ML18022A195

Updated Final Safety Analysis Report (Ufsar), Amendment 27, 4.10 Figure - Nuclear Steam Leakage Rate

ML18022A195
Person / Time
Site:	Browns Ferry
Issue date:	10/05/2017
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
Shared Package
ML18018A778	List: ML18018A780 ML18018A781 ML18018A783 ML18018A784 ML18018A785 ML18018A787 ML18018A788 ML18018A790 ML18018A792 ML18018A793 ML18018A795 ML18018A796 ML18018A797 ML18018A798 ML18018A800 ML18018A801 ML18018A802 ML18018A804 ML18018A806 ML18018A807 ML18022A114 ML18022A115 ML18022A116 ML18022A117 ML18022A118 ML18022A119 ML18022A120 ML18022A121 ML18022A123 ML18022A124 ML18022A125 ML18022A127 ML18022A128 ML18022A129 ML18022A130 ML18022A131 ML18022A132 ML18022A133 ML18022A148 ML18022A155 ML18022A156 ML18022A157 ML18022A158 ML18022A159 ML18022A161 ML18022A162 ML18022A163 ML18022A164 ML18022A165 ML18022A166 ... further results
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Download: ML18022A195 (3)

Text

{{#Wiki_filter:RBCCW ~ SUPPLY ~ ~ I I ~-~ ~--- -vv; I ~---TJ TO EQUIP'. SUMP BFN-17 REACTOR TYPtCAL T!Mfl. P'ICI(-up ~--{E==~ 8-f-::;_ __ ALL AIR / COOLERS NO. OF TE'S -~ DftAIM TO ~ fl~UR'IED ~;.....,~ 8 l"L.OOft SUMP TYPICAL PilES$, e-~~-~--., {t:===::t <~----c..-- ltQ. Of" !IT'S AS lt!QUI<<ED AMENDMENT 17 BROWNS fERRY NUCLEAR PLANT fiNAL SAFETY ANALYSIS REPORT DRYWELL LEAK DETECTION SYSTEM DIAGRAM FIGURE 4.10-1

BFN-16 Figure 4.1 0-2 (Deleted by Amendment 16)

7 1 5~ 4 3 v~ll xlO X 2L 0 0 tc.;;;; CRITICAL CRACK LENGTH (INCHES) D = MEAN PIPE DIAMETER . ~h = PIPE HOOP STRESS MATERIAL - Al06B 8 9 10 ~ = 15000 12 lf Gk 15 Dh xlC X ** X X X G E.DATA (N6£fF> X B M I DATA X X AMENDMENT 1 6 .>r BROWNS FERRY NUCLEAR PLANT 40 FINAL SAFETY ANALYSIS REPORT 50 Axial Through-wall Crack Data 60 Correlation 70 FIGURE 4.lo-3 I I .2 .4 .6 .8 1.0 1.2 1.4 1.':: ~/n}}