Document: NUREG-0800
Document ID: bbe13c46-bc12-4c59-9966-19a63f926116
Document Type: srp
Title: evaluate source terms and doses from gaseous effluents and solid wastes.  In turn,
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1007/ML100740449.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.4
CFR Part: 
CFR Title: 

Content:
limiting objectives by proposing a LWMS that is capable of maintaining releases of radioactive materials in liquid effluents such that the calculated individual doses in an unrestricted area from all pathways of exposure are less than 0.03 mSv (3 mrem) to the total body and 0.1 mSv (10 mrem) to any organ. The staff=s evaluation has considered releases of radioactive materials in liquid effluents for normal operation, including AOOs, based on expected radwaste inputs over the life of the plant for each reactor on the site, in accordance with SRP Section 11.1. 2. The applicant has met the requirements of Section II.D of Appendix I to 10 CFR Part 50 with respect to meeting the ALARA criterion. The staff has considered the 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-mi) radius of the reactor at a cost of less than $1000 per man-rem or man-thyroid-rem. 3. 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 1 percent of the operating fission product inventory in the core being released to the primary coolant for a PWR, or Aa fission product release rate consistent with a noble gas release to the reactor coolant of 3.7 MBq/s per MWt (100 FCi/s per MWt) for 30 minute decay@ for a BWR. The staff has determined that under these conditions the concentrations of radioactive materials in liquid effluents in unrestricted areas will be a small fraction of the limits specified in Table 2, Column 2, of Appendix B to 10 CFR Part 20. In making the above determination for radioiodines; however, the staff has considered TS limits for iodine-131 dose equivalent concentration in the primary coolant for PWRs, as defined in the plant TS. 11.2-17 Revision 4 - May 2010 4. The