Document: NUREG-0800
Document ID: feb81401-32fe-404e-84da-ff4b36e788bf
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF MAIN STEAM LINE FAILURE OUTSIDE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350151.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.4
CFR Part: 
CFR Title: 

Content:
flect the regulatory positions of Regulatory Guide 1.5 (Ref. 2) except for the atmospheric dispersion factors which are reviewed under SRP Section 2.3.4. 4. A plant specific technical specification is required for both cases of iodine activity in the primary coolant. This specification is acceptable if the calculated potential radiological consequences from the MSLB acci- dent are within the exposure guidelines for the above two cases. III. REVIEW PROCEDURES The reviewer selects and emphasizes specific aspects of this Standard Review Plan (SRP) section as appropriate for a particular plant. The judgment which areas need to be given attention and emphasis in the review is based on a deter- mination if the material presented is similar to that recently reviewed on other plants and whether items of special safety significance are involved. At the construction permit (CP) stage, the review is limited to a survey of the pertinent portions of the plant design and the applicant's discussion of the accident to determine that there are no unusual features that would prevent limitation of doses to acceptable levels by appropriate limits on coolant activity concentrations. Standard technical specifications regarding coolant activity concentration limits have been issued for BWR plants and the radio- logical consequences of a steam line failure have been evaluated for a stand- ard GESSAR plant using this activity limit to determine the limiting atmos- pheric dispersion factors (X/Q values). Consequently, the radiological conse- quences of a steam line failure accident need not be explicitly calculated for a standard GESSAR plant located at a site where the X/Q value is equal to or less than the limiting X/Q value. The detailed review of the radiological consequences of a main steam line failure outside containment is done at the operating license (OL) stage when system parameters and accident analysis are fully developed. The review at the OL stage consists of the following