for PWR plants of similar design, we have concluded that the consequences of these accidents can be controlled by limiting the permissible primary and secondary coolant system radioactivity concentrations and/or primary-to-secondary leak rates so that potential offsite doses are small. At the operating license stage, we will include appropriate limits on these parameters to be included in the plant technical specifications. For design