Document: NUREG-0800
Document ID: a387e63b-f08f-4013-a693-4fa080d0bff9
Document Type: srp
Title: and BTP 11-5.  Supporting information on the staff’s evaluation of
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1502/ML15027A302.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
CFR Part: 
CFR Title: 

Content:
the site’s atmospheric dispersion characteristics in transporting radioactive materials to a dose receptor located at the EAB is presented in SRP Section 2.3.4. The staff concludes that the analysis provided by the applicant is consistent with the guidance of BTP 11-5 and with the dose acceptance criteria for an individual located at the EAB. The results are also consistent for a case where the waste gas system (is) / (is not) designed to withstand the effects of an internal hydrogen explosion and earthquakes. (Note to staff: Specify the applicable case in the SER.) B. The staff concludes that the applicant’s proposed TS limiting the total amounts of radioactivity in tanks and components, as described in the application, are adequate based on the results of the staff’s review and evaluation. The staff' bases its acceptance of the TS on the evaluation of the selected GWMS failed component or leak, assumed inventory of radioactive materials in the failed component or leak, assumed failure scenario, methods and assumptions used in BTP 11-5-9 Revision 4 – January 2016 modeling the transport of radioactivity to a dose receptor located at the nearest EAB sector, and definition of exposure scenario. SRP Section 2.3.4 presents supporting information on the staff’s evaluation of the site’s atmospheric dispersion characteristics in transporting radioactive materials to a dose receptor located at the EAB. C. The evaluation demonstrates that the results are consistent with BTP 11-5 acceptance dose criterion of 1 mSv (0.1 rem) for systems not designed to withstand explosions and earthquakes; or a dose of 25 mSv (2.5 rem) for systems designed to withstand explosions and earthquakes. The staff confirmed that the proposed TS limiting the radioactivity content for the stated GWMS tank and components have been incorporated into Chapter 16, Section 5.5, “Programs and Manuals,” of the Final Safety Analysis Report (FSAR), and identified as a program element in the