ML18024A343

Browns Ferry Nuclear Plant Updated Final Safety Analysis Report (Ufsar), Amendment 27, 14.6 Figure - Analysis of Design Basis Accidents

ML18024A343
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
References
Download: ML18024A343 (18)

Text

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AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT DBA-LOCA SHORT-TERM CONTAINMENT TEMPERATURE RESPONSE (102Z Of UPRATED POWER, 81Z CF) FIGURE 14.6-1 mm a,. Cl. -1 _. I er a, !i I.LI ..... c.. = "-...... I a.. ...... < .... .... 113 > 0 I-u -. 0 cg . 0 ... . a N C9ISd>

. Q ... . Cl I() . o-(\I U) u u.J Ul --ot-AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT DBA-LOCA SHORT-TERM CONTAINMENT PRESSURE RESPONSE (102J Of UPRATED POWER, 81J CF) FIGURE 14.6-2

..... ----u ->-d c:: -a: LL.I u.. (J1 &. z a u c:: co u I . . H't u \ uJ U'l --(!) a . -' N --------j 830 -

AMENDMENT 17 BROINS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT DBA-LOCA LONG-TERM WETWELL TEMPERATURE RESPONSE (1021 Cf UPRATE POWER, 1001 CF) FIGURE 1'4.6-3 9 w 5' 5 < --Ill ----------AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT DBA-LOCA LONG-TERM DRYIELL TEMPERATURE RESPONSE (102S OF UPRATED POWER, 100S CF) FIGURE 14.6-4 BROWNSFERRYNUCLEARPLANTFINALSAFETYANALYSISREPORTDBA-LOCALONG-TERMPRESSURERESPONSE(102%OFUPRATEDPOWER,100%CF)FIGURE14.6-5 50 10 o.* .. *20,0QDpi ACC£PTA8LE w 1 O.Dllll 11111 IJEIHUDC ACCEPTABLE RE.ACTIOK-DURATION COMBINATIONS 8£LOr ll*E 0.1 1.0 IJ DURATION OF RELEASE (hit BASED ON ltlAXIMlll ALLDWABt.£ CONTAl-llT PRESSURE u u AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Accideat.

Prhlary Coata1rm8"t Capability for Metal-Water FIGURE 14.6-6 PRIMARY COITAINMENT REACTOR TURBIKE DRIVEN fEEO PUMPS 13) GEN CONO. AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Main Bruk Accident Break Location FIGURE 14.6-15 FIGURE 14.6-7 0 0 ...... .. 'It" ::!; ;;; Q z I-0 (/) '\ (') 0 0 ' w 5 tn 0 -:J w =s i= N id _J ____ ..,... > w I-

> w w en _J a::> w z :::iWXcn 0 I-g u LIJ

<(

0:: :J w I-(/) 0 0 8 0 0 § 0 0 0 8 0 0 0 0 0 0 N 0 ao ID 'It" N ..-...... (03S/B1)

M01.:I SSVW lNV1000 AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT MAIN STEAMLINE BREAK ACCIDENT MASS OF COOLANT LOST THROUGH BREAK (HOT STANDBY CONDITIONS)

FIGURE 14.6-8

...... ----.-----

.......

.......

D.Z -10 SECOND ISOt.ATION

-PUMPS TRIPPED AT T*O -REACTOR AT T*O TIME{SEC)

AMENDMENT 17 BROWN$ FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Main Steamline Break Accldeac Normalized Core

'Flcnr FIGURE 14.6-9 u ----...---..------,----....,...---r---

2.D -10 SECOND ISOLATJOH

-PUMPS TRIJtPED AT T*D UI O"-----....i.------...._

______ ,,__ ____ __.. _______________

,,__ ____ __, 4 ' I 1D 12 \4 Tiii! (2C) (Al'TU BREAK) AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Main st ...

Accident K.iaillUtl Heat Ratio FIGURE 1+. 6-10 BFN26Figure14.611DeletedbyAmendment26.

BFN26Figure14.612DeletedbyAmendment26.

BFN-16 Figure 14.6-13 Deleted by Amendment

9.

BFN26Figure14.614DeletedbyAmendment26.

BFN26Figure14.615DeletedbyAmendment26.

BFN26Figure14.616DeletedbyAmendment26.

BFN26Figure14.617DeletedbyAmendment26.

BFN26Figure14.618DeletedbyAmendment26.