browns ferry nuclear plant updated final safety analysis ... · 090~ ~-£ ~93lt-z v'-1 ls i i...
TRANSCRIPT
090~ ~-£ ~93Lt-Z V'-1 Ls
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REACTOR
8" ---< 2-47E818-1,C7
C--,,--'PS I /'. 71.:.!A f...--1 PDT \.'---~~--" PS
PRIMARY CONTAINMENT \ SYSTEM PRESS. - TEii' DATA 1 .. FROM CRD LINE DESIGN DESIGN
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I
71.:.!A 71.:J.B
~ L_____r,;;\ CONDENSING NOTE 14 (TYP /, CHAMBER
RTV-1AL 71.:!D 71.:JA
ECKV-71-1AA
(TYP 2) --;r:=CP:jO"-Ti:-7..:1_-1..:A:.....--ll::F-:.!.l ;;," ~~,.:X::;-~5l~F--~~L~-{:-
MAIN STEAt.4 ll .----1•:• 1" X SlE RTV~1AH -LECKV-71-1AB
2 47E801 1, FS - 1h 1 " X-33F L -
I
w w
I tFE) 3" 7~
ECKV-71-1BA
.---ti CPOT-71-18 RTV-lBL L._ECKV-71-188
- " 'h 31"-X-:;,3:.:<3-".E ---t<H:cJ---1' 1 " RTV-1 BH -@cv (TYP 2) FCV
1-2 1-3 r
X-10 HPCI SYSTEM
____ ..,,} 2-47E812-1 GS
FLG-71 - l I' '°t~:---0-----</~0~4~7~E~8~20~1_:·.:C4~ SEE NOTE 16 __..,,
3/4"
SHV-71-62 : 5 12
FCVtJ •--l( 71-19 ' ~
m . !l'
' ' I- i;;;: _____ .. u
MK NO. PRESSURE (PSIG) TEt.tP( 't)
1 1146 562 2 150 325
1375 545 4 1500 200 5 150 200 6 1375 200 7 1500 40 TO 140 8 1250 575 9 165 366 10 270 415 11 400 450 12 250 150 13 100 103 14 200 200
LOV-565 1 4 ,, T 1/4" I
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-' ., I 3• 4" 4• (FE j--,---o(>-~-3-fl""~\ol,_.;....,T'" __ [>lo.::J-----~-J----------;_,..,_...;, ______________________________ .;.._ .. ____________ ~M~A~I~N~S~TE~A~M::.,;S~U~P~P~LY:.,. ______________ .., _____________________________ .......
u w z --" " < • w w r N
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STEAM /' DRAIN __,,,..
TEST
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TEST (F5V\ 1~-;a
w 1/2" . in
.., • ..:..:-1.-1--1_ ~ DRV-556 SHV-556 U
~-{]r FCV • 71-38
~
.........--PUMP TEST RETURN TO ..,,,..- CONDENSATE STORAGE
LOV-18
6"
. ~ co 71-20B,C--=-, 1 /2"
PT LL-J:)o::!--f 71 -20 ~ RTV-20
(PS' J/2"
• '
7 1 - 21 A)r-{)o::!;_-f 1 " ....._,. RTV-21 1---..
RELIEF VALVE SET O 150 PSIG RFV-19
---1: 2-47E852-2,B5
1 /2. 1 " VENT 1 " VTV-530 . 3/4" LOW POINT DRAIN
1 /2. • w
N
1 .. HPCI DRAIN ~ VTV-529
14---< 2-+7E812-1. G7 I f. Fg_\_ '-----'---' 71..:;.~1/2" TELL-TALE
_j TO CRW ~2-47E852-2,E5 ••
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TEST
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NOTE 15
SHV-553 DRV-554
-=-=1.5375" PR0-38
~ 7~ -37
6" . -
LOV-37
z -< ~ 0
r z -0 ~
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N N ~
' ;:; 0
~ 71-358 ~
PT 71-35 ~
.;-~ 0.375. PR0-547
PUMP MINIMUM ,,,;t FLOW BYPASS___,,,,.
/3/4" VENT m
V SPOOL PIECE SPPC-71-19 (NOTE 13)
11 /2" PRESS. .....-- 3/4" TEST
. N
1 " ... .... .. RTV-4
TURBINE TRIP
PT 71-4 ~
PI 71-4B ~
THROTTLE VALVE - ~
FCV 2
' 1-9
~ ~ 1/2" 8
TURBINE GOVERNING VALVE --lf--.j/.FCV~fl:f"r-)l~~------~-....;3:.,"+::l-t~-4-·--1
1 "
RTV-5H
(t.tOUNTED TO TURBINE CASING) 1/2" 7 \.::1E/ J;...ml ,._.;....-t~1-~~~~~~~~~-1-~--='--~
,...------------~~-----.. 112..: 0.185" ..Lo.185"~~~
PI 71-56 ~
PR0-9A,\-PR0-98 7 rs ::2
ABOVE AND BELOW SEAT DRAINS --..':::",f---J
1 "
2
, , • -
SHV-570
SHV-618
STEAM SUPPLY DRAIN POT CPOT-5
1 " RTV-5L
0 STEAM TRAP TRP-10 PISTON REMOVED
SHV-617 SHV-571
1 •
... ,__ _____ -J~---------'---[><_(]-----1..-.~1-.----~_(;·-l-~---r--i------. TEST
. N
' N z - 1 " ~ CKV-3-572
(LG\
X-98 -'
THIS DWG.C4
THERt.4AL SLEEVE
. .. N
\_REACTOR FEEDWATER LINE 8
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v
1 +f-+-[+8· I
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VENT TO -
~ TO ATM
< ~ 0
AUX BLR SYS 2-47E815-4,G6 >---
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7~B
1 .. _ I _
LS 1-5
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rTl\ 71-509
: r 7 -46 T ~ ...... 1-l"<J.! TW 1-1i2" TE
~:MJ~ -~-1 om=,=-~'": I 1" ~o "">-'---I •
- [VENT r o::. -RPD-11B -"' 0
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71-47 '-
·11-46 7!.._-~8 ..----------<THIS OWG.C4 I •
1/2" TEST_..
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" -[ PMP-19 RCIC PIM'
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'r- RPD-11 A ,_ _____________________ ..,....,. ________ ..... ...,, -' :+--..::-~-~~'· .. ~~·~":i;,,;· ....
L_~'~1~·r·''.::~~·~C:~·- ~ ~§~ - fu~iINE ~~ ~3140
TRB-9 ~ Q[: 71-507, 1/2" TW "ir'7-~l/~2:-" ~-1._·_·-"i:,..,.,.-~~"""i.f" 1 • ..__ 1 F 2 " TE
1 • VENT__},
,---1 /4"
PI TI 7t:_01 7~3
71-45" 3t4n OI ,.3i /R" I ..- 71-24 t"''._ . ....,..£>1..t L o ~/2"
TI 1 PUMP ..__.112 • ~
:!J!P~•1Pri4~5-'l~l.._-li(,i~f-:l ' 71.2..5 = ,- QI: ~ ~ N 0 DRV-45 Ct:.
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w
1 ..
-3 TW
71-23 ,_ • 3/4"
1 /2" GASKET TEST -
- . - 2" ' •
CKV-598 CKV-597
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~ (HcV\ ':( 7,,1_;.!.4 L£>V-141/2" 8'"- I
TEST
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1 O" . - TURBINE EXHAUST ' ' ~I) ::::. •
N .. CKV-580 TEST
SUMP I
3/4"
PS 7~4
~
1 /4"
... ,___ ____________________ .. _
- . ' CKV-600
- . ' CKV-599
TURB EXH VAC RELIEF_J
SHV -520 2"
RCIC LUBE OIL PIPING DIAGRAM (C4) FCV , 1/2", 71-~::r j ~
1/2" CAP --._ .. 1/4" -
• X-218---
r3" 1'4!.. ..... ,._....,,..-{)f11~'2 0TEST
SHV-602
-0 w
' ~
. N
TV-603 . N
• N
--r-STRAINERS
b SUPPRESSION POOL RING HDR 7
-' i".
X-221-._
X-212 • N
3/4" LOW POINT DRAIN
TEST .. 1120 (sHV\ SHV-551 DRV-552 -
2" 71-32 ::-.--
0. 625" .:..'::. PR0-551T
3/4" l<l---tc .......... ,.._-1 ~ L TV-610 SHV-609 w
J ' ' 1/2" TEST >
iii
18"
/X-210A
• N
< 2-47E852-2, B5 !--"'
14
18"
FROM RESIDUAL HEAT REMOVAL SYSTEM
...._2-47E811-1, E7
~PRIMARY CONTAINMENT
(sHV\ ~ 71-16 7.,.1-_!.7
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TEST
. '
CKV-592
I L~6 LOV-17 SUPPRESSION POOL SUCTION
• N
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{1" PRESSURE VALVE
CONTROL
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r-~
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~
~ '70 ' -"
71-22 ~
~· 1.{2" LOW POINT DRAIN 1--to .... --talll-----.
SHV-538 DRV-539
1 " .
N
' N
• N
~ -~ "' ~ " ~ ~
1 /2" PT )-,-{)XJ---f
71-12 RTV-12 ~
@ 71-12B ~
EXHAUST
• • . " ••
DRAIN POT--.... ·~
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• -TNK-642 ......... ,__,_ __ .....; ____ ~
STEAM TRAP TRP-9
1 •
PRESSURE RELIEF SET o 10 PSIG
2"
- ~RFV-27 .J_
-'
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' N
VALVE
-' TV-540 ~
m w ~ ..
z - (Pl)
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:i ' N RTV-27L 1 " 1 "
7Fo.416" PR0-540 ' N
0 r '~ .
71-27: ,;;- . ::!: v -· - - -•
TV-541
• N
v w i;1 < ~
ITHIS DWG,E7)>-----~ .. IB--J......1:::::=1'~::::::==:::::J~-~~-~ ........ -~
l_ BAROMETRIC
-' Go:J 7~~7
CONDENSER _ CND-27
~....'::::;i· t' ii' '.:"if'''::;'r'-@:::P::S::--. 2_5_0_" --'r'r:~~~M TANK ...... -
w -< I ,... 3/4" THIS DWG,E71-----~l"'"'"-f
LUBE OIL COOLER 16 GPM 140"F MAX CLR-25
11-28!-;=Q 5 ~
PRESSURE RELIEF VALVE SET o 75 PSIC RFV-543
""" H. 2-47EB52-2,85
2" 1 " .
w 0 z 8
--~I
-----' -(;;'\ .
N
1" (TYP 4)---
2"
LS ;-,----'
7.!_-:39 ~ MECH LINK
1/2" t--i::o:l--'---1t:xx:r--:!.PI
ISiv-_502 11 -..!02 RTV-502
SEE NOTE 9
;:; ,..,_ ..... __ _.__-r.l',11/2" \. ~~. f!~~
... PRESS.
... TEST TV-26
2-47E852-2,B5 >
~ 1-1/4'~~, l!) ~ SHV-26 DRV-26
2" . -
112" . RTV-27H
~ 71-3U"' ~ .
BYPASS ~ CONTROL "1 VALVE
'
• ::!:
6" .~1/4" 1/2" 6" ~-----~------"' .~---1,· --.... ~ ..... ------.... -w-----1 ..... J-.---------... CKV-589
CONT ON 2-47E814-1, B7
8 7 6
~ CKV-508 ' >
iJi
TEST
5
2"
1 /2 .. TEST - 3/4"
TV-591 SHV-590
x~ ~
< 2-47E852-2,B5
VACUUM PUMP DISCHARGE TO SUPPRESSION VESSEL
CALCULATION REFERENCES: MD00000712012000031: RCIC PUMP NPSHa AND SYSTEM HYDRAULICS
4 3
VACUUM PUMP 17 CFM PMP-31
COMPANION DRAWINGS: 1-,3-47EB13-1
N
• . N
' TEST
NOTES' 1. CRW DRAINS ARE CONNECTED TO REACTOR BUILDING EQUIPMENT DRAIN SUMP. 2. DRW DRAINS ARE CONNECTED TO REACTOR BUILDING FLOOR DRAIN SUMP . 3. ALL VALVES ARE THE SAME SIZE AS PIPING, UNLESS OTHERWISE NOTED. 4. ALL VALVE DRAINS AND VENTS ARE PIPED TO CRW. 5. UNIDS ON DRAWINGS ARE FOR REFERENCE ONLY AND ARE ABBREVIATED AS
SHOWN IN THE EXAMPLE TO MEET SPACE CONSTRAINTS. REFER TO MEL FOR COMPLETE UNIDS. ALL UNIDS ARE IN UNIT 2, SYS 71 UNLESS OTHERWISE NOTED. LEADING ZEROES SHOWN IN MEL AS PART OF THE UNID ARE NOT DEPICTED. FOR ADDITIONAL GUIDANCE, REFER TO NEDP-4 . EXAMPLE: MEL UNID
BFN-O-SHV-018-0502 BFN-2-PT-003-0204C
6. []] ETC, DENOTES DESIGN PRESSURE THIS DRAWING.
7. DELETED
DRAWING UNID SHV-502 PT-204C
AND TEMPERATURE AS GIVEN IN TABLE,
8. THE DESIGN PRESSURE AND TEMPERATURE OF ALL DRAIN AND VENT LINES THROUGH THE LAST ISOLATION VALVE SHALL BE THE SAME AS THE PROCESS LINE .
9. CONDENSATE PUMP AND VACUUM PUMP SUCTION LINES ARE INTERNAL TO TANK AND SHOWN ONLY FOR CLARITY.
10. HYDROTESTING OF THERMOWELLS AND FITTINGS SHALL BE PERFORMED IN SHOP AT 30 PSIG. SYSTEM LEAK TEST PER ANSI B31.10 POWER PIPING CODE.
11. FOR DESIGN PRESSURE AND DESIGN TEMPERATURE SEE TERRY STEAM TURBINE MANUAL, CONTROL# 0467 (CONTRACT# 90744).
12. VENT, DRAIN AND TEST CONNECTIONS 1-1/2" AND BELOW CAN BE PROVIDED WITH PIPE CAPS OR HOSE CONNECTION FITTINGS WHERE REQUIRED BY PLANT PERSONNEL. THIS CONFIGURATION IS SUPPORTED BY ENGINEERING CALCULATION CD-00999-923399.
13. SPOOL PIECE MAY BE REPLACED BY STRAINER DURING MAINTENANCE. THE SPOOL PIECE MUST BE INSTALLED PRIOR TO RETURNING THE SYSTEM TO SERVICE. SEE 0-47E456-1. -2 FOR STRAINER DETAIL.
14. ORIFICE COUPLING, SEE 0-471600-20, DETAIL P20. 15. VALVE 2-FCV-071-0039 WILL SEAL LEAK TIGHT ONLY IN THE DIRECTION OF
FEEDWATER TO RCIC SYSTEM DUE TO A PRESSURE LOCKING ~ODIFICATION WHICH DRILLED A 1/4" HOLE IN THE FEEDWATER SIDE FACE OF THE VALVE . (DCN T41301)
16. THE PIPING COMPONENT IDENTIFIED IS A LINE STOP FITTING WITH AN INTERNAL PLUG AND BLIND FLANGE. NORMAL CONFIGURATION DOES NOT ISOLATE FLOW AND FITTING, PLUG AND BLIND FLANGE ARE CONSIDERED PRESSURE RETAINING.
REFERENCE DRAWINGS: MEL ................... VALVE MARKER TAG TABULATION 2-47E456-408 .......... MECHANICAL-RCIC OIL PIPING INSTRUMENTS 2-47E852-1 ,-2 ......... FLOW DIAGRAM - DRAINAGE
INSTALLATION SECTIONS ANO DETAILS 0-47E820-1 ............ FLOW DIAGRAM - CONTROL ROD DRIVE 0-47E800-1 ............ FLOW DIAGRAM - GENERAL PLANT SYSTEMS 0-47E800-2 ............ MECHANICAL - SYMBOLS & FLOW DIAGRAM DRAWING INDEX 2-47E815-4 ............ FLOW DIAGRAM AUXILIARY BOILER SYSTEM 2-47E801-1 ............ FLOW DIAGRAM - MAIN STEAM 2-47E811-1 ............ FLOW DIAGRAM - RHR SYSTEM 2-47E812-1 ............ FLOW DIAGRAM - HPCI SYSTEM 0-47E815-1 ............ FLOW DIAGRAM - AUX BOILER SYSTEM 2-47E818-1 ............ FLOW DIAGRAM - CNDS STORAGE & SUPPLY SYSTEM MEL ................... INSTRUMENT TABULATION 2-47E610-71-1,2 ....... CONTROL DIAGRAM - RCIC SYSTEM 2-47E803-1 ............ FLOW DIAGRAM - REACTOR FEEDWATER 2-47E810-1 ............ FLOW DIAGRAM - REACTOR WATER CLEANUP 2-47E814-1 ............ FLOW DIAGRAM - CORE SPRAY
AMENDMENT 26
POWERHOUSE UNIT 2
BROWNS FERRY FINAL SAFETY
NUCLEAR PLANT ANALYSIS REPORT
REACTOR COOLING
CORE ISOLATION SYSTEM
FLOW DIAGRAM FIGURE 4.7-1a
H
G
F
E
D
c
B
A
tto~l-ll-Ol93Lt-Z V'l L9
r--1-1--1- --;-----;------- --1-1--1--1-- --1--r--1--1--- -1--1--;--1
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TO XM-69-29 ~ ------T------- -,----------- -----,-------- --- -------------- --- -, 1
:::::.-.------T-------.-,-----------1--------------.---1-, I I I I Q-47E610-69-1,G2 ~--.------T-------.-------------1--, I I I I I I
REACTOR WATER ' -@ 11 ~4: ~4: I -®: CLEANUP ' ~ 9-21 +- _J 2-45E779-12 I 9-21 9-21 ~ 9-21 ~ ~TE~ R ~ . TE TS TE TS (TE~ R
- 71-41A 1-41A I 71-418 1-41 71-41C 1-41 71-410 1-41 -- -- r--------, -- -- -- -- -- --
- - I ~s (HS\-' I - - ------~
•
8
THERMAL SLEEVE
t 71-2 7~A H 2-45E714-4 I [CiSS] I LOG I ILciGl [CiSS] 1 ,1 ,--a.J ~-' 1 o::::i _71-3 CL_
25-31 x
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MIMIC 71-28 ~3L- 71-JC I ..__, LOG I C!SS I ..__,
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I
L---
25-7A PDT
lt:l__)-l:XX:Kl>----, 71 -1 B
71-J 0
9-19 'If/ 9-19 9-3 @ !FM\ -- /Fl\ 25-7A 71-18 ~~
FT ------'t'---Y ..__, 71-18
r_J 25-7A 25-7A I PS PS
25-7A.)_!-82 9-81 25-7A 7YA lye cdNDENSING POT
FT ~ ~ PDT +----+--42-45E626-2 I 71-lA 71-18 71-1A 71-1A A5-7A,.....L.__ . .
9-3 v-;. 9-18 !Fr\ - v /"FM\ 'rf:";t-~t ..__, ..__, I
I T T (PS' ( PS,25-7A
71-1B 71-1D
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(HS) 71-58
~ 71-58
s
(HS) 71-57
A 71-57
s
CONDENSATE TO HPCI TEST LINE AND CNDS & DEMINERALIZED WATER STORAGE SYS
2-47E610-73-1 ,E5 r-----r-,----------, I I I I
II '@' '@) r-----J / ~ / ~ I I
I 6Ji::i9-3 * '# I I MCC 71-388 ~ /~ I I __);;-( y fHs\9-3
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71-38 -1- 71-38 R G
I I ' ' 12-45E714-6 f--J L _ _ffiS\
71-J8C ..__,
~-J LOG 1'f:3s'A A71033
25-31 y i (Pi(\"_ ...l ~ I ~- j__ ~~-47
L (PT \25-58 ~ 1 71-35 7J-54-1 J
I DISK 71n5 8 I POSITION
CRW y 9-3 /FA\ I 25-58 I u--;i,_ 25-58 : ~
(FIS):: ___ _.. (TE' 71-36 I 71-33
I (R1 ~ I /Y.:-~ w
9-3 25-58 (Pi\, PT
9-3 IPA\ ,... ""TI:2;i,
I ..__, 25-58 7T=2oA...,. 71-20_0-,~--1
..__, I ..__, t--...-.\ PS ,......i......_2s-J1 25-58 7!.3J B
( PX j Pl 71-20 71 -20B 25-58 I ...._........ ...._........ PS 4
71-21A -~--r- I ...._........ 9-3 PA I
1-21 A I ..__, I
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(Li\ 71-509
L
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THIS DWG, C6
d5-58 I el \ 71-4B
25-58 I ,_, PT j /pj\
71-4 - -~
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ZI-71 ~ ....__,,,9-3 ~ -1 0 "Cr'-----=-; r-3®: I mis owo. 01 >-, I _J;,( FROM XS-71-368 _J I rJSz ,_, 11 FC SC hff'--.J
71-10 71-10
THIS owe.cs ~ (;\_ ~-3
Loe 1 ..__, r-
..__,
71-42A~ -1-~A Rcic TURBINE A5156 I I RCIC PUMP
PMP-19 TRB-9 ~I~ T ~ IT"""-@Iill : I /~25-32 :
DRAIN POT CPOT-5
0
LS 71-5
STEAM TRAP TRP-71-10 PISTON REMOVED
I _J,9-3_JZI-71 t-----1--·~---------- ~25~C'J" iA7c.r-71 : x
"~5-425 I: @ 11-56/~:1 9-b ---, II TT
FE ,_~~~--~~..---~~~~ TW ;...~~~~..-~~~~~~~~• •-t--');,-1 ·:i--'Y.::L! 11-36 I 1-!5' CKV-71-40 -...J s-3JSCT - 9-3/~ ~25-5a I
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TO SC-71-10
r ~ I r G§:::\ I 71-36 I ~ FCV 71-39A I ~ FCV 71-l7A I y ~5-311 =i-----1 ~ 7~~ 'f *1 ,®._ 7~~ 'f *1 l-?1~~s1 I r- FCV I MCC ~u9'1 ~ MCC ~u1'1 ~ : ..__, : :®: 7-Yr4 '<R(cq:
(HS\ (Hs\ +---1::IB] (HS' (Hs\ I I I •cc l~~J.:+ 71-398 11-39c I ~ 71-378 71-37C 1 I ~ I I~
'rG{'---"~ ..__, *1 (G)'---"¥ ..__, :@8_J t-~ ~ - - -.1.- _ __(HS\ ''t:_..::'C----:t r1- ___ 1 fxs\_ 1c:f"
SEE NOTE TW ..__, Wll .1.1 c_TR_j _J 4
TS I TE 71-46 TE s 73-54-11 L-71 48 -1- 71 4 "'-"" 71-47 TO RCIC ...._........ I J .._:..- 1 - r 1 I ' TURBINE oIL PUMP 1 r
I I 71 - 46 THIS DWG, C5 $ I
~ : _t}Js41 r ;;:,8-1 L~c I-~Px 2-;:_;;--•: s 6 5-32 :I
~-1-73~-12 II I"'' (PX\ I 71-12B A5152 71-12 I ZI-71-6At--12-45E626-41 I
' ,.. ~ << ~
' 0
1----_J I _25-58 I l-®9 _31 J;,< I I ,--+---, ~ _J__/pT\__ 4 ___ j_ PI 1 r~,@-3 I ~5-58@' ~5-58 71-12 1-12A I I HS 'cf -t
( PS'\ PA ( PS\ ! ...._........ !;=- VENTS .....__,,, I +.-i'V 71-6 /~i':'7T-68 ~ 25-31 ~ tf!C\9-3 +s 25-31 ! r 71x_s,4 1
r-r-i1~~6~----------~------{,~~~ 5 I ...._........ I 1 (THIS DWG, F3
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I y ..__, SEE NOTE 10 _/Y ~ ~-3 ,l__ I ~ J I I ~ HS (Hs'\ 1 ~- I I 1-34A 71-34C I
L ____ fi[C\_ _____________ _J R ,c, 'lR1 'rGl I I 25-32 I ~~ ..__, , ,
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y FC _ !- __(HS\ 11-59 I 1~s
SEE NOTE 11
TW 71-23
0r'\ 7 1 - 23 TE )--.H'-t---,! P I ...._........ 71-24 71-501
25-425~ 9-47 ( TS \..// TR 1y 4 73-54-10
1~2--4-5-E 6-2-6--,~~ -; :
25-31.,...l.._ LOG 'r.< ___ J xs\ A11024 /\..!Y; 71-24 25-32 ~ XI-71-24 ~-J _
TA : 71-2 I-.._, 0
z
71-13B 7~ 71-13A - -- 25-58 25-581 : / ~ }Et----_J 11~~1A 11~~18 II L _______________ _J
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-T 11-25 I y y 9-3 +----+--.! (PA\ I ..__, I 11 11
,...l.....25-58 ~5-58 ...._........ 111 ~ (PS\ (PS\ c-.i
MCCj_ GI Y.;1~-, '''1 "T°'' L ..(HS\ I
I FCV 71-258 I I lllt;) (PI\ 71-27 71-11C 71-11D .l,
~~71~~02 ~(Ti\ ~
11T!26 11 7J7~--------!---~ ..__, {pi\\ -
9-J'7'i":"28 1-.-.;.-1 ~
L 11-25 ..__,~..! I
=-.:r-- - -'-4_J
LUBE -..,.-_,,,,.__ __ -I OIL
COOLER CLR-25
y 1-<*-I BARCMETRIC 71-30 CONDENSER CND-27
PS I I 11-28;--;-;-, L--~--J---Ci'x::Jf-, ..__,
w ~ 4%-3 ~ ~ LS ~ ~ FROM RCIC TURBINE ;::::: - 71-29 =i OIL PUMP LL. .....__,,, :;-,--'
: ~ THIS OWG, E3 FG l2-45E714-6 H LI o 11~1 -:@),~
; ~ {G)'HS''<R( '(G1 ~~3 R G HS R,:
VACUUM -TANK -
TNK-27
'l}1~~9rr' '111_,., 71-29• 1, l_'{J_J_r_L.:=:@s \ ~~B~ ~ ~ !
LOGIC B 9-3 9 _ 3 ;.ESE!_~
/XS\ . RCIC~UTO_!SOLATIO~-l___)A< ~ ~LOGIC A RESET --;c,z
...._........ LJ..\<IL-71-51A Il-71-518 9-3 A
fXS\ RCIC INITIATION '7T::521sEAL~N i"""RESET-
...__.... :@:Il-71-52
S-J RCIC /HS\ AUTO INITIATION ~ MANUAL ISOLATION ..__,
,,,-.__ 25-32
( " ' 71-498
11 - 29 --Y-1--.!PMP-29 I ~ - (HS\I:;; 9-3 t.tCC '®- _........ \ 71-31 B i r
Zl-71-32~ (sHV\ / ' (!) ...---.~----.., i I"" :ct MC~--~ :@:
TI SEE NOTE 11
(ZS\_TJ!.R!!~.!.R.!f'~D--~5~1 fli:\9-3 71-49 71-24 ~A
I '-j 2-<5E11•-12 I
71-32 -~ (!) ;..-_.
r-~~~~~~~~--£~~~~~-\/"1---~,---;-~~~~~~~~~~~~~---.-i___/ l'-3V:M
x x
-:::r--, VACUUM A - r@9,-3 PUMP (xs\_ __ PMP-31 71-31
y I ..__,
..__, ..__, ..__, 25-32 SEE NOTE 11 XI-71-44
TURBINE BRG OIL 1... 11-44 PREssuRE Tow---- --
-@9-3
..__, ..__,
~ 9-J I~ 1~5 ~I
I I I I I I I I
1-_J I
25-32 s
5
---==! ==--- L~~ DQ 9-3 :@ti I 00_ 9-YHS\ I (A} 25-32 (A)" 25-J2
~~I-7~~---::)°'' XI-71-48 - I
I ~·l 12-45E714-5 ~l l~1'8A I --._r---.1 I I I ~
FCV 71-7A
I I
J-_
FCV 71-78 ~I:®: 25-425 ~25-31
ECCS-ANALOG TRIP POWER
12-47E61D-71-2,F5 >-~-{TI)(j) I I _fxS\_ -1- _fXs\_ I 1 j\z.2.;.11--r- -r--\?_!_;.1•i 1
8* I r~ : : :@(--, I ~ CRW
(HS'\ 71-J1C ..__,
(TS"LHP BRG OIL J XS L GA\ 9-J 71-47 TE.ieHTGH"-r 71-47 -r- 11-47 k ..__, ..__,
11 I I -425 I I
SEE NOTE
, I !HS\_ J I (HS\_ ___tHs\ I L _IHs\ I -::.I 1 \z2_:;.17c I \z2_:;.17B \z.2_;.1'80 I ~1'8c I
~ ~~ FC FC ~_j *-1 L-~-,-;-_;;=;-,;--i 11-1 11-18 : I
6 {Rf9_3 L- -, I I __ J' L- --+---~-----_j
12-47E610-71-2.F4>-~-{TI)@
7 6 5 4 3
,,-.__TA 9-3 P_BRG_QI_C__J L_ I !A' 71-48 TEIAP HIGH _.,,_7°""1-"+""8 ..__, ..__,
COMPANION DRAWINGS: 1-47E610-71-1 3-47E610-71-1 2-47E610-71-2
NOTES:
1. THE REACTOR CORE ISOLATION COOLING SYSTEM IS DESIGNED TO COOL THE CORE WHEN THE REACTOR VESSEL IS ISOLATED AND REACTOR FEEDWATER IS UNAVAILABLE. WHEN THE WATER LEVEL IN THE REACTOR VESSEL REACHES SETPOINT, THE RCIC SYSTEM IS AUTOMATICALLY STARTED BY ACTIVATION OF REACTOR LEVEL SWITCHES LIS-3-58A, LIS-3-58B, LIS-3-58C ANO LIS-3-580 (2-47E610-3-1), ARRANGED IN ONE-OUT-OF-TWO-TWICE LOGIC TO OPEN VALVE FCV-71-8. THE SAME SIGNAL CLOSES DRAIN LINE VALVES FCV-71-SA AND FCV-71-6B.
2. A MECHANICAL SPEED GOVERNOR PREVENTS TURBINE OVERSPEED BY TRIPPING THROTTLE TRIP VALVE FCV-71-9 WHEN A TURBINE OVERSPEED OCCURS. A CONTROL GOVERNOR, FIC-71-J6, EQUIPPED WITH AUTOMATIC AND MANUAL MEANS FOR SPEED SET POINT CONTROL REGULATES TURBINE SPEED VIA "TURBINE SPEED CHANGER" TO CONTROL RCIC MAIN PUMP DISCHARGE FLOW.
3A. A RCIC STANDBY td:JDE SIGNAL SHALL BE INITIATED AT REACTOR VESSEL WATER LEVEL 8 (HIGH LEVEL). THE REACTOR VESSEL WATER LEVEL 8 SIGNAL SHALL BE INITIATED BY TWO LEVEL SWITCHES ARRANGED IN A TWO-OUT-OF-TWO LOGIC CONFIGURATION. THE REACTOR VESSEL WATER LEVEL 8 SIGNAL SHALL: (A) CLOSE THE STEAM ADMISSION VALVE FCV-71-8 AND (B) CLOSE THE MINI-FLOW ISOLATION VALVE FCV-71-34. IN THE EVENT AN INITIATION SIGNAL IS RECEIVED AFTER THE SYSTEM HAS BEEN SHUTDOWN ON HIGH RV LEVEL, THE SYSTEM SHALL BE CAPABLE Of AUTOMATIC RESTART.
3B. THE RCIC TURBINE TRIP VALVE IS TRIPPED BY: A. TURBINE OVERSPEED VIA THE SPEED GOVERNOR.
C. LOW RCIC PUMP SUCTION PRESSURE SENSED BY PS-71-21.
D. HIGH RCIC TURBINE EXHAUST PRESSURE SENSED BY EITHER PS-71-1JA OR PS-71-13B.
E. MANUALLY FROM THE MAIN CONTROL ROOM BY HS-71-9A OR BY HS-71-9C ON PANEL 25-J2.
A TURBINE TRIP,
A. CLOSES FCV-71-9. B. CLOSES FCV-71-J4. C. ANNUNCIATES ON ZA-71-49A OR 49B. D. ACTIVATES THE ALARM ASSOCIATED WITH THE CONDITION INITIATING
THE TRIP.
4. THE TURBINE CASING IS PROTECTED FROM OVERPRESSURE BY TWO RUPTURE DISCS. PS-71-11A THRU D DETECTS DISC RUPTURES AND ANNUNCIATES ON PA-71-11 IN THE MAIN CONTROL ROOM. PROVIDES 1 OUT OF 2 TWICE LOGIC TO INITIATE AUTO ISOLATION OF TURBINE (SEE NOTE 5).
5. THE RCIC TURBINE WILL BE AUTOMATICALLY ISOLATED FROM THE STEAM SUPPLY BY CLOSING ISOLATION VALVES FCV-71-2 AND FCV-71-3 IF: A. A HIGH PRESSURE DROP OCCURS ACROSS THE RCIC ELBOW TYPE FLOW
ELEMENT FE-73-1A & 18 WHEN THE STEAM LINE RUPTURES. THE HIGH FLOW IS SENSED BY EITHER PDT-71-1A OR PDT-71-1B AND ANNUNCIATED ON PDA-71-1 .
B. HIGH AREA TEMPERATURES INDICATING A STEAM LINE BREAK ARE DETECTED BY ANY OF FOUR SETS OF TEMPERATURE SWITCHES CTS-71-2A THROUGH TS-71-2S EACH SET CONNECTED IN ONE-OUT-OF-TWO-TWICE LOGIC. FOUR INDEPENDENT TEMPERATURE SENSING ELEMENTS AND ASSOCIATED TEMPTERATURE SWITCHES TE-71-41A AND TS-71-41A THROUGH TE-71-41D AND TS-71-41D SET AT 175" F ACTIVATE THE MAIN CONTROL ROOM ANNUNCIATOR TA-71-41.
C. LOW REACTOR PRESSURE IS DETECTED BY PS-71-1A THROUGH PS-71-1D ARRANGED IN ONE-OUT-OF-TWO-TWICE LOGIC.
D. HIGH PRESSURE BETWEEN THE TURBINE EXHAUST RUPTURE DISCS (SEE NOTE 4).
6. NORMALLY MAKEUP WATER FOR THE RCIC PUMP SUCTION IS SUPPLIED BY THE CONDENSATE STORAGE TANK THROUGH FLOW CONTROL VALVE FCV-71-19. AN ALTERNATE SOURCE OF WATER IS OBTAINED FROM THE SUPPRESSION POOL THROUGH ISOLATION VALVES FCV-71-17 AND FCV-71-18. PUMP DISCHARGE FLOW ROUTES ARE AS FOLLOWS:
A. NORMALLY VIA THE FEEDWATER LINE TO THE REACTOR THROUGH ISOLATION VALVES FCV-71-37, FCV-71-39, AND CHECK VALVE FCV-71-40.
B. DURING TESTING VIA TEST LINE TO CONDENSATE STORAGE THROUGH FLOW CONTROL VALVE FCV-71-38.
C. MINIMUM FLOW BYPASS TO THE SUPRESSION POOL THROUGH FLOW CONTROL VALVE FCV-71-34.
7. IF RCIC SYSTEM OPERATION IS REQUIRED WHEN IT IS IN THE TEST MOOE, THE CONTROL SYSTEM IS DESIGNED TO AUTOMATICALLY RETURN THE SYSTEM TO THE OPERATING MODE.
8. COOLING WATER FOR THE PUMP, TURBINE, AND LUBE OIL COOLER IS SUPPLIED FROM THE PUMP DISCHARGE LINE THROUGH PRESSURE CONTROL VALVE PCV-71-22 SET AT 75 PSIA.
9. TRANSFER AND CONTROL SWITCHES ASSOCIATED WITH BACKUP CONTROL WILL BE ON THE DESIGNATED PANELS OR LOCATED ON THE APPROPRIATE 250V DC M:JV BOARDS.
10. XS-71-36B IS SHOWN TWICE TO SHOW HOW THIS TRANSFER SWITCH DISCONNECTS FIC-71-36A AND CONNECTS FIC-71-36B LOCATED AT THE BACKUP CONTROL CENTER.
11. XS-71-24, PS-71-44, TS-71-47 & TS-71-48 ARE SHOWN TWICE TO SHOW HOW THESE SWITCHES TRANSFER INDICATION FROM THE MAIN CONTROL PANEL 9-J TO THE BACKUP CONTROL PANEL 25-J2.
12. UNIDS ON DRAWINGS ARE FOR REFERENCE ONLY AND ARE ABBREVIATED AS SHOWN IN THE EXAMPLE TO MEET SPACE CONSTRAINTS. REFER TO MEL FOR COMPLETE UNIDS. All UNIDS ARE IN UNIT 2 SYSTEM 71, UNLESS OTHERWISE NOTED. LEADING ZEROES SHOWN IN MEL AS PART OF THE UNID ARE NOT DEPICTED. FOR ADDITIONAL GUIDANCE, REFER TO NEDP-4. EXAMPLE: MEL UNID DRAWING UNID
BFN-O-SHV-018-0502 SHV-18-502 BFN-1-HS-031-0160A HS-31-160A BFN-2-PT -003-0204C PT -3-204C
13. CCMPLETE LOGIC FOR REACTOR CORE ISOLATION SYSTEM IS SHOWN ON MECHANICAL LOGIC DIAGRAM LISTED IN REFERENCE DRAWINGS.
REFERENCE DRAWINGS: 0-47E800-1 .................. FLOW DIAGRAM-GENERAL PLANT SYSTEMS 0-47E800-2 .................. MECHANICAL SYMBOLS AND FLOW DIAG DWG INDEX 2-47E2847-5 ................. FLOW DIAGRAM-CONTROL AIR SUPPLY 2-47E813-1 .................. FLOW DIAGRAM-RCIC 2-47E610-73-1 ............... CONTROL DIAGRAM-HPCI 2-47E610-3-1 ................ CONTROL DIAGRAM-REACTOR FEEDWATER 2-47E610-1-1 ................ CONTROL DIAGRAM-MAIN STEAM 2-47E610-69-1 ............... CONTROL DIAGRAM-REACTOR WATER CLEANUP 0-47E610-2-2 ................ CONTROL DIAGRAM-CONDENSATE SYSTEM 0-47E610-12-1 ............... CONTROL DIAGRAM-AUXILIARY BOILER SYSTEM 0-47E456-1,-2 ............... RCIC SYSTEM MECHANICAL DRAWINGS 0-47W456-3,-4 ............... RCIC SYSTEM MECHANICAL DRAWINGS MEL ......................... INSTRUMENT TABULATIONS FOR SYSTEM 71 2-45E670-SERIES ............. WIRING DIAGRAM-ECCS 2-45E626-1 ,-2,-3,-4 ......... WIRING DIAG REACTOR CORE ISOLATION COOLING 2-45W670-21 ................. WIRING DIAG EMERG CORE COOLING SYS DIV I 2-45E714-5.-6 ............... WIRING DIA 250V REAC MOV BO 2C 2-45E779-5,-12 .............. WIRING DIAGRAM 480V SHUTDOWN AUX POWER SCH DIA 2-47E611-64-SERIES .......... MECHANICAL LOGIC DIAGRAM PRIMARY CONTAINMENT
ISOLATION SYSTEM 2-47E611-71-SERIES .......... MECHANICAL LOGIC DIAGRAM REACTOR CORE ISOLATION
COOLING SYSTEM GE DRAWINGS:
729E652-1 .............. FUNCTIONAL CONTROL DIAGRAMS-RCIC 2-729E652-4 ............. FUNCTIONAL CONTROL DIAGRAMS-RCIC
TERRY TURBINE CO.: C-883-X ............... RCIC TURBINE GOVERNOR CONTROL SYSTEM
NASH ENGR CO. : D-14-1365 ............. RCIC BAROMETRIC CONDENSER
SYMBOLS:
~ QUICK DISCONNECT WITH SINGLE END SHUTOFF
~ QUICK DISCONNECT
AMENDMENT POWERHOUSE UNIT 2
26
BROWNS FERRY FINAL SAFETY
NUCLEAR PLANT ANALYSIS REPORT
REACTOR CORE ISOLATION COOLING SYSTEM
MECHANICAL CONTROL DIAGRAM FIGURE 4.7-1b
H
G
F
E
D
c
B
A
' ii
8 7 6 5
AMENDMENT 27 I'OIEIIIHOUSE LINtTJ
BROWNS fERRY NUCLEAR PLANT F INAL SAFETY ANALYSIS REPORT
H
8
REACt~Lj~SEs~~~QTIOH A FLOW DIAGRAM
FIGURE 4.7-lc
~to!! l- lL-O l93Lt-£ It-I L9
~-3 r---r--1---,.-
~~~~ 71-2A 71-28 71-2C 71-20
-,----,-------I L-j 0-45ES2S-1 I I I
--,...-1--"t--t---
~ ~~~ 71-2E 71-2F 71-2G 71-2H
--t--,---,--t---~ ~~~ 71-2J 71-2K 71-2L 71-2M - - - -L __ -----~------- +-=r_-------- ----t--------
To XM-69-29 / ======I======= r-~-------------. --------<3-47E610-69-11(E:::-:------1--------r 1 =-+-========r-~------------
REACTOR WATER ' I L _J .....l... 4P.: CLEANUP ' ..fTE'L. ~9-21 I --,3-45N3654-1 (TE\_ TS 9-21
LOCi LOG - 71-41A ~A l 71-418 1-41 71-2 0 71-2 CL -- ...._.., r-------1 ....._ --
--------------' I
' -, I ' I ,-1-..4:-21 (TE\_ TS 71-41C 1-41
'----' .___, 1 I ~~~~~~
CISS A
CISS A 1 ----------4 t-------------, r----13-45E11•-5
*-*-i~--,- **-----11 3-45E779-121 r---- *i--1--i~-~:e;-*-1-1 .i'1ic fHs\ 9 c 3 ~ __/Hs\ I : @-3 4 _fHs\ .ii.ire 11 11
~_J7~71~ tdCC MCC 70A ~\.... 7~C I I
~ * I 11L~30 o I 1c18ss1 J L 1cr;s1 L
-.,---,...--.,.--1 ~~~~ 71-2N 71-2P 71-2R 71-25 - - - -------,
.., I ' I I ' I ~~-21 (TE\_ TS 71-410 1-41
'----' .___,
FROM AUXILIARY BOILER SYSTEM
0-47E610-12-1 ,03 ~.~5-31 25-58 25-58 I I 9-3
(Pl\ PT I ... IP!\ 71-48 71-4 t"" -~
I '----' L - - --jr-3--4-5_E6_2_6_-3..,
fit:~ !~9-3
NOTES: 1. THE REACTOR CORE ISOLATION COOLING SYSTEM IS DESIGNED TO
COOL THE CORE WHEN THE REACTOR VESSEL IS ISOLATED AND REACTOR FEEDWATER IS UNAVAILABLE. WHEN THE WATER LEVEL IN THE REACTOR VESSEL REACHES 31 .5" BELOW REACTOR FEEDWATER ZERO. THE RCIC SYSTEM IS AUTOMATICALLY STARTED BY ACTIVATION OF REACTOR LEVEL SWITCHES LIS-3-58A. LIS-3-58B, LIS-3-58C, AND LIS-3-58D (SEE 3-47E610-3-1), ARRANGED IN ONE-OUT-OF-TWO-TWICE LOGIC TO OPEN VALVE FCV-71-8. THE SAME SIGNAL CLOSES DRAIN LINE VALVES FCV-71-6A AND FCV-71-SB.
2.
3A.
A MECHANICAL SPEED GOVERNOR PREVENTS TURBINE OVERSPEED BY TRIPPING THROTTLE TRIP VALVE FCV-71-9 WHEN A TURBINE OVERSPEED OCCURS. A CONTROL GOVERNOR, FIC-71-36, EQUIPPED WITH AUTOMATIC AND MANUAL MEANS FOR SPEED SET POINT CONTROL REGULATES TURBINE SPEED VIA "TURBINE SPEED CHANGER" TO CONTROL RCIC MAIN PUMP DISCHARGE FLOW. A RCIC STANDBY MODE SIGNAL SHALL BE INITIATED AT REACTOR VESSEL WATER LEVEL 8 (HIGH LEVEL). THE REACTOR VESSEL WATER LEVEL 8 SIGNAL SHALL BE INITIATED BY TWO LEVEL SWITCHES ARRANGED IN A TWO-OUT-OF-TWO LOGIC CONFIGURATION. THE REACTOR VESSEL WATER LEVEL 8 SIGNAL SHALL: (A) CLOSE THE STEAM ADMISSION VALVE FCV-71-8 AND (B) CLOSE THE MINI FLOW ISOLATION VALVE FCV-71-34. IN THE EVENT AN INITIATION SIGNAL IS RECEIVED AFTER THE SYSTEM HAS BEEN SHUTDOWN ON HIGH RV LEVEL, THE SYSTEM SHALL BE CAPABLE OF AUTOMATIC RESTART.
3B. THE RCIC TURBINE TRIP VALVE IS TRIPPED BY:
4.
A. 8. c. D.
E.
TURBINE OVERSPEED VIA THE SPEED GOVERNOR. DELETED. LOW RCIC PUMP SUCTION PRESSURE SENSED BY PS-71-21A. HIGH RCIC TURBINE EXHAUST PRESSURE SENSED BY EITHER PS-71-13A OR PS-71-13B. MANUALLY FROM THE MAIN CONTROL ROOM BY HS-71-9A OR BY HS-71-9C ON PANEL 25-32.
A TURBINE TRIP: A. CLOSES FCV-71-9. 8. CLOSES FCV-71-34. C. ANNUNCIATES ON ZA-71-49A OR 49B. D. ACTIVATES THE ALARM ASSOCIATED WITH
INITIATING THE TRIP. THE CONDITION
THE TURBINE CASING IS PROTECTED FROM OVERPRESSURE BY TWO RUPTURE DISCS. PS-71-11A THRU D SET AT 10 PSIG DETECTS DISC
1-------------------------------------------r-~-1-,
.- .... --•-•-----•------, r=--..25 32 l~<I I .-1,---------------. r -13-45'626-3
: I 9-3 : ~5-32
I~ 5.
RUPTURES AND ANNUNCIATES ON PA-71-11 IN THE MAIN CONTROL ROOM. THE RCIC TURBINE WILL BE AUTOMATICALLY ISOLATED FROM THE STEAM SUPPLY BY CLOSING ISOLATION VALVES FCV-71-2 AND FCV-71-3 IF: I
25-7A
FT 71-18 ------,---,
I I @-19~-19 9-3
FM FI 71-1 --@
y
'----' '----' '----'
, 1 , ' • • .... --j3-45E714-5 I 1 Hs 1 - 1:::'1' I 1 1 r--------;r...,---, : : +>If '®' * I FROM CNDS ~ DEMINERALIZED 7~c '®' '{< I I I [J][J__J/ I I
~ ~ r:::--.. /~' 9-3 II WATER STORAGE SYS A5-32 /-@' ~ 3 I ~ I I G r HS \.._.J xs '- HS 0-47Es10-2-2.c4 ( xsL HS - I I ll-S '@' ~
71-19C 71-19 1-19A I 71-9A .... 71-9 I I L~MCC / '/~ {HS\_ __ ':" ___ .:r __ ':"_ jrToG-l'---' I '--t------0s I 11-190 3-45E626-2 ~ I I *---=..-i __ _,I '----' r------t----- rt '>RL J o-45E626-+ r- "'1 I I
~ I 0-45E626-1 f..l xx 11 ~ 3-45E714-5 I R G I MCC I 3-45E714-6 f-.... 71-9 11 I . . ("j:jS\9-3 ,.... ....
3-45E626-3 I--, 9-3 I
@A : 25-31 'f----_J LfXi_ LOG
~--+ A71033 r_. ~· 9-47 [1Q[J_j .,.l..._ TR ~(PT) 7 -54-13
71-35 y
11 3-45E626-3 1: @t--r 1-9 ,, I ~--~ ~ :©:: rl I d-3 : 0-45E626-1 HTRIP LINKAGE L_...:~:: __ -~ _fHs\
3-45E626-3 I r-t;-::ill I I f--i 0-45E626-4 I ~ \...- 7~c ~-3 I 25- 58 L_ .... 25':;; I ®9-3 A 'A9-3 FROM XS-71-368 71=2ot PT _1-,---1 I .I XS \25-32 I ~ -@ .___,A 1 100 t--..-i Ps 1 11-9e 1 c zr-11-10 r 08 25 _32
7..!_=3-18 ...._.... y ' 25-672 ~ ~x2 25-31 25-58 25-58 I 25 32 I THIS SM SI (PX'\ Pl PS 1 /::X~- DWG,CS 71-10 l-42 71-20 71-208 71-21A ......... -, '11H_::>9J--_J ~ ..., y ...._.... I '----' .___, .___, I ~-3 I .___, ~ .:, I ~OG 9-31
I 3-45Es2s-2 ~- ___ _J ~A t---l J-45Es20-2 6~A~cs ~ I A6156 fsl\ : - . - . ::l 65 672 ®7:j
RCIC PUMP PMP-19
II LG ! _1 ___ _J
JB 10035 I 'f''-
RCIC TURBINE TRB-9
F'---~ SE I 71-10A 71-42A_L ,
DRAIN POT CPOT-5
3-47E3847-5,F6
I - -111-o--<-5E-s2-s--1--,
I I 3-45E626-3. -4
I I I I
I I I I I _J r
s I I=='
STEAt.4 TRAP TRP-10 PISTON REMOVED
.3-45E626-3, -4
6.
A. A HIGH PRESSURE DROP OCCURS ACROSS THE RCIC ELBOW TYPE FLOW ELEMENT FE-71-1A & 1B WHEN THE STEAM LINE RUPTURES. THE HIGH FLOW IS SENSED BY EITHER PD1S-71-1A OR PD1S-71-1B AND ANNUNCIATED ON PDA-71-1.
B. HIGH AREA TEMPERATURES INDICATING A STEAM LINE BREAK ARE DETECTED BY ANY OF FOUR SETS OF TEMPERATURE SWITCHES (TS-71-2A THROUGH TS-71-2S SET AT 194°F). EACH SET CONNECTED IN ONE-OUT-OF-TWO-TWICE LOGIC. FOUR INDEPENDENT TEMPERATURE SENSING ELEMENTS AND ASSOCIATED TEMPERATURE SWITCHES TE-71-41A AND TS-71-41A THROUGH TE-71-41D AND TS-71-41D SET AT 175 F ACTIVATE THE MAIN CONTROL ROOM ANNUNCIATOR TA-71-41.
C. LOW REACTOR PRESSURE IS DETECTED BY PS-71-1A THROUGH PS-71-lD EACH SET AT 50 PSIG ANO ARRANGED IN ONE-OUT-OF-TWO-TWICE LOGIC.
NORMALLY MAKEUP WATER FOR THE RCIC PUMP SUCTION IS SUPPLIED BY THE CONDENSATE STORAGE TANK THROUGH FLOW CONTROL VALVE FCV-71-19. AN ALTERNATE SOURCE OF WATER IS OBTAINED FRCJ.l THE SUPPRESSION POOL THROUGH ISOLATION VALVES FCV-71-17 AND FCV-71-18. PUMP DISCHARGE FLOW ROUTES ARE AS FOLLOWS: A. NORMALLY VIA THE FEEDWATER LINE TO THE REACTOR
THROUGH ISOLATION VALVES FCV-71-37, FCV-71-39, AND CHECK VALVE FCV-71-40 .
B. DURING TESTING VIA TEST LINE TO CONDENSATE STORAGE THROUGH FLOW CONTROL VALVE FCV-71-38.
C. MINIMUM FLOW BYPASS TO THE SUPPRESSION POOL THROUGH FLOW CONTROL VALVE FCV-71-34.
7. IF RCIC SYSTEM OPERATION IS REQUIRED WHEN IT IS IN THE TEST MODE, THE CONTROL SYSTEM IS DESIGNED TO AUTOMATICALLY RETURN THE SYSTEM TO THE OPERATING MODE.
8. CCXJLING WATER FOR THE PUMP, TURBINE, AND LUBE OIL COOLER IS SUPPLIED FRCJ.l THE PUMP DISCHARGE LINE THROUGH PRESSURE CONTROL VALVE PCV-71-22 SET AT 75 PSIA.
9. TRANSFER AND CONTROL SWITCHES ASSOCIATED WITH BACKUP CONTROL WILL BE ON THE DESIGNATED PANELS OR LOCATED ON THE APPROPRIATE 250V DC MOV BOARDS.
10. XS-71-368 IS SHOWN THREE TIMES TO SHOW HOW THIS TRANSFER SWITCH DISCONNECTS FIC-71-36A AND CONNECTS FIC-71-36B LOCATED AT THE BACKUP CONTROL CENTER.
~3_-_•5_E_6_2_6-_3~~ -~-3 25-58 1 I ~ 25-58 R, I
CRW~ >-<._2s-sa PI ,_ _ _, I {FIS'---- l 71-358 TE
(IT\ SEE NOTE 11 71-48
Y (x•\"5-672
I 11-10 ly I
11. XS-71-23, XS-71-45, TS-71-45 & -46, XS-71-24 AND PS-71-44 ARE EACH SHOWN TWICE TO SHOW HOW THESE SWITCHES TRANSFER INDICATION FROM THE MAIN CONTROL PANEL 9-3 TO THE BACKUP CONTROL PANEL 25-32.
12. UNIDS ON DRAWINGS ARE FOR REFERENCE ONLY AND ARE ABBREVIATED AS SHOWN IN THE EXAMPLE TO MEET SPACE CONSTRAINTS. REFER TO MEL FOR COMPLETE UNIDS. ALL UNIDS ARE IN UNIT 3 UNLESS OTHERWISE NOTED. LEADING ZEROES SHOWN IN MEL AS PART OF I
L---------CKV-71-40
4 71F-E36 i .....__, 71T-W33 t-- r----t- 11-36 I 11-33~-----...--------
11 (Pl\
rt- __,.__,.., I T , _,-~-, ?-<.25-58 I '----' I 1,1-~5 I I >!< FCV I I I I I >!< FCV I I I I FT ' -
I I >!!Z 71-39* '#I I I~' 1-!.;J1w ~I 7~6 r:X5-31 r I ___ -.., SEE N0~~-;~511's. I I .cc I~ /~'I MCC I /~"")El.. I ...: PX\ I ........ ...,-..,, I -
I I {;;;;\9 - 3 1 : I 19-3f"ii5\ +- 7~A I I FCV J.,, I I I I l w I ~A I w w I ~A I I 71 - 34 ~..,J.; ..,J.;I t---t .. - PRESS. TEST I /~ /\Q : x II /~ /~ : x ~_J l T MCC >!!Z )9)_11 I
_______ J
~ 25-31 1 ~~ NOTE 11 , fri\ (x's\_ ¥-~
TS TW 71-56 71-368 71-45 71-45 ...._.... 'J-"
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3
~-- A XI-71-46 I / L------1 0-45E626-4
THE UNID ARE NOT DEPICTED. FOR ADDITIONAL GUIDANCE, REFER TO NEDP-4. EXAMPLE: MEL UNID DRAWING UNID
BFN-0-SHV-018-0502 SHV-18-502 BFN-1-HS-031-0160A HS-31-160A BFN-2-PT-003-0204C PT-3-204C
13. FLEX HosEf ll'lJ'I~ TO BE INSTALLED FOR TESTING PURPOSES ONLY. REFERENCE DRAWiNGS: MEL .......................... INSTRUMENT TABULATIONS 3-47E610-1-1A ................ CONTROL DIAGRAM-MAIN SYSTEM 0-47E610-2-2 ................. CONTROL DIAGRAM-CONDENSATE SYSTEM 3-47E610-3-1 ................. CONTROL DIAGRAM-REACTOR FEEDWATER 3-47E610-69-1 ................ CONTROL DIAGRAM-REACTOR WATER CLEANUP 2-47E611-71-4 ................ LOGIC DIAGRAM-RCIC 0-47E800-1 ................... FLOW DIAGRAM-GENERAL PLANT SYSTEM 0-47E800-2 ................... MECHANICAL SYMBOLS~ FLOW DIAGRAM
INDEX 3-47E610-73-1 ................ HPCI SYSTEM 3-47E813-1 ................... FLOW DIAGRAM-RCIC SYSTEM 3-45E779-12 .................. WIRING DIAGRAM-480V SHUTDOWN
AUXILIARY POWER SCHEMATIC DIAGRAM 3-45E714-5,-6 ................ WIRING DIAGRAM-250V MOV BOARD 1C
SCHEMATIC DIAGRAM 0-45E626-1 .-4 ................ WIRING DIAGRAM-RCIC SCHEMATIC DIAGRAM 3-45E626-2,-3 ................ WIRING DIAGRAM-RCIC SCHEMATIC DIAGRAM 0-47E610-12-1 ................ CONTROL DIAGRAM-AUXILIARY BOILER 3-45E620-2.-3 ................ KEY DIAGRAM-ANNUNCIATOR SYSTEM 3-47E811-1 ................... FLOW DIAGRAM-RHR SYSTEM 3-45N3654-1 .................. WIRING DIAGRAM-UNIT CONTROL BOARDS
PANEL 9-21. SH 1 3-45W670-SERIES .............. WIRING DIAGRAM ECCS
GE DRAWINGS: 729E652, SH 1 THRU 4 .... FUNCTIONAL CONTROL
TERRY TURBINE CO. DIAGRAMS-RCIC C-883-X ................. RCIC TURBINE GOVERNOR
NASH ENGR CO. CONTROL SYSTEM D-14-1365 ............... RCIC BAROMETRIC CONDENSER
AMENDMENT 26 POWERHOUSE UNIT 3
BROWNS FERRY FINAL SAFETY
NUCLEAR PLANT ANALYSIS REPORT
REACTOR CORE ISOLATION COOLING SYSTEM
MECHANICAL CONTROL DIAGRAM FIGURE 4.7-ld
H
G
F
E
D
c
B
A
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-:r ... \l.o ............... ---
AMENDMENT 27
BROWNS fERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT
REACTOR CORE I SOLATION COOLING SYSTEM
MECHANI CAL CONTROL DIAGRAM
FIGURE 4. 7-le
8 7 5 2
AMENDMENT 27 I"'OEIIHOUSE UNIT1
BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT
H
B
REACt~L 1~~E S~~~Q liON A MECHANICAL CONTROL DIAGRAM
FIGURE +. 7-1f
BFN-22
Figures 4.7-2a through 4.7-2h (Deleted by Amendment 22)