Document: NUREG-0800
Document ID: c544c383-46ca-4e10-8688-4fd295af8a61
Document Type: srp
Title: provide guidance in evaluating the source terms and doses from gaseous effluents
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1304/ML13044A644.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.4
CFR Part: 
CFR Title: 

Content:
he potential effectiveness of augmenting the proposed LWMS using items of reasonably demonstrated technology and has determined that further effluent treatment will not effect reductions in cumulative population doses reasonably expected within an 80-km (50-mile) radius of the reactor and the proposed LWMS complies with the cost-benefit ratio of Section II.D of Appendix I. 2. The applicant has met the requirements of 10 CFR 20.1301 and 20.1302, as the staff has considered the potential consequences resulting from reactor operation with design basis fuel defect level fission product inventory in the core for PWRs or offgas noble gas release rate assumed after 30-minute decay for BWRs, and TS limits for dose equivalent halogens and noble gases. The design basis fuel defect level for PWRs and noble gases release rate for BWRs were reviewed using the guidance in SRP Sections 11.1 and the guidance of SRP Section 11.2 as radioactive source terms to the primary and secondary coolant and reactor steam. The staff has determined that under these conditions, the concentrations of radioactive materials in liquid effluents discharged in unrestricted areas will comply with the concentration limits specified in Table 2, Column 2, and Note 4 of Appendix B to 10 CFR Part 20. In making the above determination for radioiodines, the staff has considered TS limits for iodine-131 dose equivalent concentration in the primary and secondary coolant for PWR and BWR designs, as defined in the plant TS. 3. The staff has reviewed the sources of radiation and radioactivity and associated doses to members of the public and concludes that annual doses from all sources of 11.2-30 Draft Revision 5 – August 2014 radioactivity and radiation from the site (which may have either a single or multiple reactor units), including liquid and gaseous effluents and external radiation exposures from buildings and storage tanks, and N-16 skyshine from BWR turbine buildings as sources of external radiation, will