ML21286A352
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{{#Wiki_filter:Security-Related Information - Withhold Under 10 CFR 2.390 Figure 5.2-1a BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT PRIMARY CONTAINMENT VESSELS FIGURE 5.2-1a
BFN-16 Figures 5.2-1 b through 5.2-1c Deleted
BFN-16 Figure 5.2-2 Deleted by Amendment 11 l.
,------7 990~ L9 r------------------------------------------7 I
~ FAN~
---t-- 64-71 I
r--------7 ." 1-47E1847-2. D6
,..,,,_-< I FAN D 64-71
~
~ _..J.FAN~
I 1-- 64-70
~
(:i r+-45E779-1s.E10 FAN NE I I FROM I I FAN C 64 U) (rs\ I /Hs\ TURB BLDG EXHAUST DUCT 7 I ~ ~ ' I I ~ IFAN!/H5\ ~ 64-73 64-73 FAN NE I I I I I FAN B 64 --;- - 64-69 Cj 0s\__J__ _j;;;\ H
~
FROM REACTOR ZONE EXHAUST DUCT
~ I I
~
6~8
--+-- I --
...{HS\
6~8 6-4-72
~
T I 6-4-72
~
NOTE 10 0 ' L-r---Ws---dt\ . ~H~,._..,To PUMPRHR ROOM TO CORE SPRAY
..... t--t<-'V'-
PUMP tv10TORS
~~~
X X X ~ I ~ ~ ROOM ~ A & C 0' THV-64-12AB MOTOR A AIR
.;;5,,.:f..,,:,..20<} THV-64-11AB I FAN NI ROOM AIR { THV-64-12AA AIR FAN-6-4-72 THV-64-11AA I ....__,,, FAN AF AN-64-68 COOLER NI (FCo\ (FCo\ FAN~B...._,_ COOLER ACLR-64-68 CLR-6-4-72 FCC 64-12A THIS DWG 64-9A a. B 64-11A
"----'--v'---' ~ CORE SPRAY NI ROOM COOLER
,~ ~7 NE ROOM COOLER SIMILAR ECCS ANALOG OUTSIDE AIR I
++---C:...: RHR PUMP MOTOR A COOLER PUMP tv10TOR COOLERS 8, C & D SIMILAR TRIP POWER 11-47[610-71-2, C3 >- ~ + ---@v l~¥ib 1~iE~,E LIMITER I I s4-5\.00-"D 5 DETAIL 1C2 X
REACTOR ZONE X 9-25 FROM REFUELING ZONE 9-25 L~ l1-45E614-5,81h rl 1-45E614-6,G81 EXHAUST FANS ~ 64-+4 J
~
64-45
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l.....--=:9-81 PIS
~ TO REFUELING ZONE 25-213 25 221 9-25 X
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64-38 y DETAIL 1D2 l1-45E614-6,C4f---i +-----11-45E614-5, HG L--@)© PIS 64-58D 9-81
~
OUTSIDE AIR t-----_J X
\--tf!I FCC 64-42A I:. B ~
I
~
I 9-22 6-4--44 6-4--45 l~frIBRPiffluRE LIMITER 1-47E1847-7, E3 1-47E1847-7, E3 C wPDA iii
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NOTES:
- 1. THIS CONTROL DIAGRAM COVERS PORTIONS OF THE FOLLOWING SYSTEMS:
A. PRIMARY CONTAINMENT SYSTEM. B. SECONDARY CONTAINMENT SYSTEM.
~ FAN A C. ATMOSPHERIC CONTROL SYSTEM.
D. REACTOR ANO TURBINE BUILDING VENTILATION SYSTEM. F FAN B THE DIAGRAM INCORPORATES THOSE CONTROL DEVICES NECESSARY FOR
~ AIR PURGE OF THE DRYWELL, DRYWELL PRESSURE INTERLOCKS TO ENGINEERED SAFEGUARD SYSTEMS AND PROTECTION SYSTEM, REACTOR 0
l~OG TBDOOS
-----; AND TURBINE BUILDING ISOLATION, AND ZONE CONTROL RELATIVE TO BUILDING PRESSURE LEVELS AND RADIATION LEVELS, REFER TO THE
~~x I 9-1s I LOGIC DIAGRAM 47E611-64 SERIES FOR THE SPECIFIC INTERLOCK FAN-64-38 FUNCTIONS RELATIVE TO THE FOLLOWING:
~
*-1
~
w I I~ A. ISOLATION OF THE REFUELING ZONE AND REACTOR ZONE ON HIGH
~
~ X X I
I I 64-52CA L-':r"" FS 64-501 9-19 8. RADIATION. CONDITIONS CAUSING TRANSFER TO THE STANDBY GAS TREATMENT y G - SYSTEM.
-o!l
~<
<~ I I
{HS\_..J I GD 64-1608 y C. VACUUM RELIEF FOR THE DRYWELL.
- 0. INTERLOCK AND VENTILATING FOR TRIP REQUIREMENTS RELATIVE TO HIGH ANO LOW (VACUUM) PRESSURE IN THE REACTOR BUILDING.
'f
~
I2-45E777-30,A7 f--'_____
~
64~ 88 I J ~5-6A E. INTERLOCK FUNCTIONS FROM DRYWELL PRESSURE SENSORS RELATIVE TO REACTOR PROTECTION SYSTEM, ENGINEERED LOG _/ PT\ SAFEGUARD SYSTEM, ANO AUTO SLOWDOWN SYSTEM. I ~.~4""-"1s;,O~B+- 1608 2. DRYWELL PRESSURE AND TEMPERATURE AND SUPPRESSION POOL {HS\_ I PRESSURE~ TEMPERATURE, AND LEVEL ARE RECORDED AND/OR 64-23A - - ,
~ I 64-47
~
SEE NOTE 6
." 3.
INDICATEu IN THE MAIN CONTROL ROOM. THE NORMAL REACTOR BUILDING VENTILATION CONTROL IS THROUGH PDC-64-1 AND PDC-64-2 WHICH MAINTAIN THE REACTOR
~ <THIS DWG,D5 PA-64-58 \..:
9-82
~
"w' 4.
BUILDING AT -1 /4" OF WATER PRESSURE. DELETED PD! 64-22 64-23A y PI 6~9 r t" --II[;@
----+--=="
(ill- -t 6~F HS-84-20 1-47E610-84-1,HS 0' 5. IN THE EVENT THAT VACUUM INSIDE THE REACTOR ZONE INCREASES FROM THE NORMAL (-3/B* OF WATERb PDIC-64-16 SENDS E
-47E610-64-2, G6 w AN OPENING SIGNAL TO POC0-64-16 TO ALLOW UTSIOE AIR TO w
I t=------------:::f.-1r-i-C;~::J-f----_-_-_-l-_-_-_-_-_---l--:--'--':-7 I1-45E670-9 f- J25-6APT
-831_ 25-68 9-85 6~F 9-~~
LOG HS6435 ~
~J .,.
~
0' ENTER THE BUILDING. IF EITHER PDS-64-62A OR PDS-64-628 SENSES A POSITIVE PRESSURE GREATER THAN 1/4* OF WATER, OR IF EITHER POS-64-62C OR POS-64-620 SENSES A ~RESSURE MORE 9-82 NEGATIVE THAN -1/4* OF WATER, THEY WILL TRIP BOTH THE ZONE
§ ~ SUPPLY AND EXHAUST FANS.
r-ffl 1~~~4JO
---,L. PT PT~
1-45E670-8r, r-1 64 _57 A 6. FIELD TO CONNECT PORTABLE GAUGE AND PLANT AIR, VALVED AS 64-20-4A 64-57A 64-SBH 64-56C ~ I ::l NECESSARY, TO ORYWELL FLANGE EACH TIME ORYWELL HEAD IS G6 9-81 I I
~
2s=e'e '~,...,...., I I1-45E670-9 t--- J- ~_ITciGl
~
I I T L~~ 7. REFITTED, TO TEST SEAL OF HEAD. PURGE AIR FILTER. CRYENCO CONTRACT 85083.
.: PT ~IS I 9-02 25-SA A25-6A,---l5-6H-86 __[i]i;] E r--' 8. INSTRUMENT TAG NUMBERS ARE PREFIXED UNIT 1 UNLESS OTHERWISE NOTED.
64-578 64-578~ 1-45[670-21 r.vn,_I ~
,-w~-CL
--~ @ ( PT) ( PT \-;=~,.,;,.-r.~ in I 9. POWER HAS BEEN DISABLED TO EQUIPMENT ACCESS LOCK EXHAUST 25-5A FAN AND ASSOCIATED DAMPERS.
7 ~~ _.J ~ 64-57C 64-57C 64-58H 64-56D 64-56D "'f" I I
~ ' X-27 X-52 ~ ~
r--o::::r~-o 10. FOR REACTOR BUILDING VENTILATION AND REFUEL FLOOR RADIATION
!I !:1 25-5A PT PIS 9 - 81 ©@}l-- 11.
MONITORING SEE 1-47E610-90-1. UNIOS ON DRAWING ARE FOR REFERENCE ONLY ANO ARE ABBREVIATED II z
...I
........ 64-570 64-570 64-206A TO PT-76-14 1-47E610-76-1 ,F6 TO REFUELING ZONE (TYPICAL 3)
TO MEET SPACE CONSTRAINTS, REFER TO MEL FOR COMPLETE UNIDS.
!--~--~
I X
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...I ORYIELL
~
X-26 I I s4-600
--i I ~ -----1 SYMBOL:
D
- ~_j:;=~~
i t sf;c~----<
~ CONTROL AIR SUPPLY OIL FILLED RESERVOIR ANO LINE I I I~~ x CHANGE REFERENCE DRAWINGS:
I LOG I HS641 I~ V -~;!;I- ROOM ~ 47E600-SERIES ..... , .. INSTRUMENTS AND CONTROLS I I _frco\ MEL .................. INSTRUMENT TABULATIONS
~
I 47E605-SERIES ........ CONTROL BOARDS I t, ~ 64-GOD 64-238 y CISS A I 730E933-1 I _J 9-25 1-47E610-24-1 ...... , .CONTROL DIAGRAM-RAW COOLING WATER 0-47E610-65-1 ..... , .. CONTROL DIAGRAM-STANDBY GAS TREATMENT SYSTEM 1-47E610-76-1 ........ CONTROL SIAGRAM-CONTAINMENT INERTING SYSTEM {HS\__.J I I
**-** I
'l:'-J LS TM-64-52CA I1-730E933-2 f--1 ~-'--
64-GOA
~
I I I 1-47E610-84-1 ........ CONTROL DIAGRAM-CONTAINMENT ATMOPPHERE DILUTION SYSTEM 1-47E610-90-1 ........ CONTROL DIAGRAM-RADIATION MONITORING 1-45E614-5.-6 ........ WIRING DIAGRAM-120V AC/250V DC VALVES AND MISC 6t=9B I I ~- I 1-45E777-6 ........... WIRING DIAGRAM-480V AU~ILIARY POWER SCHEMATIC 0-47E800-1 ........... FLOW DIAGRAM-GENERAL PLANT SYSTEMS I I , 9-25 I I 0-47E800-2 ........... MECHANICAL SYMBOLS AND FLOW DIAGRAM DRAWING INDEX
.l I ~--,
/ '
+-- 1-47E844-2 ........... FLOW DIAGRAM-RAW COOLING WATER SYSTEM C
@--4 {HS\__: __ ..JI 0-47E845-2 ........ , .. FLOW DIAGRAM-COMPRESSED AIR-STATION SERVICE
*~0
~
~---+ I 0-47E847-SERIES ...... FLOW OIAGRAM-H&V AIRFLOW 1-47E1847-SERIES ..... FLOW DIAGRAM-CONTROL AIR 1-45E615-SERIES ...... CONTAINMENT ISOLATION STATUS SYSTEM (CISS)
~,..,...
64-52A TIS 6-4-52AA
~-v~r
~~x*~A _,,o_._t::-El.::-V-A-TORJ 1-1--7-30_E_93_3--1~f- - J : SHAFT FROM 11-130.,20-12 t---t I REACTOR ZONE i~~JrvH~k~
FAN-64-60 I THIS DWG,D7>--J __fciss]_JLOGl r-o::::r~-CL
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"-w ZQ 64-66 B w
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~
9-3 47E1847-6, m~-CL
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m~-0 AMENDMENT 27 FAN ROOM~ LT ____ ~--9-=iil 64-33 I 7 w_ ~ I C
- A 9-3 LT
~---r-----11-45E777-6 I AIR '
I u:o......= I ....[J]D 64~9s s4-159e LOG
~
I POWERHOUSE I
~ I 64-159A -,-lE!m I HS6433 w I UNIT 1 X-2068 // I
.-FcOI --+--...fo?n----+-x ..Af-"<'--i> - I --~ I I I I I>>* -
x-+- ~' ( I
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(aj 9-18 I LOG _j <1---;,f--:,,,.,,,,,---1 DEMIN5-.,....J CISS
~4-65A 64-65D T T 9-3 9-18 ....L.9-V 164-1598 - WATER ~ I
! ~ :$:>>: M -r
@\
DEMIN '( WATER{._filY' 6~9A1 9-3 I 8 i!l I BROWNS FERRY NUCLEAR PLANT NOTE 9 NOTE 9 64-54A 64-54A y St:9A L -~~ fflRESSION Cu:\ _ _J LOG 1-47E1847-7, CJ
~
~ I x - + - ~ - - ~ - - rrco\... 1 1 ... x
~
I I ~5-32 TE
~rRESSION 164~~9AI TE TE 6-4-66
~
64-34-0 ____ J FINAL SAFETY ANALYSIS REPORT
-;~~r- 64-55D 64-55F I ~-3 Cott.PAN ION DRAWINGS:
Am
- ~658
,,~>&._ ~_ 4 J I dls3 64-54A A
(LA\ 64-548 TE TE 6~8 1-47E1847-10,C3
~
LOG 64-34-C CISS A ______L_.~
- , 34 1-47E610-64-2 &-3 2-47E610-64-1, -2 a. -3 3-47E610-64-1, -2 & -3 A
PRIMARY CONTAINMENT SYSTEM
~
64-55E 64-55A 25-32 _..._, ZI-64-3481 I L __________________________________________ _ MZI-64-34 lf'R'( 'fai" ZI-64-34A XS CISS A 9-5~!
~1i_ 64-34 FCV 9-3 MIMIC
~
I~ ,-y, 9-3 MECHANICAL CONTROL DIAGRAM
=_J Lt--t-------~~
64~ EQUIPMENT ACCESS LOCK L ----1/4=--~ ___,.l m ~4
----+---- x FIGURE 5.2-2a SH 1 8 7 6 5 4
D~D~ l-t9-0 l93Lt-Z 11"1 L9 2-45[777-3 FROM TURB BLDG FAN D Gs\ 64-71
~
Q 64-71 FAN D EXHAUST DUCT m r 45E779-161 hs\ ~ 2-47[610-64-2,83
, - -1 ~rti~E,~:..i4-1.Es FAN C FAN B 64-70 Gs\
~
~
N 64-70
~
FAN C FAN 8 Gs\ s4-7J I I I
~ FANS s1--1J B .t. D 1---------+-! RE ,);t---, 64-69 64-69 (7s\_ I __/i;'s\
FROM REACTOR ZONE EX L'~OJ r7s\_---f--~ 64-68
~
64-68
~
64-72
~
I 64-72 FANS A&. C
~
H TO CORE SPRAY SHY-61-16 1 t L.J....,. NOTE 13 ROOM ROOM .....H~Pu"**P~MOTORS X X A& C AIR AIR 8 & D POI 64-1348 1;;~5~flfAirE r---1=-= COOLER A COOLER HEPA ~ FAN B I FILTER I RHR PUii' MOTOR A COOLER CORE SPRAY NI ROOM COOLER FAN B PUMP MOTOR COOLERS 8, C ~ 0 TYPICAL NE ROOM COOLER TYPICAL SEE I RPS ANAL<:X; DET 2A2 2-47'610-64-2, ZONE 8-7 I TRIP POWER (TURBINE ROOM EXHAUST FANS A-J) ATtdOSHPERE I l2-47E610-99-1>---!Fr>-----@)<D I I :!: 12-47E610-99-1>---ID---@) I ~ I FAN A I !..,,, I 2-47E2847-7 ,CJ 12-47E610-99-1>---lfr'.>-----@)@ I ~25 ~ - - ~ _&25 I L 64 _9 l2-45E614-5f-- 6:_"10 ROOM >--'. PDS PDS_i.,--<ROOM l2-47E610-99-1>---ID-----@)© G L---c:~gJ: AIR St:9A/C 64~8/D AIR ECCS ANALOG TRIP POWER r~~ I2-47E610-71-2' ">- -IE'.>-t--@>@
~
OUTSIDE AIR 9-25 L-@)@ AIR CONDITIONING UNIT ~~frJ8RPii~iuRE LIMITER 25-22{Px"\ 64-38 ll-64-488 2-ACU-064-0134 J r~ IL-64-388 (xs\_..JHS\ 64-38
~
A 25-222 NOTE 13 I2-47E610-71-2,F4>--ITE>---t--@) FILTER (FIT\
&-!©
~6~4BRC
____ J R IL-64-JBC 64-135 64-135
~ 'rc;(_ y 64-38 N
0 w z 0 Nr ~ NOTES: L-@)© _;B(-4 r12-45E779-181 "' 1 ' THIS CONTROL DIAGRAM COVERS PORTIONS OF THE FOLLOWING
- 0
~:,
SYSTEMS:
~I I cc I ....' ""'
2'JiSIDE 2-47[2847-7.
@ I ai-5Je y ~
,=-
,a(..4 I
r-_j I n 0 r Or
<<n W=>
~<
C A. PRIMARY CONTAINMENT SYSTEM.
- 8. SECONDARY CONTAINMENT SYSTEM.
C. ATMOSPHERIC CONTROL SYSTEM. D3
,...,.,...,,6~~~A {Hs'\
64-4C L-~ I 64-38 I I ....-------1,1------ ..' w w N ox r~ cc cc r D. REACTOR AND TURBINE BUILDING VENTILATION SYSTEM. THE DIAGRAM INCORPORATES THOSE CONTROL DEVICES NECESSARY FOR AIR PURGE OF THE DRYWELL, DRYWELL PRESSURE INTERLOCKS TO ENGINEERED SAFEGUARD SYSTEMS ANO PROTECTION SYSTEM, REACTOR ANO TURBINE BUILDING ISOLATION, AND ZONE CONTROL RELATIVE TO
~
Dcoy I 't;J'I 64-1A i ~l-li I ...._ ~
- 1- ....._..
BUILDING PRESSURE LEVELS AND RADIATION LEVELS. REFER TO THE SCHEMATIC ELEMENTARY DIAGRAMS FOR THE SPECIFIC INTERLOCK F FUNCTIONS RELATIVE TO THE FOLLOWING: 0 A. ISOLATION OF THE REFUELING ZONE ANO REACTOR ZONE ON HIGH
~
o1 I FANxA : I I I I (Fee\ 64-5B (Fee\ 64-68 2-rAN-M-ue STEMI VAULT ElCH 100STER FAN 6~78 XA-64-67 ,C4 uiLl 25-321 9-19 25-6A. II I CNTIIT PURCE FILTER FAN
~2 64-132 SEE NOTE 7 RADIATION.
B. CONDITIONS CAUSING TRANSFER TO THE STANDBY GAS TREATMENT SYSTEM. VACUUM RELIEF FOR THE DRYWELL. INTERLOCK ANO VENTILATING FOR TRIP REQUIREMENTS RELATIVE TO HIGH ANO LOW (VACUUM) PRESSURE IN THE REACTOR BUILDING INTERLOCK FUNCTIONS FROM DRYWELL PRESSURE SENSORS RELATIVE TO REACTOR PROTECTION SYSTEM. ENGINEERED SAFEGUARD SYSTEM ANO AUTO BLOWOOWN SYSTEM. (THIS DWG,C4>---0a-+- -~--::;:::-~ L--~-----.J LOG I~
- 2. ORYWELL PRESSURE AND TEMPERATURE AND SUPPRESSION POOL pI I I 25-32 IA5136 I
-----, 9-3
~---- (rs\_
64-128 H6~4""-1"'2"-s PRESSURE, TEMPERATURE, AND LEVEL ARE RECORDED AND/OR INDICATED IN THE MAIN CONTROL ROOM. I L..,,._,. PDM 64-18 *~ I r-
~ I {Px'\ ck:::. -©~ 3. THE NORMAL REACTOR BUILDING VENTILATION CONTROL IS THROUGH PDC-64-1 AND POC-64-2 WHICH MAINTAIN THE REACTOR BUILDING AT (HS\_ ~ (POI\
(r?; I 64-48 : 9-19LJD
~ (PDI\- -1/4" OF WATER PRESSURE.
64-23A - ,
~ I I V I TO XR-64-159 64-1608 I
6~8 64-125 64-129 64-126
~
I 1-47E610-64-1.E3 4. HS-64-48. LOCATED ON PANEL 9-25. IS USED TO ISOLATE All THE TURBINE BUILDING EXHAUST FANS ANO DAMPERS IN THE EVENT OF HIGH RADIATION. EA.CH FAN AND DAMPER ASSEMBLY HAS A LOCAL SWITCH TO I+-- I
,is'\
64-23A y
~--0 (THIS OWG,B4 f---t SEE NOTE 6 25-6~ I l.ED I ,-< IS-64-67A THIS OWG,C4)
I e-730E927-8f-7
~~
64-130 64-130
~ ~
I I TO STANDBY GAS TREATMENT SYSTEM 2-47E610-84-1,H5 START AND STOP THAT ASSEMBLY.
- 5. IN THE EVENT THAT VACUUM INSIDE THE REACTOR ZONE INCREASES FROM THE NORMAL (-3/8" OF WATER) PDIC-64-16 SENDS AN OPENING SIGNAL TO PDC0-64-1~ TO ALLOW OUTSIDE AIR TO ENTER THE BUILDING.
IF EITHER PDS-64-62A OR PDS-64-628 SENSES A POSITIVE PRESSURE L12-45E614-61 GREATER THAN 1,4* OF WATER. OR IF EITHER POS-64-62C OR I E 64-16081 25-6A 9-821 ~H~Y 6iiEfDT~i~ ~aT~ ~~~s~g~~ rup~l~EjAiir~HX~~~ Fi,~: I I /PT\_ _/PIS\_ 7
~ 64-58F 64-58F t ~
PA-64-58 6. FIELD TO CONNECT PORTABLE GAUGE AND PLANT AIR. VALVED AS NECESSARY, TO ORYWELL FLANGE EACH TIME DRYWELL HEAD IS REFITTED, TO TEST SEAL OF HEAD. OF WATER. ,7, \i ~ I ~ 7. PURGE AIR FILTER. CRYENCO CONTRACT 85083. / / / / rr.!2;;£;,:i::J-,,;:_:;;8:;-22~5--6;;8;, \~ 6 /PIS\ PT PT 6 f1 PIS _J r~ ~
---,-'---,---,.=,,.----:-----,25-se
~ 64-56C ~
~
9-85 8. A. UNIOS 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 UNIOS ARE UNIT 2 UNLESS OTHERWISE NOTED. LEADING ZEROES SHOWN IN MEL AS PART OF THE UNID ARE NOT DEPICTED. / < ~ 64-57 A 64-57 A 64-58A 64-58A I ~ REFER TO NEOP-4.
~ ~
/ / / n N w I x-52 u....,: I
~
+-
~
...__.. 25-6~
~2-73 E927-8.,_ 7 ( PIS\
1 H2 I I 6 ~- I- _J _l_ 9_82 2-45E671-33 2-45E671-45 EXAMPLE: MEL UNID BFN-2-HS-064-0011AB BFN-2-FSV-064-0029 DRAWING UNID HS-64-11AB FSV-64-29 B. All VALVES IDENTIFIED AS "Fcv* HAVE VALVE OPERATORS. / cc
~ THE MEL UNI FOR THE VALVE OPERATOR IS DEVELOPED AS FOLLOWS:
/ "'"' ...... -~ 9-82 25-6A 9-82 I 64-58H y 4 G1 - / ~ JPT', (PT\_ ms\ I ~5-6A -68 -86 VALVE DRAWING UNI VALVE OPERATOR MEL UNID / .., z 6~C 64-57C 64-SBC 6t:;,!IC ( PT\ (PTL PIS FCV-64-20 2-MVOP-064-0020
- 9. All HANDSWITCHES AND CONTROLS ARE LOCATED LOCAL UNLESS
/ ..J II. 25-68 64-58H 64-56D 6~6D OTHERWISE NOTED. / / ....., 10. THE VALVE POSITION LIGHTS COVERED BY THIS NOTE ARE LOCATED ON THE GRAPHIC DISPLAY PANEL (9-3) . 11' THE TWO VALVES IN SERIES THAT ADD WATER TO THE REFERENCE LEG /
-. OF THE LEVEL TRANSMITTERS SHALL ALWAYS BE CLOSED DURING NORMAL
..J
/ / z 25-58 DRYIELL 12, ~rirri~ 0r&IaEfo~*~Rt~t~~ 58C~tilNMENT SYSTEM IS SHOWN ON / m n N PT-64-SBE.ES PT-64-58F.E3 LOG MECHANICAL LOGIC DIAGRAM LISTED IN REFERENCE DRAWINGS.
- 13. FOR REACTOR BUILDING VENTILATION AND REFUELING FLOOR RADIATION
...::lNITORING SEE 2-47E610-90-1.
D / ' PT-64-58H.E3 4-31
~
/ cc' 0 /
"'"' ---j THIS DWG
/ SYMBOL: / / / ~ OIL PRESSURIZED ACCUMULATOR / ~CONTROL AIR SUPPLY /. ~ O I L FILLED RESERVOIR A.ND LINE REFERENCE DRAWINGS: LS 0-47E800-2 ........... MECHANICAL-SYMBOLS AND FLOW DIAGRAM DRAWING INDEX 64-46 47E800-1 ............. FLOW DIAGRAM-GENERAL PLANT SYSTEMS y 47E600-SERIES ........ INSTRUMENTS AND CONTROLS
~
64-238
~-3 MEL .................. INSTRUMENT TABULATIONS FOR PRIMARY CONTAINMENT SYSTEM 47W605-SERIES ........ CONTROL BOARDS 2-47E610-76-1 ........ CONTROL DIAGRAM-CONTAINMENT INERTING SYSTEM
~ 47E865-SERIES ........ FLOW DIA.GRAM-TURBINE&. REACTOR BLDG. H &. VA.IR FLOW (HS\_
6t_:9B
'TI 64-46
~
2-47E610-84-1 ........ CONTROL DIAGRAM-CONTAINMENT ATMOSPHERE DILUTION SYS 2-47E610-90-1 ........ CONTROL DIAGRAM-RADIATION MONITORING 2-47E610-85-1 ........ CONTROL DIAGRAM-CR HYDRAULIC SYSTEM 2-47E610-24-2 ........ CONTROL DIAGRAM-RAW COOLING WATER I __Elli]_ I
~ 6 4 - 3 0 c~
LOG I 2-47E2847-SERIES ..... FLOW DIAGRAM-CONTROL AIR 2-47E856-2 ........... FLOW DIAGRAM-DEMINERALIZED WATER SYSTEM TO 2-FCV-84-20 2-47E610-73-1 ........ MECHANICAL CONTROL DIAGRAM-HPCI SYSTEM 0-47E845-2 ........... FLOW DIAGRAM-COMPRESSED AIR-STATION SERVICE C
--j2-47E610-84-1,G7) 2-47E610-99-1 ........ CONTROL DIAGRAM-REACTOR PROTECTION SYSTEM 2-45E614-5,-6 ........ SCHEMATIC DIAGRAM-REACTOR & REFUELING ZONE ISOLATION
~
w 2-45E779-16 .......... SCHEMATIC DIAGRAM-480V AC REACTOR BUILDING PUMPS cc 2-45E777-3 ........... SCHEMA.TIC DIAGRAM-480V AC REACTOR EXHAUST FANS 2-45E670-14.20 ....... SCHEMATIC DIAGRAM-ECCS ANALOG TRIP UNITS
,.!:! 2-45E671-27.33,39,45.SCHEMATIC DIAGRAM-ECCS ANALOG TRIP UNITS
~m M
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~=l~~~t~=~s:; ::::: ::::~a2,R8CA8~~~R~O!s~~5i~GGJ~TT~EATMENT 2-47E610-71-2 ......... MECHANICAL CONTROL DIAGRAM RCIC SYSTEM eel 0-45E773-3 ............ WIRING DIAGRAM 480V AUX POWER SCHEMATRIC DIAGRAM r~ 2-47E611-1-SERIES ..... MECHANICAL LOGIC DIAGRAM MAIN STEAM SYSTEM 2-+7E611-6+-SERIES .... MECHANICAL LOGIC DIAGRAM PRIMARY CONTAINMENT ISOLATION SYSTEM OUTS IDE >--~ 2-47E611-68-SERIES .... MECHANICAL LOGIC DIAGRAM REACTOR WATER RECIRCULATION AIR SYSTEM 2-47E611-69-SERIES .... MECHANICAL LOGIC DIAGRAM REACTOR WATER CLEANUP 2-47E2847-6, SYSTEM E5 2-47E611-73-SERIES .... MECHANICAL LOGIC DIAGRAM HIGH PRESSURE COOLANT INJECTION SYSTEM 2-+7E611-74-SERIES .... MECHANICAL LOGIC DIAGRAM RESIDUAL HEAT REMOVAL SYSTEM 2-+7E611-75-SERIES .... MECHANICAL LOGIC DIAGRAM CORE SPRAY SYSTEM 2-47E611-99-SERIES .... MECHANICAL LOGIC DIAGRAM REACTOR PROTECTION SYSTEM X-2090
-205 X-206A.
r, _-_-_-_-_c_-z::-::_-_-_-_- B 1I ~ II ~ II II II X232A 9~A
/LI\9-:_J\ T '\
6 ~ 64-159A
~3 I ~>--I LJxR \. 64 _159 LT 64-1598 X206D LT 64-66 7 AMENDMENT 27 II ,:;-~- -7 T r.?\-19 X206C IDIXJI I II TYPICAL OF 12 PX I m PX SUPPR POOL TEMP MONITORING SYSTEM
~
I I POWERHOUSE SUPPRESSION POOL---~ (AA THRU MAJ X232Bl,r-t><I-I 64-.]_59A ~ LOG
~ ...
~ ...,.
6H59B H><I-"- X232D (2-47E610-64-3) 64-66 i UNIT 2 II A5123 'f l;I i;: c POOi.SUPPRESSION c.::.:.::_:.::_c..,,~ IA51LOG35 1-::-1
- _.l..!'-3/ s-18 I 111 ~ TW Lille--'
64-66 ICIASS I -t,.,-'L~Oc-G=I BROWNS FERRY NUCLEAR PLANT
~
~
I ~ 64-55C 0E\ 64-34 Cl FINAL SAFETY ANALYSIS REPORT
-47E610-2-2,E4 lL-__@T -~ _liliil_ ~
64-54 25-32 I (PX\_ __ r-~-i __________ _fxs\_ __ _ 25-32 64-54 LT FIC 64-54.~-~~64-54 DEMINERALIZED WATER SUPPLY I TW 64-55A 64-55C SPARE...__,. ro:::r-~ 9-3 ~-18 ~-3 2s-32 25-31 I ~ I ,--------------------------------7 PRIMARY CONTAINMENT SYSTEM A 64-54A
-~
64-54A C!D 64-54A {LA\_ _ _jcs\_ _ 64-548 64-548
--f r-1 I I I GE DRAWINGS AND DESIGN SPECIFICATIONS, I COMPANION DRAWINGS:
1-47E610-64-1, -2 &. -3 2-47E610-64-2 &. -3 MECHANICAL CONTROL DIAGRAM
...__.. ...__.. ...__.. ...__.. ...__.. ~5-32 2-730E927-20 L- - - - - - __ J ~1 ~~g~3:::::::::: :~~1~:~~ ~6~¥l~~~~~~sv~~~. v~5¥¥~R~~~A~~~~Es 22A1132AE ......... CONTAINt.ENT ISOLATION SYSTEM L-64 _5~~ 3-47E610-64-1. -2 ~ -3
( LI\ ~--------< 2-47E610-73-1 .87 22A1169 ........... DESIGN SPECIFICATION FOR REACTOR CONTAINMENT 64-548
~
2-730E927-7,-8.-20 ............. ELEMENTARY DIA.GRAM PRIMARY CNTMT ISLN SYS 2-730E927RF-16,-17A,-19 .......... ELEMENTARY DIAGRAM PRIMARY CNTMT ISLN 9-54 FIGURE 5.2-2a SH 2 ZI-64-348 8 7 6 5 3
zso~ l-t9-0l93Lt-£ V'l L9 r-----------------------------------------------------------------------------------------7 PUMP MOTOR D 64-71 (T0, 3-47E3847-5,A3 '° PUMP MOTOR C ~ 64-70 t [:i MCC m
~
~
~
MCC PUMP MOTOR 8 ~ ~
..., r--- FSV FS -, PUMP MOTORS B & D (T0, "'"t '>i(' IL-64-72 1 I 64-11 Ay--y'-t.J.LcU Lf--l,L-JC1.l-~64-12A 1 64 _69 ,)., )-')-;;{
- -<. IL-64-68 64-73 ,.., ),-<.
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64-68 I 64-68 ~---i--l/HS'\ 64-72 I 64-72 H
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....w' N
...w' - I - - I - TO CORE SPRAY
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StJ._., 118 I r---------+----J I < ~ ' ~ ' < L--..----------------~ I 64-12A ROOM A ROOM PUMP MOTORS X 1 I I < "'< "'< N
~
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N I I
'r I AIR AIR A& C REFUELING FLOOR r--------* *-------, I I I : ..,.'
I I FAN-64-68 FAN-64-72 EXHAUST FANS I r------ *----, I ~ I
\_J FAN A I1 :
~
....w' w (Fed\ !I ~ COOLER A CLR-64-68 COOLER CLR-64-72 RPS ANALOG ~ ~ 64-9A FCO FCO ~~ "'.J.
/ XS 64-11A FAN-64-11A
~
(Fed\ 64-11A I'
~
I'
~ 64-12A FAN 8 fAN-64-12A 64-12B
.....__,,, RHR PUMP MOTOR A COOLER CORE SPRAY NW ROOM COOLER L----1T TRIP POWER 9-25 64-1 DA _
9 25 PUMP MOTOR COOLERS 8, C & D TYPICAL NE ROOM COOLER TYPICAL l3-47E610-99-1>--~---§)(D
+ .--i?J I / , 9-25 9-25 NOTES:
THIS CONTROL DIAGRAM COVERS PORTIONS Of THE FOLLOWING I3-47E610-99-1 >--1 DIV IIA>----§) X X I,~ {FSv\____________ _, Gs:\ 1. SYSTEMS: XS-64-118 ..............9-25 ,,~ 64-43 64-43 A. PRIMARY CONTAINMENT SYSTEM.
- REACTOR ZONE I B. SECONDARY CONTAINMENT SYSTEM.
l3-47E610-99-1 >--1 DIV IB >----§)@
>--~---§)© I 3-4SE614-6 ~-, I
~-----~
I ~ .L...!§__\
~ - - - 11 A EXHAUST FANS I I I I I I S 3-47E3847-7,C2 I . . .__,, C. ATMOSPHERIC CONTROL SYSTEM.
D. REACTOR AND TURBINE BUILDING VENTILATION SYSTEM. l3-+7E610-99-1
,---t.;.....,_ TD REFUELING I FCD[B----'-X'--\-~*~*-l!J I THE DIAGRAM INCORPORATES THOSE CONTROL DEVICES NECESSARY FOR
~o*
- ZONE (i;-25 ,-4-25 13-45E614-S ~-, r-13-4SE614-s I 25-222 64- 3A L-13-45E614-61 AIR PURGE OF THE DRYWELL. DRYWELL PRESSURE INTERLOCKS TO r l..!:'..:!./'V ECCS ANALOG ENGINEERED SAFEGUARD SYSTEMS AND PROTECTION SYSTEM, REACTOR TRIP POWER HS 64-9 L!fil 64-10 I
I 25-213 I 25-221 LlD AND TURBINE BUILDING ISOLATION, AND ZONE CONTROL RELATIVE TO BUILDING PRESSURE LEVELS AND RADIATION LEVELS. REFER TO THE G 13-47E610-71-2>--~+~ >---,,PDS PDS 64-38 LOGIC DIAGRAM 47E611-64 SERIES FOR THE SPECIFIC INTERLOCK I 'Y' FUNCTIONS RELATIVE TO THE FOLLOWING: L-@) ROC>A { **SAIC 64@/D ROC>A I .,...-l-25 A. ISOLATION Of THE REFUELING ZONE AND REACTOR ZONE ON HIGH AIR } AIR ~------~ I 64-38 RADIATION.
- 8. CONDITIONS CAUSING TRANSFER TO THE STANDBY GAS TREATMENT r~ I -
SYSTEM. C. VACUUM RELIEF FOR THE DRYWELL. 13-47[610-71-2>--~+~ ~ 0. INTERLOCK AND VENTILATING FOR TRIP REQUIREMENTS RELATIVE I L-@) OUTSIDE AIR Il2s-222 TO HIGH AND LOW (VACUUM) PRESSURE IN THE REACTOR BUILDING. E. INTERLOCK FUNCTIONS FROM DRYWELL PRESSURE SENSORS RELATIVE TO REACTOR PROTECTION SYSTEM. ENGINEERED SAFEGUARD SYSTEM, AND AUTO BLOWDOWN SYSTEM. M __/xs\___~___________ J LIMITER A 2. DRYWELL PRESSURE AND TEMPERATURE AND SUPPRESSION POOL PRESSURE. TEMPERATURE. AND LEVEL ARE RECORDED AND/OR 64-4C 3-47Ll847-8,83 'T""" 64-48 I
~--/Hs'\
64-38 64-3C 64-38
- FE 64-38 J---------------t-i 9-25 *-1
'r.::;{_~I
~II
., . . . . , r--3:§l'..
I,¥ I I ")C<_ 9-25 4. INDICATED IN THE MAIN CONTROL ROOM.
- 3. THE NORMAL REACTOR BUILDING VENTILATION CONTROL IS THROUGH PDC-64-1 AND PDC-64-2 WHICH MAINTAIN THE REACTOR BUILDING AT -1 /4" Of WATER PRESSURE.
f------------,
'Y' - I I I I I I I I s. IN THE EVENT THAT VACUUM INSIDE THE REACTOR ZONE II (Fed\ II I I I I INCREASES FROM THE NORMAL (-3/8* Of WATER) PDIC-64-16 SENDS
**-oo-** AN OPENING SIGNAL TO PDC0-84-16 TO ALLOW OUTSIDE AIR TO
~
I ENTER THE BUILDING. IF EITHER PDS-64-62A OR PDS-64-628 ft s+-Js I ll SENSES A POSITIVE PRESSURE GREATER THAN 1/4" OF WATER, OR IF ix ~ I 8
~-,L_3_-4_S_E_6_2_0_-_3__.r----, EITHER PDS-64-62C OR PDS-64-620 SENSES A ~RESSURE MORE NEGATIVE THAN -1/4* OF WATER, THEY WILL TRIP BOTH THE ZONE F SUPPLY AND EXHAUST FANS.
3-FAN-064-0135 6. FIELD TO CONNECT PORTABLE GAUGE AND PLANT AIR, VALVED AS MAIN STEAM VAULT NECESSARY, TO DRYWELL FLANGE EACH TIME DRYWELL HEAD IS 0 EXH BOOSTER FAN REFITTED, TO TEST SEAL OF HEAD.
~
~
13-4SE614-S r--+ I 7. PURGE AIR FILTER. CRYENCO CONTRACT 85083.
- 8. INSTRUMENT TAG NUMBERS ARE PREFIXED UNIT 3 UNLESS OTHERWISE I
I NOTED.
;o PA-64-58 A-2s 9. FOR REACTOR BUILDING VENTILATION AND REFUEL FLOOR RADIATION MONITORING SEE 3-47E610-90-1.
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'1' I
r-<THIS DWG,D5 I I t-73-45'670-271
> 9-3 Gu (I5-64-67A.CJ 9-19 LlD 64-159 64-1608
- r 'Y'
/....!iD 64-41
- 10. THE VALVE POSITION LIGHTS COVERED BY THIS NOTE ARE LOCATED 11.
ON THE GRAPHIC DISPLAY PANEL (9-3). INDICATING LIGHTS AND HANDSWITCHES LOCATED ON 3-9-3 GRAPHIC DISPLAY PANEL.
- 12. UNIDS ON DRAWING ARE FOR REFERENCE ONLY AND ARE ABBREVIATED I
I I LT-64-15981 I TO MEET SPACE CONSTRAINTS, REFER TO MEL FOR COMPLETE UNIDS. (Hs\_ [E)----1 AS-SA 64-23A
----t I II
~---@)@
~-81 L...,._J
[J][J_ __ J 64-1608 PT) SYMBOLS: {PIS'\ ~
~
64-23A y I I
*1:_,.
~
SEE NOTE 6 ( PA-64-58 >-------, 9-82 1268 2-47E610-64-1,E2 FROM HPC1 3-47E610-73-1,C2 E 64-58[ r--------------J--~ TO FCV-84-20
~
OIL FILLED RESERVOIR AND LINE 7' /
~-ill)© ©(ill--1 S~F 3-47E610-84-1,G7
/ / rt:~--....:...---:--'--,',--, I I3-4SE670-33 ~- I i-..::=====:..._--1 J2S-SAI PT CONTROL AIR SUPPLY / ..,.' 9-82 821 64-58F REFERENCE DRAWINGS: / m w 25-5A 9-81 -~ PT ./Pis't8S _ , , ; :
< 0' PT __ jPis\______ 'f ___ _ I3-45E670-32 ~- - --------~-ft!S\ PT MACH. 0-47E800-1 ......... , .. FLOW DIAGRAM-GENERAL PLANT SYSTEMS
/ ~ N
..,.w' --~ 3-45E670-26
- I 64-57A 64-57A 64-58H 64-56C ~OCT~ ROOM 0-47E800-2 ............ MECHANICAL-SYMBOLS AND FLOW DIAGRAM tT
/ ..,.' 64-578 64-578 I DRAWING INDEX w I - 25°=60 y~---- ~ ILOGI N 47W600-SERIES ...... , .. INSTRUMENTS ANO CONTROLS / / I'
.,"' "'I ' - - I I X-27 X-52 !I9-82 1 1 3-45E670-33r----J - 9JE015 ~ MEL ................... INSTRUMENT TABULATIONS 25-5A 25-GA I I :!i 47E605-SERIES .... , . , .. CONTROL BOARDS
/ :::. 3-47E610-24-1 .... , . , .. CONTROL DIAGRAM-RAW COOLING WATER {ei'\ __/PJs\:'~~~--l---- /PT\
,--l-_2S-6A~-6h-8~- LOG
- , 3-47E610-76-1 ......... CONTAINMENT INERTING SYSTEM CONTROL
/ z ;:;' 'M7'-- - --------l-ft!S\ ( PT l ( PT LJ PIS \.l 9JE016 '°
"'"' 64-510 64-570 TO REFUELING 4-608 DIAGRAM
/ w ~ 64-57C 64-57C 64-58H 64-56D 64-56D -, "f ZONE 3-47E844-2 ....... , . , .. FLOW DIAGRAM-RAW COOLING WATER
"'I '
~---1
/ -' IL - I ~ 3-47E3847-SERIES ...... FLOW DIAGRAM-CONTROL AIR SYSTEM / ©@}+----- / >- REST :-..J 0,3-47E865-SERIES ..... TURBINE & REACTOR BLDG. H&V AIRFLOW 3-47E610-85-1 ......... CONTROL DIAGRAM-CRD HYDRAULIC SYSTEM / w z I TO fCV-84-19 ROOM I _f-- 3-47E610-73-1 .. , ...... MECHANICAL CONTROL DIAGRAM-HPCI SYSTEM 3-47E610-84-1 ......... CONTROL DIAGRAM-CONTAINMENT ATMOSPHERIC / / /
~
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~ !(Hs\_ ____ _/xs\
-+---i I
i...i 19-3A 3-47E610-84-1,F7 1*
,....i: __:.-:::.
X
-_+_~--~=-~-=~==!I!=,~--~-~----
r-*-- ----, '#
-m
~ ~='-=--I 1**:~% al I DILUTION SYSTEt.t 3-47E610-90-1 ......... CONTROL DIAGRAM-RADIATION MONITORING SYSTEM 0-47E845-2 ............ FLOW DIAGRAM-COMPRESSED AIR-STATION SERVICE 3-47E856-2 ............ FLOW DIAGRAM-DEMINERALIZED WATER SYSTEM D
f m ls4-L300G CL Ir---------
~ __ J
~ '{< I
/ 0 w I I .. 3-45E614-5,-6 ......... WIRING DIAGRAM 120V AC/250V DC VALVES AND / 'f' 164-11C co 64-118 iii {PDA' ~ MISCELLANEOUS SCHEMATIC DIAGRAM
~~ 64-27 >,!X ~ I FCV ~ ~ ~
/ / I ......
~
-- co '--r""
I < I ~ O~<i~< ti]~ 9-3 I 64-30 I 9-3 I I G ---------+ I I 3-4SE614-19 ........... WIRING DIAGRAM 120V AC[2SOV DC VALVES AND MISCELLANEOUS SCHEMATIC DIAGRAM 0-45E777-4 ............ WIRING DIAGRAM 480V UNIT AUXILIARY POWER / ILi V I I I L.--- ------------- )c;,(_ 9-25 I SCHEt.tATIC DIAGRAM
,._ w I .., 3 A --------1-7 3-45E777-3,-5,-6 ...... WIRING DIAGRAM 480V UNIT AUXILIARY POWER
~
/ "f ~ I '° I SCHEt.tATIC DIAGRAM / /
,.., ::c r I
*~
r 6~7 9-25 I 3-45E670-26,-27 ....... WIRING DIAGRAMS EMERGENCY CORE COOLING SYSTEM DIVISION 1 ANALOG TRIP UNITS / PDM r- ------*-, I .:::-:.-.. I 00-------~1 64-60A SCHEt.tATIC DIAGRAM 3-45E670-32,-33 ....... WIRING DIAGRAMS EMERGENCY CORE COOLING SYSTEM DIVISION II ANALOG TRIP UNITS I 64-2A
>-<.. '1* f FCO) I 64-118 I
- I I SCHEt.tATIC DIAGRAM
~
3-45E671-57 ........... WIRING DIAGRAMS REACTOR PROTECTIVE SYSTEM 64-238 ~~~~~ ~ I I I 3-4SE777-6 ~-1 DIVISION IIA ANALOG TRIP UNITS SCHEMATIC DIAGRAMS
'f ....- I ~ 0 FANXA i {Hs\________ ~
! MCC 3-45E671-51 ........... WIRING DIAGRAMS REACTOR PROTECTIVE SYSTEM DIVISION IA ANALOG TRIP UNITS SCHEt.t DIAGRAMS.
3-45W671-63 ........... WIRING DIAGRAM REACTOR PROTECTIVE SYSTEM (Hs\_ I : 0 ~...._ FAN-64-110 I DIVISION II 8 ANALOG TRIP UNITS SCHEMATIC DIAGRAMS 64-23B--- e~e r-----1--~
~ ~
3-45E671-69 ........... WIRING DIAGRAM REACTOR PROTECTIVE SYSTEM
~4~i 2f------~ ! ~
DIVISION II 8 ANALOG TRIP UNITS SCHEMATIC
*:r
- I ,!. I IL-64-60 1 :
~
*---~----------*
......,...... -- I f f YxA 7 ~ ~YiA ~ "-.C-r/
DIAGRAMS 3-45E779-16 ........... WIRING DIAGRAM 480V SHUTDOWN AUXILIARY POWER SCHEMATIC DIAGRAM 3-45E777-21., ......... 480V WIRING DIAGRAM AUX POWER C SCHEMATIC DIAGRAM
~
;R:;-rx REACTOR 3-45E620-8.-10 ........ KEY DIAGRAM ANNUNCIATOR SYSTEM 3-47E812-1 ............ FLOW DIAGRAM HIGH PRESSURE COOLANT INJECTION SYSTEM ZONE STAIR 3-47E865-12 .. , ........ FLOW DIAGRAM HEATING & VENTILATING SUPPLY FAN ELEVATOR GE DRAWINGS:
AIR FLOW FAN-64-60 SHAFT 21A1053 ............ GENERAL REQUIREMENTS FOR VACUUM BREAKERS 21A1363 ............ PRIMARY CONTAINMENT VENT, BUTTERFLY VALVES 22A1132AE .......... CONTAINMENT ISOLATION SYSTEM FROM FCV-64-141 AND 22A1169 .. , ......... DESIGN SPECIFICATION FOR REACTOR CONTAINMENT DRYWELL COMPRESSOR 3-730E927-17 ....... PRIMARY CONTROL ISOLATION SYSTEM 3-730E927-16 ....... PRIMARY CONTAINMENT ISOLATION SYSTEM 3-47E610-64-2,F5
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AMENDMENT 28 3-47E3847-8,A4 3-47E610-84-1,C7 " .... J
~
~
QD-3 0
~ ~ ' POWERHOUSE 1~3--_*s_E_s_,._-_s_~r_, 3-47E610-64-3,84 HARDENED SUPPR 64-21 UNIT 3 CHBR VENT 'Y' FCV (FSV-64-221. 222)
I ~~ 64-21
}i!'____~~
I I L ____ .J L--4------...::1::.._______J I BROWNS FERRY NUCLEAR PLANT
.....,_ ___..r .J I I1----
0 COMPANION DRAWINGS: 1-47E610-64-1, -2 & -3 2-47E610-64-1. -2 & -3 FINAL SAFETY ANALYSIS REPORT ROOM AIR 3-47E610-64-2 & -3 TO fCV-64-141 AND PRIMARY CONTAINMENT SYSTEM A DRYWELL COMPRESSOR 3-47E610-64-2,F2 MECHANICAL CONTROL DIAGRAM FIGURE 5.2-2a SH 3 8 7 6 5 4 3
H G rn,***.,m...,.,,...................... D--"-**-* t . . . . - ... D
! l I x
- f~~. ... C L-j,l'!
f--@-, 1 ____
©~*
1 _____ _ B AMENDMENT 22 UNIT:! BROWNS F'ERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT PRIMARY CONTAINMENT SYSTEM A MECHANICAL CONTROL DI AGRAM F'IGURE 5. 2-2b 8 6 5
llO~ £-t9-0 ~93Lt-Z V'-1 L9 INTEGRATED LEAK RATE TEST ELEMENTS (SEE 0-471600-122 FOR GENERAL PLANT LOCATIONS) r-----------------------------------------------1 H (TE\ (TE\ (TE\ (TE\ 64-83 64-86 64-85 64-84 El 625'-0" (TE\ (TE\ (TE\ (TE\ (TE\ (TE\ (TE\ 64-91 6... -87 64-88 64-92 64-93 64-89 64-94 EL 584'-0" G TORUS PENETRATION (TYP)7 DIVISION I X-234A TW 64--161 TE 64--161A , -
-@1A _ j ___ 9...5 7 - - - - - - - - - - - 7 9-87 EL 562'-0" r-----------J L-~,--, I I ~
I 9--87 ~A, I ~ (TE\ (TE\ (TE\ (TE\ I x--2348 n 64-161 TE -----~--r----- 1I ----1-------- 64-161 B I ~B 9-87 I 9-87 7 1 I I 9-3 64--95 64-97 64-98 64-96 r1 ___________ J L _ _/rs\___',-4 1--~M 1 1 r_.J ___ __/T!\ I I X--234C TW TE _/TM\_' 64--161 64--16.-cT-~c-r--- 9--87 L------------J 9... 87 ~* I L _ _/rs\___'_
- ------r-- I I
64--161J 1----, I I I I I L I I CH 1 I L -, CH-,-----,
~61 I 9--87 ~c' I --,-----, I i x--2,40 TW TE - - - - - ~ - - r - - - - - i1 ___ J.... __ i __ _, L---1--fl:!....~-----,_' i I 64--161D 64--1610 I ~D 9--87 ~ 8 7 '------1 CH 4 ---- 9--3 L__________________ \
PRIMARY CONTAINMENT __________________________ J F 1------------J L _ ~ s ...J TM -------t.£H_9___ TR ro rcs 2--45E614-21 I 1 X--234E n TE 64--161 64--161E I
-@ TM 9-87 64--161E 64-161D7
- - r - - - - ----,..--- 1__ ....,
9--87 I I 64-161L
,-----1--------
CH 5 r - - cH- s- - _/, 1 64-161
...LSEE NOTE 3 1 ___________ J L _ _/rs\___',-4 I I I 1 --1 ~~ : __ ...J I r
i x--,,., n 9--87 ~EI TE - - - - - ~ - - r - - - - - i -----+---1 ___ ...J i i I I I I ,-1------__J
, --@9--87 r------------------ ----------------------------1 I 64-161F 64-161f 1 ~F 9-87 I ~-87 '------ TM I EL 540'--D" I
!. J L ~ I I- TM I I I 64--161M I --x--234;----;;-- ~87 -~,i I - 64--161K JI : I 9--87 I
I I
------------------------- I I
I 64--1610,-~c-r--- 9--811 - - - - t - - - - - - - - 1 ,.. _____ .../TS'C_ 1 I I
/TE\
64-100
/TE\
64-101
/TE\
64-104
/TE\
64-105
/TE\
64-103
/TE\
64-102 I I t------------J L _ _/rs\___'_j I I I ~ J 71 9-87 ~GT I I I 1 1 TE __ 1 _...6iu:: __ r _____ 1 ____ L ________ _J ,L frst.87 1 64-161H ~H 9-871 -----~-..J I I l>--45E664--2 ~_J ____________ J L_ @61H--t--------------, 64--161K I IL_______________________________________________ TORUS J I I 9--87 I E
@,J 24VDC POWER SUPPLY FOR ALL -161 LOOP INSTRUMENTS NOTES:
- 1. FOR GENERAL NOTES AND REFERENCE DRAWINGS SEE 2-47E610-64-1.
- 2. ALL INSTRUMENT TAG NUMBERS FOR DIVISION I ARE 161 AND DIVISION II ARE 162.
- 3. TEMPERATURE ELEMENTS UTILIZED FOR LEAK TESTING DATA ARE INSTALLED IN THE PLANT AND ARE NORMALLY NOT ELECTRICALLY CONNECTED. THESE TE'S WILL BE CONNECTED TO PORTABLE INSTRUMENTATION AS NECESSARY FOR LEAK RATE OR MISCELLANEOUS r----- TESTING.
- 4. ALL INSTRU~NT TAG NUMBERS ARE PREFIXED *2*.
1 5. INDICATING LIGHTS AND HANDSWITCHES LOCATED ON 2-9-3 MIMIC SUPPRESSION POOL DISPLAY. I AVERAGE TEMPERATURE I REFLASH: HI 6. STRAP ON T/C DUAL ELEMENT TEMPERATURE SENSOR. HI-HI 7. TIC-64-60 ONLY RECEIVES INPUT FROM TE-64-60A. CABLE FROM I HI-HI-HI TE-64-608 IS SPARED AND ISOLATED IN LPNL-925-236. DIVISION II f--------f--rl"-,j
~-2--_4_5E_6_6_4--_2_~~r----------7 I 9--88 REFERENCE DRAWINGS:
I : 9--88 t------ @62M 2-45E2690-41 .... ICS BLOCK DIAGRAM 2-45E614-21 ..... RECORDER SCHEMATIC DIAGRAM 1 x--2,sA n 64-162 TE 64-162A
--~-~--r---------i------------7
~A 9-88 I L--- - -@,-a TI 2--45E664--2 .... .. WIRING DIAGRAM D
rl __________ 7 9--88 L-~r,
~A I
I I I I I I 6<--162 BAILEY CONTROLS COMPANY - TVA CONTRACT 82PJJ-830911: 0566641 ......... ANALOG LOGIC i I x--,,,.64--162n TE __ .J._...6iu:: __ 64--162s ~* r----- 9--88 1 -----+-----------7 I 9--88 I i I I I L------~ 08083601 ........ CABINET ARRANGEMENT J-08083602 ...... SCHEMATIC 08083603 ........ SCHEMATIC
~
I I D8083604 ........ POWER DISTRIBUTION t----------7 9--88 L_ @62s-f i-~62J I I 08083605 ........ EXTERNAL CONNECTION DIAGRAM I 080B3606 ........ EXTERNAL CONNECTION DIAGRAM i x--,,sc n TE --.l.-~--r-----1-------1------7 i i1 I EJ053355 ........ CABINET ASSEMBLY ARRANGEMENT 1 64-162 64-162C ~c 9_88 1 1 I r---------- 1 L_~,-4 : I I CH I I L_ ca,---7 1 GENERAL ELECTRIC - TVA CONTRACT 90744 2-791E4B9 ....... PNL 2-9-3 CONNECTION DIAGRAM I x--235D ~ 9-- 88 ~c I I I L __ - - - - - - 7 I n TE __ .J._ TM --r----- 1___ _J ,....- 1----7... L ___ _ _I_Cjj_;!_ ______ \ I 64--162 64--1620 64--1620 9--88 I I (¢.;-t88 ____ _ f-----------7 1 x--2,sE n 9--88 L_ @620--t-- ____ J ~ , - - - - - - - - - TE - - . l . - ~ - - r - - - - - i1 - - - - - - - - i ____ __r----- __ .£.H_J; _ _ .../ I
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I_ !.!J .i - ----~--, TR CH 5 _,,,,.. 64-162 1 64--162 64--162E ~E 9--88 I r - - - - __ Q!L __ _, I 1------------7 L_~_J I I I ,1 - - __ CH 8_ _ _ _ J 1 9--88 ~E7 I I I I i x--,,,, n TE __ .J. _ _!rii"C __ r - - - - - i -----+--- i ______ _J , 64--162F 64--162F ~F 9--88 I I ~-88 I i I C I ----------7
,.. L-~,-4 1-- TM I 1 SUPPRESSION POOL EL 741 '-6" HCVS PIPE
~F I I I I I X--235G TW TE .J. _lrii"C 9-88 64-1621(
_M' . . 3 SINGLE ELEMENT HI 1 64--162 64--1620- - ~ c - r - - s s :----,-----------...1 1 r-----~6** OR ELEMENT FAILURE L __________ l L_~,.... I I I 9--3 9-88 ~G I I x--2,sH n 64-162 TE 64-162H __ .J. _ _!rii"C __ r _____ 1
~H 9-88 1
---~------------_J 1 I ,-----t------1 2--45E614--6f----7 LPNL-925-236 L_@62sr------------------~ I I .,. I
~OTES I ~~ I El 666.5' I NOTES I I
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~
64-222
~~ iUl I r-1 ,.-a,-...- ABANDONED IN PLACE INSTRUMENTS NOTE 5 ---""',
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I TE 64-60 TE 64-608 8 ~ ,---,.------'-"----' SUPPRESSION POOL TEMPERATURE MONITORING SYSTEM 2-47E2847-10 PLANT STM:IC B AMENDMENT 27 _1_9--4
...l.1i::i 6~1/222 POWERHOUSE UNIT 2 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT PRIMARY CONTAINMENT SYSTEM A Cot.f'ANION DRAWINGS:
1-47E610-64-1,-2 &. -3 2-47E610-64-1,-2 3-47E610-64-1,-2 &. -3 MECHANICAL CONTROL DIAGRAM DET 2A3 UNIT 2 HARDENED WETWELL VENT (2-47E610-64-1) FIGURE 5.2-2c 8 7 6 5 3
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BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT TIAlSINEflOOM-E)Q-JAIJS.fFAltS"-J A PRIWIRY CONTAINMENT.SYSTEM MECHANICAL CONTROL DIAGRAM FIGURE 5.2-2d 8 7 6 5 3 f
8 lO~ £-t9-0 (93Lt-£ ~ LS H DIVISION I r TORUS PENETRATION (TYP) 9-87 X-234A TW TE --T- --r---------r------------7 64-161 64-161A A 9-87 r __________ j 9-81 L_ @8,.-, : : ~ I X-2348 TW TE --6iiS::- I -+-- 8 l j_ e+-101 64-1610-1-~s-r- @-8~ - - - I - ~ - 87 -----7 : 9-3 _ _ _ _ _ _ _ _ _ _ ...J 9_87 - s4-1s1e7 +-- s4-1s1J I I r - - L - - @s,
- x-234C TW TE - - T - ~ - - r _____ 1 ___ __L __ 1 - - - - - - 7 i i1 i1 s4-1s1 64-1s1c ~c 9 _87 1
- I r-----------------------------------------7
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~7J 24VDC POWER SUPPLY FOR ALL - 161 LOOP INSTRUMENTS r----- PRIMARY CONTAINMENT 1 SUPPRESSION POOL L-----------,-- _________________________ J AVERAGE TEMPERATURE I REFLASH: HI HI-HI "-SEE NOTE 4 I HI-HI-HI NOTES:
I 1. FOR GENERAL NOTES AND REFERENCE DRAWINGS DIVISION II t ----- --t--.l-",-l, INTEGRATED LEAK RATE TEST ELEMENTS SEE 3-47E61D-64-1.
- 2. ALL INSTRUMENT TAG NUMBERS FOR DIVISION I ARE 161 AND DIVISION II ARE 162 E I3-45E664-3, 810 ~r----------, I a-88 (SEE 0-47W600-122 FOR GENERAL PLANT LOCATIONS) 3. DELETED
- 4. TEMPERATURE ELEMENTS UTILIZED FOR LEAK TESTING DATA ARE INSTALLED IN THE PLANT AND ARE NORMALLY NOT ELECTRICALLY
~-----~ I : 9-88 f------~62M CONNECTED. THESE TEs WILL BE CONNECTED TO PORTABLE 23
- _1i~ 6!
- 162,-~- @ 6 2 A - - r - - 8 - . - - - - r - - - - - - - - - - - - 7 L -@.- 3 INSTRUMENTATION AS NECESSARY FOR LEAK RATE OR MISCELLANEOUS TESTING.
t ----------7 -~
- 5. STRAP ON T/C DUAL ELEMENT TEMPERATURE SENSOR.
L I I - - - , - - 6!~162 6. TIC-64-60 ONLY RECEIVES INPUT FROM TE-64-60A. CABLE FROM TE-64-608 9-88 TS 64-162A n I I I I I I IS SPARED ANO ISOLATED IN LPNL-925-236. i x-2358 Tw TE __ J._--6ii'S::- __ r - - - - ---+-------------, i i L J:JJi<D REFERENCE DRAWINGS: I 64-162 64-1628 ~8 9-ss I 9 _ 88 I I ------~ 3-45E614-21 ..... RECORDER SCHEMATIC DIAGRAM l------------7 L_~_j t--~ I I I 3-45E664-3 ...... WIRING DIAGRAM - TORUS TEMPERATURE I 9-8s ~87 I ~ 62J I MONITORING SYSTEM SCHEMATIC DIAGRAM I X-235C TW TE __ J._--6ii'S::- __ T _____ 1 ___ --r---1------7 I : I SH-3 3-45E3690-41 .... ICS BLOCK DIAGRAM 64-162 64-162C ~C 9-88 I I L ~,...J I I I I L __ l_cHN!,_L _ _ 0-47W600-122 .... MECHANICAL INSTRUMENTS AND CONTROLS r----------7 9-88 -~c I I I I L _ _ _ I_CHN.b,.L_, 7 3-791E490-2 ..... PNL 3-9-3 CONNECTION DIAGRAM I TE __ J._--6ii'S::- __ r - - - - - 1 _ _ _ _1 , - - - - , L _____ 1_cHN!,_3______ , 1 64-162D ~D 9-881 1 ~-88 L._ _ _ _ _ _ _ I_CHt!b...i.-..,~-3 L __________ 7 L_~s ;;-----J T" _ _ _ _ _ _ _ _ _ _ _J_<;!!N.b..!!.._ TR f X-235E rw TE I
-@ TM 9-88 64-1 2D I
- - r - - - - - - , - - 1 ____
64-162L _ r - - - - - _ _ _ _ _ _,,, CHNL 5 CHNL 6 ../, 64-162 BAILEY CONTROLS CCJ.lPANY - TVA CONTRACT 82PJ3-830911: 0566641 .... ANALOG LOGIC D I 64-162 64-162E 64-162E 9-ss r---- ------ _ _ CHN.1..L_..J 1 D8083601 ... CABINET ARRANGEMENT 08083602 ... SCHEMATIC r----------7 9-88 L_ @62(~ : : : ,-, __ .f.H.fil...§ _ _ _ J HCVS PIPE EL 741 '-6* 08083603 ... SCHE*ATIC 08083604 ... POWER DISTRIBUTION i x-23s, Tw TE --.l.-~--r----- i ----'--- i _ _ _ _ _ _ _J i i 08083605 ... EXTERNAL CONNECTION DIAGRAM 64-162f 64-162F ~F 9-88 I I ~-88 I I D8083606 ... EXTERNAL CONNECTION DIAGRAM I
,- ----------7 9-88 L-~~
~F I
+--
I T* 64-162K I I I I 9 3 SUPPRESSION POOL SINGLE ELEMENT HI 1 -----,-7 3-45E614-6f- (n\,9-3 64-60 E3053355 ... CABINET ASSEMBLY ARRANGEMENT I X-235G TW TE ~ l I y I 64-162 I 64-162G_..,_~c-r-----88 :----,-.----------_J I t-----~628
~- OR ELEMENT FAILURE I I
~NL-925-236 L __________ 7 L_~,.... II I II I I 9-88 ~G 1 ~OTE 10 : 64-60 X-235H TW TE __ j__~--r----- II _ _ _ _j _____________ _j I y EL 666.5' 64-162 64-162H ~H 9-88 I ~' I 1...!iOTES 5 & 6 L-@s2sf-------------------J )'o{___; ~ I -7 r-l>----ABANDONED
~~
~-, 64-222 IN PLACE I
@:BJ 24VDC POWER SUPPLY
~ : T E 10 64-60A 64-608 C
FOR ALL - 162 LOOP INSTRUMENTS 3-47E3847-10 FROM SHV-32-2704
>----------e~:i.,,,_. 64~
FCV T1
-- X SUPPRESSION POOL TEMPERATURE MONITORING SYSTEM ~--ili~o-;,~;------~
r-----r--i 3-45E614-sl I I I I I "' I I I ~ ~ I NOTE 10 I ~ ~ I I ~ j. I ~-4
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----------11~::1,t,>W FCV 64-221 T1
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3-47E610-64-1,C6 AMENDMENT 28 DET 3A3 POWERHOUSE UNIT 3 HARDENED CONTAINMENT VENT (3-47E610-64-1) UNIT 3 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT COMPANION DRAWINGS: 1-47E610-64-1, -2 & -3 2-47E610-64-1, -2 & -3 PRIMARY CONTAINMENT SYSTEM A 3-47E610-64-1 & -2 MECHANICAL CONTROL DIAGRAM FIGURE 5.2-2e 8 7 6 5 3
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H B AMENDMENT 22 POWERHOUSE UNIT 1 r--- 1-~ BROWNS FERRY NUCLEAR PLANT I L~ BROWNS FINAL FERRY FINAL NUCLEAR SAFETYANALYSIS SAFETY PLANT ANALYSIS REPORT REPORT
- ... * -1,i.&LU. -*
PRIMARY CONTAINMENT SYSTEM
......-! 0 0 PRIMARY MECHANICAL MECHANICAL CONTAINMENT SYSTEM CONTROL DIAGRAM CONTROL DIAGRAM A
~: ~"::.J5 ... FIGURE5.2-2f flGURE 5.2-2f o............,... ;,.J
H G TORUS PENETRATION (TYP)7 X-2J4A TW TE __r;:;;-c 9-87 DIVISION I 64-161 64-161T1-~1,-j---*-B1----7---------7 r ___________ J L-~~
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, x 234C n TE --.--~--r-----1-----+--- ,----, , , ,
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..fHN!,_L_ +-- ~ LOG I _o;:;-t 87 1
_J_ 1 I 1 L _ _ _ I _sHN!,_3_ """"\ I F I X-234D TW 64-161D L ___________ J TE 64-161°01-~ -r--- L_~_J 1 9-871 _ _ _ - ~ - . -77L ____ T* i CHNL 4 . : : : : ~ \9-3
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, x-23+* n TE - - - . - - ~ - - r - - - - - , -----+---' ___ _J , , , -@9-87 64-161F 64-161F 1 ~F 9-871 I ~-87 ~----- TM NOTES:
L ~ I t----------- 1 x-23+G n TE J 9-87 -~,""1 i-
- - - . - - ~ - - r - - - - - 1 _ _ _ _ _ _ _ _ _ _ _ _ _J 1 T*
64-161K I I I I I I 6+-161*
-@,9-87
- 1. FOR GENERAL NOTES AND REFERENCE DRAWINGS SEE 1-... 7E61D-6 ... -1.
2, ALL INSTRUMENT TAG NUMBERS FOR DIVISION I ARE 161 AND DIVISION II ARE 162 1 3. ALL INSTRUMENTS ARE PREFIXED WITH A UNIT 1 (1-) UNLESS OTHERWISE NOTED, I 64-161 64-161G 1 ~G 9-87 1 I I r------ TS _ 4. STRAP ON T/C DUAL ELEMENT TEMPERATURE SENSOR. L ___________ J L_~_J 1 1 1 I 6+-161J 71 J 9-87 ~G J I REFERENCE DRAWINGS: 1 x-23+H n TE ----~--r-----' ----L--------_J 1L __/rs'\"_87 1 I 64-161 64-161H 1 ~H 9-871 -----~- BAILEY CONTROLS CCMPANY - TVA CONTRACT 82PJ3-830911: I1-+sE66+-1,a+~-j _ _ _ _ _ _ _ _ _ _ _ _ J L_ {rlys1Hi---------------, 64 - 161 < I D566641, ........ ANALOG LOGIC D8083601 ........ CABINET ARRANGEt.ENT D8083602 ........ SCHEMATIC E DIVISION II 9-87 _J I 24VDC POWER SUPPLY r----- I
~~ II D8083603 ........ SCHEMATIC D8083604 ........ POWER DISTRIBUTION D8083605 ........ EXTERNAL CONNECTION DIAGRAM D8083606 ........ EXTERNAL CONNECTION DIAGRAM FOR ALL -161 LOOP 9-J I SUPPRESSION POOL AVERAGE TEMPERATURE E3053355 ........ CABINET ASSEMBLY ARRANGEMENT I1-45E664-1, INSTRUMENTS I I
TA 64-162A _j REFLASH: HI HI-HI HI-HI-HI I I r----- TS 64-162K I 9-88 t------@62M I 9-3 f----,--@s2 I I iLOOl I CHNL , L - - - - - ~
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~
LNOTE 4 INSTRUMENTS
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~ ~ -3 64-222 ;:;:; Ul 2
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1-47E1847-13, D3 ABANDONED PLANT STACK IN PLACE FROM SHV-32-2704 2721 TT II
,---,----------------U ili ~
B AMENDMENT 27 POWERHOUSE UNIT 1 1-47E1847-13, EJ FCV - X FROM SHV-32-2703 TT 2720 s4.::31 II BROWNS FERRY NUCLEAR PLANT
,---,----------------U FINAL SAFETY ANALYSIS REPORT ili ~ 9-3 COMPANION DRAWINGS:
1-47E610-64-1,-2 PRIMARY CONTAINMENT SYSTEM A 1-47E610-64-1.C6 2-47E610-64-1, -2 & -3 3-47E610-64-1. -2 & -3 MECHANICAL CONTROL DIAGRAM FIGURE 5.2-2g 8 7 6 5 3
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AMENDMENT 16 BROWNS FERRYNUCLEAR BROWN,J FERRY NUCLEARPLANT PLANT FINAL SAFETY FINAL SAFETY ANALYSIS REPORT ANALYSIS REPORT Types of Penetrations for Process Lines Types t)f Penetrations for Procea Linet FIGURE FICURE5.2-35.2-3
11_.CAI. IIIIIUI - APIUIUU PUNMI! a.,AllltalT-
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AMENDMENT 16 BRO!,MS FERRY NUCLEAR PLANT FIN~J.. SAFETY ANALYSIS REPORT \ .. hnitra'lkm .Ammbly fol' Proc:ea Lines FIGURE&2-4
i" e ASTH A5I,, (iRADE ' B.ROWNS BROWNS FERRY FERRYNUCI..EAR NUCLEAR FINAL SAFET"* ANALVSIS REPORT PLANTPLANT
-.2.9M FINAL SAFETY ANALYSIS REPORT " DE.TAIL £. 134 314 '
Compression Fitting Assellbly forCompression 5111all, LowFitting PnssureAssembly 8
.SCAI-£: 2.,.
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- Line Small, Low Pressure Line Penetrations FIGURE 5.2-4a FIGURE 5,2-4a AMENDMENT 16
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' FINAL SAfETY ANALYSIS ~EPORT ELEffltCAL AND CORTllOL P~~TION FICUIE s.2-s AMENDMENT 16
BFN-28 Figures 5.2-5b through 5.2-5e Deleted
z:z;o~ t-9L-O !93Lt- I 11',J L9 NOTES,
- 1. THE OBJECTIVES OF THE CONTAINMENT INERTING SYSTEM ARE TO MAINTAIN THE TOTAL OXYGEN CONTENT OF THE PRIMARY CONTAINMENT BELOW 4.91 AND TO PROVIDE A LEAK RATE MONITORING SYSTEM FOR DETECTION OF GROSS LEAKS IN THE CONTAINMENT VESSEL. THE FLOW RATE OF NITROGEN ENTERING THE PRIMARY CONTAINMENT IS MONITORED BY FR/PR-76-14 ANO BY FA-76-16. EXCESSIVE FLOW INDICATES A GROSS PRIMARY CONTAINMENT LEAK.
- 2. THE ATMOSPHERE OF THE PRIMARY CONTAINMENT SHALL BE MAINTAINED AT A POSITIVE PRESSURE BY THE NITROGEN MAKEUP H
EQUIPMENT DURING NORMAL PLANT OPERATION AND DURING PERIODS OF SHUTDOWN WHEN ACCESS TO THE PRIMARY CONTAINMENT IS NOT REQUIRED. PRIMARY CONTAINMENT PRESSURE IS SENSED BY PT-76-14 AND CONTROLLED BY PC-76-14.
- 3. THE PRIMARY CONTAINMENT MAY BE PURGED WITH NITROGEN GAS FOR INERTING THE ATMOSPHERE FOR NUCLEAR BOILER OPERATION. OR BY AIR FROM THE REACTOR BUILDING VENTILATION SYSTEM FOR OCCUPATION BY PERSONNEL.
- 4. EXHAUSTING OF THE PRIMARY CONTAINMENT IS NORMALLY ACCOMPLISHED BY ROUTING THE GASES THROUGH THE REACTOR UNIT 1 SECONDARY CONTAINMENT YARD BUILDING VENTILATION SYSTEM. IN CASE OF HIGH RADIATION, THESE GASES SHALL BE ROUTED THROUGH THE STANDBY GAS TREATMENT SYSTEM. (SEE 0-47E610-65-1 .)
- 5. YARD NITROGEN SUPPLY EQUIPMENT IS Cotv'MON TO ALL THREE UNITS.
- 6. THE OXYGEN AND HYDROGEN MONITORING SYSTEM CONSISTS OF
-47E610-64-1, D4
@-18 TWO SEISMICALLY QUALIFIED. REDUNDANT SYSTEMS. THE OXYGEN MONITORS ARE USED DURING NORMAL PLANT OPERATION IN CONJUNCTION WITH THE INERTING SYSTEM. IN THE EVENT OF A LOSS OF COOLANT ACCIDENT, THE OXYGEN AND HYDROGEN MONITORS y ARE USED WITH THE CONTAIJIIJENT ATh,OSPHERE DILUTION SYSTEM.
(SEE 1-47E610-84-1.l PT --------------..l..----- @-3 25-6 1 1 ~~ 4 I -4 PC ____ ~ PM fHE SYSTEM CAN RECD~ CONTINUOUSLY OR CAN BE PLACED IN STANDBY. IN THE STANDBY MOOE THE SYSTEM IS STARTED AUTOMATICALLY BY AN INTERLOCK WITH THE CORE SPRAY SYSTEM IN THE EVENT Of AN ACCIDENT SIGNAL. G 76-14 .,...1..... 19
- 76-1
,___.. 76-14 7. AN INDICATING RECORDER. 02R-76-39. 41 IS SUPPLIED TO RECORD THE ANALYZER MEASUREMENTS IN THE CONTROL ROOM. A LO~~~ 9-3@ ~ -J REMOTE OXYGEN INDICATOR, C>iI-76-39, IS MOUNTED AT THE ENTRANCE OF THE DRYWELL TO INDICATE THE OXYGEN CONTENT OF THE DRYWELL ATMOSPHERE TO PERSONNEL BEFORE THEY ENTER.
HS7i"8 ~~ ,___..-,~ - i i i I 8. SEE 45N1631-24 FOR CONNECTION TO SPARE SENSORS.
-r--m l,~-~~-JL 7~~6 r----------
- 9. ALL INSTRUMENTS ARE PREFIXED "1-* UNLESS NOTED OTHERWISE.
$ L ICI;SSI 8
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~
1 I 'Tr' PCV L_-rn-ISS ~ O G 10. 11. ALL NUMBERED MANUAL VALVES ARE PREFIXED *1-76-* UNLESS NOTED OTHERWISE. UNIDS ON DRAWING ARE FOR REFERENCE ONLY AND ARE ABBREVIATED TO MEET SPACE CONSTRAINTS, REFER TO MEL FOR COMPLETE UNIDS. I ' TI \ 76-14 A 76 FROM CONTAINMENT INERTING 1-47E1847-8, GB 7 I 1 76-15 NITROGEN MAKEUP SUPPLY II FE ............__76-15 76-16_ TW '-1'""---~f,----TT-----+-----< 0-47[610-76-1, 11 PI _I-,~~ II 76-50 X REFERENCE DRAWINGS: I 16- ------ II ---- DRYG-76-1 ------ l 539 I MEL ................... CONTAitlvlENT INERTING SYSTEM INSTRl..t.tENT TABULATION X-518
,----f--3'§t ~*-3 0-47E610-12-1 ......... MECHANICAL CONTROL DIAGRAM-AUXILIARY BOILER SYSTEM SHV-76-538 CONN FOR PORTABLE N2 II I
L~ 16-~1
+:'.---------
_J _ ~------- fil~ CISS A LOC HS7617 1-47E610-64-1 ......... MECHANICAL CONTROL DIAGRAM-PRIMARY CONTAINMENT SYSTEM 1-47E860-1 ............ CONTAINMENT INERTING SYSTEM FLOW DIAGRAM 471600-134 ............ CONTAINMENT INERTING INSTR. AND F X-468 fFSV)... _ _ -1 1-730E927RE-16 C71 BOTTLE I CONTROLS DIAGRAM X-52-2C 76-17 7 * .
~~
CKV-76-551 CKV-76-552 I I PURGE AIR SUPPLY FROM REACTOR BUILDING
--r-m~L 0-47E800-1 ............ FLOW DIAGRAM-GENERAL PLANT SYSTEMS 0-47E800-2 ............ MECHANICAL SYMBOLS AND FLOW DIAGRAM DRAWING INDEX 1-47E610-84-1 ......... MECHANICAL CONTROL DIAGRAM-CONTAINMENT I
TO ORYWELL CONTROL AIR VENTILATION SYSTEM L ~~ ATMOSPHERE DILUTION SYSTEM 1-47E600-14 ~ 15 ...... MECHANICAL INSTRUMENTS AND CONTROLS FI 76-502
,...;.l_ _ _ _ _ __,__-<,-41Es10-s4-1 as ---cIT~ 0-47E610-65-1 ......... MECHANICAL CONTROL DIAGRAM STANDBY GAS TREATMENT SYSTEM 1-45E615 SERIES ....... CONTAINMENT ISOLATION STATUS SYSTEM (CISS)
I~ I~
+-3§:( 9-3 I
MIMIC 9-3 I 00 I :::ro< 76 - 24
~
TO HS-64-25 iJB.I. 'f---<1-47E610-64-1 E7) GE DRAWINGS: I ,----------- ----~~ 1 I ---cIT~ 22A1209AB ............. ATMOSPHERIC CONTROL SYSTEM DESIGN SPECIF I CATION X-35F I 21A1375 ............... PRIMARY CONTAINMENT OXYGEN ANALYZER SYSTEM BASE SPECIFICATION I 21A1370 ............... MISCELLANEOUS VALVES FOR ATMOSPHERIC I CONTROL SYSTEM, PURCHASE SPECIFICATION 1-730E927-16A,-17A .... PRIMARY CONTAINMENT ISOLATION SYSTEM E X-46A TO INDEXING MECHANISMS 1-47[600-14 ~ 15 X I L - - - ~ __ _J (FCV', 76-24 *f 9-3 MIMIC
.J FROM CONTAINMENT INERTING NITROGEN PURGE SUPPLY SYMBOLS:
-I I I-X Q------6-2.J-J TW ....---'. J-1-'-----1 / - - -- 0-47E610-76-1, J1 NITROGEN CONTROL GAS SUPPLY LINES.
6~~r. ~ PRIMARY X CONTAINMENT L_ ~ 1-730E927-17A, 18
~@9-3 X ------
X-51A : 1'.--~-----
~I
-m IH~~.1 I ~nrt,..,
I DRYWELL I MIMIC (FCv', PERSONNEL BLOWERS I I
~---~=:::::.-=. G 1s-1s ~ f 9-3 D
-,--~~L R
AIR LOCK TORUS H20 2SAMPLE i I
"'"1 1-730E927-17A, 7 X
I L_.J.. ~~ 1-47E610-76-3,J1 SUPPRESSION CHAMBER L Jc:iill_~ m~ DRYWELL DRYWELL H202SAMPLE 1-47E1610-76-3.(F8) H202SAMPLE RETURN _ _,__ _ _ _ 1-47E610-76-3,I1 C B AMENDMENT 27 POWERHOUSE & YARD UNITS 1 & 0 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT COMPANION DRAWINGS: 0-47E610-76-1 2-47E610-76-1,-4 CONTAINMENT INERTING SYSTEM A 3-47[610-76-1 -4 1-47E1610-76-j 2-47[2610-76-3 3-47E3610-76-3 MECHANICAL CONTROL DIAGRAM FIGURE 5.2-6a SH 1 8 7 6 5 3
CLO~ t,-9L-0 L93Ll>-Z ~ L9 H G D C B AMENDMENT 24 PO\IERHOUSE UNIT2 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT CONTAINMENT INERTING SYSTEM A MECHANICAL CONTROL DIAGRAM FIGURE 5. 2-6a SH 2 8
L-9£-0l93Ltr-f i,,. L9 I ,,.,. '""~, " __ J
-iii
~
D C 8 AMENDMENT 24 POWERHOUSE UNl13 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT CONTAINMENT INERTING SYSTEM A MECHANICAL CONTROL DIAGRAM FIGURE 5.2-6a SH 4
AMENDMENT 24 PO\IERHOUSE UNIT3 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT CONTAINMENT INERTING SYSTEM MECHANICAL CONTROL DIAGRAM FIGURE 5.2-6a SH 5
H ~ ~ ~ I ~,_,,: @,_,, I i&'" L_JL ____ L_'Y
,_,.w:
L_J i ____ _J G Y'
.@-1~-F=~-~:'~'-~l Wffi--jI :'
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,@,c.:S'OC""""
,,::*,,.'""-***@--co
*- ,,,'"" _,,, @- - co D
*-',,,"'""""' @--co C
B AMENDMENT 24 P0\IERH0US[ UNIT1 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT CONTAINMENT INERTING SYSTEM A t.1ECHANJCAL CONTROL DIAGRAM FIGURE S.2-60 SH 7 8
l-09-0193Lt-lV<L9 AMENDMENT 25 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT
LlOiJ l-08-0l93Lt-Z Vil L9 NOTES:
- 1. FDR SYSTEM OPERATION REFER TO MECHANICAL FLOW DIAGRAMS, SCHEMATIC DIAGRAMS, REFERENCE DRAWINGS, SYSTEM OPERATING INSTRUCTIONS AND RESTART DESIGN CRITERIA.
- 2. FOR INSTRUMENT SETPOINTS REFER TO INSTRUMENT TABULATIONS AND NUCLEAR ENGINEERING SCALING AND SETPOINT DOCUMENT MANUAL.
- 3. ALL COMPONENTS SHOWN HAVE UNIT PREFIX 2- UNLESS NOTED OTHERWISE. H
- 4. NOZZLES N4D AND N4C (SHOWN) ARE OPPOSITE N4F AND N4A RESPECTIVELY ON THE VESSEL. THERMOCOUPLE ARRANGEMENTS ARE SIMILAR TE-3-238F1, -2,
-3, -4 ON N4F AND TE-3-238A1, -2, -3 ~ -4 ON N4A. THE EXACT ARRANGEMENT IS SHOWN ON 47W600-91.
- 5. INOPERATIVE (NOT IN SERVICE), EQUIPMENT ABANDONED IN PLACE.
6, DELETED.
- 7. UNIDS ON DRAWING ARE FOR REFERENCE ONLY AND ARE ABBREVIATED TO MEET SPACE CONSTRAINTS, REFER TO MEL FOR COMPLETE UNIDS.
(rr\_ _____________ 2~~~~. 8. DELETED. 80-27 (TE\ (TE\_ ___________ TR-80-1-28--J 80-26 80-28 I I REFERENCE DRAWINGS: TR-80-1-21 I
~------------""! 47W600-90 ................ INSTRUMENTS ANO CONTROLS 0-47E600-91 .............. INSTRUMENTS ANO CONTROLS
~ _ _ _ _ _ _ _ _TR-80-_t-22--: MEL ...................... INSTRUMENT TABULATION-TEMP MON SYS MEL ...................... INSTRUMENT TABULATION-PR! CNTMT CLG SYS 45N803-SERIES ............ CONDUIT AND GROUNDING DETAILS
{7E\_ _ - - - - !!-.!_Cl:.! :.!,3_ I 80-23 'II MEL ...................... INSTRUMENT TABULATION-REACTOR FEEDWATER SYSTEM 0-47E800-1 ............... FLOW DIAGRAM - GENERAL PLANT SYSTEMS G
~ -------""'1I TE (NOTE 5) 0-47EB00-2 ............... MECHANICAL SYMBOLS AND FLOW DIAGRAM
~
80-24
-- TE 80-25
_TR-80-..!._-25 l DRAWING INDEX 2-47E610-3-1 ............. CONTROL DIAGRAM - REACTOR FEEDWATER SYSTEM MEL ...................... INSTRUMENT TABULATION - REACTOR WATER RECIRCN SYS 45N2616-SERIES ........... WIRING DIAGRAMS, THERt.40COUPLES & RTDS I 45N2631-SERIES ........... WIRING DIAGRAMS, MISC. 45N2635-SERIES ........... WIRING DIAGRAMS, LOCAL INSTR. PANELS VESSEL HEAD 2-47E600-7DJ ............. INSTRUMENTS AND CONTROLS 2-47E610-90-1 ............ CONTROL DIAGRAM - RADIATION WNITORING 0-471600-110 ............. INSTRUMENTS AND CONTROLS I TE TR-68-37 /2 UPPER SUPPLY! 68-37B.,....IR-68-37 /1 ~ - 4 RING HEADER I
, ~ I TE '----' I TE 'ic REACTOR%"
VESSEL --l--468-37 A I
~=*~'~*~-~
25-397 r:::-...XR 56-12*~--....J TE _ SUPPLY DUCT I ( XK \ -- 8-7 TO UPPER AREA I 3-238 y l2-47E610-3-1.f6>-7 TE ---- sea ------ ~:--~-----------7 F t'----------- 'i' I
~I I
I I I
"--- TE I
I I 3-&E1 q;_ FW r-r-- ________i!:L _______________
"i' I I
I t-- ~* I 9-*1
-1 NI
'I' -I ' TE ---~:!!0.:.!~L-1 1
1 r---00 80-I @* 0 '
~I' ~ o1 80 17 9- 3 TE - TE __TR-80-..!_-.!!'~l 56-16 ~I r rJoi 80-19 I I "
y I I .._, TR-80-1-2o_J I 80-I I I ---- I I I ",~kl,.;%--- OLE-SUPPLY I L __ I ,. RING HEADER .,,--RETURN RING I
~80-10
_____ HEADER TR-80-1-1v!I TE 56-19 - - - - - - - - - TR-80-1-~I
.._, PUMP 80-16 MOTOR B - - _ _ _ _ _ _ _ _ _ _ TR-80-1-~ E TE _ _ _ _ _ _ _ _ _ _ _ _ _TR-80~~
56-22 TE COOLER A TR-80-1-~ 80-3 _________ COOLER B TR-80-1-5 .JI RECIRCN PUMP MOTOR ZCll Zill
=> -
A ORB ',--"--I "' --' "'
..-;==',--' zo
< 00 0
LL< U<C SUPPLY DUCT VESSEL MOUNTING FLANGE TE TABLE 1 u.....-----56-3
.._,8 TEMP ELEMENT LOG CONTROL ROD DRIVE HOUSING TE TE-56-13 A56013 A56014 D
TE-56-14 56-39 TE TE-56-15 A56015
- 40 DRAIN TO CRW
.._, TE-56-16 A56016 TE-56-7 A56007 TE-56-35 A56035 VESSEL TEMPERATURE MONITORING TE-56-8 A56008 TE-56-23 A56023 TE-56-26 A56026 TE-56-29 A56029 TE-56-10 A56010 PRIMARY CONTAINMENT ATMOSPHERIC MONITORING TE-56-5 A56005 TABLE 2 TEMP ELEMENT LOG TE-80-1 A80001 TE-80-2 TE-80-3 A80002 A80003 C
TE-80-4 A80004 TE-80-5 A80005 TE-80-6 A80006 TE-80-7 A80007 TE-80-8 A80008 TE-80-9 A80009 TE-80-10 A80010 TE-80-11 A80011 TE-80-12 A80012 TE-80-13 A80013 TE-80-14 A80014 TE-80-15 A80015 TE-80-16 A80016 TE-80-17 A80017 TE-80-18 A80018 TE-80-19 A80019 TE-80-20 A80020 TE-80-21 A80021 TE-80-22 A80022 TE-80-23 A80023 TE-80-25 TE-80-26 A80025 A80026 B TE-80-27 A80027 TE-80-28 A80028 TE-80-29 TE-80-30 TE-80-31 TE-80-32 A80029 A80030 A80031 A80032 AMENDMENT 26 POWERHOUSE UNIT 2 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT PRIMARY CONTAINMENT COOLING A TEMPERATURE MONITORING MECHANICAL CONTROL DIAGRAM FIGURE 5.2-6c 8 7 6 5 3
AMENDMENT 25 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT
Security-Related Information - Withhold Under 10 CFR 2.390 Figure 5.2-6e BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Drywell Pipe Whip Projection Figure No. 5.2-6e
VENT HE~D\:.R
+-------
45UPPRE.'SS\QN C~A.MEER AMENDMENT 16 BROWNs:>fERRY NUCLEAR PLANT
' FINAL SAFEtY lNALYSIS REPORT Dll'YVEl4. ;¥E1ff PIPE EXPANSION BELLOWS, FIGURE S. 2-fif
...-f\f:.l. L.O'N':i GUl\\<f, P\.f\l'E
.( ~ND TES, CO\rE..k
. 2"
~r-*------~
.GUILES
\JE.NT PIPE
~" SST 6ELL0W5
\J\E.W ~
AMENDMENT 16 BROWNS"f:ERRY NUCLEAR PLANT AFIN*AL SAFETY ti&ALYSIS REPORT Dnm.t 'Vi111T PIPE EXPANSION BEW>Q*ft~ A FIGURE S.*}Z-61
LZO~ l-Z983Lt- l ~ L9
,---------+1-47E865-1,E2 32-1206 FSV 64-34 ..,.
N rev FLOOR EL 621 STANDBY GAS TREATMENT BLDG ORV-360-720 0 m
"' H 84-19 FCV ~
z 64-34 RFV-360-712 r FE !,--.--,,.-------------1 2"
,----to*----.-.,,., < 84-19 * <
(PCV\ VALVE SET X N N
'r.-1 1--:-'i 360-700 AT 100 PSI T
m '\zONT ON s.r (1-47E865-1, C2) VALVE SET SHV-360-748 AT 150 PSI
"' PI 32-1254 360-752 1 PSIG MAX '--'
1-47E865-1,E3 CONTROL AIR SYS 1-FCV-84-34 r-1:-_---:4-:-7::-E1:-8:-4-:-7--7::-,--:D--:3---.. SEE DETAIL 1A1 CONTROL AIR SYS FOR FUNCTION (THIS DWG)
'r.-1 1--:-'i 1-PCV-84-33 CONT ON \XI G
-47E1847-7 .D SEE DETAIL 181 FOR FUNCTION *0 32-1282 (1-47E865-1, E3) y TRK-360-758 FLEX NITROGEN CART B1 CAD SYS (THIS DWG) 0
~ PCV (PEN X-50) DRYWELL 84-34 TO ORYWELL 1-FCV-64-29 1/4" CONT ON 1-47E1847-6,D3 1-47E865-1,EJ (1-47E1847-7,D3) lsHOWN FOR FUNCTION ONLY
-'r-t-, 84-32Tw_.----------------------, CAD SYS (PEN X-22)
TO DRYWELL DET 1A1 (THIS OWG, GS) 1/4mis DWG,G7) ORV-360-721 RFV-360-713 N 1-47E1847-6 (PCV\ VALVE SET DRYWELL (PEN X-25) 360-701 AT 100 PSI 1-FCV-64-18 '--' 2" 1-47E865-1, E3 1-47EB65-1. 85 TEST CONN 1JUi--+--....l-'---r'---'.;--'l"""f--r---l:Xx:J--l--+--+----ll<>II
- i 32-1205 SHV-360-717 VALVE SET SHV-360-750 SHV-360-751 rsv 84-48 S m
;:;' f--m AT 150 PSI PI 360-753
. 0 N TEST CONN TORUS (PEN X-205)
N m 0 F 1-FCV-64-19 3 4" H f-'> 0 m TEST 1/2" 1-47E865-1 , CS l-~~ s
~
z CONN ~CONT ON r 84-679 84-678 (1-47E865-1, C2) 2" TEST C ~ N N B (NOTE 7) 32-2570 TRK-360-759 FLEX NITROGEN CART B2 p I \--8r-4!)-067:J-7-A-l
- m 0
.N TEST CONN TEST CONN 7
84-51 ~ m 1/2" "m m 1 2"
- i' 1/2" 3/4" .,:_ N m 3/4" N m 84-619 84-618 VALVE SET O 110 PSI SUPPRESSION CHAMBER N m ;:;' N m
T m' m T m N m p I );--8r-4C-0 61::}6-A-,
"' FSV 3 4" ;:;' 3 84-50 1/2" 3/4"
~
J 84-19 CONT ON ( 1-47E865-1, m 32-1283 m N VALVE SET PCV o 110 PSI 84-33 2 1/2" CONT ON 1/4" 120 121 FLOOR EL 565 1 /2" N 0 m * (1-47E1847-7,D2) 'ri,.t:i:;f--__J E
~ VALVE SET SHOWN FOR 123 122 7 o 100 PSI FUNCTION ONLY m
2" " 0 0 DET 1Bl (THIS DWC,H7)'Y 601 (THIS DWG, GS) THV
- PRE 84-37 2 ~ 4-54 1/2" RTV- RTV-84-118A 84-119A 84-612 84-613 84-614 1" N
N 84-675 84-674 84-669 1" REACTOR BUILDING PCV 84-704 2" 2" 2" 84-706 3-47E862-1,D SHV-84-671 *N NOTES: 84-707
.,.ao 84-703 0
T 2"
....- - - . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . . . I L . . . - - - - - - - - - - - ' a . . . - - o j 3 _ 4 7 E a 6 2 - 1 ,07 2" 1. All INSTRUMENT/COMPONENT NUMBERS SHALL BE PREFIXED WITH THE "BFN-1" EXCEPI AS NOTED. UNIDS ON DRAWING ARE FOR REFERENCE m *N ONLY AND ARE ABBREVIATED TO MEET SPACE CONSTRAINTS, REFER TO PI MEL FOR COMPLETE UNIDS.
- 2. All VALVES ARE SAME SIZE AS PIPING UNLESS OTHERWISE NOTED.
D 84-708 2" .250" 1 2" 3. All PRESSURE AND TEST CONNECTIONS ARE 1/2" UNLESS OTHERWISE 0-RTV-84-105 NOTED. SHV-84-670 1/2" 4. OPERATIONAL VALVES ARE SHOWN IN THEIR NORMAL OPERATING 0-RTY-84-111 POSITION. 1/2" 5. m ETC, DENOTES ZONE FOR DESIGN PRESSURE AND TEMPERATURE
~ GIVEN IN TABLE, THIS DWG .
. 250" 1/2" 6. FOR FSV-84-5 AND -16 RELOCATION SEE VENDOR DIGS 0-27204, 0-27203
. 250" UNDER CONTRACT NUMBER 84939 .
o-r 1 2" 84-7 7. ZONE 8 IS QUALITY RELATEO. AND Will ONLY BE USED FOR FLEX 1/2" 0-RTV-84-110 NITROGEN CARTS. FLEX NITROGEN CARTS ARE NOT NORMALLY CONNECTED
.250" TO SYSTEM 84. THIS CONNECTION TO BE USED FOR BEYOND DESIGN BASIS SHELL EVACUATION O-RFV-84-518 1/2" EXTERNAL EVENTS.
AND PRESSURE RELIEF--=- 0-RTV-84-104 1--*a.:2a:5a;O_"_ ___._ _--(,O-PT REFERENCE DRAWINGS: SET AT SET AT 84-17 1-47E865-1 .......... FLOW DIAGRAM - HEATING & VENTILATING AIR FLOW 250 PSI 250 PSI 1-47E610-64-1 ....... CONTROL DIAGRAM - PRIMARY CONTAINMENT SYSTEM 1-47E610-76-1 ....... CONTROL DIAGRAM - CONTAINMENT INERTING SYSTEM YARD 1/2" YARD 1/2" 1-47E610-84-1 ....... CONTROL DIAGRAM - CONTAINMENT ATMOSPHERIC DILUTION SYSTEM O-RFV-84-523 0-RFV-84-57 3 1-47E1847-7 ......... FLOW DIAGRAM - CONTROL AIR SYSTEM MEL ................. VALVE MARKER TABULATION ELECTRIC ELECTRIC 0-47E800-2 .......... MECHANICAL SYMBOLS AND FLOW DIAGRAM
.375" HEATER 0-HTR-84-5 O-SHV-84-56 HEATER 0-HTR-84-16 DRAWING INDEX 0-47E800-1 .......... FLOW DIAGRAM-GENERAL PLANT SYSTEMS C
0-171341-1 .......... YARD PIPING NITROGEN STORAGE NITROGEN STORAGE MEL ................. INSTRUMENT TABULATION (SYSTEM 84) TANK A TANK B GE DRAWING: 4000 GAL CAP. 4000 GAL CAP. 0-TNK-84-635 O-TNK-84-636 SK-1 ................ CONTAINWIENT ATMOSPHERIC DILUTION SYSTEM P.t..lD 2 CONTRACT NO. 74C35-84939 I SET AT 140 PSI SET AT 140 PSI 0-FSV 0-FSV 0-PE l!L4!.."-Jlilil!lf-----\ *0 84-5 0-PE 1.!L4!.."-Jlilil!lf-----\ *0 :;; 84-16 84-1 1 .250" 3
~
84-12 ' ~ 0-RTV-84-100 N
.375" s O-RTV-84-106 N
;:;' .375" s
AMBIENT NITROGEN 1/2" 1 /2" >' AMBIENT NITROGEN
. 1 r C\I VAPORIZER A 6000 SCFH .
N
*N
~
VAPORIZER B 6000 SCFH N 0 0-VPR-84-639 0 0-VPR-84-640
' .500" 0 E ;:;
~
= ~ I m C\I a:
I
~--. .._~ ~
~'
0-SHV-84-520 N
~~~o~~~;;:;:=i.J" 0 N FULL TRYCOCK r,:
~
FULL TRYCOCK ...., 0-EQY-B4-516 0' r<n .375" m
<IL 1-0 W-<-
0-LT 84-2 >
- a B
1/1- .250" rSET AT 140
....--*1 '
!\
I N
,->-,~---, D PT
° I:!::'?
Ill
. 250" 0-RTV-84-3 84-6001 O-SHV-0-RFV-84-136
~---.-+-AMBIENT HEAT SET AT 140 PSI AMENDMENT 27
~ .250"
- C
<n om IV 2" 84-135 1" EXCHANGER 0 ' ,_
N . O-HEX-84-641 SET AT >.-- 0-RFV- 1-1 /4" 0
- i
. 250" POWERHOUSE & YARD
. .250" 148 PSI -1!;;'? ~-512 . 1*
UNITS 1 & 0 N 6:
- 1. -
l 0-RFV- 2"
. SET AT 120 PSI 2"
N 1*
'tr 0-RFV-84-563 SET AT 148 PSI 84-513 VENT .375" FILL CONN
. 375" BROWNS FERRY NUCLEAR PLANT 0-SHV-84-650 0-CKV-84-552 1 /2" PRESS. BUILD SYSTEM PRESS.- TEMP DATA FINAL SAFETY ANALYSIS REPORT ZONE DESIGN DESIGN REGULATOR PRESSURE (PSIG) TEMP (°F) 1 /4" SET AT 140 PSI 1 /4" 2
56 150 281 150 CONTAINMENT ATMOSPHERE A PRESS. BUILD COIL 0-COl-84-644 VENT 3 4 15D 138
-320 TO +100
-320 TO +100 DILUTION SYSTEM 2"
2" 5 6 FULL VACUUM 150 150 CCJ.itPANION DRAWINGS: 2- .t.. 3-47E862-1 FLOW DIAGRAM O-RFV-84-558 7 100 AMBIENT SET AT 140 PSI 8 10D AMBIENT FIGURE 5.2-7 SH 1 8 7 6 5 3
!.lOij ~-Z983Lt-Z V'-l L9 NOTES: 1, ALL VALVES AND INSTRUMENT NUMBERS SHALL BE PREFIXED WITH THE UNIT NUMBER 2- I.E., 2-FCV-84-19. TRK-360-759 FLEX NITROGEN CART 82 TO STANDBY GAS TRK-360-758 FLEX NITROGEN CART 81 2. ALL VALVES ARE SAME SIZE AS PIPING UNLESS OTHERWISE NOTED.
- 3. ALL PRESSURE AND TEST CONNECTIONS ARE 1/2" UNLESS OTHERWISE NOTED.
H TREATMENT BLOC
- 4. OPERATIONAL VALVES ARE SHOWN IN THEIR NORMAL OPERATING POSITION.
2-47E2865-12.D3 5. [I] ETC, DENOTES ZONE FOR DESIGN PRESSURE AND TEMPERATURE AS GIVEN IN TABLE. {FCv\ *N 6. UNIDS ON DRAWING ARE FOR REFERENCE ONLY AND ARE ABBREVIATED TO MEET 84-19 FLOOR EL 621 ' SPACE CONSTRAINTS. REFER TO MEL FOR COMPLETE UNIDS. DRV-360-721 DRV-360-720 7. ZONE 8 IS QUALITY RELATED AND WILL ONLY BE USED FOR FLEX NITROGEN CARTS. RFV-360-713 RFV-360-712 FLEX NITROGEN CARTS ARE NOT NORMALLY CONNECTED TO SYSTEM 84. 360-701 FE 2* 360-700 THIS CONNECTION TO BE USED FOR BEYOND DESIGN BASIS EXTERNAL EVENTS. VALVE SET AT 100 PSI G~ X _ 84-19
~~
N
~
e VALVE SET AT 100 PSI REFERENCE DRAWINGS: 2-47E610-76-1 ........ CONTROL DIAGRAM - CONTAINMENT INERTING SYSTEM
~f--------l-+----l---i:xxJ----.--f>l<fL---lc.......JL,---4104----t,,'""11JUI r> ' .
N >' IIJUl--+-~J-L-++4>'<:f-.-------Ca:J-+--+------1f-----l~ 2-47E610-84-1 ........ CONTROL DIAGRAM - CONTAINMENT ATMOSPHERIC DILUTION SYSTEM SHV-360-751 SHV-360-750 VALVE SET SHV-360-717 r SHV-360-716 VALVE SET SHV-360-748 SHV-360-749
"' 84-19
~
FT MEL .................. TABULATION OF VALVE MARKER TAGS AT 150 PSI
~
"' 1--@ AT 150 PSI 2-47E860-1 ........... FLOW DIAGRAM - CONTAINMENT INERTING 0-47W461-1 ........... MECHANICAL CONTAINMENT ATMOSPHERIC DILUTION SYSTEM 0-47E800-2 ........... MECHANICAL SYMBOLS AND FLOW DIAGRAM DRAWING INDEX 360-753 360-705
. HVAC DUCT
/Fcv\
84-20 1 PSIG t.1AX 360-704 360-752 0-47E800-1 ........... FLOW DIAGRAM - GENERAL PLANT SYSTEMS 2-47E2865-12 ......... FLOW DIAGRAM - HEATING AND VENTILATING AIR FLOW 2-47E610-64-1.,., .... CONTROL DIAGRAM - PRIMARY CONTAINMENT SYSTEM N (PEN X26) VALVE 2-FCV-64-31 2-47E2847-7 .......... FLOW DIAGRAM - CONTROL AIR SYSTEM MEL .................. INSTRUMENT TABULATION (SYSTEM 84) G 2-47E2865-12,E4 2-47E2847-5 .......... FLOW DIAGRAM - CONTROL AIR SYSTEM 2-4712461-2 & -3 ... , .PIPING
~
17W341-1 ............. YARD PIPING GE DRAWING: CONTROL AIR SYS SEE DETAIL 2A1 CONTROL AIR SYS SK-1 ............ CONTAINMENT ATMOSPHERIC DILUTION SYSTEM P & ID
.----t 2-47E2847-7.85 BELOW FOR FUNCTION HVAC DUCT SEE DET 281 BELOW
~----12-47E2847-7, 85 FOR FUNCTION CONTRACT NO. 74C35-84939 (PEN X26)
VALVE 2-FCV-64-29
~-/4 2-47E2865-12.E4 DRYWELL TW);;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;,;;;;;,;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;1 ----------------'l'-----------------i CAD SYS 84-32 . N (PEN X-50)
TO DRYWELL CAD TO DRYWELL 2-47E2847-5,C4 1/2" .,., : N TEST~ CONN 7 3/4" (PEN X-22)
---------<12-47E2847-5, 04)
.,..,.' HVAC DUCT
~
~ Jl-+:i+._31.:,4~*~0lllf--{112
- 1" aoSH\1-84-632
>' 2*
- i 1
TV-84-630 TV-84-631 TEST CONN
""' 2-47E2865-12, 82 ;I;'
1* 1 HVAC F
~ ~
2-FCV-64-18 2-47[2865-12, 86 BYV-84-687 BYV-84-686 ~
;I; ' .,..,.'
N HVAC 2-FCV-64-19 TEST CONN '--.,,4-"3!../+:_*~f,--,
~
""' 2-47[2865-12,86 T\1-84-619 TV-84-618 1/2" 3/4"
..,.' ____/'pr\ VENT TO
., RTV-84-616 ~ O HVAC DUCT X
~---l*--------<12-47E2865-12,83>
1/2. rZ TEST V,Z CONN ~o rU TV-84-679 TV-84-678 2" TW
"'112" X 1" TO HVAC DUCT 2-47E2865-12,C3 1/2" PI 4-51 84-31
~ SHV-84-622
~ n:sT CONN
~
RTV-84-677 ~ r 3/4" RFV-84-676 VALVE SET SUPPRESSION CHAMBER VALVE SET AT 110 PSI 1 .1 AT 100 PSI ..,. N w
>+
cc-Ji:'3"--'4'--"...:r"'~ E X .
.,' X r N
PREG 1/2" 1e* X 1 " 2 1/2" ~ ,,_
>~' N 1/2" ::::_
4-52 TV-84-120 TV-84-121 T ST CONN FLOOR EL 565' 1/2"X1" T'EST CONN TV-84-123 1 2. TV-84-122
~
0
~
v,w w I-'-----' r 0 1/2" VENT >' ~ 1/2" VENT 1/2" r'
~
2* > u 2* u VTV-84-605 \ITV-84-604 VTV-84-606 VTV-84-607 CKV-84-601 ~ N SHV-84-674 N THV 84-38 1 /2" 1/2"X1" r> CKV-84-612 SHV-84-675 CKV-84-66 TEST CONN RTV-84-119 RFV-84-704 VALVE RTV-84-118 SET AT 95 PSIG PCV 84-654 . N 8" 2-47E2847-5,C7
/4" FROM N2 TANK B D
.500" 1-47E862-1.E4 SHV-84-707 --1-- SHV-84-705 SHV-84-703 SHV-84-708 TV-84-702 m--Lm PI 84-708 FROM N2 TANK A REACTOR BUILDING 1-47E862-1, E4 (ecv\ SHOWN FOR FUNCTION ONLY (ecv\ SHOWN FOR FUNCTION ONLY C
PCV PCV 84-33 (Fsv\ 84-34 (Fsv\ CONT ON 1 /4" I 84-19 CONT ON 1 /4
- 84-20 (2-47E2847, 8-5) (2-47E2847-7. 8-5) f---CO(}------l>'<J------_J,FCV 84-19 f---t:o(}------l>'<l----------(Fcv 84-20 32-1252 32-1248 (Fsv\ ~CONT ON (Fsv\ ~ C O N T ON 64-29 THIS DWG (G-5) 64-31 THIS DWG (G-5) f----{:>Xf---<1----{>'<f---------lFcv 64-29 f---Co::l---0-----1>'<1---------(Fcv 64-31 32-1253 32-1249
¥ ¥
~CONT ON ~CONT ON (Fsv\ (2-47E2865-12. E-4) (FSV\ (2-47E2865-12. E-4) 64-32 64-34 B
L-----CXXJ------{)J'<l--------{Fcv 64-32 L-----CXXJ------l>'<l--------{Fcv 64-34 32-1254 32-1208
¥ ¥ AMENDMENT 26
~ O N T ON ~ O N T ON (2-47E2865-12. 8-3) (2-47E2865-12. 8-31 SYSTEM PRESS.- TEMP DATA POWERHOUSE DESIGN DESIGN UNIT 2 DET 2A1 DET 281 ZONE PRESSURE (PSIG) TEMP( °F)
G6 G3 1 56 281 2 3 150 150 150
-320 TO +100 BROWNS FERRY NUCLEAR PLANT 4 -320 TO +100 5
6 138 FULL VACUUM 1 150 150 FINAL SAFETY ANALYSIS REPORT 7 100 AMBIENT 8 100 AMBIENT CONTAINMENT ATMOSPHERE A DILUTION SYSTEM FLOW DIAGRAM COMPANION DRAWINGS: 1- & 3-47E862-1 FIGURE 5.2-7 SH 2 8 7 6 5 3 2
Z£0!1 L-Z983Lt-£ ~ LS NOTES:
- 1. ALL INSTRUMENT NUMBERS SHALL BE PREFIXED WITH THE UNIT NUMBER, "J-"
I.E., 3-FCV-84-19,
- 2. ALL VALVES ARE SAME SIZE AS PIPING UNLESS OTHERWISE NOTED.
TO STANDBY GAS 28" ~: s~~R~~~5~~~Ev~~eE~E~~Ec~~~i~ 1 12"¥H~~~ ~6~~A~N5~f~A9l~~R~E>§~r~8~: 0*
- 5. IT] ETC. DENOTES ZONE FOR DESIGN PRESSURE AND TEMPERATURE AS GIVEN IN TABLE.
H TREATMENT BUILDING
- 6. ALL VALVES ARE PREFIXED WITH UNIT NUMBER "3-" UNLESS NOTED OTHERWISE.
fF&, FLOOR EL 621 .25 " 0
- 7. UNIDS ON DRAWING ARE FOR REFERENCE ONLY AND ARE ABBREVIATED TO MEET 84-19 N SPACE CONSTRAINTS. REFER TO MEL FOR COMPLETE UNIOS.
~' 8. ZONE 8 IS QUALITY RELATED, AND WILL ONLY BE USED FOR FLEX NITROGEN CARTS.
2" Z<O FLEX NITROGEN CARTS ARE NOT NORMALLY CONNECTED TO SYSTEM 84. THIS FE om
. . w CONNECTION TO BE USED FOR BEYOND DESIGN BASIS EXTERNAL EVENTS.
X N 84-19
~ N N
r~ z .. o, u" r
~
FT r
~
1 PSIG MAX i's
~
~
m REFERENCE DRAWINGS: MEL ................... VALVE MARKER TAG TABULATION 84-19
~
.., 84-20 ." r z
w 9 MEL ................... INSTRUMENT TABULATION FOR SYSTEM 84 3-47E610-64-1 ......... MECHANICAL CONTROL DIAGRAM - PRIMARY CNTMT SYS
.250" PCV 0
~
84-20
"~
." 8 3-47E610-76-1 ......... MECHANICAL CONTROL DIAGRAM - CONTAINMENT INERTING SYSTEM J-47E610-84-1 ......... MECHANICAL CONTROL DIAGRAM - CONTAINMENT ATtdOSPHERE DILUTION SYSTEM 0-47E800-1 ............ FLOW DIAGRAM - GENERAL PLANT SYSTEMS 84-33 0
~ FROM 3-FCV-64-31 *N > > 0-47E800-2 ............ MECHANICAL SYMBOLS AND FLOW DIAGRAM DRAWING INDEX DET JA1 r ~ r 2" 3-47E865-12 ........... FLOW DIAGRAM - HEATING~ VENTILATING AIR FLOW 3-47E865-12.04 )>--- ' ~
FE 84-2D
~
DET 381 3-47E3847-7 ........... FLOW DIAGRAM - CONTROL AIR SYSTEM 1-47E862-1 ............ FLOW DIAGRAM - CONTAINMENT ATMOSPHERE DILUTION SYSTEM G
~
~
3-17W341-1., .......... YARD PIPING CONT ON I 1 /4" 1 /4" ICONT ON
*3-47E3847-7 ,A+ "3-47E3847-7 ,A't
.g ~ ~
GE DRAWING:
~31 SK-1 .. , ........ CONTAINMENT ATMOSPHERIC DILUTION SYSTEM P~ID CONTRACT NO. 74C35-84939
~
9 DRYWELL TO 3-FCV-64-30 1 8"
~-47E865-12,D41-- ......... -+
CAD SYS (PEN X-50) TO DRYWELL J-47EJ847-5,C5 FROM 3-FCV-64-32
;t- -r-+-a84-32 0 TW
~
64-18
*N CAD SYS (PEN X-22)
TO DRYWELL TRK-360-758 FLEX NITROGEN CART 81
~r-@
2" 3-47E3847-5,D4 3-47E865-12, CJ m m 1---, *N z~'
"'u
-ill N
m+J
;fi18" I
20" TEST CONN
*N r
~
8 m
*N 0
rw z~ 0 .. u .), CONT ON 0
~
N DRV-360-720 RFV-360-712 360-700 F TEST CONN (NOTE 8) ."'"'"'"' r "' u u TEST CONN N 3-47E865-12,B7 TW N m m
."' 8 VALVE SET AT 100 PSI
~
2" N N N 0 7 "' . 84-31'--r--"l'P TEST 1 /2" 84-679 84-678 u
~
"'0 "'w r
~
"'"' 0 N
~
N CONN
*N *N CONN
*N 3/4" m TEST 1/2" CONN 84-619 84-618 IIJUf->\\,-l-~l-'--.1-+-'J>l<I----.--C::o::J--+--1---+--....,_
f---m SHV-360-716 VALVE SET AT 150 PSI SHV-360-748 SHV-360-749
' 1/2"X1" 1/2" " 0 n:sT CONN 84-677 3/4" 84-676 3/4"
."'"" N N
Pl '--r-f>x:J-"'-'-1 360-704 360-752 VALVE SET o 11 a PSI 1 SUPPRESSION CHAMBER "' 3/4" N m 3/4"
"'N
. 84-50 84-616 3 4" VALVE SET . ." .'
~ ~
I-""--' o 110 PSI ~ ~ ~ 0 ' 0 0
~ VALVE SET "' "' "'
7 o 100 PSI X s FSV X "'N "' "' "' 2 84-8A 1/2" ...I---Kl.--1 /2" X 1 " 1/2" 7
.N VALVE SET
~
z r
~
z r
~
z r E t,!L~ o 100 PSI Tt:ST CONN '
*N PREG 84-52 1/2" VENT 0
0 12D 121 FLOOR EL 565. 0 1/2
- X 1 * ~.,[>f--~~1!-'/:!2_"
TEST CONN 123
~:4--i 122 .
N 0 N 0
"' 1/2" 1/2" VENT 2 2" *N 2" 606 607 N
6D5 6D4 TRK-360-759 FLEX NITROGEN CART 82 601 ' THV 2
~
84-675 84-674 1* 84-669 N 84-3 TO 32-1230 1/2"X1" TEST CONN --~.:j'\ . N RTV-84-119 84-612 84-613 84-614 1* RTV-84-118 .N RFV 84-704 3-47E3847-5,C71--""'I 1* g SET AT 100 PSIG ~ DRV-360-721 RFV-360-713 1 2" 2" 1/2" 1/2" 360-701 84-707
~
. N
. "'0 84-703 84-709 0 0 8 VALVE SET AT 100 PSI D
0 0 ~ N ~ N ~
' ' ' 11JUi,....,1--1~-'--~----,--'C>1<1--.--ox::1--1---+-+----901 PI O>
~
~
u.
~
~ f---m SHV-360-717 VALVE SET AT 150 PSI SHV-360-750 SHV-360-751 8e,' "'
N
~
~
w
~
360-705 360-753
~
N
- REACTOR BUILDING N
"0 a, 0
~
z N
' ~
z N '
"'mw "'mw r<
z N 0
~
r
,.z 0
N
~
C
~ ~
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SHOWN FOR FUNCTION ONL Csv\ SHOWN FOR FUNCTION ONLY Csv\ 64-32 64-34 32-1866 32-1208 FCV 64-34 Ej3 ( l j (
~( ~(
Csv\ 84-19 XCO~T ON Q X CO~T ON 84- 0
~ 3-47E865-12,83
~ 3-47E865-12,B2 84-33 8 -3 1/4" 1 4" B
FCV FCV 84-19 84-20 AMENDMENT 26 m Csv\ 64-29 tTON THIS DIG (G6) O> Csv\ 64-31
~TON THIS OWG (GS)
SYSTEM PRESS.- TEMP DATA ZONE 1 DESIGN DESIGN PRESSURE {PSIG) TEMP( °F) 56 281 POWERHOUSE UNIT 3 32-1250 ~ 32-1249 2 150 150
~ wt,
~" FCV > 3 150 -320 TO +100 Jt,
<., 138 -320 TO +100 Jt,
>o 64-29 Ej3
>o
~~
4 5 6 FULL VACUUM 1 150 150 BROWNS FERRY NUCLEAR PLANT
~~
~""
~r
( j
~(
~"'
~r (
l
~(
7 8 100 100 AMBIENT AMBIENT FINAL SAFETY ANALYSIS REPORT X CO~T ON X CO~T ON THIS DWG (GS) 3-+7E865-12,E4 CONTAINMENT ATMOSPHERE DILUTION SYSTEM A DETAIL 3A1 DETAIL 381 COMPANION DRAWINGS: FLOW DIAGRAM G7 GS 1- ,t. 2-47E862-1 FIGURE 5.2-7 SH3 8 7 6 5 4 3
~"';--1
~- ,..., -- ~~~~~l:r~r-=:-r...f;fl,'""i;:;:-J UNIT 2 UNIT 3 UNIT 1 r E D C B AMENDMENT 22 POWERHOUSE PDIEAIIOI.ISE UNITS UNITS 11 &* 0D BROWNS BROWNS FERRY FERRY NUCLEARPLANT NUCLEAR PLANT FINAL F INA.L SAFETYANALYSIS SAFETY ANALYSIS REPORT REPORT CONTAINMENT ATMOSPHERE CONTAINMENT ATMOSPHERE A DILUTION SYSTEM DILUTION SYSTEM MECHANICAL MECHANICAL CONTROLCONTROL DIAGRAM DIAGRAM FIGURE 5.2-8 SH 1 FIGURE 5.2-8 SH 1 B 6
!llfll;\cc********,ffl~ ...,_,.,.,_,,. .... ~ ,...............
o----*.. -* G D C B AMENDMENT 22 POWERHOUSE & YARD UNIT 2 BROWNS BROWNS FERRY FERRYNUCLEAR NUCLEARPLANT PLANT FINAL FINAL SAFETY ANALYSIS SAFETY ANALYSIS REPORT REPORT CONTA1NMENT ATMOSPHERE CONTAINMENT ATMOSPHERE A DILUTION SYSTEM DILUTION SYSTEM MECHANICAL CONTROL DIAGRAM MECHANICAL CONTROL DIAGRAM FIGURE 5.2-8 SH 2 7 FIGURE 5.2-8 SH 2
- .r-" *-** - - 'l!r Ji( l l f r ~ l f ')j(
---!-..L;.--~:--__. l '*\\f."'"'""_""'_""",.. .,._... °"" __ .........
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*Q~'lf~,~1!'11.ll':'"'1.mD10WIT
---~-'a*------- . --- *_____.1,.__,g§l c--+/-i::;::!i='.-----1~
D C B AMENDMENT 22 POWERHOUSE & YARD UNIT 3 BROWNS FERRY BROWNS FERRYNUCLEAR NUCLEAR PLANT PLANT
,_'T'IIPOi',mm* FINAL SAFETY FINAL SAFETY ANALYSIS REPORT ANALYSIS REPORT CONTAINMENT CONTAINMENT ATMOSPHERE ATMOSPl-£R£ DILUTION OILUTJ~ SYSTEM A MECHANICAL SYSTEM COITROL DIAGRAM MECHANICAL CONTROL DIAGRAM FIGURE 5.2-8 SH 3 6 FIGURE 5.2-8 SH 3
BFN-16 Figures 5.2-9 through 5.2-10 Deleted
BFN-18 Figure 5.2-11 (Deleted by Amendment 17)
BFN-16 Figure 5.2-12 Deleted
BFN-28 21, ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ - - - ~
- D¥>ei + Wew eUOx),ge11
- IDl}9,'el + WetNe11 H}dr(>lf~II Z,:)
,= =*a, E
- J 0
~ 6 1.:, 'i L
~
a, (J u 5 0 0 ---"T"""-..--"T""""T""".,....,........- t - - - - . - - " T " " "............"T"""....... . - t - - -.......- - . -..............................+-----.----.----.----.-............,-,-1 o.o* 0. 1 10 Tine After Loe.A (days.) BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT HYDROGEN AND OXYGEN CONCENTRATIONS IN CONTAINMENT FOLLOWING LOCA WITHOUT NITROGEN INJECTION (SAFETY GUIDE 7 ASSUMPTIONS, ATRIUM-10 FUEL, NO CONTAINMENT LEAKAGE, 3952 MWt) FIGURE 5.2-13
BFN-28 Figure 5.2-13a Deleted by Amendment 28
BFN-28 Z,J ~ - - - - - - - - - - ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ i .:1 I ""=E C)
~
0 ~ ti \0 e-
- ~
~ C, 0
u 6 Ntrog;en laj:,c6on
.:, e- T V
0 + - - - ~ - ~ - ~ ~ ~ ~......- - ~ . - - ~ . - - ~ ~ ~ ~ . . , . . . , , - - - - - r - - - r - ~ ~ ~ ~ ~ " T " " " - - ~ - ~ - ~ ~ ~ ~..-i
*J.o* 0. l *o Time After LO CI\ (day s)
BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT HYDROGEN AND OXYGEN CONCENTRATIONS IN DRYWELL FOLLOWING LOCA WITHOUT NITROGEN INJECTION (SAFETY GUIDE 7 ASSUMPTIONS, ATRIUM-10 FUEL, NO CONTAINMENT LEAKAGE, 3952 MWt) FIGURE 5.2-14
BFN-28 Figure 5.2-14a Deleted by Amendment 28
BFN-28 L':> ~;::::::::::::::::::::::::::::===.- - - - - - - - - - - - - ~ - - - - - - - - - ~ - - - - - - - - - ~ 15 i: E
- J 0 ** * * - --. --- --- **
~ 6 iO "iii
~
OJ (J u 6 I N""Jtrogen lajeciion Beans I 5 - ---- ----+----------I
~~
L-- ---~....,........,.----- 0 +---,-----,-,--,.......,.........,.......,,------,----.----,~~-.-.--.-+------.----,-----,----.---.-.....,..-,-+----,----r---,---.-"T"""O--.-rl
*~.o* 0. l 10 T ime After LOCA ( da.y s)
BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT HYDROGEN AND OXYGEN CONCENTRATIONS IN PRESSURE SUPPRESSION CHAMBER FOLLOWING LOCA WITH NITROGEN INJECTION (SAFETY GUIDE 7 ASSUMPTIONS, ATRIUM-10 FUEL, NO CONTAINMENT LEAKAGE, 3952 MWt) FIGURE 5.2-15
BFN-28 Figure 5.2-15a Deleted by Amendment 28
BFN-28 1400000 ~ - - - - - - - - - - - - - - - - - - - - - - - - - - ~ - - - - - - - - - - - - - - - - ~ 1200000 c=- 1000000 0 .e, 1: E C oi 800000 1: 0 0 2 i:, i:, 600000 i:, <( C C) E
- ! 400000 200000 0 20 40 60 80 100 Time After LOCA (days)
BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT MAXIMUM NITROGEN REQUIRED FOR DILUTION, SGF AT 20 DEGREES C AND 1 ATM (SAFETY GUIDE 7 ASSUMPTIONS, ATRIUM-10 FUEL, NO CONTAINMENT LEAKAGE, 3952 MWt) FIGURE 5.2-16
BFN-28 Figure 5.2-16a Deleted by Amendment 28
BFN-28 60 r - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -.---- - ~
------- W~hout Nitrogen Injection
- - W~h Nitrogen Injection 50 40 ci
'iii ~
~
- l
"'"' 30 ~
0.. 'ai C
~
20 t-10 l 0+--------~--r+----------~~-----------~------------l 0.01 0.1 10 100 Time After LOCA (days) BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT MAXIMUM CONTAINMENT PRESSURE FOLLOWING LOCA WITH NITROGEN INJECTION (SAFETY GUIDE 7 ASSUMPTIONS, ATRIUM-10 FUEL, NO CONTAINMENT LEAKAGE, 3952 MWt) FIGURE 5.2-17
BFN-28 Figure 5.2-17a Deleted by Amendment 28
BFN-17 Figure 5.2-18 (Deleted by Amendment 17)
I ROOF OPENINGS ARE FQR VALVE OPERATORS. MINIMUM FLOW AREA fS 10 SQ. FT. EL639.0 11 I0.5 R I0.5"R EL 510.0 El 565.0 PERSONNEL ACCESS ROOM DETAIL A
<PLAN v1sw::1
(£L 590) EL519.0 AMENDMENT 16 BROWNS FERRV11flJql;EAR PLANT FINAL SAFETY ,l\NALVSIS REPORT ELEVATION ComoectlaR,l'low Path lhrouth Penon"",Accen Room FIGURJ 5.2--19
f:J 4 6
* ~ .. . ..*.
--D ~- ~
. 1m11mm111n,
.' STAIRWAYS OPEf!I MATCH
* . * . -..... -* :*:~.""*-:-
. . . . ,. ,._,,...,___,... **:._...,.....,..,...--,-_,..1.**':-;--,-...---.-~.'.
FLOOR PLAN EL 565.0 FLOOR OPENINGS OD OF,Pll*tNC THRU SLEEVE AMENDMENT 16 SLEEVE 00 ID INCLUDING INSULATION FLOW AREA UNJ !IN.I CIN.I (FT.2t 1 311 35.&7 25 3.5 2 311 35.17 29 2.3 .
~llffCtion Fl- Path Through 3 38 35.tlJ 29 2.3 24 Per111nnal Acaln:Roam 1.9, 1.315
' 23.61 TOTAL
....!:.L 11.2 FIGURE 6.2..-20
~VENTS---'i _
.. , --~ STAIRWAYS -:;;?.~c;.:._,....
- .... .-:~-:--:*-.:::,t PLAN EL. 519 AMENDMENT 16 BRO.Sf ER,fiV NUCLEAR !It.ANT FINAL Mi=Etv ANALVSIS REPORT.
Conncttiin Aow Path Tllrouah
'Penonnel Aacen Room FIGURE 5.2-21
BFN-16 Figure 5.2-22, Sheets 1, 2, and 3 Deleted by Amendment 15.}}