ML18018A793

Updated Final Safety Analysis Report (Ufsar), Amendment 27, 1.8 Summary of Radiation Effects

ML18018A793
Person / Time
Site:	Browns Ferry
Issue date:	10/05/2017
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
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Text

BFN-21 1.8-1 1.8

SUMMARY

OF RADIATION EFFECTS

1.8.1 Normal

Operation The gaseous and liquid radioactive waste syst ems are designed so that dose to any offsite person will not exceed t hat permitted within the limits specified in the Offsite Dose Calculation Manual (ODCM), applic able limits in the plant technical specifications, and technical requirements manual. The expectancy, based on operating experience, is that dose to any off-site person from gaseous waste discharge will not average more than a small fraction of the permissible dose, and that concentrations of liquid waste at the point of discharge will average less than 1% of the concentrations permitted by 10 CFR 20. Both effects are only a small fraction of the effect of natural background radiation.

1.8.2 Abnormal

Oper ational Transients A design objective is to avoid fuel damage as a result of abnormal operational transients. Analyses of t hese events, which are described in the "Plant Safety Analysis", show that abnormal operational transients do not result in any significant increase of radioactive material release to the environs over t hat experienced during normal operation.

1.8.3 Accidents

The ability of the plant to withstand the consequences of accidents without posing a hazard to the health and safety of the public is evaluated by analyzing a variety of postulated accidents. The calculated cons equences of the design basis accidents, which result in the greatest potential off-site radiation exposur es, are presented in Chapter 14. These doses are substantially below the guideline doses given in 10 CFR 50.67.