ML21286A549

Amendment 29 to Updated Final Safety Analysis Report, Chapter 14, Section 14.1, Analytical Objective

ML21286A549
Person / Time
Site:	Browns Ferry
Issue date:	10/04/2021
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
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BFN-29 14.1-1 14.0 PLANT SAFETY ANALYSIS 14.1 ANALYTICAL OBJECTIVE The objective of the Plant Safety Analysis is to evaluate the ability of the plant to operate without undue hazard to the health and safety of the public.

Previous sections of this report provide the objective, design basis, and description of each major system and component. Systems that have unique requirements arising from considerations of nuclear safety are evaluated in the safety evaluation portions of those sections of the report. The safety evaluations consider the effects of failures within the system being investigated. Systems essential to safety are capable of performing their functions in adverse circumstances.

This chapter provides the analytical objective, design basis, and safety evaluation for the overall plant integrated systems. Limiting events which may be affected by reload core designs are evaluated and documented in reload licensing reports for each fuel cycle. Safety evaluations for specific reload fuel types are documented or referenced in either the Reload Licensing Report for the specific cycle or in the licensing topical report, "General Electric Standard Application for Reactor Fuel,"

NEDE-24011-P-A, and revisions thereto.

Safety analyses have also been performed to justify plant operating flexibility options such as operation in the Extended Load Line Limit (ELLL) Region, operation in the Increased Core Flow (ICF) Region and operation with Final Feedwater Temperature Reduction (FFWTR). Subsequent to these analyses, additional analyses have been performed1, and plant performance improvements have been implemented on Units 1, 2, and 3 for operation in the Maximum Extended Load Line Limit (MELLL) Region.

Analyses have also been performed for Extended Power Uprate (EPU) (120%

OLTP) and for operation in the Maximum Extended Load Line Limit Analysis Plus (MELLLA+) domain.2, 3, 4, 5 Results of these analyses are reconfirmed with each reload analyses as documented in the Reload Licensing Reports for a specific cycle.

1 NEDC-32422P, "Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Browns Ferry Nuclear Plant Unit 1, 2 and 3," GE Nuclear Energy, April 1995 2 NEDC-33860P, Safety Analysis Report for Browns Ferry Nuclear Plant Units 1, 2, and 3 Extended Power Uprate, GE Hitachi Nuclear Energy, July 2015 3 ANP-3403P, Fuel Uprate Safety Analysis Report for Browns Ferry Nuclear Plant Units 1, 2, and 3, AREVA Inc., June 2015 4 NEDC-33877P, Safety Analysis Report for Browns Ferry Nuclear Plant Units 1, 2, and 3 Maximum Extended Load Line Limit Analysis Plus, GE Hitachi Nuclear Energy, February 2018 5 ANP-3551P, AREVA MELLLA+ Safety Analysis Report for Browns Ferry Units 1, 2, and 3, AREVA Inc., December 2017

BFN-29 14.1-2 Definitions for key terms used in this section are presented in Subsection 1.2, "Definitions."

It should be noted that AREVA Nuclear Reactor Operations was renamed Framatome in 2018. For the purposes of this chapter, AREVA should be considered synonymous with Frameatome.