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:
analysis and the staff's independent calculations support conclusions of the following type, to be included in the AEB safety evaluation report at the operating license stage: The steam generator tube failure accident has been evaluated with and without a concurrent loss of offsite power. The assumptions used in our analysis are listed in Table . The calculated doses are presented in Table The staff concludes that the distances to the exclusion area and to the loe population zone outer boundaries for the (insert PLANT NAME) site, in conjunction with the operation of the dose mitigating ESF systems, are sufficient to provide reasonable assurance that the calculated radiological consequences of a postulated steam generator tube failure accident do not exceed: (a) the exposure guidelines as set forth in 10 CFR Part 100, Section 11 for the accident with an assumed preaccident iodine spike or with the highest worth control rod stuck out of the core and (b) 10 percent of these exposure guidelines, for the accident with an equilibrium iodine concentration in combination with an assumed accident generated iodine spike. The staff conclusion is based on (1) the staff review of the applicant's analysis of the radiological consequences, (2) the independent dose calcu- lation by the staff using conservative assumptions including atmospheric dispersion factors as discussed in Chapter 2 of this report, (3) the appli- cant's analysis and the staff's independent dose calculations which were performed using the guidelines of Regulatory Guide 1.4, and (4) 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 assure that the dose guidelines stated above are not exceeded. The following paragraph is inserted prior to the last paragraph if fuel damage is found to be a