Document: NUREG-0800
Document ID: 2f527583-f167-477c-9a93-bc8f7db676b6
Document Type: srp
Title: for the LWMS and GWMS, respectively.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1307/ML13072A545.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
CFR Part: 
CFR Title: 

Content:
peration of the SWMS and plant facilities, where systems are located, will not be compromised in meeting radiation protection dose standards for workers and effluent concentration limits and doses for members of the public under the requirements of 10 CFR Part 20. This conclusion is based, in part, on the results of a parallel evaluation and fire protection analysis performed in SRP Section 9.5.1.1 for plant areas where combustible or flammable radioactive materials are expected to be present during operation. The staff finds the scope of the fire protection program and operational safeguards adequate as it they relates to system design features and commitment to conduct fire hazards analyses involving the presence of combustible or flammable radioactive materials. 11. The staff has reviewed the sources of radiation and radioactivity and associated doses to members of the public and concludes that annual doses from the SWMS and other sources of radioactivity and radiation from the site (which may have either single or multiple reactor units), including liquid and gaseous effluents and external radiation exposures from buildings and storage tanks, as a source of external radiation, will not exceed the EPA generally applicable environmental radiation standards of 40 CFR Part 190, as implemented under 10 CFR 20.1301(e). SRP Section 12.3-12.4 evaluates the doses associated with external radiation from buildings and sources of radioactivity contained in systems and components. 12. All liquid and gaseous effluent releases associated with the operation of the SWMS are controlled by the ODCM, as it relates to the PCP’s aspect with process and effluent monitoring and sampling. The applicant has committed in SRP Sections 11.5, 13.4, and 13.5 to develop a plant and site-specific ODCM before fuel load, based on NEI ODCM Template 07-09A, “Generic FSAR Template Guidance for Offsite Dose Calculation Manual (ODCM) Program Description.” The staff’s evaluation of the ODCM and