ML21286A274

Amendment 29 to Updated Final Safety Analysis Report, Chapter 1, Section 1.12, General Conclusions

ML21286A274
Person / Time
Site:	Browns Ferry
Issue date:	10/04/2021
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
Shared Package
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References
Download: ML21286A274 (1)

Text

BFN-28 1.12 GENERAL CONCLUSIONS Based on the favorable plant site characteristics, on the design of the plant herein analyzed, on the criteria, principles, and design requirements pertinent to safety, on the calculated potential consequences of routine and accidental release of radioactive material to the environs, on the results of research and development programs, and on the technical competence of the applicant and his contractors, there is reasonable assurance that the Browns Ferry Nuclear Plant can be operated without endangering the health and safety of the public.

NRC has accepted these conclusions and has issued operating licenses for all three units of the Browns Ferry Nuclear Plant. The dates of issuance for each unit's operating license are as follows:

UNIT ONE - June 26, 1973 UNIT TWO - June 28, 1974 UNIT THREE - July 2, 1976 A subsequent license amendment for a five percent core thermal power uprate, from 3293 MWt to 3458 MWt, was issued for Units 2 and 3 on September 8, 1998, and for Unit 1 on March 6, 2007. On August 14, 2017, license amendments were issued for all three units for a core thermal power uprate from 3458 to 3952 MWt.

Operating data for each unit will be provided to the NRC. This operating data shall comply with the operating data (for each calendar month) as described in Generic Letter 97-02 Revised Contents of the Monthly Operating Report. This data will be provided by the last day of the month following the end of each calendar quarter.

This operating data may be provided by the use of an Industry Database (e.g., the Industrys Consolidated Data Entry Program (CDE) or other reports to prevent any gaps in the monthly operating statistics and shutdown experience provided to the NRC.

1.12-1