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| number = ML18022A325 | | number = ML18022A325 | ||
| issue date = 10/05/2017 | | issue date = 10/05/2017 | ||
| title = | | title = Updated Final Safety Analysis Report (Ufsar), Amendment 27, 7.4 Figure - Emergency Core Cooling Control | ||
| author name = | | author name = | ||
| author affiliation = Tennessee Valley Authority | | author affiliation = Tennessee Valley Authority | ||
| Line 14: | Line 14: | ||
| page count = 30 | | page count = 30 | ||
}} | }} | ||
=Text= | |||
{{#Wiki_filter:BFN-18 Figure 7.4-1a (Deleted by Amendment 18) | |||
HO~ l -ZLll3£ t -z r< ti H | |||
Ill G m | |||
c | |||
'ffij\...,,**,., | |||
B AMENDMENT 27 POWERHOUSE UNIT2 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT HIGH PRESSURE COOL ANT A IN J ECTION SYSTEM FLOW DI AGRAM FIGURE 7 .4-lb SH 1 4 | |||
H G | |||
c B | |||
HIGH P~ET~~UN SYSTEM I N~~ow DIAGRAM FIGURE 7 .4-lb SH 2 8 | |||
B | |||
~ ,. c.. | |||
AMENDMENT 27 POWERHOUS E UNIT1 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT HIGH PRESSURE COOLANT A I NJECTION SYSTEM FLOW DIAGRAM FIGURE 7 .4-1 b SH 3 8 | |||
BFN-22 ' :. | |||
\.," | |||
~ | |||
Figures 7.4-2a through 7.4-2h (Deleted by Amendment 22) | |||
I | |||
BFN-22 Figure 7.4-3 | |||
{Deleted by Amendment 22) | |||
BFN-19 Figure 7-4-4 (Deleted by Amendment 17) | |||
I I '~ I I I I I l I 10 I 11 I 12 SY~BOLS l~W: | |||
10 L""!'i11,'"LOC~IC, | |||
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AMENDMENT 26 POIERHOUSE UNIT:Z | |||
- BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT ECCS PREFERRED PUMP MECHANICAL CONTROL DIAGRAM FIGURE 7. 4-5a l I I ! I I I I I I I 10 | |||
BFN-22 Figures 7.4-5b and 7.4-5c (Deleted by Amendment 22) | |||
~. | |||
AME NDMENT 23 BROW NS f[ RRY tt UC LE ... R PLMH r hlAL SAFCTY Att,f,.LYSIS 11£PORT PR£-ACD 4. COii Jl!:D SIGN AL WrOf.toNICAL C-3MTROL DJ,1,[; i;" A\1 fJGVft( 7 .f-5d | |||
BFN-22 Figures 7 .4-5e through 7 .4-5h (Deleted by Amendment 22) | |||
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AMENDMENT 27 PO'llERl-IOUSE UNJTI BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT ECCS PREFERRED PUMP MECHANICAL CONTROL DI AGRAM FIGURE 7 .4--5i | |||
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cs DIV II AUTOMATIC 1 "-' " " " " ' " " '"' " ' " " " " ' ' ' * ' - | |||
INII~1~:°N INHIBIT AMENDMENT 27 POWERHOUSE UNIT3 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT 1~:11:rnu 1 ECCS PREFERRED PUMP MECHANICAL CONTROL DIAGRAM FIGURE 7 .4-5m I I I I I I I I I | |||
H D | |||
c AMENDMENT 27 POWERHOUS E UNIT2 BROWNS FERRY NUCLE AR PLANT FINAL SAFETY ANALYSIS REPORT RESIDUAL HEAT REMOVAL SYSTEM A FLOW DI AGRAM FIGURE 7 .4--60 SH 1 | |||
m ' | |||
D c | |||
B AMENDMENT 27 POWER HOU SE UNITI BROWNS FERRY ~~;~~~isp~~~~RT FINAL SAFETY A RESIDUALFt6~TD~~~~XC L SYSTEM FIGURE 7.4-Sa SH 2 7 5 4 | |||
H G | |||
D c | |||
B AMENDMENT 27 FINAL SAFETY ANALYSIS REPORT RESIDUAL HEAT REMOVAL SYSTEM A FLOW DIAGRAM FIGURE 7. 4-6a SH 3 | |||
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AMENDMENT 27 | |||
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rt!it ' RHR STEA~ LINE MECHAN I CAL CONTROL DI AGRAM | |||
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LEAK DETECTION FIGURE 7 .4-6b SH 1 | |||
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- IL-74-59RX --t FROM XS 74 121 122 125 * ' * ~ ~ . NOTES: | |||
: 1. FOR GENERAL NOTES AND REFERENCE DRAWINGS SEE DRAWING 2-47E2610-74-J. | |||
- 2. CIRCUIT BREAKER IS NORMALLY OPEN EXCEPT FOR TESTING OR WHEN RHR IS - | |||
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- J. ALL COMPONENTS PREFIX IS *2- 11 UNLESS OTHERWISE NOTED. - | |||
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: 4. A. UNIDS ON DRAWING ARE FOR REFERENCE ONLY AND ARE ABBREVIATED AS SHOWN BELOW IN THE EXAMPLE TO MEET SPACE CONSTRAINTS. - | |||
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9-3 REFER TO MEL FOR COMPLETE UNIDS. ALL UNIDS ARE IN UNIT 2 AND SYSTEM 74 UNLESS OTHERWISE NOTED. FOR ADDITIONAL GUIDANCE REFER TO NEDP-4. | |||
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- B. ALL VALVES IDENTIFIED AS *rev* HAVE VALVE OPERATORS. | |||
THE MEL UNID FOR THE VALVE OPERATOR IS DEVELOPED - | |||
- 74-49 '74-49 AS FOLLOWS: - | |||
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1 1 | |||
1 4 74-82 | |||
* R R _ G 1 : :11 H Z,_4-11G_ x_s r_J I l2-45E779-10 Hs | |||
~ rw°"LiJ* TE -1,..Ts 25_-2_24A----~--_J Ll 4~A ~ 17~~*8cc ~ | |||
' TW \ ,>;;;\ HTX C ' I ,::jJ - I I 'lf<{ (Cf I | |||
- \4-1~Mz4-8! ~r:L.J:::;:---1iJ( 4-135C~5C - | |||
- zs' -@47 I 9 3@ LPCI INIT. INHIBITS | |||
- ,- 1/2' __'--- I LOG I TR - *--' | |||
* MCC I "'C,_".l'_J - HS AND INTERLOCKS | |||
~ "f"I 6-2-10_.....J 74-1~5C);;(IL-74-1J5C I L 74-153 - - - - - - - - , - - SHOWN ON 2-45E765-4 | |||
."T_;-_--------------... - | |||
--- -...__....- \IC'*IT "H* TELL-TALE 74-BJ IA74017HI IL-74-96tR1' IL-74-2 ZI-74-22 L....lTHis DRAWING. F4 ~ ..........,-1*v'1-i+.:~::--:--:===~~....;;;;.-...,.-----l.,_~~~P | |||
--= - 125-579 lL 1 r-c 1 - - - , - r_ _ _ _ _ _ _._..__ _ _ | |||
~--;!.(25-252 II 11 XS FCV '1.JI | |||
-~ 2-45E11s-13 I I ~AN~D~2-_4~5~E7~7~9_-~22~~ | |||
I I | |||
- }R( SHV ZS TE TO TR 80 - _!_ l ~ AUTO INIT INHIBITS ---=--25-224AI 9-J r 7 ~~ 4:!_ | |||
7... 6 II~ | |||
ili - | |||
- >r<- -- - a~ ~ PI "'\ ~, '7 r SHV | |||
~I~ 86)174-81 ZS I-74-86~-J r.< | |||
9-J 25-59 | |||
+++ SHOWN ON 2-45E765-4 ..J L | |||
@----rl I | |||
9-J L_____ | |||
~~4;~~~~-23-1, H7 )-- | |||
--1----:::;;o | |||
~-24-~1 TW GG7_+-1.13 3 | |||
TW' | |||
~ | |||
J,_ | |||
'PS,£ES 74-1; 74-l~B 4-19A | |||
-=. | |||
yJ_l/',f-------, | |||
-c__~ | |||
TA 56-2 | |||
@ A. .1 FIS 4-15 *-,y74-15 PI ' | |||
4-14 1 | |||
>!.{ j.Q | |||
~A 9-J | |||
~ | |||
I I | |||
@9 G?E'\ | |||
9-47 I | |||
....1.. | |||
TR\ | |||
.:>6 2.,11 IA74006AI | |||
- I LOG I 74-135A 74-135A TW 4-135A ~IL 135 A 74-135 c ~J | |||
*-1: FIGURE 1. ECCS AUTO INITIATION INHIBITS I - - - . r"'TO""'R"'8F:'O":"SU"'M"'P.,.,--..... I .' 1 I TE I , ~ 25-232 >£<"' I | |||
- 1-~~~~~~~...;1.......;:::::::i:::::.~~~~~.:::..~~~~~...!L;;.;;;;j;;;~-;;.;;;.;;;;.;;:.,.~~~~~~~..!.~~~-~-~~..... ~-~:2-47E852-1, A6 > I II 4-6A~ L .,-._~ .... ~.,...~~~~....;~~~.................._J;;;1....1...;..i,...~~~~~~-t>i-<1'~~~~..... | |||
~ | |||
- '--l~l---.:4---'H2-47E852-1. | |||
* TO DRW D7 > ~. | |||
.l2-45ES14-10 L r1 I | |||
}';;{_R _ - ..1... - -, | |||
~ | |||
MCC ,(Fcv_) | |||
~- | |||
I TO UNIT 1 RHR CROSSTIE HEADER L-r--'f"--1'"-,...--1 1 47ES10 74 1A. C1 I | |||
G$) I I | |||
I I | |||
~J4-S8 TE | |||
- , 9-47 I I 'r | |||
>-- ~ | |||
: ~ CD N I r--=---_J I I SHV\ 'r I 174-1\ | |||
~ | |||
IL-74-1.)::.\ | |||
};;-{__ - ..1...- | |||
FCV | |||
~ | |||
~ | |||
TO TR-74 @2-47E610-74-I, GS | |||
~ l I IL-74-100 74-100 TR LOG | |||
~ l , ~ ~ ~ ~ I 9-3 I2-45E779-47~-, | |||
74-1 | |||
~ | |||
r TI ~ r.;;"\, 1 ' ' 0 ;t i1 1r~ 1 1 t:: | |||
- s- 21 XO ' | |||
1 4-81 TE V4~i4:rrvr:1~~ ~sr+s I : : I MOTOR ' I ~ ~ ~ ~ I IZI-74-11 rx-i L I r i~ *~ | |||
1r:146 __/;\ I TR LOG I | |||
{:~11}1 Tw'\ | |||
-e;,0 ~.......... | |||
2-45E6~4-10 ri( ~Oc | |||
~' "u . - | |||
I~- 5@s | |||
~ | |||
~:.2: 3 ~~4~~~ ~ ! ~ ~ IL,~ 1 | |||
'-...../ ~-47 I-HTX A ...__,,, | |||
_1µ_ - - - 1/2" I r----1---------'1 | |||
: N | |||
+-I V!)'74-6F I * - I ISQ_.l.Q I I HS eY | |||
)--!... --' | |||
N AMENDMENT 26 | |||
- | |||
* 74-5C 74-11 XS I I I I 74-1C 74-1 -- | |||
J- | |||
- ZI:7-~-10 | |||
?'RS' | |||
;-v I 1 | |||
ZS | |||
~ VENT .G. TELL-TALE 1/2" | |||
'-~ ' | |||
VENT "J" TELL-TALE | |||
--ITHIS DRAWING. F4 "'> | |||
I t-i:E{@-3 I I | |||
1---,--, | |||
I HS | |||
@m-t I;!: ~ | |||
I0 ~ | |||
~~ | |||
~ ~ | |||
,.!. : 'tG5 '(Ri' L_T_T 1::6J TR | |||
;;i6 2~4 I IA74006FI L-----t LOG I I , | |||
- - I L~l | |||
~ | |||
9-3 I - | |||
:I @--19@74H_s1A T | |||
POWERHOUSE | |||
- TO re 74-10 74-10 | |||
-- <---- ----,, __J";;' YTHIS DRAWING, F4 TI 4-109 TW ' | |||
L-m HS 74-100A I 4-1D08m-.i r 'vJ~----~I LOG I 9-47 | |||
~-10T~E~~~~o::::~-------------tJ | |||
*~ 74 s~ ~RHR' | |||
!~_r.-s ___ r.-s_ ro5 UNIT 2 RHRSW _ _ _ _J 2-47ES1D-23-1. F7 \- -:::::::::----, 74-9 1---------1,4-10~9"'"T_;~--l_/'1.--..... | |||
L--------=11-45E779-10 | |||
,----L-----------@~==--...!:=====!.:=::;:..~11 ....::::::::::.._.::::;::::~ PUMP r1 ~----- | |||
llA7400SHI I | |||
L ....T x T .X._j_ BROWNS FERRY NUCLEAR PLANT | |||
- | |||
* _1_25 59 _1_25 59 __!25-59 ------ 4H_~ 04 1 r- A __, -----<,>----~------,~ ----------- -..., | |||
>---~ ~:-s.~ I 1:~. l J::.~ I~ ~:ra4 ~ t9- 3 -------..+/-_----=~ 59_ _ _ _ ,_ _ _ _ J FINAL SAFETY ANALYSIS REPORT | |||
( 7 ::, J To rn-14-so | |||
~-J~-47E2S10-74-1. | |||
Gs) T 1 | |||
- I 1 | |||
I~ ~- -----~- | |||
'1 | |||
""c M | |||
@ ---j j 4I:4 J i7:_I3 ) | |||
TO R8FD SUMP l2 - 45 E777 -sH | |||
© ' - FROM coNoENsATE-HDR I 2-47E818-1. c1 >-- | |||
FROM Fcv- 74 _ 35 I 2_47 E2 S10_74 _1. | |||
L---========:::::'.:___ ,_ | |||
E2 >-J I | |||
K-L--J:~t--H 1-47Ea52-1, TO DRW 01 | |||
> LJ 2-730E937-S 1L - - - - - - - '1 | |||
~ | |||
L-12-45E779-491 @ I 9_3 : | |||
2 4 7 552 1 | |||
- E - * (:As 7\ '.: | |||
IL 74 105 I TO MAIN CONDENSER A | |||
-~_...J_,,--::J-l.f--.....J-'-1-~2lll~l-4-7E_2Ts_1_o-_1_4_-1_._I'_ _>_ _J RESIDUAL HEAT REMOVAL SYSTEM 2 | |||
I ......,. - 1 - - - COMPANION DRAWING: | |||
MECHANICAL CONTROL DIAGRAM | |||
- 117 n | |||
'k:..J ~ | |||
~ SYS I | |||
- 2-47E2610-74-1 | |||
- 3 I "' ~ FLUSH PUMP 1-47E610-74-1A 3-47E610-74-l, 2 FIGURE 7.4-6b SH 2 I I I I 1 I I I I I I I I I 2 I I I I I I I I I 3 I I I I I I I I I 4 I I I I I I I I I 5 I I I I I I I I I 6 I I I I I I I I I 7 I I I I I I I I I 8 I I I I I 10 I I I | |||
~-~+~:~:.::1~i:~ttt1Jftf | |||
~j!,l ''-'"' @-:~~ | |||
H | |||
~'..L_,:~.~- ~ii'. ... , | |||
G D | |||
c B | |||
AMENDMENT 27 POWERHOUS E UNIT1 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT RESIDUAL HEAT REMOVAL SYSTEM A MECHAN I CAL CONTROL DI AGRAM FIGURE 7 .4-6b SH 3 7 5 4 3 | |||
,_,,,, :--~~-~--'"@. "., ": | |||
~~!M~,-~ ,___f[~j~~f~i F IGU RE 1 ECCS AUTO INITl ... TION 1NH181TS | |||
__ .,".)" | |||
r_,:-.:~,:*i*_,., | |||
*-@--~ AMENDMENT 27 | |||
'@-__L_,*::,-.::;::.,,, | |||
~-~-~-~ ~ ..~ ~-~-~- , | |||
$t* $t ~ ..~ | |||
"~:;~~"' | |||
BROWNS FERRY NUCLE AR PLANT | |||
.,,,.,.,. $t- ~~ | |||
<,?,;,.10-11-1.">--1---.J ___ .J. ___ J. ___ j_ ___ L __ ...J.... __ ...J FINAL SAFETY ANALYSIS REPORT RESIDUAL HEAT REMOV AL SYSTE M MECHANICAL CONTROL DI AGRAM | |||
@RHRSTE AMLINELE Al< DETEC T ION FIGURE 7. 4-6b SH 4 | |||
' + o~ l-*H-OL93Lt-£ 3 l~ | |||
FI GU RE 1 ECCS AUTO INITI ATION INHIBITS AMENDMENT 27 BROWNS FERRY NUCLE AR PLANT FINAL SAFETY ANALYSIS REPORT RESIDUAL HEAT REMOV AL SYSTE M MECHANICAL CON TROL DI AGRAM FIGURE 7. 4-6b SH 5 | |||
BFN-22 Figure 7.4-7a (Deleted by Amendment 22) | |||
~*- ,/*.** | |||
' *~* ~ | |||
, . *._.,.,,,,,,.,. ,,,,,,. *.._~.\>..; u,,;H,,~1*.wll lil.l:.LLIWl-.:ldf.lt;i;~~-~. .a. t:i : ... . | |||
I I I I 11 I I I I I I I ~ I I I I I I I I ~ I I I I I I I I .,. I I I I I I I I I 1 I I I I I I I I ~ I I I I I I I I ~ I I I I I I I I ~ I I I I I I I I ~ I I I I I I I I I I I I I I I I I 1 I | |||
- too~ £-tL-OL93Lt-Z LS | |||
- PIS-3-74A REACTOR PRESS. LOW TEST A- (TYPICAL OF 4) PIS-68-95 PIS-64-SBA DRYWELL PRESS. HIGH | |||
_._ 9-3 HS \ | |||
'-A | |||
- (TYPICAL OF 4) PIS-64-58C PIS-3-748 PIS-68-96 75 51 | |||
- PIS-64-588 PIS-64-588 AUTO | |||
- l I y y I y '-- | |||
B-I I | |||
'--8 REACTOR PRESS. LOW | |||
- DRYWELL PRESS. HIGH '-- | |||
- DET A3 DET 83 '-- | |||
- DRYWELL PRESS HIGH (SEE DETAIL B THIS SHEET) | |||
- REACTOR PRESS LOW c-- (SEE DETAIL A THIS SHEET) | |||
LS-J-58A | |||
'-C | |||
'°'- PB9-J RX VESSEL LVL LOI (TYPICAL OF 4) LS-3-58B J HS\ LS-3-58C LS-3-58D | |||
- ~:Jl '-- | |||
- RESET - | |||
I THIS UNIT 2. RHR CLPCI) - | |||
- owe. DET 03 >>---~o:i.1vw1~AJi.UT!Jow1!!N:i.nws..,1li.cN!!lAl!L~~ | |||
10A-K9A y y - | |||
- UNIT 1, RHR (LPCI) - | |||
- I1-47 E610-7 4-3. G7 )>---~D:i.IVwlLJ!AJi.UT!JOwI!!N;!.ITWS;!.I~GN!!JAl!L.., | |||
1-RLY-74-10A-K73A D- I -D | |||
- UNIT 1 . CS - | |||
11 47E610 75 2, 08 '" | |||
DIV I AUTO INIT SIGNAL -- | |||
- 1 RLY 75 14A K11A - | |||
- I - | |||
_J UNIT 1 ACCIDENT - | |||
- 10A-K36A(B) | |||
SIGNAL. DIV I (CH Al (DET C-3 THIS SHEET) | |||
THIS DIG. DET C-3 I h - | |||
- 10A-K107A _/ - | |||
........ 10A-K109A | |||
~ | |||
TO UNIT 2 ECCS PREFERRED PUMP LOGIC INHIBIT AUTOMATIC (LPCI) START OF RHR PUMPS 2A ~ 2C | |||
- ~ 10A-K9A I 2-45E765-4, G-4 THIS DIG, DET C-3 E- | |||
- <THIS DWG DET 03 0 | |||
SEAL-IN I INHIBIT AUTOMATIC OPENING OF LPCI | |||
~E TRIP PUMP 1 2-45E765-4, CS 10A-K73A(B) RHR (LPCI) AUTO INIT LOGIC INHIBIT SIGNAL I UNIT PRIORITY DG BKR RE-TRIP SIGNAL CH A 2-47E610-75-2, A 7"> | |||
INJECTION VALVE FCV 74 SJ I 2-45E779-22. G-5 > | |||
(OET G-3 THIS SHEET) | |||
- INHIBIT PUMP INHIBIT THE INITIATION OF THE UNIT 1 ECCS PREFERRED PUMP LOGIC ON A UNIT 2 DIV I LPCI SIGNAL TO UNIT PRIORITY DG BKR TO RHR PUMPS 1 2 -730E927 -;* r'> 1 THIS DWG, DET D-J NOTES: | |||
: 1. ALL COMPONENTS ARE PREFIXED "2-* UNLESS OTHERWISE SHOWN. | |||
RE-TRIP !NIT LOGIC 2A AND 2C, 2. FOR GENERAL NOTES AND REFERENCE DRAWINGS SEE 2-47E610-75-1 .2. | |||
- DIV I (CHANNEL A) AUTO START AND RHR (LPCI) AUTO INITIATION '-- | |||
INHIBIT INDICATION. | |||
PUMP TRIP LOGIC DIV I (CHANNEL A) | |||
DETAIL D I TO UNIT 1 RHR AND CORE SPRAY ECCS PREFERRED PUMP LOGIC CHANNEL A (B) | |||
'-----------------{A | |||
- 9-3 IL-74-153 | |||
: 3. DELETED T ~-47E61D-74-3, c 1 > | |||
- RHR (LPCI) | |||
F-UNIT 2 ECCS PREFERRED PUMP LOGIC DET C3 RHR AUTO INIT SIGNAL, CHANNEL A (Bl DET D3 L...J1-47E61D-75-3, | |||
*-* AUTOMATIC INITIATION INHIBIT LOGIC DE T G-3 ~F | |||
- SYMBOLS: | |||
- ANO GATE: OR GATE: '-- | |||
(INPUT A) (INPUT BJ | |||
- UNIT 2 (INPUT A) (INPUT B) | |||
DIVISION I I I '-- | |||
- I I G- DRYWELL PRESS HIGH | |||
~G | |||
- (SEE DETAIL B THIS SHEET) | |||
- REACTOR PRESS LOW (OUTPUT) '-- | |||
(SEE DETAIL A THIS SHEET) | |||
- LS-3-58A (OUTPUT) | |||
RX VESSEL LVL LOW THE "AND* GATE GIVES AN OUTPUT MOM PB LS-3-58B SIGNAL IF AL.I.. INPUTS ARE PRESENT | |||
- (TYPICAL OF 4) THE "QR* GATE GIVES AN OUTPUT SIGNAL IF '-- | |||
_,.-...,,9-3 f HS\ LS-3-58C LS-3-58D AMY INPUT ARE PRESENT .....__ | |||
- ~_;)2 RESET NOT GATE: | |||
UNIT 1, RHR (LPCI) l | |||
- DIV II AUTO INIT SIGNAL ,.,.-=,,-,,:-:-,--:-,,-,,, | |||
- UNIT 2, RHR (LPCI) 1 RLY-74-10A-K73B 1-47E610-74-3. K-71 y y (INPUT) | |||
DIV II !NIT SIGNAL H- ITHIS DWG, DET F3 1 OA-K368 ~H UNIT 1, CS DIV II AUTO INIT SIGNAL..-". | |||
1-RL Y-7!S-14A-K11 B -..,J-47E610-75-2. H-8 I I '-- | |||
- I I (OUTPUT) | |||
UNIT 2. RHR (LPCI) | |||
DIV II AUTO INIT SIGNAL THIS DIG DET Fl I NORMA.MA~ (9-3) | |||
THE *Nor* GATE GIVES AN OUTPUT SIGNAL ONLY IF THERE IS NO INPUT SIGNAL | |||
- t ~10A-K7JB " ' HS (HS-74-154) | |||
\ 74-154 RHR <LPCI/ AUTO !NIT | |||
- SEAL-IN '- _;,,* INHIEiIT K YLOCK '-- | |||
INHIBIT SWITCH | |||
- UNIT PRIORITY DG BKR 10A K36A(B) | |||
- T RE-TRIP SIGNAL CH B 2-47E610-75-2, B-7 10A-K107B __/ | |||
I - TO UNIT 2 ECCS 10A-K109B INHIBIT AUTOMATIC (LPCI) START OF RHR PUMPS (2B ~ 20). | |||
- 10A-K73B PREFERRED PUMP LOGIC 2-45E765-4, C-4 | |||
- 10A K36B | |||
- THIS DWG, OET E3 " INHIBIT AUTOMATIC OPENING OF LPCI | |||
- INJECTION VALVE FCV-74-(67). | |||
..,__---------------!: 2-45E779-22. G-5 | |||
- 10A-K73A(B) RHR (LPCI) AUTO INIT LOGIC INHIBIT SIGNAL INHIBIT THE INITIATION OF THE UNIT 1 (DET H-3 THIS SHEET) ECCS PREFERRED PUMP LOGIC ON A UNIT 2 (DIV II) LPCI SIGNAL l-'"'-'"-'="-'--"'.:..:..-'-'"'-"'-"'-"'=""----1 1 1 THIS DWG, DET F-J ")o | |||
- RHR (LPCI) AUTO INITIATION | |||
.__I_NH_I_*_Ir_IN_o_I_c*_r_I_o,_._ _ _ _ _ _-{ii)~ 9_3 J- | |||
- I 2-45E7 65-4. CB I | |||
TO UNIT 1 RHR AND CORE SPRAY ECCS PREFERRED PUMP LOGIC CHANNEL A (B) | |||
~ ),.Q IL-74-154 AMENDMENT 26 1-+7E610-7+-3, I-+ "> | |||
- TO RHR PUtr.f>S 28 AND 2D, RHR (LPCI) POWERHOUSE PUMP TRIP LOGIC AUTOMATIC | |||
- DIV II (CHANNEL 8) RHR AUTO INIT SIGNAL, CHANNEL A (B) U-47E610-75-3, G-4 "> INITIATION INHIBIT UNIT 2 | |||
- DET E3 DET F3 LOGIC DET H3 BROWNS FERRY NUCLEAR PLANT | |||
- DIVISION II FINAL SAFETY ANALYSIS REPORT K- ECCS PREFERRED PUMP LOGIC | |||
- MECHANICAL CONTROL DIAGRAM | |||
- COMPANION DRAWINGS: | |||
1-47E610-74-1 , -2. -3 | |||
- 2-47E610-74-1 .-2 | |||
- 3-47E610-7+-1,-2,-3 FIGURE 7.4-7b I I I I ~ I I I I I I I I I I I I I 2 | |||
I I I I 3 I I I I I I I I 4 | |||
I I I I I I I I I I 5 | |||
I I I I I I I I 6 | |||
I I I l I I I I I I I I I 7 | |||
I I I I BI I I I I I I I 9 | |||
I I I I I I I I I I 10 I I | |||
BFN-22 Figures 7.4-7c through 7.4-7h (Deleted by Amendment 22) | |||
~ | |||
~ | |||
AMENDMENT 23 8"°'HS P't:RRY HUCLEAR rLANT FINAL SAFETY At4ALYSIS R£PORT PRE-ACD l COt1 A CO SICtlAI. | |||
Air:CHAMICA.l COMTIOL OIACIMI f'IOURE 7.4-7; | |||
*.. ,_,,,.. __ ,.,...__,...W!A:O., j.! .~ >1--...i-,.Ji~l* ...-.. 1o.-- - ~** -t'*iiioo-: :1-*,.,..,,..;n...+=~~*~* ;."".,.,,_,,_. __ ..t.,-1,,..;.;,,.4, ~1'-ll--- lo;~fl:.;J. ioo1IJi .;:t.;../...--~ .. ;t.*..;..,,1 .. ' ***--~ -'-*- * * * * * * *******., _ . , . . . ..~. . . . . . .J!~~.,. .i~ | |||
_,_____ ~ "-..,. ... ..,._, . . , _ u.-..,_ ._...... . | |||
BFN-22 Figures 7.4-7j through 7.4-7n (Deleted by Amendment 22) | |||
-~~ ~ ' z ~ | |||
:,: . - *~ ~* .. -_ *- | |||
. l1.;_ll ; *~-U.!l.t .J.l ,~ *..JUi *l~[, j j lL -~ .U( .... 1 .: .* __._.i -- ~ * *** *1, 4** !IU ,,;_jJ, . | |||
* bJ,. .,,;;J ;;t.J:;~ ,_ 1'Hii'tjbhl!J i.Jfli li11lfili:"Zi.:M1.:.kli!il:1!IU.E,i,Ji1u~.I-' ' I ~a,_._, :, .l ,1 Jllr.1 ~ - ,._ !1- 1.. * .. :*:.1.1 i :.. ' ! I , __ *:- id*' I. ,.!_,_, *- .,. H .:..- Id~- '- ' ,,, | |||
~tr r ~":~t*~ | |||
* **~- | |||
"'""1°" "'"'* "" "'"'" "'" * ""' r:;r'i.i,i~t':; . 'lm ....,,, | |||
UNIT1 DIVISION I T>l< "- " o;.l [ " \<:S /,N lllJH'IJT 1:C.l.llf.1U.Um 1 *1t< m "MT | |||
.1 AMENDMENT 27 POWERHOUS E UNIT1 BROWNS FERRY NUCLE AR PLANT FINAL SAFETY ANALYSIS REPORT ECCS PREF PMP RESIDUAL HEA T REMOVAL SYSTE M MEC HANICAL CONTROL DIAGRAM FIGURE 7 .4-7p | |||
BFN-16 Figure 7-4-8 Deleted by Amendment 9. | |||
BFN-22 Figures 7.4-8a through 7.4-8d (Deleted by Amendment 22) | |||
BFN-22 Figure 7.4-9 (Deleted by Amendment 22) | |||
: ,* :.}} | |||
Latest revision as of 00:27, 18 March 2020
| ML18022A325 | |
| 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: ML18022A325 (30) | |
Text
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H G c B HIGH P~ET~~UN SYSTEM I N~~ow DIAGRAM FIGURE 7 .4-lb SH 2 8
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BFN-22 ' :.
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Figures 7.4-2a through 7.4-2h (Deleted by Amendment 22) I
BFN-22 Figure 7.4-3 {Deleted by Amendment 22)
BFN-19 Figure 7-4-4 (Deleted by Amendment 17)
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H D c AMENDMENT 27 POWERHOUS E UNIT2 BROWNS FERRY NUCLE AR PLANT FINAL SAFETY ANALYSIS REPORT RESIDUAL HEAT REMOVAL SYSTEM A FLOW DI AGRAM FIGURE 7 .4--60 SH 1
m ' D c B AMENDMENT 27 POWER HOU SE UNITI BROWNS FERRY ~~;~~~isp~~~~RT FINAL SAFETY A RESIDUALFt6~TD~~~~XC L SYSTEM FIGURE 7.4-Sa SH 2 7 5 4
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>---~ ~:-s.~ I 1:~. l J::.~ I~ ~:ra4 ~ t9- 3 -------..+/-_----=~ 59_ _ _ _ ,_ _ _ _ J FINAL SAFETY ANALYSIS REPORT
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- 3 I "' ~ FLUSH PUMP 1-47E610-74-1A 3-47E610-74-l, 2 FIGURE 7.4-6b SH 2 I I I I 1 I I I I I I I I I 2 I I I I I I I I I 3 I I I I I I I I I 4 I I I I I I I I I 5 I I I I I I I I I 6 I I I I I I I I I 7 I I I I I I I I I 8 I I I I I 10 I I I
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G D c B AMENDMENT 27 POWERHOUS E UNIT1 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT RESIDUAL HEAT REMOVAL SYSTEM A MECHAN I CAL CONTROL DI AGRAM FIGURE 7 .4-6b SH 3 7 5 4 3
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@RHRSTE AMLINELE Al< DETEC T ION FIGURE 7. 4-6b SH 4
' + o~ l-*H-OL93Lt-£ 3 l~ FI GU RE 1 ECCS AUTO INITI ATION INHIBITS AMENDMENT 27 BROWNS FERRY NUCLE AR PLANT FINAL SAFETY ANALYSIS REPORT RESIDUAL HEAT REMOV AL SYSTE M MECHANICAL CON TROL DI AGRAM FIGURE 7. 4-6b SH 5
BFN-22 Figure 7.4-7a (Deleted by Amendment 22) ~*- ,/*.**
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- 1 RLY 75 14A K11A - - I -
_J UNIT 1 ACCIDENT -
- 10A-K36A(B)
SIGNAL. DIV I (CH Al (DET C-3 THIS SHEET) THIS DIG. DET C-3 I h -
- 10A-K107A _/ -
........ 10A-K109A
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TO UNIT 2 ECCS PREFERRED PUMP LOGIC INHIBIT AUTOMATIC (LPCI) START OF RHR PUMPS 2A ~ 2C
- ~ 10A-K9A I 2-45E765-4, G-4 THIS DIG, DET C-3 E- - <THIS DWG DET 03 0
SEAL-IN I INHIBIT AUTOMATIC OPENING OF LPCI
~E TRIP PUMP 1 2-45E765-4, CS 10A-K73A(B) RHR (LPCI) AUTO INIT LOGIC INHIBIT SIGNAL I UNIT PRIORITY DG BKR RE-TRIP SIGNAL CH A 2-47E610-75-2, A 7">
INJECTION VALVE FCV 74 SJ I 2-45E779-22. G-5 > (OET G-3 THIS SHEET)
- INHIBIT PUMP INHIBIT THE INITIATION OF THE UNIT 1 ECCS PREFERRED PUMP LOGIC ON A UNIT 2 DIV I LPCI SIGNAL TO UNIT PRIORITY DG BKR TO RHR PUMPS 1 2 -730E927 -;* r'> 1 THIS DWG, DET D-J NOTES:
- 1. ALL COMPONENTS ARE PREFIXED "2-* UNLESS OTHERWISE SHOWN.
RE-TRIP !NIT LOGIC 2A AND 2C, 2. FOR GENERAL NOTES AND REFERENCE DRAWINGS SEE 2-47E610-75-1 .2.
- DIV I (CHANNEL A) AUTO START AND RHR (LPCI) AUTO INITIATION '--
INHIBIT INDICATION. PUMP TRIP LOGIC DIV I (CHANNEL A) DETAIL D I TO UNIT 1 RHR AND CORE SPRAY ECCS PREFERRED PUMP LOGIC CHANNEL A (B)
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*-* AUTOMATIC INITIATION INHIBIT LOGIC DE T G-3 ~F - SYMBOLS: - ANO GATE: OR GATE: '--
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- UNIT 2 (INPUT A) (INPUT B)
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RX VESSEL LVL LOW THE "AND* GATE GIVES AN OUTPUT MOM PB LS-3-58B SIGNAL IF AL.I.. INPUTS ARE PRESENT
- (TYPICAL OF 4) THE "QR* GATE GIVES AN OUTPUT SIGNAL IF '--
_,.-...,,9-3 f HS\ LS-3-58C LS-3-58D AMY INPUT ARE PRESENT .....__
- ~_;)2 RESET NOT GATE:
UNIT 1, RHR (LPCI) l
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DIV II !NIT SIGNAL H- ITHIS DWG, DET F3 1 OA-K368 ~H UNIT 1, CS DIV II AUTO INIT SIGNAL..-". 1-RL Y-7!S-14A-K11 B -..,J-47E610-75-2. H-8 I I '--
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UNIT 2. RHR (LPCI) DIV II AUTO INIT SIGNAL THIS DIG DET Fl I NORMA.MA~ (9-3) THE *Nor* GATE GIVES AN OUTPUT SIGNAL ONLY IF THERE IS NO INPUT SIGNAL
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I - TO UNIT 2 ECCS 10A-K109B INHIBIT AUTOMATIC (LPCI) START OF RHR PUMPS (2B ~ 20).
- 10A-K73B PREFERRED PUMP LOGIC 2-45E765-4, C-4
- 10A K36B
- THIS DWG, OET E3 " INHIBIT AUTOMATIC OPENING OF LPCI
- INJECTION VALVE FCV-74-(67).
..,__---------------!: 2-45E779-22. G-5
- 10A-K73A(B) RHR (LPCI) AUTO INIT LOGIC INHIBIT SIGNAL INHIBIT THE INITIATION OF THE UNIT 1 (DET H-3 THIS SHEET) ECCS PREFERRED PUMP LOGIC ON A UNIT 2 (DIV II) LPCI SIGNAL l-'"'-'"-'="-'--"'.:..:..-'-'"'-"'-"'-"'=""----1 1 1 THIS DWG, DET F-J ")o
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TO UNIT 1 RHR AND CORE SPRAY ECCS PREFERRED PUMP LOGIC CHANNEL A (B)
~ ),.Q IL-74-154 AMENDMENT 26 1-+7E610-7+-3, I-+ "> - TO RHR PUtr.f>S 28 AND 2D, RHR (LPCI) POWERHOUSE PUMP TRIP LOGIC AUTOMATIC - DIV II (CHANNEL 8) RHR AUTO INIT SIGNAL, CHANNEL A (B) U-47E610-75-3, G-4 "> INITIATION INHIBIT UNIT 2 - DET E3 DET F3 LOGIC DET H3 BROWNS FERRY NUCLEAR PLANT - DIVISION II FINAL SAFETY ANALYSIS REPORT K- ECCS PREFERRED PUMP LOGIC - MECHANICAL CONTROL DIAGRAM - COMPANION DRAWINGS:
1-47E610-74-1 , -2. -3
- 2-47E610-74-1 .-2 - 3-47E610-7+-1,-2,-3 FIGURE 7.4-7b I I I I ~ I I I I I I I I I I I I I 2
I I I I 3 I I I I I I I I 4 I I I I I I I I I I 5 I I I I I I I I 6 I I I l I I I I I I I I I 7 I I I I BI I I I I I I I 9 I I I I I I I I I I 10 I I
BFN-22 Figures 7.4-7c through 7.4-7h (Deleted by Amendment 22)
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AMENDMENT 23 8"°'HS P't:RRY HUCLEAR rLANT FINAL SAFETY At4ALYSIS R£PORT PRE-ACD l COt1 A CO SICtlAI. Air:CHAMICA.l COMTIOL OIACIMI f'IOURE 7.4-7;
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BFN-22 Figures 7.4-7j through 7.4-7n (Deleted by Amendment 22)
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UNIT1 DIVISION I T>l< "- " o;.l [ " \<:S /,N lllJH'IJT 1:C.l.llf.1U.Um 1 *1t< m "MT
.1 AMENDMENT 27 POWERHOUS E UNIT1 BROWNS FERRY NUCLE AR PLANT FINAL SAFETY ANALYSIS REPORT ECCS PREF PMP RESIDUAL HEA T REMOVAL SYSTE M MEC HANICAL CONTROL DIAGRAM FIGURE 7 .4-7p
BFN-16 Figure 7-4-8 Deleted by Amendment 9.
BFN-22 Figures 7.4-8a through 7.4-8d (Deleted by Amendment 22)
BFN-22 Figure 7.4-9 (Deleted by Amendment 22)
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