ML18024A343: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
(2 intermediate revisions by the same user not shown) | |||
Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:~~ | ||
c:: c:: | |||
~~ | |||
~~ | |||
~~ | |||
E~ | |||
0 I. 0 rucn | |||
0 | ~ a | ||
-a: | |||
FIGURE 14.6- | 0! ;.....c 8 l.:..J a.. ~ ~ | ||
- CJ) | |||
- --s ... | |||
I a.. ~ ~ | |||
Cl) | |||
< ~ | |||
I- | |||
-0 j | |||
-l I .. --- | |||
0 0 | |||
.. . ' I I I ' ' I 0 | |||
0 0 | |||
Ill | |||
~ | |||
0 I/) | |||
(~ S33~930) 3C!fllV~3dW31 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 | |||
...... ----.----- | Q mm | ||
....... | ~~ | ||
....... | a,. Cl. | ||
-1 _. | |||
-PUMPS TRIPPED AT T*O -REACTOR AT T*O TIME{SEC) | -1~ | ||
AMENDMENT 17 BROWN$ FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Main Steamline Break Accldeac Normalized Core | ~~ | ||
'Flcnr FIGURE 14.6-9 u ----...---..------,----....,...---r--- | s~ | ||
2.D -10 SECOND ISOLATJOH | Cl I() | ||
-PUMPS TRIJtPED AT T*D UI O"-----....i.------.... | I o-(\I U) | ||
~ | |||
,, | a, !i er ~ | ||
Accident K.iaillUtl Heat Ratio FIGURE 1+. 6-10 | u | ||
= "- | |||
BFN-16 Figure 14.6-13 Deleted by Amendment | u.J I.LI ..... | ||
c.. | |||
...... Ul | |||
~ I a.. | |||
...... ~~ .... | |||
~ | |||
I- | |||
.... 113 | |||
~ 0 u - ot- - | |||
. . a 0 | |||
cg ... | |||
0 N C9ISd> 3Hn553~d 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 | |||
~ | |||
~ | |||
- I ~ | |||
u | |||
~ | |||
- .u H't c:: | |||
a: | |||
-d \ uJ U'l LL.I u.. ~ - ~ | |||
(J1 z | |||
a | |||
~ | |||
u | |||
~ | |||
(!) | |||
c:: ~ ~ | |||
co u . a-' | |||
-- N j 830 - 3~0lY~3dW31 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 | |||
Ill 9 | |||
w | |||
~ | |||
5' 5 | |||
~ | |||
- ~ | |||
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 | |||
BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT DBA-LOCA LONG-TERM PRESSURE RESPONSE (102% OF UPRATED POWER, 100% CF) | |||
FIGURE 14.6-5 | |||
.. *20,0QDpi ACC£PTA8LE 50 w~ 1O.Dllll 11111 IJEIHUDC ACCEPTABLE RE.ACTIOK-DURATION COMBINATIONS 8£LOr ll*E BASED ON ltlAXIMlll ALLDWABt.£ CONTAl-llT 10 PRESSURE o.* 0.1 1.0 IJ DURATION OF RELEASE (hit u u AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Loa*-of-Coolan~ Accideat. | |||
Prhlary Coata1rm8"t Capability for Metal-Water Reac~ion FIGURE 14.6-6 | |||
PRIMARY COITAINMENT GEN ERATO~ | |||
CONO. | |||
REACTOR TURBIKE DRIVEN fEEO PUMPS 13) | |||
AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Main S~eamU.ne Bruk Accident Break Location FIGURE 14.6-15 FIGURE 14.6-7 | |||
.. 'It" Q | |||
~ z I-(/) 0 | |||
'\ 0 w | |||
-=s | |||
(') | |||
0 5 | |||
0 | |||
:J | |||
' tn w | |||
i= | |||
N id _J ~ ____ ..,... | |||
> w I- | |||
~~Cl) > | |||
w w en _J z | |||
a::> w 0 | |||
:::iWXcn I- g u LIJ ~:ii | |||
?;SrJ>~Z <( | |||
w | |||
:ii~ 0:: :J I-(/) | |||
0 0 0 0 0 0 | |||
0 0 | |||
0 0 | |||
80 8ao 0 0 § 0 0 | |||
~ | |||
N 0 | |||
ID 'It" N (03S/B1) )fV3~9 H~nmfHl 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 | |||
1~------. . . ----.-----.. . . ----~-----,...---- ....----"""""----.------.~---... | |||
- 10 SECOND ISOt.ATION | |||
- PUMPS TRIPPED AT T*O | |||
- REACTOR ~RIMll!O AT T*O D.Z TIME{SEC) | |||
AMENDMENT 17 BROWN$ FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Main Steamline Break Accldeac Normalized Core Iale~ 'Flcnr FIGURE 14.6-9 | |||
u ----...---..------,----....,...---r--- | |||
2.D | |||
-10 SECOND ISOLATJOH | |||
- PUMPS TRIJtPED AT T*D UI O"-----....i.------...._______,,________.._______________,,________, | |||
I 1D 12 4 | |||
Tiii! (2C) (Al'TU BREAK) | |||
\4 AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Main st...lin~ B~eak Accident K.iaillUtl C~itical Heat Flu~ Ratio FIGURE 1+. 6-10 | |||
BFN26 | |||
Figure14.611 | |||
DeletedbyAmendment26. | |||
BFN26 | |||
Figure14.612 | |||
DeletedbyAmendment26. | |||
BFN-16 Figure 14.6-13 Deleted by Amendment 9. | |||
BFN26 | |||
Figure14.614 | |||
DeletedbyAmendment26. | |||
BFN26 | |||
Figure14.615 | |||
DeletedbyAmendment26. | |||
BFN26 | |||
Figure14.616 | |||
DeletedbyAmendment26. | |||
BFN26 | |||
Figure14.617 | |||
DeletedbyAmendment26. | |||
BFN26 | |||
Figure14.618 | |||
DeletedbyAmendment26.}} |
Latest revision as of 21:06, 23 February 2020
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:
|
References | |
Download: ML18024A343 (18) | |
Text
~~
c:: c::
~~
~~
~~
E~
0 I. 0 rucn
~ a
-a:
0! ;.....c 8 l.:..J a.. ~ ~
- CJ)
- --s ...
I a.. ~ ~
Cl)
< ~
I-
-0 j
-l I .. ---
0 0
.. . ' I I I ' ' I 0
0 0
Ill
~
0 I/)
(~ S33~930) 3C!fllV~3dW31 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
Q mm
~~
a,. Cl.
-1 _.
-1~
~~
s~
Cl I()
I o-(\I U)
~
a, !i er ~
u
= "-
u.J I.LI .....
c..
...... Ul
~ I a..
...... ~~ ....
~
I-
.... 113
~ 0 u - ot- -
. . a 0
cg ...
0 N C9ISd> 3Hn553~d 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
~
~
- I ~
u
~
- .u H't c::
a:
-d \ uJ U'l LL.I u.. ~ - ~
(J1 z
a
~
u
~
(!)
c:: ~ ~
co u . a-'
-- N j 830 - 3~0lY~3dW31 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
Ill 9
w
~
5' 5
~
- ~
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
BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT DBA-LOCA LONG-TERM PRESSURE RESPONSE (102% OF UPRATED POWER, 100% CF)
FIGURE 14.6-5
.. *20,0QDpi ACC£PTA8LE 50 w~ 1O.Dllll 11111 IJEIHUDC ACCEPTABLE RE.ACTIOK-DURATION COMBINATIONS 8£LOr ll*E BASED ON ltlAXIMlll ALLDWABt.£ CONTAl-llT 10 PRESSURE o.* 0.1 1.0 IJ DURATION OF RELEASE (hit u u AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Loa*-of-Coolan~ Accideat.
Prhlary Coata1rm8"t Capability for Metal-Water Reac~ion FIGURE 14.6-6
PRIMARY COITAINMENT GEN ERATO~
CONO.
REACTOR TURBIKE DRIVEN fEEO PUMPS 13)
AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Main S~eamU.ne Bruk Accident Break Location FIGURE 14.6-15 FIGURE 14.6-7
.. 'It" Q
~ z I-(/) 0
'\ 0 w
-=s
(')
0 5
0
- J
' tn w
i=
N id _J ~ ____ ..,...
> w I-
~~Cl) >
w w en _J z
a::> w 0
- iWXcn I- g u LIJ ~:ii
?;SrJ>~Z <(
w
- ii~ 0:: :J I-(/)
0 0 0 0 0 0
0 0
0 0
80 8ao 0 0 § 0 0
~
N 0
ID 'It" N (03S/B1) )fV3~9 H~nmfHl 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
1~------. . . ----.-----.. . . ----~-----,...---- ....----"""""----.------.~---...
- 10 SECOND ISOt.ATION
- PUMPS TRIPPED AT T*O
- REACTOR ~RIMll!O AT T*O D.Z TIME{SEC)
AMENDMENT 17 BROWN$ FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Main Steamline Break Accldeac Normalized Core Iale~ 'Flcnr FIGURE 14.6-9
u ----...---..------,----....,...---r---
2.D
-10 SECOND ISOLATJOH
- PUMPS TRIJtPED AT T*D UI O"-----....i.------...._______,,________.._______________,,________,
I 1D 12 4
Tiii! (2C) (Al'TU BREAK)
\4 AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Main st...lin~ B~eak Accident K.iaillUtl C~itical Heat Flu~ Ratio FIGURE 1+. 6-10
BFN26
Figure14.611
DeletedbyAmendment26.
BFN26
Figure14.612
DeletedbyAmendment26.
BFN-16 Figure 14.6-13 Deleted by Amendment 9.
BFN26
Figure14.614
DeletedbyAmendment26.
BFN26
Figure14.615
DeletedbyAmendment26.
BFN26
Figure14.616
DeletedbyAmendment26.
BFN26
Figure14.617
DeletedbyAmendment26.
BFN26
Figure14.618
DeletedbyAmendment26.