ML18024A356

Updated Final Safety Analysis Report (Ufsar), Amendment 27, 14.1 Plant Safety Analysis

ML18024A356
Person / Time
Site:	Browns Ferry
Issue date:	10/05/2017
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
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Download: ML18024A356 (1)

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BFN-25 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 heal th and safety of the public.

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

This chapter provides the analytical obj ective, design basis, and safety evaluation for the overall plant integrated systems. Limiting events which may be affected by reload core designs are evaluated and doc umented in reload licensing reports for each fuel cycle. Safety evaluations for s pecific reload fuel types are documented or referenced in either the Reload Licensing Report for the specific cycle or in the licensing topical report, "Gener al Electric Standard Application for Reactor Fuel," NEDE-24011-P-A, and re visions thereto.

Safety analyses have also been performed to just ify plant operating flexibility options such as operation in the Extended Load Li ne Limit (ELLL) Region, operation in the Increased Core Flow (ICF) Region and opera tion with Final Feedwater Temperature Reduction (FFWTR). Subs equent to these analyses, ad ditional analyses have been performed 1 , and plant performance improvem ents have been implemented on Units 1, 2, and 3 for operation in the Maximum Extended Load Line Limit (MELLL) Region. Results of these analyses are reconfirmed with each reload analyses as documented in the Reload Licensing Reports for a specific cycle.

Definitions for key terms used in this section are presented in Subsection 1.2, "Definitions."

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