ML21286A541

Amendment 29 to Updated Final Safety Analysis Report, Chapter 14, Section 14.7, Conclusions

ML21286A541
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Site:	Browns Ferry
Issue date:	10/04/2021
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
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Text

BFN-16 14.7-1

14.7 CONCLUSION

S Because the spectrum of abnormal operational transients has been approached and analyzed by a method that included the various combinations of plant problems and operating conditions, general conclusions regarding the plant's behavior in response to operational problems can be made. Because none of the abnormal operational transients results in any fuel parameter exceeding its limiting value (no fuel damage), it can be concluded that unacceptable safety result l and 2 are precluded.

Because peak nuclear system pressure does not exceed 1375 psig as a result of any abnormal operational transient, it can be concluded that unacceptable safety result 3 for abnormal operational transients is precluded.

The broad approach to and methodical categorization of accidents leading to unplanned releases of radioactive material from the fuel barrier and the nuclear system process barrier also justify general conclusions. A comparison of each of the design basis accident analyses with the unacceptable safety results for accidents show that items 1, 3, 4, 5 and 6 are satisfied. In Section 6 ("Core Standby Cooling System"), it is shown that in no portion of the core does the cladding attain a temperature of 2200°F for any loss of coolant accident. Thus, unacceptable safety result 2 for accidents is precluded.