ML18024A354

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Updated Final Safety Analysis Report (Ufsar), Amendment 27, 14.11 Figure - Analysis of Design Basis Accidents
ML18024A354
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 10/05/2017
From:
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation
Shared Package
ML18018A778 List: ... further results
References
Download: ML18024A354 (15)
v • d • e


Text

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MUIMUM OUT OF SEQUENCE WITH ACUACl!HT IN S!QUtNCI!.

AOD WITMDMWN 20 MAXIMUM OUT OF SEQU!NC!

OI MAXIUUMINS!QU1£NC£ 04 oo"'-~------~----.._ ______________.._.______.______ ._.~~~~~__.

1.0 IUI 0 93 0 II Clt4 OIO D76 D.72 AVIUGI MODU~TO" DENSfTV. p*lflt. tc1 AMENDMENT 17 IROWH$ FERRY HUC:L!AR PL..,HT FINAi. SAFETY AHAL YSIS REPORT Maximum Rmt Worth Venu1 Moc:ler1tor 01n1ity FIGURE 14 .11-1

8d Ill~ V 'Hl.llOM 0011 WnftlXYl'I BROWtlS t=ERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT M1xlmum Rod Worth V1r1U1 Power LAvel AMENDMENT 17 FICURE 14.11-2

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300 i----------1~-----------------t-2$0

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i!: 200 f5 CUR\'E NUMBER INITIAL POWER

"'...:::. 2 II: l to-f A DESIGN

5 2 1rxots1GN L

150 3 3 lo-3 a DESIGN c

!i 4 10-l 11 DESIGN Iii.

4 111 50 a

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INITIAL ENTHALPY 6JVCONTROL ROD AMENDMENT 17 BROWNS FERRY HUCLEAR PLANT l'IHAL SAFETY AHAL. YSIS REPORT Rod Orop Accid1nt (Cold, Crit1cal l Ptak Futl En1halpv FIGURE 14. 11-3

lSO 250

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CURVE HUllBER INITIAl POIER 1 lo-' 1 DESIGN

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3 10-l 1 DESIGH lllO 0

D.02 a.m O.D4 AIVCONTROl ROD AMENDMENT 17 IROWHS FERRY NUCLEAR PLANT l'IN.+.L SAF!TY .t.H.+.L YSIS REPORi Roel Drop Accident (Hot, Ctiticall Peak F1.1el EnU'11lpy FIGURE 1+. 11 -4

220 210

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200 190

1..-.-----------z FINAL llAXIMUll ENTHALPY 110 170 ', l 160 EXCURSION

' INCREMENT 150

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f. 140 w

130 \

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120 OOTIAL POWER

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\ 3SOF DESIGN 3°' OF 0£SIGN w.I \

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70 60 /

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INITIAL MAXIMUM 40 CENTERLINE .ENTHALPY 30 20 10 0

0 0.01 D.02 Q.03 0.04 4 k/CONTROL ROD IROWMS FERRY NUCLEAR P~AHT PfNAL SAFETY AN4LYSIS REPORT Rod Drop Accident lPawwr R*n91}

Peale Fuel Enthllpy AMENDMENT 17 FIGURE 14. 11-5

BFN-17 Figures 14.11-6 through 9 Deleted by Amendme nt 17

DRYWl!LL.

AHR COMBINATIONS A - 2 LOOf'S,

  • lo4X 8 - Z LOOflS. Z HX
  • C - 1 LOCf'. 2 HX fO o ...._____.______...._______......_____...______________.._______,

ac** \o 0 to* ,oia 10" \o4 ,ois 1o'-

T1 Me AFTER ~C:.C.\OEN\'" (-SSC:.:')

BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Losa-of-Coolant Accident Pri. .ry Conta111J98ftt Preeaure

Response

AMENDMENT 17 F IGURE 14 . 11 -10

350 r

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250

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AHA COM&INATIONS A - Z LOOPS. 4 HX B - .2 LOCf'S, 2 HJC C-1 LOOP,2HX so.._--____.______....._______.________......______..._____________ ~

19 to*l t0° 10 1 lOz. tO~ 104- 105 10

  • -r-1ME P-.S:TER ~lOENT {-Sec.:,

BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Losa-of-Coo lant Accident Dryve11 Temperature Reaponae AMENDMENT 17 F IGUR-E 14 . 11 -11

00 0

g 0 0 g

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If. 2.50

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a ZLOOP.tHX b HOOP, ZllX t ILOOP.2 HX 0

10 I 101 tOz. \O~ 10'-

TIME - SRCONDfS BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Loss-of-Coolant Accident, Pressure Suppression AMENDMENT 18 Pool Temperature Response FIGURE 14.11-12

BFN-17 Figures 14.11-13 Deleted by Amendment 17

I *20,000111111 ACCEPTAIL!

50 W* JO.om fPlll ACCEPTABl! REACTIOll *DURATION COMBINATIONS BELOI UNE IASED OH MAXllut ALLOWABLE COllTAINMEllT JD 'ff!SSURE DJ u ll IJ JJ u u 1.8 2.0 l:IURATION OF RELEASE 1111)"

AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Loaa-of-Coolant: Accident:,

Prillary Containment capability for Metal-Water Reaction FIGURE 14.11-14

PRIMARY CONTAINMENT BYPASS HEADER STOP VALVES I ~ONTROL VALVES GENERATOR FLOI

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u o/ BYPASS*

~ VALVUlfJ REnRICTORS ~ _y-ISOLATION VALVES COllD.

REACTOR TURBINE tlRIVEN FEEO PUMPS (3l AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT F!NAL SAFETY ANALYSIS REPORT Hain Steamline Break Accident lreak Location FIGURE 14.11-15

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<col ~ oes/q1) ~V3~e HenoYH! 101~ ssv~ !NV100~

AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT MAIN STEAIA.INE BREAK ACCIDENT MASS OF COOLANT LOST THROUGH BREAK FIGURE 14.11-16

l~------------.------r-----..---- ......----------...------...-----.,.------.

-10 S£C0H0 ISOLATION

- P\111'5 TIHPPED *T T*O

- REACTOR SCRAMll!O AT T*O TM! CS!CJ AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FtNAL SAFETY ANALYSIS REPORT Main Steaal.:l.ne Break Accident Noraalized Core Inlec Plov YICUlt! 14.6-17 FIGURE 14.11-17

3~~ -------...-..-----._.~----...-------~ ........ . . .-...------ ~------~

- 10 SECOND ISOLATION

- PUMPS TltlPP!D AT T*O 1.0 a...____________________________________________.._______,

4 I a 12 14 TIME CSECI (AFTER B..EAKI AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYS15 REPORT Main St..aline Break Accident Minillua CT1tical Beat l'lux llatio FIGURE 14.11-18

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