ML21286A352

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Amendment 29 to Updated Final Safety Analysis Report, Chapter 5, Figure 5.2, Primary Containment
ML21286A352
Person / Time
Site: Browns Ferry  
Issue date: 10/04/2021
From:
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation
Shared Package
ML21286A574 List: ... further results
References
Download: ML21286A352 (54)
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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

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990~ L9 ROOM { AIR .;;5,,.:f..,,:,..20<} ~~~ THIS DWG X "----'--v'---' OUTSIDE AIR ECCS ANALOG TRIP POWER 11-47[610-71-2, ,~ C3 >-~ + ---@v L~ l~¥ib1~iE~,E LIMITER ~7 I I I s4-5\\.00-"D5 l1-47E610-71-2, ~ w ~ ~ ~< - <~ o!l .... ~ 'f I {HS\\_ I 64-23A --, ~ I PD! 64-22 ~ 64-23A y I ~ !I !:1 ,---§)© C5>-~+~ L--@)© 0 FAN-64-38 z ...I.. ...I z ~ I ~ 64-238 y I {HS\\__.J 6t=9B I I .l 1-47E1847-7,87 I ~---r-----11-45E777-6 I ~ I x-+- .-FcOI --+--...fo?n----+-x I ~4-65A 64-65D T T I NOTE 9 >>* - ~ :$:>>: NOTE x-+-~--~-- rrco\\... 1 1... x - ~658 -;~~r-Am ,,~>&._ EQUIPMENT ACCESS LOCK 8 X ~. ~ ' w w ~.. ' EXHAUST FAN 9 7 ~x 64-7 ~ 9-22 w~ C PDA iii 64-2

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.... ~ '-r,' ~- it:< ~-7 _il~iiy LftDrs\\..J 64-26 ~ ~ l.....--=:9-81 PIS 64-588 9-81 PIS 64-58D ~ ~ l~OG TBDOOS ~~x I 9-1s ~ I I~ w.. z ~ 0 N ~ ' ZQ -w w J>- w W< ~ ~J.. ~o WV, ~- ROOM~ AIR ' I X LOG I HS641 I CISS A I 9-3 M -r 64-54A ~ I I I ~_J 4 9-18 @\\ 64-54A y dls3 A 64-54A ~ I I 64-52CA I L-':r"" ~5-32 (LA\\ 64-548 - 6 FROM TURB BLDG EXHAUST DUCT FROM r--------7 I I I r------------------------------------------7 1-47E1847-2. D6 I I 7 I I I I I I ,------7 ~ FAN~ I FAN D 64-71 ---t-- 64-71 ~ I ~ ~ _..J.FAN~ (:i FAN C 64 1-- 64-70 U) ~ ~ ' ~ IFAN!/H5\\ ~ FAN B 64 --;- - 64-69 Cj I ~ r+-45E779-1s.E10 I FAN NE I (rs\\ I /Hs\\ 64-73 I 64-73 FAN NE 0s\\__J __ _j;;;\\ REACTOR ZONE EXHAUST DUCT ~ I I L-r---Ws---dt\\ ~ --+--...{HS\\ 6-4-72 T 6-4-72 ~ I ~ X FCC 64-9A a. B ~ DETAIL 1C2 ~ TO REFUELING ZONE m ~ w ' FAN A 1-47E1847-2,C6 ~ m ~ w w w " ~ w ~ ~ ~ X X-+- m m ~ w ' ~ 8 FAN B I FS *-1 64-501 *, y G I I I {HS\\_..J I 2-45E777-30,A7 f--' 64~ 88 I ~ _____ J 64-47 ~ -47E610-64-2, G6 G6 64-20-4A 9-81 PT ~IS 64-578 64-578~ 1-45[670-21 25-5A _.J 25-5A --~ PT PIS 9-81 64-570 64-570 64-206A LS I

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'l:'-J NOTE 10 X 0 ~ ' 0 THV-64-11AB THV-64-11AA (FCo\\ 64-11A THV-64-12AB THV-64-12AA (FCo\\ 64-12A I ~ ~ I I FAN~B...._,_ ROOM AIR 6~8 6~8 . ~H~,._..,To RHR ~ PUMP MOTOR A ....__,,, FAN AF AN-64-68 COOLER A CLR-64-68 ROOM AIR COOLER NI CLR-6-4-72 TO CORE SPRAY ..... t--t<-'V'- PUMP tv10TORS A & C FAN NI FAN-6-4-72 X + +---C:...: X RHR PUMP MOTOR A COOLER PUMP tv10TOR COOLERS 8, C & D SIMILAR CORE SPRAY NI ROOM COOLER NE ROOM COOLER SIMILAR l1-45E614-5,81h rl 1-45E614-6,G81 25-213 25 221 ROOM {>---,6*4.:;/C 6~28;0 }ROOM AIR AIR ~ OUTSIDE AIR l~frIBRPiffluRE LIMITER rxs\\.._../HS'\\ 64-135 64-135 ~ y ~-r=-..:r

@t-1-1 1-45£779-18 9-19 GD 64-1608 y

~5-6A LOG _/ PT\\ ~.~4""-"1 s;,O~B+- - 64-1608 SEE NOTE 6 REACTOR ZONE EXHAUST FANS 25-221/PX'\\ 64-38 9-25 UL) 64-38 y y t-----_J < PA-64-58 \\..: 9-82 THIS DWG,D5 ---, ~ PI r

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6~9 t" --II[;@ (ill- -t 6~F t=------------:::f.-1r-i-C;~::J-f----_-_-_-l-_-_-_-_-_---l--:--'--':-7 I 1-45E670-9 f-J25-6A PT -831_ 25-68 9-85 6~F X-27 X-52 ORYIELL X-26 9-82 r-1 ---,L. § 1-45E670-8r, 64_57A I ~ I I 9-02 r.vn,_I @ ~ 64-57C ~ PT 64-57A 2s=e'e 25-SA ~ 64-57C TO PT-76-14 1-47E610-76-1,F6 730E933-1 I TM-64-52CA I 1-730E933-2 f--1 I I I @--4 TIS 64-52A 6-4-52AA ~,..,... 1-1 --7-30_E_93_3--1~f- - J I 11-130.,20-12 t---t I THIS DWG,D7>--J XR-64-159 ~ PT~ 64-SBH 64-56C ~ '~,...,...., J- _ITciGl I I 1-45E670-9 t--- ~ ~ A25-6A,---l5-6H-86 __[i]i;] E ( PT) ( PT \\-;=~,.,;,.-r.~ in 64-58H 64-56D 64-56D 7 "'f" ~ LE 64-66 ~ ©@}l-- 9-3 NOTE 10 9-~~ I

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T I r--' I I 9-25 ~ X 64-+4 y I DETAIL 1D2 l1-45E614-6,C4f---i I FROM REFUELING ZONE J 9-25 ~ 64-45 y I +-----11-45E614-5, HG I I \\--tf!I FCC X 64-42A I:. B ~ 6-4--44 ~ 6-4--45 1-47E1847-7, E3 1-47E1847-7, E3 HS-84-20 1-47E610-84-1,HS LOG ~ J HS6435 ~ r-ffl 1~~~4JO L~~ ,-w~-CL I ~~ r--o::::r~-o I TO REFUELING ZONE I (TYPICAL 3) I X !--~--~ I I s4-600 --i I ~ -----1

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i t sf;c~----< I I I~~ x CHANGE I~ V -~;!;I-ROOM ~ I I _frco\\ I t 64-GOD _J ,~.. 9-25 ~-'-- 64-GOA I ~ I I ~- I 9-25 I I ~--, +-- / ' I {HS\\__: __..J

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THIS CONTROL DIAGRAM COVERS PORTIONS OF THE FOLLOWING SYSTEMS: A. PRIMARY CONTAINMENT SYSTEM. B. SECONDARY CONTAINMENT SYSTEM. C. ATMOSPHERIC CONTROL SYSTEM. D. REACTOR ANO TURBINE BUILDING VENTILATION SYSTEM. THE DIAGRAM INCORPORATES THOSE CONTROL DEVICES NECESSARY FOR AIR PURGE OF THE DRYWELL, DRYWELL PRESSURE INTERLOCKS TO ENGINEERED SAFEGUARD SYSTEMS AND PROTECTION SYSTEM, REACTOR AND TURBINE BUILDING ISOLATION, AND ZONE CONTROL RELATIVE TO BUILDING PRESSURE LEVELS AND RADIATION LEVELS, REFER TO THE LOGIC DIAGRAM 47E611-64 SERIES FOR THE SPECIFIC INTERLOCK FUNCTIONS RELATIVE TO THE FOLLOWING: A. ISOLATION OF THE REFUELING ZONE AND REACTOR ZONE ON HIGH RADIATION.

8.

CONDITIONS CAUSING TRANSFER TO THE STANDBY GAS TREATMENT SYSTEM. C. VACUUM RELIEF FOR THE DRYWELL.

0.

INTERLOCK AND VENTILATING FOR TRIP REQUIREMENTS RELATIVE TO HIGH ANO LOW (VACUUM) PRESSURE IN THE REACTOR BUILDING. E. INTERLOCK FUNCTIONS FROM DRYWELL PRESSURE SENSORS RELATIVE TO REACTOR PROTECTION SYSTEM, ENGINEERED SAFEGUARD SYSTEM, ANO AUTO SLOWDOWN SYSTEM. DRYWELL PRESSURE AND TEMPERATURE AND SUPPRESSION POOL PRESSURE~ TEMPERATURE, AND LEVEL ARE RECORDED AND/OR 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 BUILDING AT -1 /4" OF WATER PRESSURE. DELETED IN THE EVENT THAT VACUUM INSIDE THE REACTOR ZONE INCREASES FROM THE NORMAL (-3/B* OF WATERb PDIC-64-16 SENDS AN OPENING SIGNAL TO POC0-64-16 TO ALLOW UTSIOE AIR TO 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 NEGATIVE THAN -1/4* OF WATER, THEY WILL TRIP BOTH THE ZONE SUPPLY AND EXHAUST FANS. FIELD TO CONNECT PORTABLE GAUGE AND PLANT AIR, VALVED AS NECESSARY, TO ORYWELL FLANGE EACH TIME ORYWELL HEAD IS REFITTED, TO TEST SEAL OF HEAD. PURGE AIR FILTER. CRYENCO CONTRACT 85083. INSTRUMENT TAG NUMBERS ARE PREFIXED UNIT 1 UNLESS OTHERWISE NOTED. POWER HAS BEEN DISABLED TO EQUIPMENT ACCESS LOCK EXHAUST FAN AND ASSOCIATED DAMPERS. FOR REACTOR BUILDING VENTILATION AND REFUEL FLOOR RADIATION MONITORING SEE 1-47E610-90-1. UNIOS ON DRAWING ARE FOR REFERENCE ONLY ANO ARE ABBREVIATED TO MEET SPACE CONSTRAINTS, REFER TO MEL FOR COMPLETE UNIDS. SYMBOL: ~ CONTROL AIR SUPPLY OIL FILLED RESERVOIR ANO LINE REFERENCE DRAWINGS: 47E600-SERIES.....,.. INSTRUMENTS AND CONTROLS MEL.................. INSTRUMENT TABULATIONS 47E605-SERIES........ CONTROL BOARDS 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 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 1-45E777-6........... WIRING DIAGRAM-480V AU~ILIARY POWER SCHEMATIC 0-47E800-1........... FLOW DIAGRAM-GENERAL PLANT SYSTEMS 0-47E800-2........... MECHANICAL SYMBOLS AND FLOW DIAGRAM DRAWING INDEX 1-47E844-2........... FLOW DIAGRAM-RAW COOLING WATER SYSTEM 0-47E845-2........,.. FLOW DIAGRAM-COMPRESSED AIR-STATION SERVICE 0-47E847-SERIES...... FLOW OIAGRAM-H&V AIRFLOW 1-47E1847-SERIES..... FLOW DIAGRAM-CONTROL AIR 1-45E615-SERIES...... CONTAINMENT ISOLATION STATUS SYSTEM (CISS) ~ I ~ ~~x*~A _,,o_._t::-El.::-V-A-TORJ -v~r SHAFT FROM REACTOR ZONE i~~JrvH~k~ FAN-64-60 __fciss]_JLOGl r-o::::r~-CL ...J ~~ m~-o ~~ m~-CL AMENDMENT 27 LT ____ 7 ~--9-=iil A 9-3 w_ LT ~ 64-33 ~ 47E1847-6, I I ~~ m~-0 u:o......= I....[J]D 64~9s s4-159e X-2068 // ( / DEMIN '(....L.9-V WATER{._filY' St:9A 64-159A -,-lE!m I C ..Af-"<'--i> I --~ I 9-18 I I LOG I _j <1---;,f--:,,,.,,,,,---1 (aj 164-1598 DEMIN5-.,....J WATER TE TE 64-55E 64-55A TE 6~8 1-47E1847-10,C3 6~9A1 ~rRESSION L -~~ 164~~9AI fflRESSION TE TE 64-55D 64-55F ~ I XS L __________________________________________ _ 64~ 5 4 9-3 I Cu:\\ _ _J 6-4-66 ~ LOG 64-34-C 25-32 _..._, CISS A L LOG HS6433 I CISS 8 ~ w I I ~ I ~ I i!l I ~ LOG 1-47E1847-7, CJ ~ I 64-34-0 ____ J CISS A ZI-64-3481 MZI-64-34 9-5~! FCV 9-3 MIMIC ~1i_ 64-34 ! ~ ----1/4=--~ I ~-3 Cott.PAN ION DRAWINGS: ______L_.~ 1-47E610-64-2 &-3 64-34 2-47E610-64-1, -2 a. -3 3-47E610-64-1, -2 & -3 lf'R'( 'fai" ZI-64-34A I~,-y, 9-3 Lt--t-------~~ = _J ___,.l m ~4

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x POWERHOUSE UNIT 1 BROWNS FERRY FINAL SAFETY NUCLEAR ANALYSIS PLANT REPORT CONTAINMENT SYSTEM PRIMARY MECHANICAL CONTROL DIAGRAM FIGURE 5.2-2a SH 1 H G F E D C B A

D~D~ l-t9-0 l93Lt-Z 11"1 L9 SEE DET 2A2 2-47'610-64-2, ZONE 8-7 (TURBINE ROOM EXHAUST FANS A-J) ATtdOSHPERE 2'JiSIDE 2-47[2847-7. D3 I (HS\\_ I 64-23A -, ~ I ,is'\\ 64-23A y I I ,7, / / / / / / n N / / w I / cc / ~ "' / z / / ..J II. / / / ..J / z - / m / n N / / ~ / cc / / / / / /. ~ 64-238 (HS\\_ 'T 6t_:9B I I ~ w cc ~m M <~ eel r~ OUTS IDE >--~ AIR 2-47E2847-6, E5 FAN A ll-64-488 IL-64-388 ~6~4BRC R IL-64-JBC &-!© ____ J FILTER @ ai-5Je ~ I y ~ I ,...,.,...,,6~~~A {Hs'\\ L-~ I 64-4C I 64-38 I Dcoy I 't;J'I 64-1A i ~l-li I o 1 0 FANxA ~ I I I I I L--~-----.J p I I I (Fee\\ (Fee\\ 64-5B 64-68 L..,,._,. PDM 64-18 *~ I ~ I r-64-48 : 8 ~ I V I I+-- ~--0 ~ 25-32 I 25-32 (PX\\_ __ r-~-i __________ _fxs\\_ __ _ 64-54 64-54 9-3 ~-18 ~-3 2s-32 25-31 I - ~ C!D {LA\\_ _ _jcs\\_ _ --f 64-54A 64-54A 64-54A 64-548 64-548 ~5-32 7 ( LI\\ 64-548 ~ HEPA FILTER X POI 64-1348 ~ 1;;~5~flfAirE FAN B SHY-61-16 1 t L.J....,. X r---1=-= I I I I I I I :!: I ~ I 2-45[777-3 FROM TURB BLDG EXHAUST DUCT 2-47[610-64-2,83 ,- -1 ~rti~E,~:..i4-1.Es 1---------+-! RE,);t---, FROM L'~OJ REACTOR ZONE EX NOTE 13 I I 2-47E2847-7,CJ I ~25 ~--~ _&25 I L 64_9 l2-45E614-5f-- 6:_"10 L---c:~gJ: ROOM >--'. PDS AIR St:9A/C PDS_i.,--<ROOM 64~8/D AIR ~ OUTSIDE AIR 9-25 AIR CONDITIONING UNIT 2-ACU-064-0134 ~~frJ8RPii~iuRE LIMITER (xs\\_..JHS\\ 25-22{Px"\\ 64-38 64-38 J LT FIC 64-54.~-~~64-54 ~ 25-32 {Px'\\ X-2090 -205 X-206A. 25-58 LS 64-46 y ~-3 ~ 64-46 ~ DRYIELL PT-64-SBE.ES PT-64-58F.E3 PT-64-58H.E3 ---j THIS DWG > 64-135 64-135 ~ 'rc;(_ y _;B(-4 I ,a(..4 ,=- I I r-_j r12-45E779-181 I .... -------1,1------ ~ A 25-222 (FIT\\ 64-38 .... _~

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I CNTIIT PURCE NOTE 13 9-19 I FILTER FAN 2-rAN-M-ue uiLl STEMI VAULT ElCH 100STER FAN 6~78 I ~2 XA-64-67,C4 25-321 25-6A. 64-132 (THIS DWG,C4>---0a-+- -~--::;:::-~ SEE NOTE 7 ILOG I~ I ~---- (rs\\_ A5136

, 9-3 64-128 H6~4""-1"'2"-s 9-19LJD 64-1608 ck:::.

-©~ 6~8 ~ (POI\\ (r?; (PDI\\- TO XR-64-159 I 64-125 64-129 64-126 ~ (THIS OWG,B4 f---t IS-64-67A SEE I,-< THIS OWG,C4) NOTE 6 25-6~ I l.ED I e-730E927-8f-7 64-16081 25-6A 9-821 I /PT\\_ _/PIS\\_ t PA-64-58 ~~ 64-130 64-130 ~ ~ ~ 64-58F 64-58F 7 ~ \\i ~ I~ ---,-'---,---,.=,,.----:-----,25-se 9-85 rr.!2;;£;,:i::J-,,;:_:;;8:;-22~5--6;;8;, \\~ 6 f1 r~ ~ ~ 6 /PIS\\ PT PT PIS _J ~ 64-56C ~ ~ 64-57 A 64-57 A 64-58A 64-58A I ~ ~ ~...__.. 25-6~ H2 I I 6 ~- ~ ~ 1 I- _J _l_ 9_82 2-45E671-33 x-52 u....,: I +- ~2-73 E927-8.,_ 7 ( PIS\\ 2-45E671-45 ...... -~ 64-58H ~ 9-82 25-6A 9-82 I y 4 G1 JPT', (PT\\_ ms\\ I ~5-6A -68 -86 6~C 64-57C 64-SBC 6t:;,!IC ( PT\\ (PTL PIS 25-68 64-58H 64-56D 6~6D LOG 4-31 0 r, _-_-_-_-_c_-z::-::_-_-_-_- 1 I I I I I I I I I I I I I SUPPRESSION POOL---~ -47E610-2-2,E4 DEMINERALIZED WATER SUPPLY II _.l..!'-3/ 111 ~ I ~ lL-__ @ -~ TW T 64-55A ~ ~ X206D X232A 9~A ~3 I ~>--I /LI\\9-:_J\\ T '\\ LJxR \\. LT LT 6~ 64-159A 64_159 64-1598 64-66 7 ,:;-~--7 T r.?\\-19 X206C IDIXJI I TYPICAL OF 12 PX I m PX SUPPR POOL TEMP ~ MONITORING SYSTEM I I (AA THRU MAJ 64-.]_59A ~ ~... 6H59B (2-47E610-64-3) X232Bl,r-t><I-I LOG ~...,. H><I-"- X232D 64-66 i A5123 'f l;I POOi.SUPPRESSION I LOG 1-::-1 i;: c c.::.:.::_:.::_c..,,~ A51 3 5 s-18 I TW 64-55C 0E\\ 64-55C SPARE...__,. ,--------------------------------7 Lille--' 64-66 ~ I I I 2-730E927-20 r-1 I I GE DRAWINGS AND DESIGN SPECIFICATIONS, I L- - ---- __ J ~1 ~~g~3:::::::::: :~~1~:~~ ~6~¥l~~~~~~sv~~~. v~5¥¥~R~~~A~~~~Es L-64_5~~ 22A1132AE......... CONTAINt.ENT ISOLATION SYSTEM ~--------< 2-47E610-73-1.87 22A1169........... DESIGN SPECIFICATION FOR REACTOR CONTAINMENT 2-730E927-7,-8.-20............. ELEMENTARY DIA.GRAM PRIMARY CNTMT ISLN SYS 2-730E927RF-16,-17A,-19.......... ELEMENTARY DIAGRAM PRIMARY CNTMT ISLN 6 5 3 9-54 ZI-64-348 FAN B N 0 -' n.... ' 0 - w w...... ' N I I I I Gs\\ ~ FAN D 64-71 hs\\ m.... FAN C ~ 64-70 ~ Gs\\ FAN B N 64-69 Q 64-71 ~ 64-70 ~ 64-69 FAN D FAN C FAN 8 r-42-45E779-161 I Gs\\ I ~ FANS B.t. D s4-7J I s1--1J r7s\\_---f--~ 64-68 64-68 ~ ~ (7s\\_ I __/i;'s\\ 64-72 - 64-72 FANS A&. C ~ I ~ ROOM ROOM AIR AIR COOLER A COOLER TO CORE SPRAY ..... H~Pu"**P~MOTORS A & C 8 & D RHR PUii' MOTOR A COOLER CORE SPRAY NI ROOM COOLER NE ROOM COOLER TYPICAL PUMP MOTOR COOLERS 8, C ~ 0 TYPICAL w z 0 Nr 0 ~ ~:, cc r Or <<n " C W=> ~< cc ox r~ "' - cc r 1-47E610-64-1.E3 TO STANDBY GAS TREATMENT SYSTEM 2-47E610-84-1,H5 RPS ANAL<:X; TRIP POWER l2-47E610-99-1>---!Fr>-----@)<D 12-47E610-99-1>---ID---@) 12-47E610-99-1>---lfr'.>-----@)@ l2-47E610-99-1>---ID-----@)© ECCS ANALOG r ~ TRIP POWER ~ I 2-47E610-71-2' ">--IE'.>-t--@>@ L-@)@ r~ I 2-47E610-71-2,F4>--ITE>---t--@) NOTES: L-@)© 1 ' THIS CONTROL DIAGRAM COVERS PORTIONS OF THE FOLLOWING SYSTEMS: A. PRIMARY CONTAINMENT SYSTEM.

8. SECONDARY CONTAINMENT SYSTEM.

C. ATMOSPHERIC CONTROL SYSTEM. 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 BUILDING PRESSURE LEVELS AND RADIATION LEVELS. REFER TO THE SCHEMATIC ELEMENTARY DIAGRAMS FOR THE SPECIFIC INTERLOCK FUNCTIONS RELATIVE TO THE FOLLOWING: A. ISOLATION OF THE REFUELING ZONE ANO REACTOR ZONE ON HIGH 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.

2. ORYWELL PRESSURE AND TEMPERATURE AND SUPPRESSION POOL PRESSURE, TEMPERATURE, AND LEVEL ARE RECORDED AND/OR INDICATED IN THE MAIN CONTROL ROOM.
3. THE NORMAL REACTOR BUILDING VENTILATION CONTROL IS THROUGH PDC-64-1 AND POC-64-2 WHICH MAINTAIN THE REACTOR BUILDING AT

-1/4" OF WATER PRESSURE.

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 START AND STOP THAT ASSEMBLY.
5. IN THE EVENT THAT VACUUM INSIDE THE REACTOR ZONE INCREASES L12-45E614-61 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 GREATER THAN 1,4* OF WATER. OR IF EITHER POS-64-62C OR ~H~Y6iiEfDT~i~ ~aT~ ~~~s~g~~ rup~l~EjAiir~HX~~~ Fi,~: OF WATER. __Elli]_ I LOG I ~64-30 c~ TO 2-FCV-84-20 --j2-47E610-84-1,G7) I CIASS I -t,.,-'L~Oc-G=I 64-34 Cl _liliil_ ~ ro:::r-~ COMPANION DRAWINGS: 1-47E610-64-1, -2 &. -3 2-47E610-64-2 &. -3 3-47E610-64-1. -2 ~ -3 SYMBOL:

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.
7. PURGE AIR FILTER. CRYENCO CONTRACT 85083.
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. REFER TO NEOP-4. EXAMPLE: MEL UNID DRAWING UNID BFN-2-HS-064-0011AB HS-64-11AB BFN-2-FSV-064-0029 FSV-64-29 B. All VALVES IDENTIFIED AS "Fcv* HAVE VALVE OPERATORS. THE MEL UNI FOR THE VALVE OPERATOR IS DEVELOPED AS FOLLOWS: VALVE DRAWING UNI VALVE OPERATOR MEL UNID FCV-64-20 2-MVOP-064-0020

9. All HANDSWITCHES AND CONTROLS ARE LOCATED LOCAL UNLESS OTHERWISE NOTED.
10.

11' 12,

13.

THE VALVE POSITION LIGHTS COVERED BY THIS NOTE ARE LOCATED ON THE GRAPHIC DISPLAY PANEL (9-3). THE TWO VALVES IN SERIES THAT ADD WATER TO THE REFERENCE LEG OF THE LEVEL TRANSMITTERS SHALL ALWAYS BE CLOSED DURING NORMAL ~rirri~0r&IaEfo~*~Rt~t~~58C~tilNMENT SYSTEM IS SHOWN ON MECHANICAL LOGIC DIAGRAM LISTED IN REFERENCE DRAWINGS. FOR REACTOR BUILDING VENTILATION AND REFUELING FLOOR RADIATION ...::lNITORING SEE 2-47E610-90-1. ~ OIL PRESSURIZED ACCUMULATOR ~OIL FILLED RESERVOIR A.ND LINE REFERENCE DRAWINGS: ~CONTROL AIR SUPPLY 0-47E800-2........... MECHANICAL-SYMBOLS AND FLOW DIAGRAM DRAWING INDEX 47E800-1............. FLOW DIAGRAM-GENERAL PLANT SYSTEMS 47E600-SERIES........ INSTRUMENTS AND CONTROLS 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 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 2-47E2847-SERIES..... FLOW DIAGRAM-CONTROL AIR 2-47E856-2........... FLOW DIAGRAM-DEMINERALIZED WATER SYSTEM 2-47E610-73-1........ MECHANICAL CONTROL DIAGRAM-HPCI SYSTEM 0-47E845-2........... FLOW DIAGRAM-COMPRESSED AIR-STATION SERVICE 2-47E610-99-1........ CONTROL DIAGRAM-REACTOR PROTECTION SYSTEM 2-45E614-5,-6........ SCHEMATIC DIAGRAM-REACTOR & REFUELING ZONE ISOLATION 2-45E779-16.......... SCHEMATIC DIAGRAM-480V AC REACTOR BUILDING PUMPS 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 ~=l~~~t~=~s:; ::::: ::::~a2,R8CA8~~~R~O!s~~5i~GGJ~TT~EATMENT 2-47E610-71-2......... MECHANICAL CONTROL DIAGRAM RCIC SYSTEM 0-45E773-3............ WIRING DIAGRAM 480V AUX POWER SCHEMATRIC DIAGRAM 2-47E611-1-SERIES..... MECHANICAL LOGIC DIAGRAM MAIN STEAM SYSTEM 2-+7E611-6+-SERIES.... MECHANICAL LOGIC DIAGRAM PRIMARY CONTAINMENT ISOLATION SYSTEM 2-47E611-68-SERIES.... MECHANICAL LOGIC DIAGRAM REACTOR WATER RECIRCULATION SYSTEM 2-47E611-69-SERIES.... MECHANICAL LOGIC DIAGRAM REACTOR WATER CLEANUP SYSTEM 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 AMENDMENT POWERHOUSE UNIT 2 BROWNS FERRY FINAL SAFETY NUCLEAR ANALYSIS 27 PLANT REPORT CONTAINMENT SYSTEM PRIMARY MECHANICAL CONTROL DIAGRAM FIGURE 5.2-2a SH 2 H G F E D C B A

zso~ l-t9-0l93Lt-£ V'l L9 M __ /xs\\ ___ ~ ___________ J 64-4C 64-48 I 3-47Ll847-8,83 'T""" ~--/Hs'\\ ~ ~ I

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~< - <~ 0~ ~~ '1' I I I (Hs\\_ I 64-23A ----t I I ~ 64-23A y I I 7' ~ / / / / / / ~ N / / w / I / / z / w / IL / / w / z / ~ / / ~ N / / w ' / I / / / ~ / / / I ~ 64-238 'f (Hs\\_ I 64-23B--- I 1 64-38 64-3C 'Y' f------------, I I I (Fed\\ I I s+-Js I I 0 m w I w ' 0 I I I -+---i ~ ! (Hs\\_ ____ _/xs\\ 'f' 164-11C co 64-118 co '--r"" I ~ I I ~ ILi V I I w I "f ~ I '°

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  • ~

r I r r- ------*-, PDM I I 64-2A '1* f FCO) I 64-118 I ~~~~~ ~ I I .... -I~ 0 FANXA i 0 ~ FAN-64-110 I ~4~i 2f------~ ! I

  • ---~----------*

~ ~ RPS ANALOG TRIP POWER l3-47E610-99-1>--~---§)(D I 3-47E610-99-1 >--1 DIV IIA>----§) l3-47E610-99-1 >--1 DIV IB >----§)@ l3-+7E610-99-1 >--~---§)© ECCS ANALOG ~o* TRIP POWER r l..!:'..:!./'V 13-47E610-71-2>--~+~ I L-@) r~ 13-47[610-71-2>--~+~ ~ ix 8 ~ i...i 19-3A 0 ~ w iii {PDA' ~ ~~ 64-27 ti]~ O~<i ~< 3 I 6~7 ~

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~ ~ ft ~ f YxA N,... zo.... -w - ~~ w W< ~ ~J "' ~o.... ~"' ' ~- ~ I L-@) ~-,L_3_-4_S_E_6_2_0_-_3__.r----, 3-47E3847-8,A4 1~3--_*s_E_s_,._-_s_~r_, 3-47E610-84-1,C7 3-47E610-64-3,84 QD-3 64-21 8 7 HARDENED SUPPR CHBR VENT (FSV-64-221. 222) 'Y' FCV I ~~ 64-21 ~~ I I L ____ }i!' ____.J I L--4------...::1::.. _______ J .....,_ ___.. r.J I I 1---- 0 ROOM AIR 6 REFUELING FLOOR EXHAUST FANS r--------* I r------ ~ ~ 9-25 FCO 64-9A X I FCO ~~ 64-1 DA 9_25 .J. I 3-4SE614-6 ~-, I I ~-----~ ~ ~ ~ ~ ~ ~ 0 ~ ' w ~ J ~ 0 ' ~ ~ ,---t.;.....,_ TD REFUELING I ZONE (i;-25 HS 64-9 PA-64-58 r-<THIS DWG,D5 I I t-73-45'670-271 I ~---@)@ ~-81 {PIS'\\

  • 1:_,.

~ 64-58[ 25-5A 9-81 PT __ jPis\\_ _____ 'f ___ _ 64-578 64-578 I I I 25-5A I {ei'\\ __ /PJs\\:'~~~--l---- 64-510 64-570 - 5 ,-4-25 L!fil 64 --~ 3-45E670-26 X-27 r-----------------------------------------------------------------------------------------7 3-47E3847-5,A3 PUMP MOTOR D PUMP MOTOR C (T0, 64-71 '° ~ t m ~ ~ ~ MCC r--- FSV 1 I 64-11 Ay--y'-t.J.LcU FS Lf--l,L-JC1.l-~64-12A 1 64-70 [:i MCC ~ ~ )-;;{ PUMP MOTORS B & D (T0, "t '>i(' IL-64-72 ~ I ~ I ~ ~ r---------+----J StJ._., 1118 I I I I I I I ~ I FAN A I / XS \\_J FAN-64-11A 1 ~ 64-11A ~ T L----1 XS-64-118 .............. 9-25 ~ .L...!§__\\ ~---- 64-11 A - (Fed\\ 64-11A X N w w I I ~ ~ REACTOR ZONE EXHAUST FANS N N w w ~ ~ ~ ~ (Fed\\ 64-12A + X N I PUMP MOTOR 8 64_69 ,)., )-':-<. IL-64-68 ~----t---l/HS'\\ 64-68 I 64-68 64-73 ),-<. ~---i--l/HS'\\ 64-72 I 64-72 I I L--..----------------~ I 64-12A ROOM I A ROOM TO CORE SPRAY PUMP MOTORS A & C I 'r I I I I ~ I FAN 8 64-12B AIR COOLER A CLR-64-68 AIR FAN-64-68 COOLER CLR-64-72 FAN-64-72 fAN-64-12A RHR PUMP MOTOR A COOLER CORE SPRAY NW ROOM COOLER NE ROOM COOLER TYPICAL .--i?J I /, 9-25 I,~ ,,~ I I I I I I PUMP MOTOR COOLERS 8, C & D TYPICAL NOTES: 9-25 {FSv\\_ ___________ _, Gs:\\ 64-43 I 64-43 S 3-47E3847-7,C2 I 1. THIS CONTROL DIAGRAM COVERS PORTIONS Of THE FOLLOWING SYSTEMS: A. PRIMARY CONTAINMENT SYSTEM. B. SECONDARY CONTAINMENT SYSTEM. C. ATMOSPHERIC CONTROL SYSTEM. D. REACTOR AND TURBINE BUILDING VENTILATION SYSTEM. 13-45E614-S ~-, I r-13-4SE614-s I 25-222 LlD FCD[B----'-X'--\\-~*~*-l!J 64-3A I L-13-45E614-61 THE DIAGRAM INCORPORATES THOSE CONTROL DEVICES NECESSARY FOR AIR PURGE OF THE DRYWELL. DRYWELL PRESSURE INTERLOCKS TO ENGINEERED SAFEGUARD SYSTEMS AND PROTECTION SYSTEM, REACTOR AND TURBINE BUILDING ISOLATION, AND ZONE CONTROL RELATIVE TO BUILDING PRESSURE LEVELS AND RADIATION LEVELS. REFER TO THE LOGIC DIAGRAM 47E611-64 SERIES FOR THE SPECIFIC INTERLOCK FUNCTIONS RELATIVE TO THE FOLLOWING: I 25-213 I 25-221 { >---,,PDS ROC>A

    • SAIC AIR PDS 64@/D

~ OUTSIDE AIR 3-FAN-064-0135 MAIN STEAM VAULT EXH BOOSTER FAN (I5-64-67A.CJ 9-3 9-19 Gu LlD 64-159 64-1608

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'Y' LT-64-15981 I [E)----1 AS-SA L...,._J PT) [J][J_ __ J 64-1608 ~ SEE NOTE 6 } ROC>A AIR LIMITER 64-38 'Y' I .,...-l-25 ~------~ I 64-38 I I l2s-222 A 64-38 FE J---------------t-i 64 1268 ( PA-64-58 >-------, 9-82 r--------------J--~ ~-ill)© ©(ill--1 S~F 9-25 *-1.,........, r--3:§l'.. 'r.::;{_~I I,¥ ~II I I ")C<_ I I I I I I I I I I I I

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9-25 l l I 13-4SE614-S r--+ I 2-47E610-64-1,E2 FROM HPC1 3-47E610-73-1,C2 TO FCV-84-20 3-47E610-84-1,G7 A-2s /....!iD 64 2.

3.
4.
s.
6.
7.
8.
9.
10.
11.

A. ISOLATION Of THE REFUELING ZONE AND REACTOR ZONE ON HIGH RADIATION.

8.

CONDITIONS CAUSING TRANSFER TO THE STANDBY GAS TREATMENT SYSTEM. C.

0.

VACUUM RELIEF FOR THE DRYWELL. INTERLOCK AND VENTILATING FOR TRIP REQUIREMENTS RELATIVE 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. DRYWELL PRESSURE AND TEMPERATURE AND SUPPRESSION POOL PRESSURE. TEMPERATURE. AND LEVEL ARE RECORDED AND/OR INDICATED IN THE MAIN CONTROL ROOM. 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. 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 PDC0-84-16 TO ALLOW OUTSIDE AIR TO 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 PDS-64-62C OR PDS-64-620 SENSES A ~RESSURE MORE NEGATIVE THAN -1/4* OF WATER, THEY WILL TRIP BOTH THE ZONE SUPPLY AND EXHAUST FANS. FIELD TO CONNECT PORTABLE GAUGE AND PLANT AIR, VALVED AS NECESSARY, TO DRYWELL FLANGE EACH TIME DRYWELL HEAD IS REFITTED, TO TEST SEAL OF HEAD. PURGE AIR FILTER. CRYENCO CONTRACT 85083. INSTRUMENT TAG NUMBERS ARE PREFIXED UNIT 3 UNLESS OTHERWISE NOTED. FOR REACTOR BUILDING VENTILATION AND REFUEL FLOOR RADIATION MONITORING SEE 3-47E610-90-1. THE VALVE POSITION LIGHTS COVERED BY THIS NOTE ARE LOCATED 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 TO MEET SPACE CONSTRAINTS, REFER TO MEL FOR COMPLETE UNIDS.

SYMBOLS: I J2S-SAI rt:~--....:...---:--'--,',--, I 3-4SE670-33 ~- I i-..::=====:..._--1 PT OIL FILLED RESERVOIR AND LINE CONTROL AIR SUPPLY I 3-45E670-32 9-82 ~- - --------~-ft!S\\ I 64-57A I X-52 I 9-82 'M7'-- - --------l-ft!S\\ ~ 64-57C - 4 PT 64-57A 25°=60 25-GA /PT\\ 64-57C 821 64-58F -~ PT./Pis't8S _,,;: 64-58H 64-56C ~OCT~ y~---- ~ ILOGI N 1 1 3-45E670-33r----J - 9JE015 ~ ,--l-_2S-6A~-6h-8~- I LOG I :!i ( PT l ( PT LJ PIS \\.l 9JE016 '° 64-58H 64-56D 64-56D -, "f I ~ ©@}+----- TO REFUELING ZONE MACH. ROOM t 4-608 ~---1 T REFERENCE DRAWINGS: 0-47E800-1.........,.. FLOW DIAGRAM-GENERAL PLANT SYSTEMS 0-47E800-2............ MECHANICAL-SYMBOLS AND FLOW DIAGRAM DRAWING INDEX 47W600-SERIES......,.. INSTRUMENTS ANO CONTROLS MEL................... INSTRUMENT TABULATIONS 47E605-SERIES....,.,.. CONTROL BOARDS 3-47E610-24-1....,.,.. CONTROL DIAGRAM-RAW COOLING WATER 3-47E610-76-1......... CONTAINMENT INERTING SYSTEM CONTROL DIAGRAM 3-47E844-2.......,.,.. FLOW DIAGRAM-RAW COOLING WATER 3-47E3847-SERIES...... FLOW DIAGRAM-CONTROL AIR SYSTEM 0,3-47E865-SERIES..... TURBINE & REACTOR BLDG. H&V AIRFLOW TO fCV-84-19 REST :-..J ROOM I _f-- 3-47E610-85-1......... CONTROL DIAGRAM-CRD HYDRAULIC SYSTEM 3-47E610-73-1..,...... MECHANICAL CONTROL DIAGRAM-HPCI SYSTEM 3-47E610-84-1,F7 X ,....i: __ :.-:::.1 -_+_~--~=-~-=~==!I!=,~--~-~-----m 1 ** :~% al I r-*-- ----, I ~ .. ~='-=--I ~ '{< I fm ls4-L300G CL I r--------- >,!X ~ I FCV ~ ~ I ~ I 9-3 I 64-30 9-3 I G ---------+ I I L.--- ------------- )c;,(_ 9-25 I A --------1-7 9-25 I 00-------~ 64-60A 1 I I I 3-4SE777-6 ~-1 {Hs\\_ _______ ~ MCC e~e r-----1--~ I __ J 3-47E610-84-1......... CONTROL DIAGRAM-CONTAINMENT ATMOSPHERIC 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 3-45E614-5,-6......... WIRING DIAGRAM 120V AC/250V DC VALVES AND MISCELLANEOUS SCHEMATIC DIAGRAM 3-4SE614-19........... WIRING DIAGRAM 120V AC[2SOV DC VALVES AND MISCELLANEOUS SCHEMATIC DIAGRAM 0-45E777-4............ WIRING DIAGRAM 480V UNIT AUXILIARY POWER SCHEt.tATIC DIAGRAM 3-45E777-3,-5,-6...... WIRING DIAGRAM 480V UNIT AUXILIARY POWER SCHEt.tATIC DIAGRAM 3-45E670-26,-27....... WIRING DIAGRAMS EMERGENCY CORE COOLING SYSTEM DIVISION 1 ANALOG TRIP UNITS SCHEt.tATIC DIAGRAM 3-45E670-32,-33....... WIRING DIAGRAMS EMERGENCY CORE COOLING SYSTEM DIVISION II ANALOG TRIP UNITS SCHEt.tATIC DIAGRAM 3-45E671-57........... WIRING DIAGRAMS REACTOR PROTECTIVE SYSTEM DIVISION IIA ANALOG TRIP UNITS SCHEMATIC DIAGRAMS 3-45E671-51........... WIRING DIAGRAMS REACTOR PROTECTIVE SYSTEM DIVISION IA ANALOG TRIP UNITS SCHEt.t DIAGRAMS. 3-45W671-63........... WIRING DIAGRAM REACTOR PROTECTIVE SYSTEM DIVISION II 8 ANALOG TRIP UNITS SCHEMATIC DIAGRAMS 3-45E671-69........... WIRING DIAGRAM REACTOR PROTECTIVE SYSTEM DIVISION II 8 ANALOG TRIP UNITS SCHEMATIC DIAGRAMS ~ I IL-64-60 7 ~ ~YiA ~ "-.C-r/

R
;-rx 3-45E779-16........... WIRING DIAGRAM 480V SHUTDOWN AUXILIARY POWER SCHEMATIC DIAGRAM 3-45E777-21.,......... 480V WIRING DIAGRAM AUX POWER SCHEMATIC DIAGRAM 3-45E620-8.-10........ KEY DIAGRAM ANNUNCIATOR SYSTEM 3

REACTOR ZONE STAIR SUPPLY FAN FAN-64-60 FROM FCV-64-141 AND DRYWELL COMPRESSOR 3-47E610-64-2,F5 COMPANION DRAWINGS: 1-47E610-64-1, -2 & -3 2-47E610-64-1. -2 & -3 3-47E610-64-2 & -3 TO fCV-64-141 AND DRYWELL COMPRESSOR 3-47E610-64-2,F2 3-47E812-1............ FLOW DIAGRAM HIGH PRESSURE COOLANT INJECTION SYSTEM 3-47E865-12..,........ FLOW DIAGRAM HEATING & VENTILATING ELEVATOR GE SHAFT AIR FLOW DRAWINGS: 21A1053............ GENERAL REQUIREMENTS FOR VACUUM BREAKERS 21A1363............ PRIMARY CONTAINMENT VENT, BUTTERFLY VALVES 22A1132AE.......... CONTAINMENT ISOLATION SYSTEM 22A1169..,......... DESIGN SPECIFICATION FOR REACTOR CONTAINMENT 3-730E927-17....... PRIMARY CONTROL ISOLATION SYSTEM 3-730E927-16....... PRIMARY CONTAINMENT ISOLATION SYSTEM AMENDMENT 28 POWERHOUSE UNIT 3 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT CONTAINMENT SYSTEM PRIMARY MECHANICAL CONTROL DIAGRAM FIGURE 5.2-2a SH 3 H G F E D C B A

! l I x f~~. L-j,l'! f--@-, ! ©~* 1 ____ 1 _____ _ 8 6 5 j ; i '-liil rn, ***.,m...,.,,...................... D--"-**-* t........ -... AMENDMENT 22 UNIT:! BROWNS F'ERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT H G D C B PRIMARY CONTAINMENT SYSTEM A MECHANICAL CONTROL DI AGRAM F'IGURE 5. 2-2b

llO~ £-t9-0 ~93Lt-Z V'-1 L9 8 TORUS PENETRATION (TYP)7 9-87 X-234A TW TE DIVISION I 64--161 64--161A,- 1A _j ___ 9... 57----7---------7 r-----------J L-~,--, I II ~ I 9--87 ~A, I ~ I x--2348 n TE -----~--r----- 1 ----1-------- 7 1 64-161 64-161 B I ~B 9-87 I I 9-87 I I 9-3 r1 ___________ J L _ _/rs\\___',-4 1--~M 1 1 r_.J ___ __/T!\\ 9... 87 ~* I I 64--161J I I ~61 I X--234C TW TE _/TM\\_' I I I 64--161 64--16.-cT-~c-r--- 9--87 :------r-- 1----, I L I CH 1 L------------J L _ _/rs\\___'_ II I II L -, CH-,-----, 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 ~87 '------1 CH 4 ---- 9--3 1------------J L_~s...J TM

t.£H_9___

TR ro rcs 2--45E614-21 9-87 64-161D7 64-161L CH 5 64-161 I X--234E ,-----1-------- 1 n TE TM --r----- 1 -----,..--- 1 __...., 1 cH s _/, 1 64--161 64--161E I 64--161E 9--87 I I r--- ---- 1 ___________ J L _ _/rs\\___',-4 I I I 1 --1 ~~ : __...J I r 9--87 ~EI I I I I,-1------__J i x--,,., n TE -----~--r----- i -----+---1 ___...J i i --@9--87 I 64-161F 64-161f 1 ~F 9-87 I ~-87 TM J L ~ I I-TM I I I 64--161M II --x--234;----;;-- ~87 -~,i I - 64--161K JI : II 9--87 1 64--1610,-~c-r--- 9--811 ----t-------- 1 ,.. _____.../TS'C_ t------------J L _ _/rs\\___'_j II I I ~J 71 9-87 ~GT I 11 TE __ 1 _...6iu:: __ r _____ 1 ____ L ________ _J ,L frst.87 1 64-161H ~H 9-871

~-..J l>--45E664--2 ~_J ____________ J L_ @61H--t--------------,

64--161K 9--87 I @,J DIVISION II 24VDC POWER SUPPLY FOR ALL -161 LOOP INSTRUMENTS r----- 1 I I I f--------f--rl"-,j SUPPRESSION POOL AVERAGE TEMPERATURE REFLASH: HI HI-HI HI-HI-HI ~-2--_4_5E_6_6_4--_2_~~r----------7 I 9--88 I 9--88 t------ @62M 11 x--2,sA n TE --~-~--r---------i------------7 64-162 64-162A ~A 9-88 rl __________ 7 L-~r, I I 9--88 ~A I I i x--,,,. n TE __.J._...6iu:: __ r----- 11 -----+-----------7 i I 64--162 64--162s ~* 9--88 I 9--88 I I t----------7 9--88 L_ @62s-f i-~62J I I i x--,,sc n TE --.l.-~--r-----1-------1------7 i i1 1 64-162 64-162C ~c 9_88 1 1 I r----------1 L_~,-4 I I I L_ I x--235D ~ 9--88 ~c I I I L __ I n TE __.J._ TM --r----- 1 ___ _J,....- 1 ----7... L ___ _ 64--162 64--1620 64--1620 9--88 I I (¢.;-t88 f-----------7 9--88 L_ @620--t-- ____ J ~,--------- 1 x--2,sE n TE --.l.-~--r----- i1 -------- i ____ __r----- 1 64--162 64--162E ~E 9--88 I r---- 1------------7 L_~_J I I I 1,-- 1 9--88 ~E7 I I I I i x--,,,, n TE __.J. _ _!rii"C __ r----- i -----+--- i ______ _J i I -@,-a L--- TI I 6<--162 I I I II L------~ ~ I I I I CH 1 ca,---7 - -----7 _I_Cjj_;!_ ______ \\ I - I_ !.!J.i - ----~--, _j_(;!il___ TR CH 5 64-162 __.£.H_J; __.../ I __ Q!L __ _, I __ CH 8 ____ J 64--162F 64--162F ~F 9--88 I I ~-88 I I ,..I ----------7 L-~,-4 1-- TM I 1 9-88 ~F I I 64-1621( I I ' 3 I X--235G TW TE .J. _lrii"C _M... 1 64--162 64--1620- -~c-r---0-ss :----,-----------...1 1 r-----~6** SUPPRESSION POOL SINGLE ELEMENT HI OR ELEMENT FAILURE L __________ l L_~,.... II II I 9-88 ~G I I x--2,sH n TE __.J. _ _!rii"C __ r _____ 11 ---~------------_J 1 64-162 64-162H ~H 9-88 I L_@62sr------------------~ I ~8J 24VDC POWER SUPPLY FOR ALL - 162 LOOP INSTRUMENTS ,-----t------1 2--45E614--6f----7 I I I ~OTES I ~~ I ~A I ,!.~ I )-;;-(_ :r ~ ~ i II ~ 64-222 ~ Ul EL 741 '-6" 9--3 LPNL-925-236 NOTES LS&.7 r-1 INTEGRATED LEAK RATE TEST ELEMENTS (SEE 0-471600-122 FOR GENERAL PLANT LOCATIONS) r-----------------------------------------------1 (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" EL 562'-0" (TE\\ (TE\\ (TE\\ (TE\\ 64--95 64-97 64-98 64-96 PRIMARY CONTAINMENT L __________________ \\ __________________________ J ...LSEE NOTE 3 r------------------ ----------------------------1 I EL 540'--D" I I I I I I I I /TE\\ /TE\\ /TE\\ /TE\\ /TE\\ /TE\\ I I 64-100 64-101 64-104 64-105 64-103 64-102 I I I I I I I I TORUS I L _______________________________________________ J HCVS PIPE El 666.5' ,.-a,-...- ABANDONED IN PLACE 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 TESTING.
4. ALL INSTRU~NT TAG NUMBERS ARE PREFIXED *2*.
5. INDICATING LIGHTS AND HANDSWITCHES LOCATED ON 2-9-3 MIMIC DISPLAY.
6. STRAP ON T/C DUAL ELEMENT TEMPERATURE SENSOR.
7. TIC-64-60 ONLY RECEIVES INPUT FROM TE-64-60A. CABLE FROM TE-64-608 IS SPARED AND ISOLATED IN LPNL-925-236.

REFERENCE DRAWINGS: 2-45E2690-41.... ICS BLOCK DIAGRAM 2-45E614-21..... RECORDER SCHEMATIC DIAGRAM 2--45E664--2...... WIRING DIAGRAM BAILEY CONTROLS COMPANY - TVA CONTRACT 82PJJ-830911: 0566641......... ANALOG LOGIC 08083601........ CABINET ARRANGEMENT J-08083602...... SCHEMATIC 08083603........ SCHEMATIC D8083604........ POWER DISTRIBUTION 08083605........ EXTERNAL CONNECTION DIAGRAM 080B3606........ EXTERNAL CONNECTION DIAGRAM EJ053355........ CABINET ASSEMBLY ARRANGEMENT GENERAL ELECTRIC - TVA CONTRACT 90744 2-791E4B9....... PNL 2-9-3 CONNECTION DIAGRAM NOTE 5 " ?l II TE TE L 64-60 64-608 8 ~ SUPPRESSION POOL TEMPERATURE MONITORING SYSTEM 2-47E2847-10 7 6 5 _1_9--4 ...l.1i::i 6~1/222 DET 2A3 UNIT 2 HARDENED WETWELL VENT (2-47E610-64-1) 3 PLANT STM:IC Cot.f'ANION DRAWINGS: 1-47E610-64-1,-2 &. -3 2-47E610-64-1,-2 3-47E610-64-1,-2 &. -3 AMENDMENT 27 POWERHOUSE UNIT 2 BROWNS FERRY FINAL SAFETY NUCLEAR PLANT ANALYSIS REPORT CONTAINMENT SYSTEM PRIMARY MECHANICAL CONTROL DIAGRAM FIGURE 5.2-2c H G F E D C B A

  • ~--~-*

.~-L~~--7~--~j; -~ I I 1 ~ 1/4~lil~~~:k:+ ~j --L ___ J.___ _ ~ .. ~ '.==-.@T-'-.;::l.. -- <l!J-.l..*= TIAlSINEflOOM-E)Q-JAIJS.fFAltS"-J 8 7 6 5 3 AMENDMENT 17 POWERHOUSE UNIT~ BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT PRIWIRY CONTAINMENT.SYSTEM MECHANICAL CONTROL DIAGRAM FIGURE 5.2-2d H G F E D C B A f

8 lO~ £-t9-0 (93Lt-£ ~ LS 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 j_ l 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 +- I ..JI L _Lrs'\\_',...J I I I I L __ l_.f.HNL_.! ___ l 9-87 -~c I I I I L---1-CHN..!,_L_-,

x-23;:_1i~ 6!:161o_T_ @6,o-r--- 9-87 :----L-~-87 --L~-----:-~~~~ ! ___ ~,

1 9-3 I L_~s.... T" __________, _<;!!N.b..!!.._ TR r---------- 9-87 64-161D I 64-161L ~ CHNL S 64-161 X-234E I _r------1----_,,, 1 rw TE ru --r----- 1 ___,..... __ 1 ____ 1 CHNL s../, I 64-161 64-161E s4-1s1E 9-87 r cHNL 7 1 I L ~_j I I I r---l-ciiNcs _ _, f-;_ 234,---------' 9-87 -~*7 I I I I,-:-------J 9-81 1 TW TE --T-~--r----- 1 ----'--- 1 ______ _J 1 1 64-161F 64-161F ~F 9-87 I I ~-87 I I t------ 64-161M ~----------j L_ *"~ +-- 6!~101* I I I X-234G ~ 87 I I I I ~67 64-1i~ 6!:1610-1-~c-r- @-87 :----r----------_J : t 1 -----~,7 r ------------' 64-161G"""1 I I I X-234H @9-87 I I 9-87 I TW TE --T-TM --r----- I ___ _j _____________ _J L ~ -t I 64-161 64-161H 64-161H 9-87

~K 3-45E664-3 ~!-----------J L_ @.1sf-------------------7 I

~7J DIVISION II 24VDC POWER SUPPLY FOR ALL - 161 LOOP INSTRUMENTS r----- 1 I I I t ----- --t--.l-",-l, I 3-45E664-3, 810 ~r----------, I a-88 ~-----~ I 9-88 f------~62M

  • -23:;_1i~ 6!:162,-~- @62A--r---9-8-.----r------------7 L

-@.-3 SUPPRESSION POOL AVERAGE TEMPERATURE REFLASH: HI HI-HI HI-HI-HI t L ~ I I ---,-- 6!~162

7 TS n

I I I 9-88 64-162A I I I i x-2358 Tw TE __ J._--6ii'S::-__ r----- 11 ----+-------------, i i L J:JJi<D I 64-162 64-1628 ~8 9-ss I 9_88 I I

~

l------------7 L_~_j t--~ II I I I 9-8s ~87 I ~ 62J I I X-235C TW TE __ J._--6ii'S::-__ T _____ 1 ___ --r---1------7 II I 64-162 64-162C ~C 9-88 I I L ~,...J I I I I L __ l_cHN!,_L __ r----------7 9-88 -~c I I I I L ___ I_CHN.b,.L_, 7 I TE __ J._--6ii'S::-__ r----- 1 ___ _1,-1-----, L _____ 1_cHN!,_3 ______, 1 L __________ 7 L_~s ;;-----J T" __________ _J_<;!!N.b..!!.._ TR 64-162D ~D 9-881 1 ~-88 L._ ______ I_CHt!b...i.-..,~-3 f 9-88 64-1 2D 64-162L CHNL 5 64-162 X-235E I -@ I _r----- _____ _,,, rw TE TM --r----- 1 ---,-- 1 ____ CHNL 6 ../, I 64-162 64-162E 64-162E 9-ss r---- ------ 1 __ CHN.1..L_..J r----------7 9-88 L_ @62(~ __.f.H.fil...§ ___ J i x-23s, Tw TE --.l.-~--r----- i ----'--- i ______ _J i i 64-162f 64-162F ~F 9-88 I I ~-88 I I I ----------7 L-~~ +-- T* I I 9-88 ~F I I 64-162K I I 9 3 I X-235G TW TE I ~ ~- I 64-162 64-162G_..,_~c-r-----88 :----,-.----------_J I t-----~628 L __________ 7 L_~,.... II II II 9-88 ~G 1 X-235H TW TE __ j__~--r----- II ___ _j _____________ _j I 64-162 64-162H ~H 9-88 I L-@s2sf-------------------J I SUPPRESSION POOL SINGLE ELEMENT HI OR ELEMENT FAILURE r-----------------------------------------7 EL. 653'-6" 3 @ 6 @ 5 @ 4 EL. 625'-0" 1 @ 7 @ 8 @ 2 @ 3 @ 9 @ 0 @ 4 (i?\\ ~5 (i?\\ ~7 (i?\\ ~* (i?\\ ~* (i?\\ ~* PRIMARY CONTAINMENT EL. 584'-0" EL. 562'-0" L-----------,-- _________________________ J HCVS PIPE 1 -----,-7 3-45E614-6f-l I I I I I ~OTE 10 ~' I )'o{___; ~ ~-, 64-222 ~:TE 10 "-SEE NOTE 4 INTEGRATED LEAK RATE TEST ELEMENTS (SEE 0-47W600-122 FOR GENERAL PLANT LOCATIONS) EL 741 '-6* (n\\,9-3 64-60 y ~NL-925-236 64-60 y 1...!iOTES 5 & 6 I -7 ~~ 64-60A 64-608 EL 666.5' r-l>----ABANDONED IN PLACE @:BJ 24VDC POWER SUPPLY FOR ALL - 162 LOOP INSTRUMENTS 3-47E3847-10 >----------e~:i.,,,_. FCV -- X FROM SHV-32-2704 64~ T1 SUPPRESSION POOL TEMPERATURE MONITORING SYSTEM 8 7 6 ~--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 .___, A ~ ~ ~ L __ ~ I ,a 6~1 /222 >a<--4 FSV "' O ~ 64-221 E ~:TE 10 3-47E3847-10

11~::1,t,>W FCV

-- X FROM SHV-32-2703 64-221 T1 5 ~--ili~o-;,~;------~ 3-47E610-64-1,C6 DET 3A3 UNIT 3 HARDENED CONTAINMENT VENT (3-47E610-64-1) 3 COMPANION DRAWINGS: 1-47E610-64-1, -2 & -3 2-47E610-64-1, -2 & -3 3-47E610-64-1 & -2 NOTES:

1. FOR GENERAL NOTES AND REFERENCE DRAWINGS SEE 3-47E61D-64-1.
2. ALL INSTRUMENT TAG NUMBERS FOR DIVISION I ARE 161 AND DIVISION II ARE 162
3. DELETED
4. TEMPERATURE ELEMENTS UTILIZED FOR LEAK TESTING DATA ARE INSTALLED IN THE PLANT AND ARE NORMALLY NOT ELECTRICALLY CONNECTED. THESE TEs WILL BE CONNECTED TO PORTABLE INSTRUMENTATION AS NECESSARY FOR LEAK RATE OR MISCELLANEOUS TESTING.
5. STRAP ON T/C DUAL ELEMENT TEMPERATURE SENSOR.
6. TIC-64-60 ONLY RECEIVES INPUT FROM TE-64-60A. CABLE FROM TE-64-608 IS SPARED ANO ISOLATED IN LPNL-925-236.

REFERENCE DRAWINGS: 3-45E614-21..... RECORDER SCHEMATIC DIAGRAM 3-45E664-3...... WIRING DIAGRAM - TORUS TEMPERATURE MONITORING SYSTEM SCHEMATIC DIAGRAM SH-3 3-45E3690-41.... ICS BLOCK DIAGRAM 0-47W600-122.... MECHANICAL INSTRUMENTS AND CONTROLS 3-791E490-2..... PNL 3-9-3 CONNECTION DIAGRAM BAILEY CONTROLS CCJ.lPANY - TVA CONTRACT 82PJ3-830911: 0566641.... ANALOG LOGIC D8083601... CABINET ARRANGEMENT 08083602... SCHEMATIC 08083603... SCHE*ATIC 08083604... POWER DISTRIBUTION 08083605... EXTERNAL CONNECTION DIAGRAM D8083606... EXTERNAL CONNECTION DIAGRAM E3053355... CABINET ASSEMBLY ARRANGEMENT AMENDMENT POWERHOUSE UNIT 3 28 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT PRIMARY CONTAINMENT SYSTEM MECHANICAL CONTROL DIAGRAM FIGURE 5.2-2e H G F E D C B A

IIOI Z-tl..Olt]Lt-1 l'I lt r--- i I Mfflorlln,.,... ~-:-~--~~-- c:::::z,~ 1 H H r--- 1-~ I L~ -1,i.&LU. ...... -! 0 0 ~: ~"::.J5... o............,... ;,.J .. ------1 l I I _u

  • ~..

@--T- ~*---@ r---+--- t-+............., L-,::m:1:::111 i 1§' -.r ***to' mw.=w...-: ~ ~ I ;:::iui::1:1 fi '°!~~------...1 ~ --a_... _, r--------m~

r-------m-~
1 ~"::

AMENDMENT 22 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT H G D C B PRIMARY CONTAINMENT SYSTEM A MECHANICAL CONTROL DIAGRAM flGURE 5.2-2f POWERHOUSE UNIT 1 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT PRIMARY CONTAINMENT SYSTEM MECHANICAL CONTROL DIAGRAM FIGURE 5.2-2f

8 7 TORUS PENETRATION (TYP)7 9-87 X-2J4A TW TE __r;:;;-c DIVISION I 64-161 64-161T1-~1,-j---*-B1----7---------7 r ___________ J L-~~ I 11 ~ ~ 9-87 ~ A I I 1 x-234B n TE --.--~--r----- 1 ----1--------7 1 I 64-161 64-161 B I ~* 9-87 I I 9-87 I I 9-3 ~-----------J L-~~ +--~ I I 1 _...! ___ ____uu I 9-87 ~* I I ~61J I I ~61 x 234C n TE --.--~--r-----1-----+---,----,, I 64-161 64-161C ~c 9-87 1 I L I CHNL 1 J L ~s I I I - -------, ~ t----------- 64_1610""1 1 1 1 L __ I..fHN!,_L_ +-- LOG I X-234D TW TE _o;:;-t87 1 _J_ I L ___ I _sHN!,_3_ """"\\ I A4127 I 64-161D 64-161°01-~ -r--- 9-871 ___ -~-.-77L ____ i CHNL 4.::::~\\ 9-3 L ___________ J L_~_J T*

r-.f.H..!:!.L_9__

TR r 9-87 ~D7 64-161L CHNL 5 64-161 X-234E ~ I ,------1-------- 1 TW TE --r-- T* --r----- ----.---I---' I CHNL 6 _/ / I 1 64-161 6+-161E 6+-161E 9-87 I r--- ---- J L ~s, I I I r--1..f!!!'!c....L_...J I ~----------- CHNL 8 I 9_87 6+-161E I I I I I r-1------....l x-23+* n TE ---.--~--r-----, -----+---' ___ _J -@9-87 64-161F 64-161F 1 ~F 9-871 I ~-87 ~----- TM I J L ~ T* I I I 6+-161* t----------- 9-87 -~,""1 i-64-161K I I I 1 x-23+G n TE ---.--~--r----- 11 ____________ _J 1 1 -@,9-87 I 64-161 64-161G 1 ~G 9-87 I I r------ TS L ___________ J L_~_J 11 1 I 6+-161J 71 J 9-87 ~G J I 1 x-23+H n TE ----~--r-----' ----L--------_J 1L __/rs'\\"_87 1 I 64-161 64-161H 1 ~H 9-871

~-

I 1-+sE66+-1,a+~-j ____________ J L_ {rlys1Hi---------------, 64-161 < I DIVISION II I 1-45E664-1, 9-87 I ~~ I _J r----- I 24VDC POWER SUPPLY I FOR ALL -161 LOOP 9-J I SUPPRESSION POOL AVERAGE TEMPERATURE REFLASH: HI INSTRUMENTS I TA _j I 64-162A HI-HI HI-HI-HI 24-VC POWER SUPPLY FOR ALL -162 LOOP INSTRUMENTS I I TS r----- 64-162K I 9-88 t------@62M I 9-3 f----,--@s2 I I iLOOl I CHNL,L-----~ ------, -I..f!!!'!c.... L - , t-iLOOl -1..f':lli!,_3_"""" \\ -~ -1 _CHNb,_!,_-----~-3 L.. CHNL 9 TR

__CHNL 5 ~

64-162 ..f!!!'!c.... L _/ I I CHNb,_l.,_ _ _J I __ CHNL 8 ___.J SUPPRESSION POOL SINGLE ELEMENT HI OR ELEMENT FAILURE r------r-41-45E614-6 I 9-3 I ~

  • I CD I

. N ~~:r2A ~ ; ~ ~ ~-3 64-222 Ul l.1§.) !;: es 6... -2228 I ~ SUPPRESSION POOL TEll'ERATURE MONITORING SYSTEM ~ ,~-, 1-47E1847-13, D3 FROM SHV-32-2704 2721 TT I I ,---,----------------U ili ~ 1-47E1847-13, EJ FCV X s4.::31 TT FROM SHV-32-2703 2720 I I ,---,----------------U ili ~ 9-3 1-47E610-64-1.C6 6 5 (TI\\ 9-3 ~b @ 9-3 I 2 El 741 '-6* HCVS PIPE LPNL-925-236 y" LNOTE 4 r-1 3 NOTES:

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

3. ALL INSTRUMENTS ARE PREFIXED WITH A UNIT 1 (1-) UNLESS OTHERWISE NOTED,
4. STRAP ON T/C DUAL ELEMENT TEMPERATURE SENSOR.

REFERENCE DRAWINGS: BAILEY CONTROLS CCMPANY - TVA CONTRACT 82PJ3-830911: D566641,........ ANALOG LOGIC D8083601........ CABINET ARRANGEt.ENT D8083602........ SCHEMATIC D8083603........ SCHEMATIC D8083604........ POWER DISTRIBUTION D8083605........ EXTERNAL CONNECTION DIAGRAM D8083606........ EXTERNAL CONNECTION DIAGRAM E3053355........ CABINET ASSEMBLY ARRANGEMENT EL 666.5' ABANDONED IN PLACE PLANT STACK COMPANION DRAWINGS: 1-47E610-64-1,-2 2-47E610-64-1, -2 & -3 3-47E610-64-1. -2 & -3 AMENDMENT 27 POWERHOUSE UNIT 1 BROWNS FERRY FINAL SAFETY NUCLEAR PLANT ANALYSIS REPORT CONTAINMENT SYSTEM PRIMARY MECHANICAL CONTROL DIAGRAM FIGURE 5.2-2g H G F E D C B A

......,~ _..,. BT Dlfl&t!II n ftOlll!IIS Plfl*~ ~>>---t , ~-, -,'l'!Pl--1-1* AMENDMENT 16 BROWN,J FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Types t)f Penetrations for Procea Linet FICURE5.2-3 f BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Types of Penetrations for Process Lines FIGURE 5.2-3

PUNMI! a.,AllltalT- <I. \\.. 11_.CAI. IIIIIUI - APIUIUU 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 ' -.2.9M 314 DE.TAIL £. 134 .SCAI-£: 2.,.8

  • t'-0" AMENDMENT 16 B.ROWNS FERRY NUCI..EAR PLANT FINAL SAFET"* ANAL VSIS REPORT Compression Fitting Assellbly for 5111all, Low Pnssure
  • Line Penetrations
  • FIGURE 5,2-4a BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Compression Fitting Assembly for Small, Low Pressure Line Penetrations FIGURE 5.2-4a

I I I I ~~"II" ' I h*-*----- 1, I',,,. ,i 1, r: I --* * -- ** ------ AMENDMENT 16 i,,, ti 'l... ~ 'I I . J.., _j i E. ,9 If,; J~ 1 ** ii 5 ,*] I C.i u ,\\ ' Ji I I ~ j(~ I ,, -~ I ; 1 4 i (!):;i Ii "'~ I (:I~ / I I.. I V q;' r le: -1 I,~ \\I~ BROW*NS FERRY NUCLEAR PLANT FINAL SAfETY ANALYSIS ~EPORT ELEffltCAL AND CORTllOL P~~TION FICUIE s.2-s ',I t

BFN-28 Figures 5.2-5b through 5.2-5e Deleted

z:z;o~ t-9L-O !93Lt-I 11',J L9 8 X-46A X-51A PERSONNEL AIR LOCK TORUS H202SAMPLE 1-47E610-76-3,J1 X-518 X-468 DRYWELL H202SAMPLE RETURN _ _,_ ____ 1-47E610-76-3,I1 7 X-52-2C -47E610-64-1, D4 @-18 y UNIT 1 SECONDARY CONTAINMENT 25-6 1 1~~4 I -4 PT --------------..l..----- @-3 ~ PC PM 76-1 76-14 7~~6 I r---------- -r--m l,~-~~-JL I 'Tr' PCV L_-rn-ISS ~OG I ' TI \\ 76-14 A 76 1 76-15 76-14 .,...1..... 19

  • LO~~~

9-3@ ~ -J HS7i"8 ~~ ,___..-, ~-iii ICI;SSI ICI;SSI 9-1~ ~:~1 8 B ~ L L--.-.------7 1-47E1847-8, GB 7 I YARD FROM CONTAINMENT INERTING NITROGEN MAKEUP SUPPLY PI _I-,~~ 76-50 I I I I FE TW '-1'""---~f,----TT-----+-----< 76-16_............ __ 76-15 0-47[610-76-1, 11 I DRYG-76-1 SHV-76-538 CONN FOR PORTABLE N2 BOTTLE CKV-76-551 CKV-76-552 TO ORYWELL CONTROL AIR I 16-l 539 X I I ,----f--3'§t ~*-3 I L~ 16-~1 fil~ I +:'.--------- CISS LOC I _J ~------- A HS7617 I fFSV)... __ _ -1 1-730E927RE-16 C71 76-17 7 I PURGE AIR SUPPLY I FROM REACTOR BUILDING I VENTILATION SYSTEM ~~ --r-m~L FI 76-502 I~ ,...;.l ______ _,__-<,-41Es10-s4-1 as +-3§:( 9-3 I 00 L ~~ ---cIT~ X-35F TO INDEXING MECHANISMS 1-47[600-14 ~ 15 PRIMARY CONTAINMENT DRYWELL BLOWERS DRYWELL H202SAMPLE 1-47E1610-76-3.(F8) 6 I~ MIMIC I 9-3 ~ E7) I :::ro< 76-24 TO HS-64-25 iJB.I. 'f---<1-47E610-64-1 I X X 1 I I I I (FCV', 9-3 MIMIC I 76-24

  • f

-I I I-TW Q------6-2.J-J.... ---'. ~@9-3 6~~r. ~ X ------ L---~ __ _J .J J-1-'-----1 / X

1'.--~-----

-m I H~~.1 ~I I ~nrt,.., I I MIMIC I (FCv', 9-3 I 1s-1s ~ f ~---~=:::::.-=. G R i I X L_.J.. "'"1 1-730E927-17A, 7 I SUPPRESSION CHAMBER 5 ~ ~ -,--~~L L Jc:iill_~ m~ L_ ~ 1-730E927-17A, 18

~~

---cIT~ FROM CONTAINMENT INERTING NITROGEN PURGE SUPPLY 0-47E610-76-1, J1 3 COMPANION DRAWINGS: 0-47E610-76-1 2-47E610-76-1,-4 3-47[610-76-1 -4 1-47E1610-76-j 2-47[2610-76-3 3-47E3610-76-3

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 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 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 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 ARE USED WITH THE CONTAIJIIJENT ATh,OSPHERE DILUTION SYSTEM.

(SEE 1-47E610-84-1.l 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.

7. AN INDICATING RECORDER. 02R-76-39. 41 IS SUPPLIED TO RECORD THE ANALYZER MEASUREMENTS IN THE CONTROL ROOM. A 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.
8. SEE 45N1631-24 FOR CONNECTION TO SPARE SENSORS.
9. ALL INSTRUMENTS ARE PREFIXED "1-* UNLESS NOTED OTHERWISE.
10. ALL NUMBERED MANUAL VALVES ARE PREFIXED *1-76-* UNLESS NOTED OTHERWISE.
11. UNIDS ON DRAWING ARE FOR REFERENCE ONLY AND ARE ABBREVIATED TO MEET SPACE CONSTRAINTS, REFER TO MEL FOR COMPLETE UNIDS.

REFERENCE DRAWINGS: MEL................... CONTAitlvlENT INERTING SYSTEM INSTRl..t.tENT TABULATION 0-47E610-12-1......... MECHANICAL CONTROL DIAGRAM-AUXILIARY BOILER SYSTEM 1-47E610-64-1......... MECHANICAL CONTROL DIAGRAM-PRIMARY CONTAINMENT SYSTEM 1-47E860-1............ CONTAINMENT INERTING SYSTEM FLOW DIAGRAM 471600-134............ CONTAINMENT INERTING INSTR. AND CONTROLS DIAGRAM 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 ATMOSPHERE DILUTION SYSTEM 1-47E600-14 ~ 15...... MECHANICAL INSTRUMENTS AND CONTROLS 0-47E610-65-1......... MECHANICAL CONTROL DIAGRAM STANDBY GAS TREATMENT SYSTEM 1-45E615 SERIES....... CONTAINMENT ISOLATION STATUS SYSTEM (CISS) GE DRAWINGS: 22A1209AB............. ATMOSPHERIC CONTROL SYSTEM DESIGN SPECIF I CATION 21A1375............... PRIMARY CONTAINMENT OXYGEN ANALYZER SYSTEM BASE SPECIFICATION 21A1370............... MISCELLANEOUS VALVES FOR ATMOSPHERIC CONTROL SYSTEM, PURCHASE SPECIFICATION 1-730E927-16A,-17A.... PRIMARY CONTAINMENT ISOLATION SYSTEM SYMBOLS: NITROGEN CONTROL GAS SUPPLY LINES. AMENDMENT 27 POWERHOUSE & YARD UNITS 1 & 0 BROWNS FERRY FINAL SAFETY CONTAINMENT MECHANICAL NUCLEAR PLANT ANALYSIS REPORT INERTING SYSTEM CONTROL DIAGRAM FIGURE 5.2-6a SH 1 H G F E D C B A

CLO~ t,-9L-0 L93Ll>-Z ~ L9 8 AMENDMENT 24 PO\\IERHOUSE UNIT2 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT H G D C B CONTAINMENT INERTING SYSTEM A MECHANICAL CONTROL DIAGRAM FIGURE 5. 2-6a SH 2

L-9£-0l93Ltr-f i,,. L9 I ,,.,. '""~, " __ J -iii ~ AMENDMENT 24 POWERHOUSE UNl13 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT CONTAINMENT INERTING SYSTEM MECHANICAL CONTROL DIAGRAM FIGURE 5.2-6a SH 4 D C 8 A

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

~ ~ ~ I ~,_,,: @,_,, I i&'" L_J L_'Y L_J L ____ i ____ _J ,_,.w: Y' ' .@-1~-F=~-~:'~'-~l Wffi--j I ~l*"*I ~--~----~--1 I I I 8 ,,::*,,.'""-***@--co

  • -,,,'"" _,,, @-- co
  • -',,,"'""""' @--co a - --@ """'","""-"

,@,c.:S'OC"""" AMENDMENT 24 P0\\IERH0US[ UNIT1 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT CONTAINMENT INERTING SYSTEM t.1ECHANJCAL CONTROL DIAGRAM FIGURE S.2-60 SH 7 H G D C B A

l-09-0193Lt-lV<L9 AMENDMENT 25 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT

LlOiJ l-08-0l93Lt-Z Vil L9 8 VESSEL HEAD ~ ~ I TE TR-68-37 /2 68-37B.,....IR-68-37 /1 ~-4 ~ TE 'ic REACTOR%" 25-397 VESSEL TE --l--468-37 A r:::-...XR 56-12*~--....J TE ( XK \\ 8-7 3-238 ~=*~'~*~-~ y l2-47E610-3-1.f6>-7 TE sea t'----------- TE I 3-&E1 I I q;_ FW TE 56-16 y I I L __ TE 56-19 TE 56-22 VESSEL MOUNTING FLANGE CONTROL ROD DRIVE HOUSING TE 56-39 TE -- 56-40 TE u.....-----56-3 8 DRAIN TO CRW VESSEL TEMPERATURE MONITORING 7 6 5 PUMP MOTOR B RECIRCN PUMP MOTOR A ORB (TE\\ 80-26 (rr\\_ _____________ 2~~~~. 80-27 (TE\\_ ___________ TR-80-1-28--J 80-28 I I TR-80-1-21 I ~------------""! ~ _______ _TR-80-_t-22--: {7E\\_ _ - - - - !!-.!_Cl:.! :.!,3_ I 80-23 'II TE (NOTE 5) I 80-24 -------""'1 TE _TR-80-..!._-25 l 80-25 I UPPER SUPPLY! RING HEADER I I I I SUPPLY DUCT I TO UPPER AREA I

~:--~-----------7

'i' I I I ~I I I "i' I I I 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.
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 SPACE CONSTRAINTS, REFER TO MEL FOR COMPLETE UNIDS.
8. DELETED.

REFERENCE DRAWINGS: 47W600-90................ INSTRUMENTS ANO CONTROLS 0-47E600-91.............. INSTRUMENTS ANO CONTROLS MEL...................... INSTRUMENT TABULATION-TEMP MON SYS TO MEET MEL...................... INSTRUMENT TABULATION-PR! CNTMT CLG SYS 45N803-SERIES............ CONDUIT AND GROUNDING DETAILS MEL...................... INSTRUMENT TABULATION-REACTOR FEEDWATER SYSTEM 0-47E800-1............... FLOW DIAGRAM - GENERAL PLANT SYSTEMS 0-47EB00-2............... MECHANICAL SYMBOLS AND FLOW DIAGRAM DRAWING INDEX 2-47E610-3-1............. CONTROL DIAGRAM - REACTOR FEEDWATER SYSTEM MEL...................... INSTRUMENT TABULATION - REACTOR WATER RECIRCN 45N2616-SERIES........... WIRING DIAGRAMS, THERt.40COUPLES & RTDS 45N2631-SERIES........... WIRING DIAGRAMS, MISC. 45N2635-SERIES........... WIRING DIAGRAMS, LOCAL INSTR. PANELS 2-47E600-7DJ............. INSTRUMENTS AND CONTROLS 2-47E610-90-1............ CONTROL DIAGRAM - RADIATION WNITORING 0-471600-110............. INSTRUMENTS AND CONTROLS SYS r-r-- -1 NI 'I -I 0 ~I o1 ~ i!:L I t ~* 9-*1 1 80-TE ---~:!!0.:.!~L-1 1 r---00 80-17 TE __ TR-80-..!_-.!!'~l I 9-3 ~I Joi r r I I I I I I SUPPLY DUCT ~ 80-10 80-19 I I I 80-TR-80-1-2o_J I ",~kl,.;%--- OLE-SUPPLY I RING HEADER.,,--RETURN RING I _____ HEADER TR-80-1-1v!I ZCll Zill => ',--"--I "' --' "'

TR-80-1-~I 80-16

-- __________ TR-80-1-~ ____________ _TR-80~~ TE COOLER A TR-80-1-~ 80-3 COOLER B TR-80-1-5 I _________.J .. -;==',--' zo 00 0 LL< U<C TABLE 1 TEMP ELEMENT LOG TE-56-13 A56013 TE-56-14 A56014 TE-56-15 A56015 TE-56-16 A56016 TE-56-7 A56007 TE-56-35 A56035 TE-56-8 A56008 TE-56-23 A56023 TE-56-26 A56026 TE-56-29 A56029 PRIMARY CONTAINMENT ATMOSPHERIC MONITORING TE-56-10 A56010 TE-56-5 A56005 TABLE 2 TEMP ELEMENT LOG TE-80-1 A80001 TE-80-2 A80002 TE-80-3 A80003 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 A80025 TE-80-26 A80026 TE-80-27 A80027 TE-80-28 A80028 TE-80-29 A80029 TE-80-30 A80030 TE-80-31 A80031 TE-80-32 A80032 3 AMENDMENT POWERHOUSE UNIT 2 26 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT PRIMARY CONTAINMENT COOLING TEMPERATURE MONITORING MECHANICAL CONTROL DIAGRAM FIGURE 5.2-6c H G F E D C B A

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 ~r-*------~ \\JE.NT PIPE 2" .GUILES ~" 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 CAD SYS (PEN X-50) TO ORYWELL 1-47E1847-6,D3 ~ L9 CONTROL AIR SYS 1-PCV-84-33 -47E1847-7.D SEE DETAIL 181 FOR FUNCTION (THIS DWG) 1-FCV-64-29 1-47E865-1,EJ rev 84-19 FLOOR EL 621 ,---------+1-47E865-1,E2 STANDBY GAS TREATMENT BLDG 2" ,----to*----.-.,,., FE !,--.--,,.-------------1 < 84-19

  • X 1-47E865-1,E3 N

N T m s. r DRYWELL 1 PSIG MAX r-t-, Tw_.----------------------, 84-32 DRYWELL (PEN X-25) 1-FCV-64-18 N 0 0 ~ CONTROL AIR SYS 1-FCV-84-34 r-1:-_---:4-:-7::-E1:-8:-4-:-7--7::-,--:D--:3---.. SEE DETAIL 1A1 FOR FUNCTION (THIS DWG) CAD SYS (PEN X-22) TO DRYWELL 1-47E1847-6 CONT ON (1-47E1847-7,D3) PCV 84-34 1/4" 32-1206 32-1254 32-1282 lsHOWN FOR FUNCTION ONLY FSV 64-34 FCV 64-34 'r.-1 1--:-'i '\\zONT ON (1-47E865-1, C2) 'r.-1 1--:-'i CONT ON \\XI (1-47E865-1, E3) y DET 1 A 1 (THIS OWG, GS) 1/4mis DWG,G7) ORV-360-720 RFV-360-712 (PCV\\ 360-700 VALVE SET AT 100 PSI VALVE SET SHV-360-748 AT 150 PSI PI 360-752 N...,. 0 m ~ z r TRK-360-758 FLEX NITROGEN CART B1 ORV-360-721 RFV-360-713 (PCV\\ 360-701 VALVE SET AT 100 PSI 1-47E865-1, E3 2" 1-47EB65-1. 85 TEST CONN 32-1205 1JUi--+--.... l-'---r'---'.;--'l"""f--r---l:Xx:J--l--+--+----ll<>II rsv 84-48 S TEST 1/2" CONN 84-679 84-678 p I \\--8r-4!)-067:J-7-A-l 84-51 1 /2"

i m '

m ~ m 3/4" m VALVE SET O 110 PSI 1 /2" N RTV-84-118A 84-675 84-674 84-669 1" SHELL EVACUATION O-RFV-84-518 AND PRESSURE RELIEF--=- YARD 0-PE l!L4!.."-Jlilil!lf-----\\ 84-1 1 0-RTV-84-100 FULL TRYCOCK 8 N 0 ~ '.. m ~ ' 0 TEST CONN 0 " m ' 3/4"

i 120 THV 84-37 121 SUPPRESSION CHAMBER 2

FLOOR EL 565 123 601 REACTOR BUILDING 84-704 TORUS (PEN X-205) 1-FCV-64-19 1-47E865-1, CS 1 /2" 2" N N N m T m 122 2" TEST CONN 3 4" m N m m N m 0 N m TEST CONN N m ' T m 3 3 4" 1 /2" N 0 m m N 1 /2" RTV-84-119A 84-612 2" l-~~ s TEST C~NN B (NOTE 7) 7 1 2" 84-619 84-618 p I );--8r-4C-061::}6-A-, 84-50 1 /2" 7 ~ 2 ~ 84-613 84-614 1" ~ 3/4" J m VALVE SET o 110 PSI VALVE SET o 100 PSI PRE 4-54 0 N m 0 N PCV 84-33 32-2570 32-1283 CONT ON 1/4" (1-47E1847-7,D2) 'ri,.t:i:;f--__J SHOWN FOR FUNCTION ONLY 2" FSV H f-'> ~CONT ON (1-47E865-1, C2) 84-19 CONT ON DET 1 Bl (THIS DWG, ( 1-47E865-1, (THIS DWC,H7)'Y GS) 2" f--m PCV 84-706 3-47E862-1,D 84-707 ao 84-703 0 SHV-84-671 N T m 2" 2" .... ---..------------------------------------------....IL...-----------'a...--oj3_47Ea62-1,07 2" SHV-84-670 NITROGEN STORAGE TANK A 4000 GAL CAP. 0-TNK-84-635 0 ~ N .250" 1 r C\\I 0 E = ~ I C\\I a: ~ ~ I ~~~o~~~;;:;:=i.J" 0-EQY-B4-516 r<n <IL 0-LT r,: 1-0 84-2 W-<- 1/1- .250" 0-SHV-84-520 .375" PI 84-708 SET AT 250 PSI 1/2" O-RFV-84-523 .375" SET AT 140 PSI .375" 0 0-FSV 84-5 s N o-r 84-7 N N ~ '.. m '

a

.... --*1 0-RTV-84-105 1 /2" 1/2" 1 /2" 0-RTV-84-104 ELECTRIC HEATER 0-HTR-84-5 AMBIENT NITROGEN VAPORIZER A 6000 SCFH 0-VPR-84-639 ! \\,->-, ~---, D PT . 250" rSET AT 140 0-RFV-84-136 SET AT 140 PSI I N ° 0-RTV-I:!::'? Ill 84-3 84-6001

C.--

IV ~ <n om 0 2". N O-SHV-84-135 1" ~---.-+-AMBIENT HEAT EXCHANGER O-HEX-84-641 0 SET AT 0-RFV-1-1 /4" 148 PSI -1!;;'? ~-512

i N

.250" 6: SET AT 120 PSI

1. -

l 2" 2" 0-RFV-84-513 VENT .375" 0-SHV-84-650 1 /4" 7 6 . 250" .250" YARD O-SHV-84-56 0-PE 1.!L4!.."-Jlilil!lf-----\\ 84-12 ' O-RTV-84-106 N .500" ~ FULL TRYCOCK FILL CONN 0-CKV-84-552 1 /2" SET AT 140 PSI PRESS. BUILD COIL 0-COl-84-644 2" NITROGEN STORAGE TANK B 4000 GAL CAP. O-TNK-84-636 N I 0 ~ N . 250" 1 /2" 1 /2" .250" PRESS. BUILD REGULATOR VENT 2" O-RFV-84-558 SET AT 140 PSI 5 1

  • 1
  • N SET AT 250 PSI 1 /2" 0-RFV-84-57 3 SET AT 140 PSI 0-FSV 84-16

~ 0 s .375" 'tr 0-RFV-84-563 SET AT 148 PSI 1 /4" . 375" SYSTEM PRESS.- TEMP DATA ZONE 2 3 4 5 6 7 8 DESIGN DESIGN PRESSURE (PSIG) TEMP (°F) 56 150 15D 138 FULL VACUUM 100 10D 3 281 150 -320 TO +100 -320 TO +100 150 150 AMBIENT AMBIENT .250" 1 2" 1/2" 0-RTY-84-111 1/2" . 250" 1 2" 0-RTV-84-110 1--*a.:2a:5a;O_" __ __. __ --(,O-PT 84-17 ELECTRIC HEATER 0-HTR-84-16 2 3 AMBIENT NITROGEN VAPORIZER B 6000 SCFH 0-VPR-84-640 CCJ.itPANION DRAWINGS: 2-.t.. 3-47E862-1 SHV-360-717 VALVE SET SHV-360-750 AT 150 PSI PI 360-753 0...,. 0 m ~ z r TRK-360-759 FLEX NITROGEN CART B2 NOTES: SHV-360-751

1. All INSTRUMENT/COMPONENT NUMBERS SHALL BE PREFIXED WITH THE "BFN-1" EXCEPI AS NOTED. UNIDS ON DRAWING ARE FOR REFERENCE ONLY AND ARE ABBREVIATED TO MEET SPACE CONSTRAINTS, REFER TO MEL FOR COMPLETE UNIDS.
2. All VALVES ARE SAME SIZE AS PIPING UNLESS OTHERWISE NOTED.
3. All PRESSURE AND TEST CONNECTIONS ARE 1/2" UNLESS OTHERWISE NOTED.
4. OPERATIONAL VALVES ARE SHOWN IN THEIR NORMAL OPERATING POSITION.
5. m ETC, DENOTES ZONE FOR DESIGN PRESSURE AND TEMPERATURE

~ GIVEN IN TABLE, THIS DWG.

6. FOR FSV-84-5 AND -16 RELOCATION SEE VENDOR DIGS 0-27204, 0-27203 UNDER CONTRACT NUMBER 84939.
7. ZONE 8 IS QUALITY RELATEO. AND Will ONLY BE USED FOR FLEX NITROGEN CARTS. FLEX NITROGEN CARTS ARE NOT NORMALLY CONNECTED TO SYSTEM 84. THIS CONNECTION TO BE USED FOR BEYOND DESIGN BASIS EXTERNAL EVENTS.

REFERENCE DRAWINGS: 1-47E865-1.......... FLOW DIAGRAM - HEATING & VENTILATING AIR FLOW 1-47E610-64-1....... CONTROL DIAGRAM - PRIMARY CONTAINMENT SYSTEM 1-47E610-76-1....... CONTROL DIAGRAM - CONTAINMENT INERTING SYSTEM 1-47E610-84-1....... CONTROL DIAGRAM - CONTAINMENT ATMOSPHERIC DILUTION SYSTEM 1-47E1847-7......... FLOW DIAGRAM - CONTROL AIR SYSTEM MEL................. VALVE MARKER TABULATION 0-47E800-2.......... MECHANICAL SYMBOLS AND FLOW DIAGRAM DRAWING INDEX 0-47E800-1.......... FLOW DIAGRAM-GENERAL PLANT SYSTEMS 0-171341-1.......... YARD PIPING MEL................. INSTRUMENT TABULATION (SYSTEM 84) GE DRAWING: SK-1................ CONTAINWIENT ATMOSPHERIC DILUTION SYSTEM P.t..lD CONTRACT NO. 74C35-84939 AMENDMENT 27 POWERHOUSE & YARD UNITS 1 & 0 BROWNS FERRY FINAL SAFETY NUCLEAR PLANT ANALYSIS REPORT CONTAINMENT ATMOSPHERE DILUTION SYSTEM FLOW FIGURE DIAGRAM 5.2-7 SH 1 H G F E D C B A

!.lOij ~-Z983Lt-Z V'-l L9 8 TRK-360-759 FLEX NITROGEN CART 82 360-701 VALVE SET G AT 100 PSI ~ DRV-360-721 RFV-360-713 {FCv\\ 84-19 X FE _ 84-19 ~~ FLOOR EL 621 ' 2* N ~ N TO STANDBY GAS TREATMENT BLOC 2-47E2865-12.D3 TRK-360-758 FLEX NITROGEN CART 81 DRV-360-720 RFV-360-712 360-700 e VALVE SET AT 100 PSI ~f--------l-+----l---i:xxJ----.--f>l<fL---lc.......JL,---4104----t,,'""11JUI N IIJUl--+-~J-L-++4>'<:f-.-------Ca:J-+--+------1f-----l~ SHV-360-751 SHV-360-750 VALVE SET SHV-360-717 AT 150 PSI 360-753 360-705 CONTROL AIR SYS .----t 2-47E2847-7.85 SEE DETAIL 2A1 BELOW FOR FUNCTION ~ HVAC DUCT (PEN X26) VALVE 2-FCV-64-29 2-47E2865-12.E4 N HVAC DUCT (PEN X26) r FT 84-19 ~ r /Fcv\\ 84-20 VALVE 2-FCV-64-31 2-47E2865-12,E4 ~ DRYWELL 1--@ SHV-360-716 1 PSIG t.1AX 360-704 VALVE SET SHV-360-748 AT 150 PSI 360-752 CONTROL AIR SYS ~----12-47E2847-7, 85 SHV-360-749 SEE DET 281 BELOW FOR FUNCTION TW);;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;,;;;;;,;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;1 ----------------'l'-----------------i 84-32 ~-/4 TEST CONN N CAD SYS (PEN X-50) TO DRYWELL 2-47E2847-5,C4 1/2" 1 *

I;

~ ' X 1 /2. TV-84-679 TV-84-678 TO HVAC DUCT 2-47E2865-12,C3 RFV-84-676 3/4" VALVE SET AT 110 PSI ~ 1/2" RTV-84-677 PREG 4-52 PI 4-51 ~ 1/2" VENT HVAC DUCT 2* 2-47E2865-12, 82 N 1/2" 1e* TV-84-120 TV-84-121 T ST VTV-84-605 \\ITV-84-604 CKV-84-601 SHV-84-674 SHV-84-675 CKV-84-66 RTV-84-118 X 1 " CONN TEST~ N CONN 7 ~ ~ Jl-+:i+._31.:,4~*~0lllf--{112

  • 1 TEST
i TV-84-630 TV-84-631 CONN 1

HVAC ~ 2-FCV-64-18 2-47[2865-12, 86 TEST BYV-84-687 BYV-84-686 3/4" 1" aoSH\\1-84-632

I;

~ N CAD TO DRYWELL (PEN X-22)

<12-47E2847-5, 04)

HVAC 2-FCV-64-19 CONN '--.,,4-"3!../+:_*~f,--, T\\1-84-619 TV-84-618 1/2" 3/4" ____/'pr\\ VENT TO 2-47[2865-12,86 2" TW 84-31 ~ SHV-84-622 RTV-84-616 ~O HVAC DUCT ~---l*--------<12-47E2865-12,83> rZ V,Z ~o rU "'112" X 1" ~ n:sT CONN ~ r SUPPRESSION CHAMBER VALVE SET FLOOR EL 565' VALVE SET AT 95 PSIG 1/2"X1" T'EST CONN RFV-84-704 1 2 TV-84-123 1 2. TV-84-122 2* 1/2"X1" TEST CONN PCV 84-654 8" 2-47E2847-5,C7 /4" .500" X 1/2" ~ 0 ~ ~ ~ u r ~ N r 1 AT 100 PSI >+ N w cc-Ji:'3"--'4'--"...:r"' ~ N >~ v,w 2* CKV-84-612 N 0 w ' ~ u N X r 1/2" I-'-----' r 1 /2" VTV-84-606 VTV-84-607 THV 84-38 RTV-84-119 FROM N2 TANK B 1-47E862-1.E4 1/2" VENT 1 /2" SHV-84-707 --1-- SHV-84-705 SHV-84-703 SHV-84-708 TV-84-702 (ecv\\ SHOWN FOR FUNCTION ONLY PCV 84-33 FROM N2 TANK A 1-47E862-1, E4 m--Lm (ecv\\ SHOWN FOR FUNCTION ONLY PCV 84-34 PI 84-708 REACTOR BUILDING CONT ON (2-47E2847, 8-5) 1 /4" I (Fsv\\ 84-19 CONT ON (2-47E2847-7. 8-5) 1 /4 * (Fsv\\ 84-20 f---CO(}------l>'<J------_J,FCV 84-19 32-1252 (Fsv\\ 64-29 ~CONT ON THIS DWG (G-5) f----{:>Xf---<1----{>'<f---------lFcv 64-29 32-1253 (Fsv\\ 64-32 ¥ ~CONT ON (2-47E2865-12. E-4) L-----CXXJ------{)J'<l--------{Fcv 64-32 32-1254 DET 2A1 G6 7 ¥ ~ONT ON (2-47E2865-12. 8-3) 6 f---t:o(}------l>'<l----------(Fcv 84-20 32-1248 (Fsv\\ 64-31 ~CONT ON THIS DWG (G-5) f---Co::l---0-----1>'<1---------(Fcv 64-31 32-1249 (FSV\\ 64-34 ¥ ~CONT ON (2-47E2865-12. E-4) L-----CXXJ------l>'<l--------{Fcv 64-34 32-1208 DET 281 G3 ¥ ~ONT ON (2-47E2865-12. 8-31 5 SYSTEM PRESS.- TEMP DATA ZONE DESIGN PRESSURE (PSIG) 1 56 2 150 3 150 4 138 5 FULL VACUUM 6 1 7 100 8 100 COMPANION DRAWINGS: 1- & 3-47E862-1 3 DESIGN TEMP( °F) 281 150 -320 TO +100 -320 TO +100 150 150 AMBIENT AMBIENT 2 NOTES: 1, ALL VALVES AND INSTRUMENT NUMBERS SHALL BE PREFIXED WITH THE UNIT NUMBER 2-I.E., 2-FCV-84-19.

2. ALL VALVES ARE SAME SIZE AS PIPING UNLESS OTHERWISE NOTED.
3. ALL PRESSURE AND TEST CONNECTIONS ARE 1/2" UNLESS OTHERWISE NOTED.
4. OPERATIONAL VALVES ARE SHOWN IN THEIR NORMAL OPERATING POSITION.
5. [I] ETC, DENOTES ZONE FOR DESIGN PRESSURE AND TEMPERATURE AS GIVEN IN TABLE.
6. UNIDS ON DRAWING ARE FOR REFERENCE ONLY AND ARE ABBREVIATED TO MEET SPACE CONSTRAINTS. REFER TO MEL FOR COMPLETE UNIDS.
7. ZONE 8 IS QUALITY RELATED AND WILL ONLY BE USED FOR FLEX NITROGEN CARTS.

FLEX NITROGEN CARTS ARE NOT NORMALLY CONNECTED TO SYSTEM 84. THIS CONNECTION TO BE USED FOR BEYOND DESIGN BASIS EXTERNAL EVENTS. REFERENCE DRAWINGS: 2-47E610-76-1........ CONTROL DIAGRAM - CONTAINMENT INERTING SYSTEM 2-47E610-84-1........ CONTROL DIAGRAM - CONTAINMENT ATMOSPHERIC DILUTION SYSTEM MEL.................. TABULATION OF VALVE MARKER TAGS 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 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 2-47E2847-7.......... FLOW DIAGRAM - CONTROL AIR SYSTEM MEL.................. INSTRUMENT TABULATION (SYSTEM 84) 2-47E2847-5.......... FLOW DIAGRAM - CONTROL AIR SYSTEM 2-4712461-2 & -3...,.PIPING 17W341-1............. YARD PIPING GE DRAWING: SK-1............ CONTAINMENT ATMOSPHERIC DILUTION SYSTEM P & ID CONTRACT NO. 74C35-84939 AMENDMENT 26 POWERHOUSE UNIT 2 BROWNS FERRY FINAL SAFETY NUCLEAR PLANT ANALYSIS REPORT CONTAINMENT ATMOSPHERE DILUTION SYSTEM FLOW FIGURE DIAGRAM 5.2-7 SH 2 H G F E D C B A

Z£0!1 L-Z983Lt-£ ~ LS 8 7 DET JA1 .250" PCV 84-33 0 0 ~ CONT ON I

  • 3-47E3847-7,A+

1 /4" CAD SYS (PEN X-50) TO DRYWELL J-47EJ847-5,C5 TEST CONN (NOTE 8) 1 /2" m m 1---, ~ m r "' u u ~ N 0 u ' ~ "' w 84-679 84-678 0 ~.. r 1/2" 84-677 7 2 3/4" VALVE SET o 11 a PSI ~ VALVE SET o 100 PSI N PREG 84-52 84-675 . g ~ N ' 84-676 1 /2" VENT 6D5 84-674 1

  • 84-669 1

2 6D4 RTV-84-118 SHOWN FOR FUNCTION ONL 32-1866 ~ 84-33 1/4" m 32-1250 ~ ~" Jt, >o ~~ ~"" ~r ~ z < r N z,. 0 ~ ~ TO STANDBY GAS TREATMENT BUILDING FROM 3-FCV-64-31 3-47E865-12.04 )>--- TO 3-FCV-64-30 ~-47E865-12,D41-- FROM 3-FCV-64-32 3-47E865-12, CJ 2" N TEST CONN N N 0 3/4".. FSV X s 84-8A 28" fF&, 84-19 X ~ 84-20 ~ ~ ~31 9 1 8" ......... -+

t-N ' " '..

r ~ FLOOR EL 621.25 0 FE 84-19. N ~ N " '.. r FT ~ 84-19 ~ DRYWELL u N -' z~ 0 ill rw z~ 0.. u.), 1 .., 84-20 "~ N r ~ ~ FE 84-2D ~ 2" PSIG MAX i's r z 8 r ~ 2" ~ ' ~.. m w 9 N ~ Z<O om w r~ z.. o, u" -r-+-a0 TW 84-32 ~ 64-18

fi18" 20" m+J I ~r-@

r 0 N CONT ON 3-47E865-12,B7 2" TW 84-31'--r--"l'P ~ CONN N N N N SUPPRESSION CHAMBER N 3/4" m 1 /2" t,!L~... I---Kl.--1 /2" X 1 " Tt:ST CONN 12D 0 0 N N :;; 0 N m w ~.. Csv\\ 64-32 ( j Csv\\ 84-19 1 21 601 1 2" 84-707 ~ 0 ~( XCO~T ON 3-47E865-12,83 FCV 84-19 N ' FLOOR EL 565. 0 1 /2

  • X 1 * ~.,[>f--~~1!-'/:!2_" ~:4--i TEST CONN 1 23 1 22 N

2" N ' ~ N 1/2"X1" TO 32-1230 TEST CONN --~.:j'\\ RFV 84-704 1

  • 3-47E3847-5,C71--""'I SET AT 100 PSIG g

~ 2" 1 /2" 1 /2" 84-703 84-709 0 N 0 0 0 ~ ~ N ~ ~ u O> ~ PI ~ ' ~ 8e,' N w ~ ~.. ~ ' ~ " REACTOR BUILDING SHOWN FOR FUNCTION ONLY 32-1208 ~ 8 -3 1 4" Csv\\ 64-34 l ( Q 84- 0 DET 381 1 /4" ICONT ON "3-47E3847-7,A't N ~ N 0 N m TEST CONN N N "' ' 3/4" I-""--' 0 N 0 2" THV 84-3 TEST CONN N ~ N m N 3/4".. m X 1/2" 1/2"X1" n:sT CONN N 1/2" 606 607 RTV-84-119 N N 0 a, ~ ' N z m r w N ~ z.. 0 ~ ~ FCV 64-34 Ej3 ~( X CO~T ON 3-47E865-12,B2 FCV 84-20 Csv\\ tTON Csv\\ ~TON 64-29 64-31 THIS DIG (G6) THIS OWG (GS) O> ~ 32-1249 wt, FCV Jt, 64-29 Ej3 >o ~~ ( ~( ~"' l ~( j ~r ( X CO~T ON X CO~T ON THIS DWG (GS) 3-+7E865-12,E4 DETAIL 3A1 DETAIL 381 G7 GS 8 7 6 5 1/2" VENT 84-612 CAD SYS (PEN X-22) TO DRYWELL 3-47E3847-5,D4 TEST 1 /2" CONN 84-619 84-618 84-616 Pl '--r-f>x:J-"'-'-1 84-50 7 N ' N 2 84-613 84-614 1

  • 4 3 4" VALVE SET o 110 PSI VALVE SET o 100 PSI 3

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.

~: s~~R~~~5~~~Ev~~eE~E~~Ec~~~i~1 12"¥H~~~ ~6~~A~N5~f~A9l~~R~E>§~r~8~:0* H

5. IT] ETC. DENOTES ZONE FOR DESIGN PRESSURE AND TEMPERATURE AS GIVEN IN TABLE.
6. ALL VALVES ARE PREFIXED WITH UNIT NUMBER "3-" UNLESS NOTED OTHERWISE.
7. UNIDS ON DRAWING ARE FOR REFERENCE ONLY AND ARE ABBREVIATED TO MEET SPACE CONSTRAINTS.

REFER TO MEL FOR COMPLETE UNIOS.

8. ZONE 8 IS QUALITY RELATED, AND WILL ONLY BE USED FOR FLEX NITROGEN CARTS.

FLEX NITROGEN CARTS ARE NOT NORMALLY CONNECTED TO SYSTEM 84. THIS CONNECTION TO BE USED FOR BEYOND DESIGN BASIS EXTERNAL EVENTS. REFERENCE DRAWINGS: MEL................... VALVE MARKER TAG TABULATION MEL................... INSTRUMENT TABULATION FOR SYSTEM 84 3-47E610-64-1......... MECHANICAL CONTROL DIAGRAM - PRIMARY CNTMT SYS 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 0-47E800-2............ MECHANICAL SYMBOLS AND FLOW DIAGRAM DRAWING INDEX 3-47E865-12........... FLOW DIAGRAM - HEATING~ VENTILATING AIR FLOW 3-47E3847-7........... FLOW DIAGRAM - CONTROL AIR SYSTEM 1-47E862-1............ FLOW DIAGRAM - CONTAINMENT ATMOSPHERE DILUTION SYSTEM 3-17W341-1.,.......... YARD PIPING GE DRAWING: SK-1..,........ CONTAINMENT ATMOSPHERIC DILUTION SYSTEM P~ID CONTRACT NO. 74C35-84939 TRK-360-758 FLEX NITROGEN CART 81 DRV-360-720 RFV-360-712 360-700 8 VALVE SET AT 100 PSI IIJUf->\\\\,-l-~l-'--.1-+-'J>l<I----.--C::o::J--+--1---+--....,_ f---m SHV-360-716 360-704 VALVE SET SHV-360-748 AT 150 PSI 360-752 ~.. ~ ' 0 ~ z r TRK-360-759 FLEX NITROGEN CART 82 DRV-360-721 RFV-360-713 360-701 8 VALVE SET AT 100 PSI SHV-360-749 ~ ~ ~ 0 0 ~ ~ z z r r 11JUi,....,1--1~-'--~----,--'C>1<1--.--ox::1--1---+-+----901 f---m SHV-360-717 360-705 VALVE SET AT 150 PSI SHV-360-750 360-753 AMENDMENT SHV-360-751 26 G F E D C B SYSTEM PRESS.- TEMP DATA ZONE DESIGN PRESSURE {PSIG) 1 56 2 150 3 150 4 138 5 FULL VACUUM 6 1 7 100 8 100 COMPANION DRAWINGS: 1-,t. 2-47E862-1 DESIGN TEMP( °F) 281 150 -320 TO +100 -320 TO +100 150 150 AMBIENT AMBIENT POWERHOUSE UNIT 3 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT CONTAINMENT ATMOSPHERE DILUTION SYSTEM A FLOW DIAGRAM FIGURE 5.2-7 SH3

~"';--1 ~- - -- ,..., ~~~~~l:r~r-=:-r...f;fl,'""i;:;:-J UNIT 2 UNIT 3 UNIT 1 B 6 r AMENDMENT 22 PDIEAIIOI.ISE UNITS 1

  • D BROWNS FERRY NUCLEAR PLANT F INA.L SAFETY ANALYSIS REPORT CONTAINMENT ATMOSPHERE DILUTION SYSTEM MECHANICAL CONTROL DIAGRAM FIGURE 5.2-8 SH 1 E

D C B A POWERHOUSE UNITS 1 & 0 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT CONTAINMENT ATMOSPHERE DILUTION SYSTEM MECHANICAL CONTROL DIAGRAM FIGURE 5.2-8 SH 1

7 !llfll;\\cc********,ffl~ ...,_,.,.,_,,..... ~ o----*.. -* G AMENDMENT 22 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT CONTA1NMENT ATMOSPHERE DILUTION SYSTEM MECHANICAL CONTROL DIAGRAM FIGURE 5.2-8 SH 2 D C B A POWERHOUSE & YARD UNIT 2 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT CONTAINMENT ATMOSPHERE DILUTION SYSTEM MECHANICAL CONTROL DIAGRAM FIGURE 5.2-8 SH 2

IE!E}! t---83

    • ~~

l J c--+/-i::;::!i='.-----1~ 6

.r-" *-**

- 'l!r Ji( llfr~lf ')j( ---!-..L;.--~:--__. l ---'---r- --------- --..1 .. ~ ---~-'a*-------. ---* _____.1,. __,g§l '*\\\\f."'"'""_""'_""",...,._... °"" __......... . ~~.,. lil.l~~.

  • -D(~*V,,..~'!.l!lll"'J"..::,mu'l-11..

'*lo!lllll.~.,,,,..*-ll'&"IIIIISl':,.".1\\1"' 'Mlt'"~..Jt ,._,_k-~~- *Q~'lf~,~1!'11.ll':'"'1.mD10WIT AMENDMENT 22 BROWNS FERRY NUCLEAR PLANT ,_'T'IIPOi',mm* FINAL SAFETY ANALYSIS REPORT H G D C B CONTAINMENT ATMOSPl-£R£ OILUTJ~ SYSTEM A MECHANICAL COITROL DIAGRAM FIGURE 5.2-8 SH 3 POWERHOUSE & YARD UNIT 3 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT CONTAINMENT ATMOSPHERE DILUTION SYSTEM MECHANICAL CONTROL DIAGRAM 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 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 21, ~ -----------------------------------~---~ D¥>ei + Wew eU Ox),ge11 IDl}9,'el + WetNe11 H}dr(>lf~II Z,:) ,= =* a, E

J 0

~ 6 1.:, 'i L ~ a, (J 5 u 0 0 ---"T"""-..--"T""""T""".,....,........ -t----.--"T"""............ "T"""........-t---....... --.-..............................+-----.----.----.----.-............,-,-1 o.o*

0. 1 10 Tine After Loe.A (days.)

BFN-28 Figure 5.2-13a Deleted by Amendment 28

BFN-28

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 Z,J ~ ----------~---------------------------------~ i.:1 I = C) E ~ 0 ~ ti \\0 e-

  • ~

~ C, 0 6 u Ntrog;en laj:,c6on .:, e-T V 0 +---~-~-~~~~...... --~.--~.--~~~~..,...,,-----r---r-~~~~~"T"""--~-~-~~~~..-i

  • J.o*
0. l
  • o Time After LOCI\\ (day s)

BFN-28 Figure 5.2-14a Deleted by Amendment 28

BFN-28 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 L':> ~;::::::::::::::::::::::::::::===.-------------~---------~---------~ 15 i: E

J 0

~ 6 iO "iii ~ OJ (J 6 u I N""Jtrogen lajeciion I Beans 5 

----+----------I

~ ~ L-- ---~....,........,.----- 0 +---,-----,-,--,.......,.........,.......,,------,----.----,~~-.-.--.-+------.----,-----,----.---.-.....,..-,-+----,----r---,---.-"T"""O--.-rl

  • ~.o*
0.

l 10 Time After LOCA (da.ys)

BFN-28 Figure 5.2-15a Deleted by Amendment 28

BFN-28

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 1400000 ~ --------------------------~----------------~ 1200000 c=- 1000000 0.e, 1:., E C 800000 oi 1: 0 0 2 i:,., 600000 i:, i:, <( C., C) E

! 400000 200000 0

20 40 60 80 100 Time After LOCA (days)

BFN-28 Figure 5.2-16a Deleted by Amendment 28

BFN-28 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 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)

BFN-28 Figure 5.2-17a Deleted by Amendment 28

BFN-17 Figure 5.2-18 (Deleted by Amendment 17)

EL639.0 EL 510.0 El 565.0 EL519.0 ELEVATION PERSONNEL ACCESS ROOM ROOF OPENINGS ARE FQR VALVE OPERATORS. MINIMUM FLOW AREA fS 10 SQ. FT. I0.5 11R DETAIL A < PLAN v1sw::1 (£L 590) I0.5"R AMENDMENT 16 BROWNS FERRV11flJql;EAR PLANT FINAL SAFETY,l\\NALVSIS REPORT ComoectlaR,l'low Path lhrouth Penon"",Accen Room FIGURJ 5.2--19 I

f:J 6

  • 4

. 1m11mm111n, .' STAIRWAYS ~. OPEf!I MATCH --D ~- ~

  • . *. -..... -* :*:~. ""* -:-.......,..,. _,,...,___,... **:._...,.....,..,...--,-_,..1.**':-;--,-...---.-~.'.

SLEEVE 00 ID UNJ !IN.I 1 311 35.&7 2 311 35.17 3 38 35.tlJ 24 23.61 FLOOR PLAN EL 565.0 FLOOR OPENINGS OD OF,Pll*tNC THRU SLEEVE INCLUDING INSULATION FLOW AREA CIN.I (FT.2t 25 3.5 29 2.3 29 2.3 1.9, 1.315 ....!:.L TOTAL 11.2 AMENDMENT 16 ~llffCtion Fl-Path Through Per111nnal Acaln:Roam FIGURE 6.2..-20

~VENTS---'i _ --~ STAIRWAYS -:;;?.~c;.:._,.... .-:~-:--:*-.:::,t PLAN EL. 519 AMENDMENT 16 BRO.Sf ER,fiV NUCLEAR !It.ANT FINAL Mi=Etv ANAL VSIS 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.}}

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