7
V'-1 Ls I I 1 REACTOR 8" ---< 2-47E818-1,C7 C--,,--'PS I /'. 71.:.!A f...--1 PDT PS PRIMARY CONTAINMENT \ SYSTEM PRESS. - TEii' DATA 1 .. FROM CRD LINE DESIGN DESIGN w I 71.:.!A 71.:J.B L_____r,;;\ CONDENSING NOTE 14 (TYP /, CHAMBER RTV-1AL 71.:!D 71.:JA ECKV-71-1AA (TYP 2) --;r:=CP:jO"-Ti:-7..:1_-1..:A: ..... --ll::F-:.!.l ;;," MAIN STEAt.4 ll .----1•:• 1 " X SlE -LECKV-71-1AB 2 47E801 1, FS - 1h 1 " X-33F L - I w w I tFE) 3" ECKV-71-1BA .---ti CPOT-71-18 RTV-lBL L._ECKV-71-188 - " 'h 3 1"-X-:;,3:.:<3-".E ---t<H:cJ--- 1' 1 " RTV-1 BH -@cv (TYP 2) FCV 1-2 1-3 r X-10 HPCI SYSTEM ____ ..,,} 2-47E812-1 GS FLG- 71 -l I' SEE NOTE 16 __..,, 3/4" SHV-71-62 : 5 12 FCVtJ •--l( 71-19 ' m . !l' ' ' I- i;;;: _____ .. u MK NO. PRESSURE (PSIG) TEt.tP( 't) 1 1146 562 2 150 325 1375 545 4 1500 200 5 150 200 6 1375 200 7 1500 40 TO 140 8 1250 575 9 165 366 10 270 415 11 400 450 12 250 150 13 100 103 14 200 200 LOV-565 1 4 ,, T 1/4" I ' i". > - ' ., I 3• 4" 4• (FE __ ______________________________ .;.._ .. ____________ ______________ .., _____________________________ ....... u w z - -" " < w w r N "' z - :ii 7..!_:J.B '- ...- .J STEAM /' DRAIN __,,,.. TEST N ' i". TEST (F5V\ w 1/2" . in .., ..:..:-1.-1--1_ DRV-556 SHV-556 U FCV 71-38 ......... --PUMP TEST RETURN TO ..,,,..- CONDENSATE STORAGE LOV-18 6" . co 71-20B,C--=-, 1 /2" PT LL-J:)o::!--f 71 -20 RTV-20 (PS' J/2" ' 71 - 21 A)r-{)o::!;_-f 1 " ..... _,. RTV-21 1--- .. RELIEF VALVE SET O 150 PSIG RFV-19 ---1: 2-47E852-2,B5 1 /2. 1 " VENT 1 " VTV-530 . 3/4" LOW POINT DRAIN 1 /2. w N 1 .. HPCI DRAIN VTV-529 14---< 2-+7E812-1. G7 I f. Fg_\_ '-----'---' TELL-TALE _j TO CRW •• < ' rW - "' 0 onz w onw w !;j: >-0 ' mu N v " w - r ' "' 0 1'ii ;; w a ; !;j: ... 0 ' .-1--UN ..,. i -"""-\. CKV-40 6" I y ' .. " r .-1--112· r , Tl::ST l N ' . ::::. "' TEST . . NOTE 15 SHV-553 DRV-554 -=-=1.5375" PR0-38 -37 6" . - LOV-37 z - < 0 r z - 0 !'; -" N N ' ;:; 0 71-358 PT 71-35 0.375. PR0-547 PUMP MINIMUM ,,,;t FLOW BYPASS___,,,,. /3/4" VENT m V SPOOL PIECE SPPC-71-19 (NOTE 13) 11 /2" PRESS. ..... -- 3/4" TEST . N 1 " ... .... .. RTV-4 TURBINE TRIP PT 71-4 PI 71-4B THROTTLE VALVE - FCV 2 ' 1-9 1/2" 8 TURBINE GOVERNING VALVE 1 " RTV-5H (t.tOUNTED TO TURBINE CASING) 1/2" 7 \.:: 1 E/ J;...ml 112..: 0.185" PI 71-56 PR0-9A,\-PR0-98 7 rs ::2 ABOVE AND BELOW SEAT DRAINS --..':::",f---J 1 " 2 , , - SHV-570 SHV-618 STEAM SUPPLY DRAIN POT CPOT-5 1 " RTV-5L 0 STEAM TRAP TRP-10 PISTON REMOVED SHV-617 SHV-571 1 • ... ,__ _____ TEST . N ' N z - 1 " CKV-3-572 (LG\ X-98 -' THIS DWG.C4 THERt.4AL SLEEVE . .. N \_REACTOR FEEDWATER LINE 8 w w :; ' N v 1 +f-+-[+8· I . N VENT TO - TO ATM < 0 AUX BLR SYS 2-47E815-4,G6 >--- - ' 1 .. _ I _ LS 1-5 . N rTl\ 71-509 : r 7 -46 T ...... 1-l"<J.! TW 1-1i2" TE om=,=- I 1" "">-'---I - [VENT r o::. -RPD-11B - "' 0 z < -" . - ' TE\ 71-47 '- ·11-46 ..----------<THIS OWG.C4 I 1/2" TEST_.. - ' > r !" ....... 1 O" w " - [ PMP-19 RCIC PIM' . n.- mo 00 'r- RPD-11 A ,_ _____________________ .., .... ,. ________ ..... ...,, - ' .. .... - TRB-9 Q[: 71-507, 1/2" TW 1 ..__ 1 F 2 " TE 1 • VENT__}, ,---1 /4" PI TI 7t:_01 71-45" 3t4n OI ,. 3 i /R" I ..- 71-24 t"''._ . .... ,..£>1..t L o TI 1 PUMP ..__. 112 ' 71.2..5 = ,- QI: N 0 DRV-45 Ct:. r' r ,I >- . w 1 .. -3 TW 71-23 ,_ 3/4" 1/2" GASKET TEST - - . - 2" ' CKV-598 CKV-597 < (HcV\ ':( 7,,1_;.!.4 L£>V-141/2" 8'"- I TEST ' N 2" 1 O" . - TURBINE EXHAUST ' ' ::::. N .. CKV-580 TEST SUMP I 3/4" PS 1 /4" ... ,___ ____________________ .. _ - . ' CKV-600 - . ' CKV-599 TURB EXH VAC RELIEF_J SHV -520 2" RCIC LUBE OIL PIPING DIAGRAM (C4) FCV , 1/2", j 1/2" CAP --._ .. 1/4" - X-218--- r 3 " 1' 4 !.. ..... 0 TEST SHV-602 - 0 w ' . N TV-603 . N N --r-STRAINERS b SUPPRESSION POOL RING HDR 7 - ' i". X-221-._ X-212 N 3/4" LOW POINT DRAIN TEST .. 1120 (sHV\ SHV-551 DRV-552 - 2" 71-32 ::-.-- 0. 625" .:..'::. PR0-551T 3/4" l<l---tc .......... ,.._-1 L TV-610 SHV-609 w J ' ' 1/2" TEST > iii 18" /X-210A N < 2-47E852-2, B5 !--"' 14 18" FROM RESIDUAL HEAT REMOVAL SYSTEM .... _2-47E811-1, E7 CONTAINMENT (sHV\ 71-16 7.,.1-_!.7 .. .. m ' > r TEST . ' CKV-592 I LOV-17 SUPPRESSION POOL SUCTION N w { 1" PRESSURE VALVE CONTROL ' r- ..... N '70 ' -" 71-22 1.{2" LOW POINT DRAIN 1--to .... --talll-----. SHV-538 DRV-539 1 " . N ' N N - "' " 1 /2" PT )-,-{)XJ---f 71-12 RTV-12 @ 71-12B EXHAUST . " •• DRAIN POT-- .... . w - TNK-642 ......... ,__,_ __ ..... ; ____ STEAM TRAP TRP-9 1 • PRESSURE RELIEF SET o 10 PSIG 2" - .J_ - ' m . N ' N VALVE - ' TV-540 m w .. z - (Pl) w w :i ' N RTV-27L 1 " 1 " 7Fo.416" PR0-540 ' N 0 r . 71-27: ,;;- . ::!: v --- TV-541 N v w i;1 < ITHIS .. ........ l_ BAROMETRIC - ' Go:J CONDENSER _ CND-27 t' ii' '.:"if'''::;'r'-@:::P::S::--. 2_5_0_" TANK ...... - w - < I ,... 3/4" THIS LUBE OIL COOLER 16 GPM 140"F MAX CLR-25 11-28!-;=Q 5 PRESSURE RELIEF VALVE SET o 75 PSIC RFV-543 """ H. 2-47EB52-2,85 2" 1 " . w 0 z 8 - -----' - (;;'\ . N 1" (TYP 4)--- 2" LS ;-,----' 7.!_-:39 MECH LINK 1/2" t--i::o:l--'---1t:xx:r--:!.PI ISiv-_502 11 -..! 02 RTV-502 SEE NOTE 9 ;:; ,..,_ ..... __ _.__-r.l',11/2" \. ... PRESS. ... TEST TV-26 2-47E852-2,B5 > l!) SHV-26 DRV-26 2" . - 112" . RTV-27H 71-3U"' . BYPASS CONTROL "1 VALVE ' ::!: 6" 1/2" 6" -- .... ..... ------ .... -w-----1 ..... J-.--------- ... CKV-589 CONT ON 2-47E814-1, B7 8 7 6 CKV-508 ' > iJi TEST 5 2" 1 /2 .. TEST - 3/4" TV-591 SHV-590 < 2-47E852-2,B5 VACUUM PUMP DISCHARGE TO SUPPRESSION VESSEL CALCULATION REFERENCES: MD00000712012000031: RCIC PUMP NPSHa AND SYSTEM HYDRAULICS 4 3 VACUUM PUMP 17 CFM PMP-31 COMPANION DRAWINGS: 1-,3-47EB13-1 N . N ' TEST NOTES' 1. CRW DRAINS ARE CONNECTED TO REACTOR BUILDING EQUIPMENT DRAIN SUMP. 2. DRW DRAINS ARE CONNECTED TO REACTOR BUILDING FLOOR DRAIN SUMP . 3. ALL VALVES ARE THE SAME SIZE AS PIPING, UNLESS OTHERWISE NOTED. 4. ALL VALVE DRAINS AND VENTS ARE PIPED TO CRW. 5. UNIDS ON DRAWINGS ARE FOR REFERENCE ONLY AND ARE ABBREVIATED AS SHOWN IN THE EXAMPLE TO MEET SPACE CONSTRAINTS. REFER TO MEL FOR COMPLETE UNIDS. ALL UNIDS ARE IN UNIT 2, SYS 71 UNLESS OTHERWISE NOTED. LEADING ZEROES SHOWN IN MEL AS PART OF THE UNID ARE NOT DEPICTED. FOR ADDITIONAL GUIDANCE, REFER TO NEDP-4 . EXAMPLE: MEL UNID BFN-O-SHV-018-0502 BFN-2-PT-003-0204C 6. []] ETC, DENOTES DESIGN PRESSURE THIS DRAWING. 7. DELETED DRAWING UNID SHV-502 PT-204C AND TEMPERATURE AS GIVEN IN TABLE, 8. THE DESIGN PRESSURE AND TEMPERATURE OF ALL DRAIN AND VENT LINES THROUGH THE LAST ISOLATION VALVE SHALL BE THE SAME AS THE PROCESS LINE . 9. CONDENSATE PUMP AND VACUUM PUMP SUCTION LINES ARE INTERNAL TO TANK AND SHOWN ONLY FOR CLARITY. 10. HYDROTESTING OF THERMOWELLS AND FITTINGS SHALL BE PERFORMED IN SHOP AT 30 PSIG. SYSTEM LEAK TEST PER ANSI B31.10 POWER PIPING CODE. 11. FOR DESIGN PRESSURE AND DESIGN TEMPERATURE SEE TERRY STEAM TURBINE MANUAL, CONTROL# 0467 (CONTRACT# 90744). 12. VENT, DRAIN AND TEST CONNECTIONS 1-1/2" AND BELOW CAN BE PROVIDED WITH PIPE CAPS OR HOSE CONNECTION FITTINGS WHERE REQUIRED BY PLANT PERSONNEL. THIS CONFIGURATION IS SUPPORTED BY ENGINEERING CALCULATION CD-00999-923399. 13. SPOOL PIECE MAY BE REPLACED BY STRAINER DURING MAINTENANCE. THE SPOOL PIECE MUST BE INSTALLED PRIOR TO RETURNING THE SYSTEM TO SERVICE. SEE 0-47E456-1. -2 FOR STRAINER DETAIL. 14. ORIFICE COUPLING, SEE 0-471600-20, DETAIL P20. 15. VALVE 2-FCV-071-0039 WILL SEAL LEAK TIGHT ONLY IN THE DIRECTION OF FEEDWATER TO RCIC SYSTEM DUE TO A PRESSURE LOCKING WHICH DRILLED A 1/4" HOLE IN THE FEEDWATER SIDE FACE OF THE VALVE . (DCN T41301) 16. THE PIPING COMPONENT IDENTIFIED IS A LINE STOP FITTING WITH AN INTERNAL PLUG AND BLIND FLANGE. NORMAL CONFIGURATION DOES NOT ISOLATE FLOW AND FITTING, PLUG AND BLIND FLANGE ARE CONSIDERED PRESSURE RETAINING. REFERENCE DRAWINGS: MEL ................... VALVE MARKER TAG TABULATION 2-47E456-408 .......... MECHANICAL-RCIC OIL PIPING INSTRUMENTS 2-47E852-1 ,-2 ......... FLOW DIAGRAM - DRAINAGE INSTALLATION SECTIONS ANO DETAILS 0-47E820-1 ............ FLOW DIAGRAM - CONTROL ROD DRIVE 0-47E800-1 ............ FLOW DIAGRAM - GENERAL PLANT SYSTEMS 0-47E800-2 ............ MECHANICAL - SYMBOLS & FLOW DIAGRAM DRAWING INDEX 2-47E815-4 ............ FLOW DIAGRAM AUXILIARY BOILER SYSTEM 2-47E801-1 ............ FLOW DIAGRAM - MAIN STEAM 2-47E811-1 ............ FLOW DIAGRAM - RHR SYSTEM 2-47E812-1 ............ FLOW DIAGRAM - HPCI SYSTEM 0-47E815-1 ............ FLOW DIAGRAM - AUX BOILER SYSTEM 2-47E818-1 ............ FLOW DIAGRAM - CNDS STORAGE & SUPPLY SYSTEM MEL ................... INSTRUMENT TABULATION 2-47E610-71-1,2 ....... CONTROL DIAGRAM - RCIC SYSTEM 2-47E803-1 ............ FLOW DIAGRAM - REACTOR FEEDWATER 2-47E810-1 ............ FLOW DIAGRAM - REACTOR WATER CLEANUP 2-47E814-1 ............ FLOW DIAGRAM - CORE SPRAY AMENDMENT 26 POWERHOUSE UNIT 2 BROWNS FERRY FINAL SAFETY NUCLEAR PLANT ANALYSIS REPORT REACTOR COOLING CORE ISOLATION SYSTEM FLOW DIAGRAM FIGURE 4.7-1a H G F E D c B A

Browns Ferry Nuclear Plant Updated Final Safety Analysis ... · 090~ ~-£ ~93lt-z v'-1 ls i i 1 reactor ---< 8" 2-47e818-1,c7 c--,,--'ps i /'. 71.:.!a f...--1 pdt \.'---~~--" ps primary

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Page 1: Browns Ferry Nuclear Plant Updated Final Safety Analysis ... · 090~ ~-£ ~93lt-z v'-1 ls i i 1 reactor ---< 8" 2-47e818-1,c7 c--,,--'ps i /'. 71.:.!a f...--1 pdt \.'---~~--" ps primary

090~ ~-£ ~93Lt-Z V'-1 Ls

I I

1

REACTOR

8" ---< 2-47E818-1,C7

C--,,--'PS I /'. 71.:.!A f...--1 PDT \.'---~~--" PS

PRIMARY CONTAINMENT \ SYSTEM PRESS. - TEii' DATA 1 .. FROM CRD LINE DESIGN DESIGN

~ w ~

I

71.:.!A 71.:J.B

~ L_____r,;;\ CONDENSING NOTE 14 (TYP /, CHAMBER

RTV-1AL 71.:!D 71.:JA

ECKV-71-1AA

(TYP 2) --;r:=CP:jO"-Ti:-7..:1_-1..:A:.....--ll::F-:.!.l ;;," ~~,.:X::;-~5l~F--~~L~-{:-

MAIN STEAt.4 ll .----1•:• 1" X SlE RTV~1AH -LECKV-71-1AB

2 47E801 1, FS - 1h 1 " X-33F L -

I

w w

I tFE) 3" 7~

ECKV-71-1BA

.---ti CPOT-71-18 RTV-lBL L._ECKV-71-188

- " 'h 31"-X-:;,3:.:<3-".E ---t<H:cJ---1' 1 " RTV-1 BH -@cv (TYP 2) FCV

1-2 1-3 r

X-10 HPCI SYSTEM

____ ..,,} 2-47E812-1 GS

FLG-71 - l I' '°t~:---0-----</~0~4~7~E~8~20~1_:·.:C4~ SEE NOTE 16 __..,,

3/4"

SHV-71-62 : 5 12

FCVtJ •--l( 71-19 ' ~

m . !l'

' ' I- i;;;: _____ .. u

MK NO. PRESSURE (PSIG) TEt.tP( 't)

1 1146 562 2 150 325

1375 545 4 1500 200 5 150 200 6 1375 200 7 1500 40 TO 140 8 1250 575 9 165 366 10 270 415 11 400 450 12 250 150 13 100 103 14 200 200

LOV-565 1 4 ,, T 1/4" I

' i". >

-' ., I 3• 4" 4• (FE j--,---o(>-~-3-fl""~\ol,_.;....,T'" __ [>lo.::J-----~-J----------;_,..,_...;, ______________________________ .;.._ .. ____________ ~M~A~I~N~S~TE~A~M::.,;S~U~P~P~LY:.,. ______________ .., _____________________________ .......

u w z --" " < • w w r N

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7..!_:J.B • '- ...- .J

STEAM /' DRAIN __,,,..

TEST

N ~ ~

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TEST (F5V\ 1~-;a

w 1/2" . in

.., • ..:..:-1.-1--1_ ~ DRV-556 SHV-556 U

~-{]r FCV • 71-38

~

.........--PUMP TEST RETURN TO ..,,,..- CONDENSATE STORAGE

LOV-18

6"

. ~ co 71-20B,C--=-, 1 /2"

PT LL-J:)o::!--f 71 -20 ~ RTV-20

(PS' J/2"

• '

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RELIEF VALVE SET O 150 PSIG RFV-19

---1: 2-47E852-2,B5

1 /2. 1 " VENT 1 " VTV-530 . 3/4" LOW POINT DRAIN

1 /2. • w

N

1 .. HPCI DRAIN ~ VTV-529

14---< 2-+7E812-1. G7 I f. Fg_\_ '-----'---' 71..:;.~1/2" TELL-TALE

_j TO CRW ~2-47E852-2,E5 ••

<

~

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. .

NOTE 15

SHV-553 DRV-554

-=-=1.5375" PR0-38

~ 7~ -37

6" . -

LOV-37

z -< ~ 0

r z -0 ~

!'; -"

N N ~

' ;:; 0

~ 71-358 ~

PT 71-35 ~

.;-~ 0.375. PR0-547

PUMP MINIMUM ,,,;t FLOW BYPASS___,,,,.

/3/4" VENT m

V SPOOL PIECE SPPC-71-19 (NOTE 13)

11 /2" PRESS. .....-- 3/4" TEST

. N

1 " ... .... .. RTV-4

TURBINE TRIP

PT 71-4 ~

PI 71-4B ~

THROTTLE VALVE - ~

FCV 2

' 1-9

~ ~ 1/2" 8

TURBINE GOVERNING VALVE --lf--.j/.FCV~fl:f"r-)l~~------~-....;3:.,"+::l-t~-4-·--1

1 "

RTV-5H

(t.tOUNTED TO TURBINE CASING) 1/2" 7 \.::1E/ J;...ml ,._.;....-t~1-~~~~~~~~~-1-~--='--~

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PI 71-56 ~

PR0-9A,\-PR0-98 7 rs ::2

ABOVE AND BELOW SEAT DRAINS --..':::",f---J

1 "

2

, , • -

SHV-570

SHV-618

STEAM SUPPLY DRAIN POT CPOT-5

1 " RTV-5L

0 STEAM TRAP TRP-10 PISTON REMOVED

SHV-617 SHV-571

1 •

... ,__ _____ -J~---------'---[><_(]-----1..-.~1-.----~_(;·-l-~---r--i------. TEST

. N

' N z - 1 " ~ CKV-3-572

(LG\

X-98 -'

THIS DWG.C4

THERt.4AL SLEEVE

. .. N

\_REACTOR FEEDWATER LINE 8

~ w w :; ' N

v

1 +f-+-[+8· I

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71-47 '-

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w

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L_~'~1~·r·''.::~~·~C:~·- ~ ~§~ - fu~iINE ~~ ~3140

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,---1 /4"

PI TI 7t:_01 7~3

71-45" 3t4n OI ,.3i /R" I ..- 71-24 t"''._ . ....,..£>1..t L o ~/2"

TI 1 PUMP ..__.112 • ~

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w

1 ..

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71-23 ,_ • 3/4"

1 /2" GASKET TEST -

- . - 2" ' •

CKV-598 CKV-597

<

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TEST

'

• N 2"

1 O" . - TURBINE EXHAUST ' ' ~I) ::::. •

N .. CKV-580 TEST

SUMP I

3/4"

PS 7~4

~

1 /4"

... ,___ ____________________ .. _

- . ' CKV-600

- . ' CKV-599

TURB EXH VAC RELIEF_J

SHV -520 2"

RCIC LUBE OIL PIPING DIAGRAM (C4) FCV , 1/2", 71-~::r j ~

1/2" CAP --._ .. 1/4" -

• X-218---

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SHV-602

-0 w

' ~

. N

TV-603 . N

• N

--r-STRAINERS

b SUPPRESSION POOL RING HDR 7

-' i".

X-221-._

X-212 • N

3/4" LOW POINT DRAIN

TEST .. 1120 (sHV\ SHV-551 DRV-552 -

2" 71-32 ::-.--

0. 625" .:..'::. PR0-551T

3/4" l<l---tc .......... ,.._-1 ~ L TV-610 SHV-609 w

J ' ' 1/2" TEST >

iii

18"

/X-210A

• N

< 2-47E852-2, B5 !--"'

14

18"

FROM RESIDUAL HEAT REMOVAL SYSTEM

...._2-47E811-1, E7

~PRIMARY CONTAINMENT

(sHV\ ~ 71-16 7.,.1-_!.7

.. ~

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TEST

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CKV-592

I L~6 LOV-17 SUPPRESSION POOL SUCTION

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~

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71-22 ~

~· 1.{2" LOW POINT DRAIN 1--to .... --talll-----.

SHV-538 DRV-539

1 " .

N

' N

• N

~ -~ "' ~ " ~ ~

1 /2" PT )-,-{)XJ---f

71-12 RTV-12 ~

@ 71-12B ~

EXHAUST

• • . " ••

DRAIN POT--.... ·~

. w

• -TNK-642 ......... ,__,_ __ .....; ____ ~

STEAM TRAP TRP-9

1 •

PRESSURE RELIEF SET o 10 PSIG

2"

- ~RFV-27 .J_

-'

~ m . N

' N

VALVE

-' TV-540 ~

m w ~ ..

z - (Pl)

~ w w ~ ~

:i ' N RTV-27L 1 " 1 "

7Fo.416" PR0-540 ' N

0 r '~ .

71-27: ,;;- . ::!: v -· - - -•

TV-541

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ITHIS DWG,E7)>-----~ .. IB--J......1:::::=1'~::::::==:::::J~-~~-~ ........ -~

l_ BAROMETRIC

-' Go:J 7~~7

CONDENSER _ CND-27

~....'::::;i· t' ii' '.:"if'''::;'r'-@:::P::S::--. 2_5_0_" --'r'r:~~~M TANK ...... -

w -< I ,... 3/4" THIS DWG,E71-----~l"'"'"-f

LUBE OIL COOLER 16 GPM 140"F MAX CLR-25

11-28!-;=Q 5 ~

PRESSURE RELIEF VALVE SET o 75 PSIC RFV-543

""" H. 2-47EB52-2,85

2" 1 " .

w 0 z 8

--~I

-----' -(;;'\ .

N

1" (TYP 4)---

2"

LS ;-,----'

7.!_-:39 ~ MECH LINK

1/2" t--i::o:l--'---1t:xx:r--:!.PI

ISiv-_502 11 -..!02 RTV-502

SEE NOTE 9

;:; ,..,_ ..... __ _.__-r.l',11/2" \. ~~. f!~~

... PRESS.

... TEST TV-26

2-47E852-2,B5 >

~ 1-1/4'~~, l!) ~ SHV-26 DRV-26

2" . -

112" . RTV-27H

~ 71-3U"' ~ .

BYPASS ~ CONTROL "1 VALVE

'

• ::!:

6" .~1/4" 1/2" 6" ~-----~------"' .~---1,· --.... ~ ..... ------.... -w-----1 ..... J-.---------... CKV-589

CONT ON 2-47E814-1, B7

8 7 6

~ CKV-508 ' >

iJi

TEST

5

2"

1 /2 .. TEST - 3/4"

TV-591 SHV-590

x~ ~

< 2-47E852-2,B5

VACUUM PUMP DISCHARGE TO SUPPRESSION VESSEL

CALCULATION REFERENCES: MD00000712012000031: RCIC PUMP NPSHa AND SYSTEM HYDRAULICS

4 3

VACUUM PUMP 17 CFM PMP-31

COMPANION DRAWINGS: 1-,3-47EB13-1

N

• . N

' TEST

NOTES' 1. CRW DRAINS ARE CONNECTED TO REACTOR BUILDING EQUIPMENT DRAIN SUMP. 2. DRW DRAINS ARE CONNECTED TO REACTOR BUILDING FLOOR DRAIN SUMP . 3. ALL VALVES ARE THE SAME SIZE AS PIPING, UNLESS OTHERWISE NOTED. 4. ALL VALVE DRAINS AND VENTS ARE PIPED TO CRW. 5. UNIDS ON DRAWINGS ARE FOR REFERENCE ONLY AND ARE ABBREVIATED AS

SHOWN IN THE EXAMPLE TO MEET SPACE CONSTRAINTS. REFER TO MEL FOR COMPLETE UNIDS. ALL UNIDS ARE IN UNIT 2, SYS 71 UNLESS OTHERWISE NOTED. LEADING ZEROES SHOWN IN MEL AS PART OF THE UNID ARE NOT DEPICTED. FOR ADDITIONAL GUIDANCE, REFER TO NEDP-4 . EXAMPLE: MEL UNID

BFN-O-SHV-018-0502 BFN-2-PT-003-0204C

6. []] ETC, DENOTES DESIGN PRESSURE THIS DRAWING.

7. DELETED

DRAWING UNID SHV-502 PT-204C

AND TEMPERATURE AS GIVEN IN TABLE,

8. THE DESIGN PRESSURE AND TEMPERATURE OF ALL DRAIN AND VENT LINES THROUGH THE LAST ISOLATION VALVE SHALL BE THE SAME AS THE PROCESS LINE .

9. CONDENSATE PUMP AND VACUUM PUMP SUCTION LINES ARE INTERNAL TO TANK AND SHOWN ONLY FOR CLARITY.

10. HYDROTESTING OF THERMOWELLS AND FITTINGS SHALL BE PERFORMED IN SHOP AT 30 PSIG. SYSTEM LEAK TEST PER ANSI B31.10 POWER PIPING CODE.

11. FOR DESIGN PRESSURE AND DESIGN TEMPERATURE SEE TERRY STEAM TURBINE MANUAL, CONTROL# 0467 (CONTRACT# 90744).

12. VENT, DRAIN AND TEST CONNECTIONS 1-1/2" AND BELOW CAN BE PROVIDED WITH PIPE CAPS OR HOSE CONNECTION FITTINGS WHERE REQUIRED BY PLANT PERSONNEL. THIS CONFIGURATION IS SUPPORTED BY ENGINEERING CALCULATION CD-00999-923399.

13. SPOOL PIECE MAY BE REPLACED BY STRAINER DURING MAINTENANCE. THE SPOOL PIECE MUST BE INSTALLED PRIOR TO RETURNING THE SYSTEM TO SERVICE. SEE 0-47E456-1. -2 FOR STRAINER DETAIL.

14. ORIFICE COUPLING, SEE 0-471600-20, DETAIL P20. 15. VALVE 2-FCV-071-0039 WILL SEAL LEAK TIGHT ONLY IN THE DIRECTION OF

FEEDWATER TO RCIC SYSTEM DUE TO A PRESSURE LOCKING ~ODIFICATION WHICH DRILLED A 1/4" HOLE IN THE FEEDWATER SIDE FACE OF THE VALVE . (DCN T41301)

16. THE PIPING COMPONENT IDENTIFIED IS A LINE STOP FITTING WITH AN INTERNAL PLUG AND BLIND FLANGE. NORMAL CONFIGURATION DOES NOT ISOLATE FLOW AND FITTING, PLUG AND BLIND FLANGE ARE CONSIDERED PRESSURE RETAINING.

REFERENCE DRAWINGS: MEL ................... VALVE MARKER TAG TABULATION 2-47E456-408 .......... MECHANICAL-RCIC OIL PIPING INSTRUMENTS 2-47E852-1 ,-2 ......... FLOW DIAGRAM - DRAINAGE

INSTALLATION SECTIONS ANO DETAILS 0-47E820-1 ............ FLOW DIAGRAM - CONTROL ROD DRIVE 0-47E800-1 ............ FLOW DIAGRAM - GENERAL PLANT SYSTEMS 0-47E800-2 ............ MECHANICAL - SYMBOLS & FLOW DIAGRAM DRAWING INDEX 2-47E815-4 ............ FLOW DIAGRAM AUXILIARY BOILER SYSTEM 2-47E801-1 ............ FLOW DIAGRAM - MAIN STEAM 2-47E811-1 ............ FLOW DIAGRAM - RHR SYSTEM 2-47E812-1 ............ FLOW DIAGRAM - HPCI SYSTEM 0-47E815-1 ............ FLOW DIAGRAM - AUX BOILER SYSTEM 2-47E818-1 ............ FLOW DIAGRAM - CNDS STORAGE & SUPPLY SYSTEM MEL ................... INSTRUMENT TABULATION 2-47E610-71-1,2 ....... CONTROL DIAGRAM - RCIC SYSTEM 2-47E803-1 ............ FLOW DIAGRAM - REACTOR FEEDWATER 2-47E810-1 ............ FLOW DIAGRAM - REACTOR WATER CLEANUP 2-47E814-1 ............ FLOW DIAGRAM - CORE SPRAY

AMENDMENT 26

POWERHOUSE UNIT 2

BROWNS FERRY FINAL SAFETY

NUCLEAR PLANT ANALYSIS REPORT

REACTOR COOLING

CORE ISOLATION SYSTEM

FLOW DIAGRAM FIGURE 4.7-1a

H

G

F

E

D

c

B

A

Page 2: Browns Ferry Nuclear Plant Updated Final Safety Analysis ... · 090~ ~-£ ~93lt-z v'-1 ls i i 1 reactor ---< 8" 2-47e818-1,c7 c--,,--'ps i /'. 71.:.!a f...--1 pdt \.'---~~--" ps primary

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COMPANION DRAWINGS: 1-47E610-71-1 3-47E610-71-1 2-47E610-71-2

NOTES:

1. THE REACTOR CORE ISOLATION COOLING SYSTEM IS DESIGNED TO COOL THE CORE WHEN THE REACTOR VESSEL IS ISOLATED AND REACTOR FEEDWATER IS UNAVAILABLE. WHEN THE WATER LEVEL IN THE REACTOR VESSEL REACHES SETPOINT, THE RCIC SYSTEM IS AUTOMATICALLY STARTED BY ACTIVATION OF REACTOR LEVEL SWITCHES LIS-3-58A, LIS-3-58B, LIS-3-58C ANO LIS-3-580 (2-47E610-3-1), ARRANGED IN ONE-OUT-OF-TWO-TWICE LOGIC TO OPEN VALVE FCV-71-8. THE SAME SIGNAL CLOSES DRAIN LINE VALVES FCV-71-SA AND FCV-71-6B.

2. A MECHANICAL SPEED GOVERNOR PREVENTS TURBINE OVERSPEED BY TRIPPING THROTTLE TRIP VALVE FCV-71-9 WHEN A TURBINE OVERSPEED OCCURS. A CONTROL GOVERNOR, FIC-71-J6, EQUIPPED WITH AUTOMATIC AND MANUAL MEANS FOR SPEED SET POINT CONTROL REGULATES TURBINE SPEED VIA "TURBINE SPEED CHANGER" TO CONTROL RCIC MAIN PUMP DISCHARGE FLOW.

3A. A RCIC STANDBY td:JDE SIGNAL SHALL BE INITIATED AT REACTOR VESSEL WATER LEVEL 8 (HIGH LEVEL). THE REACTOR VESSEL WATER LEVEL 8 SIGNAL SHALL BE INITIATED BY TWO LEVEL SWITCHES ARRANGED IN A TWO-OUT-OF-TWO LOGIC CONFIGURATION. THE REACTOR VESSEL WATER LEVEL 8 SIGNAL SHALL: (A) CLOSE THE STEAM ADMISSION VALVE FCV-71-8 AND (B) CLOSE THE MINI-FLOW ISOLATION VALVE FCV-71-34. IN THE EVENT AN INITIATION SIGNAL IS RECEIVED AFTER THE SYSTEM HAS BEEN SHUTDOWN ON HIGH RV LEVEL, THE SYSTEM SHALL BE CAPABLE Of AUTOMATIC RESTART.

3B. THE RCIC TURBINE TRIP VALVE IS TRIPPED BY: A. TURBINE OVERSPEED VIA THE SPEED GOVERNOR.

C. LOW RCIC PUMP SUCTION PRESSURE SENSED BY PS-71-21.

D. HIGH RCIC TURBINE EXHAUST PRESSURE SENSED BY EITHER PS-71-1JA OR PS-71-13B.

E. MANUALLY FROM THE MAIN CONTROL ROOM BY HS-71-9A OR BY HS-71-9C ON PANEL 25-J2.

A TURBINE TRIP,

A. CLOSES FCV-71-9. B. CLOSES FCV-71-J4. C. ANNUNCIATES ON ZA-71-49A OR 49B. D. ACTIVATES THE ALARM ASSOCIATED WITH THE CONDITION INITIATING

THE TRIP.

4. THE TURBINE CASING IS PROTECTED FROM OVERPRESSURE BY TWO RUPTURE DISCS. PS-71-11A THRU D DETECTS DISC RUPTURES AND ANNUNCIATES ON PA-71-11 IN THE MAIN CONTROL ROOM. PROVIDES 1 OUT OF 2 TWICE LOGIC TO INITIATE AUTO ISOLATION OF TURBINE (SEE NOTE 5).

5. THE RCIC TURBINE WILL BE AUTOMATICALLY ISOLATED FROM THE STEAM SUPPLY BY CLOSING ISOLATION VALVES FCV-71-2 AND FCV-71-3 IF: A. A HIGH PRESSURE DROP OCCURS ACROSS THE RCIC ELBOW TYPE FLOW

ELEMENT FE-73-1A & 18 WHEN THE STEAM LINE RUPTURES. THE HIGH FLOW IS SENSED BY EITHER PDT-71-1A OR PDT-71-1B AND ANNUNCIATED ON PDA-71-1 .

B. HIGH AREA TEMPERATURES INDICATING A STEAM LINE BREAK ARE DETECTED BY ANY OF FOUR SETS OF TEMPERATURE SWITCHES CTS-71-2A THROUGH TS-71-2S EACH SET CONNECTED IN ONE-OUT-OF-TWO-TWICE LOGIC. FOUR INDEPENDENT TEMPERATURE SENSING ELEMENTS AND ASSOCIATED TEMPTERA­TURE SWITCHES TE-71-41A AND TS-71-41A THROUGH TE-71-41D AND TS-71-41D SET AT 175" F ACTIVATE THE MAIN CONTROL ROOM ANNUNCIATOR TA-71-41.

C. LOW REACTOR PRESSURE IS DETECTED BY PS-71-1A THROUGH PS-71-1D ARRANGED IN ONE-OUT-OF-TWO-TWICE LOGIC.

D. HIGH PRESSURE BETWEEN THE TURBINE EXHAUST RUPTURE DISCS (SEE NOTE 4).

6. NORMALLY MAKEUP WATER FOR THE RCIC PUMP SUCTION IS SUPPLIED BY THE CONDENSATE STORAGE TANK THROUGH FLOW CONTROL VALVE FCV-71-19. AN ALTERNATE SOURCE OF WATER IS OBTAINED FROM THE SUPPRESSION POOL THROUGH ISOLATION VALVES FCV-71-17 AND FCV-71-18. PUMP DISCHARGE FLOW ROUTES ARE AS FOLLOWS:

A. NORMALLY VIA THE FEEDWATER LINE TO THE REACTOR THROUGH ISOLATION VALVES FCV-71-37, FCV-71-39, AND CHECK VALVE FCV-71-40.

B. DURING TESTING VIA TEST LINE TO CONDENSATE STORAGE THROUGH FLOW CONTROL VALVE FCV-71-38.

C. MINIMUM FLOW BYPASS TO THE SUPRESSION POOL THROUGH FLOW CONTROL VALVE FCV-71-34.

7. IF RCIC SYSTEM OPERATION IS REQUIRED WHEN IT IS IN THE TEST MOOE, THE CONTROL SYSTEM IS DESIGNED TO AUTOMATICALLY RETURN THE SYSTEM TO THE OPERATING MODE.

8. COOLING WATER FOR THE PUMP, TURBINE, AND LUBE OIL COOLER IS SUPPLIED FROM THE PUMP DISCHARGE LINE THROUGH PRESSURE CONTROL VALVE PCV-71-22 SET AT 75 PSIA.

9. TRANSFER AND CONTROL SWITCHES ASSOCIATED WITH BACKUP CONTROL WILL BE ON THE DESIGNATED PANELS OR LOCATED ON THE APPROPRIATE 250V DC M:JV BOARDS.

10. XS-71-36B IS SHOWN TWICE TO SHOW HOW THIS TRANSFER SWITCH DISCONNECTS FIC-71-36A AND CONNECTS FIC-71-36B LOCATED AT THE BACKUP CONTROL CENTER.

11. XS-71-24, PS-71-44, TS-71-47 & TS-71-48 ARE SHOWN TWICE TO SHOW HOW THESE SWITCHES TRANSFER INDICATION FROM THE MAIN CONTROL PANEL 9-J TO THE BACKUP CONTROL PANEL 25-J2.

12. UNIDS ON DRAWINGS ARE FOR REFERENCE ONLY AND ARE ABBREVIATED AS SHOWN IN THE EXAMPLE TO MEET SPACE CONSTRAINTS. REFER TO MEL FOR COMPLETE UNIDS. All UNIDS ARE IN UNIT 2 SYSTEM 71, UNLESS OTHERWISE NOTED. LEADING ZEROES SHOWN IN MEL AS PART OF THE UNID ARE NOT DEPICTED. FOR ADDITIONAL GUIDANCE, REFER TO NEDP-4. EXAMPLE: MEL UNID DRAWING UNID

BFN-O-SHV-018-0502 SHV-18-502 BFN-1-HS-031-0160A HS-31-160A BFN-2-PT -003-0204C PT -3-204C

13. CCMPLETE LOGIC FOR REACTOR CORE ISOLATION SYSTEM IS SHOWN ON MECHANICAL LOGIC DIAGRAM LISTED IN REFERENCE DRAWINGS.

REFERENCE DRAWINGS: 0-47E800-1 .................. FLOW DIAGRAM-GENERAL PLANT SYSTEMS 0-47E800-2 .................. MECHANICAL SYMBOLS AND FLOW DIAG DWG INDEX 2-47E2847-5 ................. FLOW DIAGRAM-CONTROL AIR SUPPLY 2-47E813-1 .................. FLOW DIAGRAM-RCIC 2-47E610-73-1 ............... CONTROL DIAGRAM-HPCI 2-47E610-3-1 ................ CONTROL DIAGRAM-REACTOR FEEDWATER 2-47E610-1-1 ................ CONTROL DIAGRAM-MAIN STEAM 2-47E610-69-1 ............... CONTROL DIAGRAM-REACTOR WATER CLEANUP 0-47E610-2-2 ................ CONTROL DIAGRAM-CONDENSATE SYSTEM 0-47E610-12-1 ............... CONTROL DIAGRAM-AUXILIARY BOILER SYSTEM 0-47E456-1,-2 ............... RCIC SYSTEM MECHANICAL DRAWINGS 0-47W456-3,-4 ............... RCIC SYSTEM MECHANICAL DRAWINGS MEL ......................... INSTRUMENT TABULATIONS FOR SYSTEM 71 2-45E670-SERIES ............. WIRING DIAGRAM-ECCS 2-45E626-1 ,-2,-3,-4 ......... WIRING DIAG REACTOR CORE ISOLATION COOLING 2-45W670-21 ................. WIRING DIAG EMERG CORE COOLING SYS DIV I 2-45E714-5.-6 ............... WIRING DIA 250V REAC MOV BO 2C 2-45E779-5,-12 .............. WIRING DIAGRAM 480V SHUTDOWN AUX POWER SCH DIA 2-47E611-64-SERIES .......... MECHANICAL LOGIC DIAGRAM PRIMARY CONTAINMENT

ISOLATION SYSTEM 2-47E611-71-SERIES .......... MECHANICAL LOGIC DIAGRAM REACTOR CORE ISOLATION

COOLING SYSTEM GE DRAWINGS:

729E652-1 .............. FUNCTIONAL CONTROL DIAGRAMS-RCIC 2-729E652-4 ............. FUNCTIONAL CONTROL DIAGRAMS-RCIC

TERRY TURBINE CO.: C-883-X ............... RCIC TURBINE GOVERNOR CONTROL SYSTEM

NASH ENGR CO. : D-14-1365 ............. RCIC BAROMETRIC CONDENSER

SYMBOLS:

~ QUICK DISCONNECT WITH SINGLE END SHUTOFF

~ QUICK DISCONNECT

AMENDMENT POWERHOUSE UNIT 2

26

BROWNS FERRY FINAL SAFETY

NUCLEAR PLANT ANALYSIS REPORT

REACTOR CORE ISOLATION COOLING SYSTEM

MECHANICAL CONTROL DIAGRAM FIGURE 4.7-1b

H

G

F

E

D

c

B

A

Page 3: Browns Ferry Nuclear Plant Updated Final Safety Analysis ... · 090~ ~-£ ~93lt-z v'-1 ls i i 1 reactor ---< 8" 2-47e818-1,c7 c--,,--'ps i /'. 71.:.!a f...--1 pdt \.'---~~--" ps primary

' ii

8 7 6 5

AMENDMENT 27 I'OIEIIIHOUSE LINtTJ

BROWNS fERRY NUCLEAR PLANT F INAL SAFETY ANALYSIS REPORT

H

8

REACt~Lj~SEs~~~QTIOH A FLOW DIAGRAM

FIGURE 4.7-lc

Page 4: Browns Ferry Nuclear Plant Updated Final Safety Analysis ... · 090~ ~-£ ~93lt-z v'-1 ls i i 1 reactor ---< 8" 2-47e818-1,c7 c--,,--'ps i /'. 71.:.!a f...--1 pdt \.'---~~--" ps primary

~to!! l- lL-O l93Lt-£ It-I L9

~-3 r---r--1---,.-

~~~~ 71-2A 71-28 71-2C 71-20

-,----,-------I L-j 0-45ES2S-1 I I I

--,...-1--"t--t---

~ ~~~ 71-2E 71-2F 71-2G 71-2H

--t--,---,--t---~ ~~~ 71-2J 71-2K 71-2L 71-2M - - - -L __ -----~------- +-=r_-------- ----t--------

To XM-69-29 / ======I======= r-~-------------. --------<3-47E610-69-11(E:::-:------1--------r 1 =-+-========r-~------------

REACTOR WATER ' I L _J .....l... 4P.: CLEANUP ' ..fTE'L. ~9-21 I --,3-45N3654-1 (TE\_ TS 9-21

LOCi LOG - 71-41A ~A l 71-418 1-41 71-2 0 71-2 CL -- ...._.., r-------1 ....._ --

--------------' I

' -, I ' I ,-1-..4:-21 (TE\_ TS 71-41C 1-41

'----' .___, 1 I ~~~~~~

CISS A

CISS A 1 ----------4 t-------------, r----13-45E11•-5

*-*-i~--,- **-----11 3-45E779-121 r---- *i--1--i~-~:e;-*-1-1 .i'1ic fHs\ 9 c 3 ~ __/Hs\ I : @-3 4 _fHs\ .ii.ire 11 11

~_J7~71~ tdCC MCC 70A ~\.... 7~C I I

~ * I 11L~30 o I 1c18ss1 J L 1cr;s1 L

-.,---,...--.,.--1 ~~~~ 71-2N 71-2P 71-2R 71-25 - - - -------,

.., I ' I I ' I ~~-21 (TE\_ TS 71-410 1-41

'----' .___,

FROM AUXILIARY BOILER SYSTEM

0-47E610-12-1 ,03 ~.~5-31 25-58 25-58 I I 9-3

(Pl\ PT I ... IP!\ 71-48 71-4 t"" -~

I '----' L - - --jr-3--4-5_E6_2_6_-3..,

fit:~ !~9-3

NOTES: 1. THE REACTOR CORE ISOLATION COOLING SYSTEM IS DESIGNED TO

COOL THE CORE WHEN THE REACTOR VESSEL IS ISOLATED AND REACTOR FEEDWATER IS UNAVAILABLE. WHEN THE WATER LEVEL IN THE REACTOR VESSEL REACHES 31 .5" BELOW REACTOR FEEDWATER ZERO. THE RCIC SYSTEM IS AUTOMATICALLY STARTED BY ACTIVATION OF REACTOR LEVEL SWITCHES LIS-3-58A. LIS-3-58B, LIS-3-58C, AND LIS-3-58D (SEE 3-47E610-3-1), ARRANGED IN ONE-OUT-OF-TWO-TWICE LOGIC TO OPEN VALVE FCV-71-8. THE SAME SIGNAL CLOSES DRAIN LINE VALVES FCV-71-6A AND FCV-71-SB.

2.

3A.

A MECHANICAL SPEED GOVERNOR PREVENTS TURBINE OVERSPEED BY TRIPPING THROTTLE TRIP VALVE FCV-71-9 WHEN A TURBINE OVERSPEED OCCURS. A CONTROL GOVERNOR, FIC-71-36, EQUIPPED WITH AUTOMATIC AND MANUAL MEANS FOR SPEED SET POINT CONTROL REGULATES TURBINE SPEED VIA "TURBINE SPEED CHANGER" TO CONTROL RCIC MAIN PUMP DISCHARGE FLOW. A RCIC STANDBY MODE SIGNAL SHALL BE INITIATED AT REACTOR VESSEL WATER LEVEL 8 (HIGH LEVEL). THE REACTOR VESSEL WATER LEVEL 8 SIGNAL SHALL BE INITIATED BY TWO LEVEL SWITCHES ARRANGED IN A TWO-OUT-OF-TWO LOGIC CONFIGURATION. THE REACTOR VESSEL WATER LEVEL 8 SIGNAL SHALL: (A) CLOSE THE STEAM ADMISSION VALVE FCV-71-8 AND (B) CLOSE THE MINI FLOW ISOLATION VALVE FCV-71-34. IN THE EVENT AN INITIATION SIGNAL IS RECEIVED AFTER THE SYSTEM HAS BEEN SHUTDOWN ON HIGH RV LEVEL, THE SYSTEM SHALL BE CAPABLE OF AUTOMATIC RESTART.

3B. THE RCIC TURBINE TRIP VALVE IS TRIPPED BY:

4.

A. 8. c. D.

E.

TURBINE OVERSPEED VIA THE SPEED GOVERNOR. DELETED. LOW RCIC PUMP SUCTION PRESSURE SENSED BY PS-71-21A. HIGH RCIC TURBINE EXHAUST PRESSURE SENSED BY EITHER PS-71-13A OR PS-71-13B. MANUALLY FROM THE MAIN CONTROL ROOM BY HS-71-9A OR BY HS-71-9C ON PANEL 25-32.

A TURBINE TRIP: A. CLOSES FCV-71-9. 8. CLOSES FCV-71-34. C. ANNUNCIATES ON ZA-71-49A OR 49B. D. ACTIVATES THE ALARM ASSOCIATED WITH

INITIATING THE TRIP. THE CONDITION

THE TURBINE CASING IS PROTECTED FROM OVERPRESSURE BY TWO RUPTURE DISCS. PS-71-11A THRU D SET AT 10 PSIG DETECTS DISC

1-------------------------------------------r-~-1-,

.- .... --•-•-----•------, r=--..25 32 l~<I I .-1,---------------. r -13-45'626-3

: I 9-3 : ~5-32

I~ 5.

RUPTURES AND ANNUNCIATES ON PA-71-11 IN THE MAIN CONTROL ROOM. THE RCIC TURBINE WILL BE AUTOMATICALLY ISOLATED FROM THE STEAM SUPPLY BY CLOSING ISOLATION VALVES FCV-71-2 AND FCV-71-3 IF: I

25-7A

FT 71-18 ------,---,

I I @-19~-19 9-3

FM FI 71-1 --@

y

'----' '----' '----'

, 1 , ' • • .... --j3-45E714-5 I 1 Hs 1 - 1:::'1' I 1 1 r--------;r...,---, : : +>If '®' * I FROM CNDS ~ DEMINERALIZED 7~c '®' '{< I I I [J][J__J/ I I

~ ~ r:::--.. /~' 9-3 II WATER STORAGE SYS A5-32 /-@' ~ 3 I ~ I I G r HS \.._.J xs '- HS 0-47Es10-2-2.c4 ( xsL HS - I I ll-S '@' ~

71-19C 71-19 1-19A I 71-9A .... 71-9 I I L~MCC / '/~ {HS\_ __ ':" ___ .:r __ ':"_ jrToG-l'---' I '--t------0s I 11-190 3-45E626-2 ~ I I *---=..-i __ _,I '----' r------t----- rt '>RL J o-45E626-+ r- "'1 I I

~ I 0-45E626-1 f..l xx 11 ~ 3-45E714-5 I R G I MCC I 3-45E714-6 f-.... 71-9 11 I . . ("j:jS\9-3 ,.... ....

3-45E626-3 I--, 9-3 I

@A : 25-31 'f----_J LfXi_ LOG

~--+ A71033 r_. ~· 9-47 [1Q[J_j .,.l..._ TR ~(PT) 7 -54-13

71-35 y

11 3-45E626-3 1: @t--r 1-9 ,, I ~--~ ~ :©:: rl I d-3 : 0-45E626-1 HTRIP LINKAGE L_...:~:: __ -~ _fHs\

3-45E626-3 I r-t;-::ill I I f--i 0-45E626-4 I ~ \...- 7~c ~-3 I 25- 58 L_ .... 25':;; I ®9-3 A 'A9-3 FROM XS-71-368 71=2ot PT _1-,---1 I .I XS \25-32 I ~ -@ .___,A 1 100 t--..-i Ps 1 11-9e 1 c zr-11-10 r 08 25 _32

7..!_=3-18 ...._.... y ' 25-672 ~ ~x2 25-31 25-58 25-58 I 25 32 I THIS SM SI (PX'\ Pl PS 1 /::X~- DWG,CS 71-10 l-42 71-20 71-208 71-21A ......... -, '11H_::>9J--_J ~ ..., y ...._.... I '----' .___, .___, I ~-3 I .___, ~ .:, I ~OG 9-31

I 3-45Es2s-2 ~- ___ _J ~A t---l J-45Es20-2 6~A~cs ~ I A6156 fsl\ : - . - . ::l 65 672 ®7:j

RCIC PUMP PMP-19

II LG ! _1 ___ _J

JB 10035 I 'f''-

RCIC TURBINE TRB-9

F'---~ SE I 71-10A 71-42A_L ,

DRAIN POT CPOT-5

3-47E3847-5,F6

I - -111-o--<-5E-s2-s--1--,

I I 3-45E626-3. -4

I I I I

I I I I I _J r

s I I=='

STEAt.4 TRAP TRP-10 PISTON REMOVED

.3-45E626-3, -4

6.

A. A HIGH PRESSURE DROP OCCURS ACROSS THE RCIC ELBOW TYPE FLOW ELEMENT FE-71-1A & 1B WHEN THE STEAM LINE RUPTURES. THE HIGH FLOW IS SENSED BY EITHER PD1S-71-1A OR PD1S-71-1B AND ANNUNCIATED ON PDA-71-1.

B. HIGH AREA TEMPERATURES INDICATING A STEAM LINE BREAK ARE DETECTED BY ANY OF FOUR SETS OF TEMPERATURE SWITCHES (TS-71-2A THROUGH TS-71-2S SET AT 194°F). EACH SET CONNECTED IN ONE-OUT-OF-TWO-TWICE LOGIC. FOUR INDEPENDENT TEMPERATURE SENSING ELEMENTS AND ASSOCIATED TEMPERATURE SWITCHES TE-71-41A AND TS-71-41A THROUGH TE-71-41D AND TS-71-41D SET AT 175 F ACTIVATE THE MAIN CONTROL ROOM ANNUNCIATOR TA-71-41.

C. LOW REACTOR PRESSURE IS DETECTED BY PS-71-1A THROUGH PS-71-lD EACH SET AT 50 PSIG ANO ARRANGED IN ONE-OUT-OF-TWO-TWICE LOGIC.

NORMALLY MAKEUP WATER FOR THE RCIC PUMP SUCTION IS SUPPLIED BY THE CONDENSATE STORAGE TANK THROUGH FLOW CONTROL VALVE FCV-71-19. AN ALTERNATE SOURCE OF WATER IS OBTAINED FRCJ.l THE SUPPRESSION POOL THROUGH ISOLATION VALVES FCV-71-17 AND FCV-71-18. PUMP DISCHARGE FLOW ROUTES ARE AS FOLLOWS: A. NORMALLY VIA THE FEEDWATER LINE TO THE REACTOR

THROUGH ISOLATION VALVES FCV-71-37, FCV-71-39, AND CHECK VALVE FCV-71-40 .

B. DURING TESTING VIA TEST LINE TO CONDENSATE STORAGE THROUGH FLOW CONTROL VALVE FCV-71-38.

C. MINIMUM FLOW BYPASS TO THE SUPPRESSION POOL THROUGH FLOW CONTROL VALVE FCV-71-34.

7. IF RCIC SYSTEM OPERATION IS REQUIRED WHEN IT IS IN THE TEST MODE, THE CONTROL SYSTEM IS DESIGNED TO AUTOMATICALLY RETURN THE SYSTEM TO THE OPERATING MODE.

8. CCXJLING WATER FOR THE PUMP, TURBINE, AND LUBE OIL COOLER IS SUPPLIED FRCJ.l THE PUMP DISCHARGE LINE THROUGH PRESSURE CONTROL VALVE PCV-71-22 SET AT 75 PSIA.

9. TRANSFER AND CONTROL SWITCHES ASSOCIATED WITH BACKUP CONTROL WILL BE ON THE DESIGNATED PANELS OR LOCATED ON THE APPROPRIATE 250V DC MOV BOARDS.

10. XS-71-368 IS SHOWN THREE TIMES TO SHOW HOW THIS TRANSFER SWITCH DISCONNECTS FIC-71-36A AND CONNECTS FIC-71-36B LOCATED AT THE BACKUP CONTROL CENTER.

~3_-_•5_E_6_2_6-_3~~ -~-3 25-58 1 I ~ 25-58 R, I

CRW~ >-<._2s-sa PI ,_ _ _, I {FIS'---- l 71-358 TE

(IT\ SEE NOTE 11 71-48

Y (x•\"5-672

I 11-10 ly I

11. XS-71-23, XS-71-45, TS-71-45 & -46, XS-71-24 AND PS-71-44 ARE EACH SHOWN TWICE TO SHOW HOW THESE SWITCHES TRANSFER INDICATION FROM THE MAIN CONTROL PANEL 9-3 TO THE BACKUP CONTROL PANEL 25-32.

12. UNIDS ON DRAWINGS ARE FOR REFERENCE ONLY AND ARE ABBREVIATED AS SHOWN IN THE EXAMPLE TO MEET SPACE CONSTRAINTS. REFER TO MEL FOR COMPLETE UNIDS. ALL UNIDS ARE IN UNIT 3 UNLESS OTHERWISE NOTED. LEADING ZEROES SHOWN IN MEL AS PART OF I

L---------CKV-71-40

4 71F-E36 i .....__, 71T-W33 t-- r----t- 11-36 I 11-33~-----...--------

11 (Pl\

rt- __,.__,.., I T , _,-~-, ?-<.25-58 I '----' I 1,1-~5 I I >!< FCV I I I I I >!< FCV I I I I FT ' -

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_______ J

~ 25-31 1 ~~ NOTE 11 , fri\ (x's\_ ¥-~

TS TW 71-56 71-368 71-45 71-45 ...._.... 'J-"

TE LsEE NOTE 1 o 71-47

TI TW SEE 71-45 71-45A NOTE

r ~1--~11 11 0-45E626-4 r

r-- -------------, I ~5-58 ~5-31

( PI ' LOG ( PX ' I THERMAL SLEEVE-~

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------....,....-, I I I I

TO SM-71-10

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I 0- 45 " 26- 1 f--, 7 3-•5•11•-5 f-J :@:1~ I 3-45E11•-5 p Jb:1~ r- 11 7-!54

11 : : : :®'(HS\,:©:: : ~r;5-58(i!~3-R;--, 5-58

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25-58 I 9-3 I : ~ ,_.....,1J;2 t_•_@, ____ J: ~~ v

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25-58 25-58t- 08 :ca= I I -- 1-U 1-C PS PS ---

25 - 31 I *9-3 I r:::--..25-31 ! I ~9-3 ~ ~.-(,1x_s2~,-3 ~.,. XS ~ FIC __ ,. __ ..J XS ~-----------------------.J I ~A 71-34C -- I -- .....__,,, ~ 1-.36 1-36 71-36B I .....__,,, ...__..... I

71-11A 71-11B I y y -@9-3 +----+--.. PA 71-1

8

I y .___,SEE NOTE 10__/'"r'" ....... ~~~~~~~~~~~~~~~....;l~~~~~~~~~...;..~~....;;........;;....~~~1-~~~~...;.....,j~~~-(Pl\~P~l....L~....;~

~ : ~25_32 : (Ti\ L--j 3-47'610-71-1 I t-j 3-45E714-5 i!lr 71-27 A6158 L ____ ..JFIC\_ ______ .J SEE NOTE 11 71-23A :cr;MCC A ~t::l (TI'\

71-36B PS '-,._,,,._---1, TW TW (Fcv\ D....1- 71 27

-- ,;-<.._ SEE

lrs\5-58 ~-58 .....__,,,

71-11C 71-11D

__ 11-4.( 7..!_:3.3 .. ,,---1.71-23,I----,..,,,.~-----.,.-,,,.--- 71 - 25 _____ _J n-SEE NOTE 11 { TS ' TE NOTE TW )-L----,

P1 7 ..!.:3.3 7..!,:34 11 ~-::::::--i=-...:7'---':::1 ::-2:'..6-~ r-L-----1-----::::::-----------' 7l:3J1 LUBO

~ -3:®: -- - -ili-fu _fHs\ t_,_ 71-59

I I .___, 1@-3 XA I 11-5 I '----' L43-45E779-12 I

7

f-... t---1 RHR TEST LINE 3-47E811-1.C6

9-3

Zl-71-32~ ~ 71-32 --r .,--t _,_ ~ - "t""--i 3-45E626-2

: : : :@::@: L--i3-45E714-5

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I :&-~----, I R G I I I l JHs\ I r 1~s I

Y..1~ I /L: 71-18 ______ J

I --_,,,,_ _ _,,,,__---I COOLER FILTER CLR-25

3-45ES20-3 L THIS ~-----'r, OWG. 03

I FROM RCIC FG .3 !TURBINE 71-507 _.£1!..!:_!_Ll~-----'=" LS

71-29 '----' I 3-45E626-2 1- ::+

" " "

BAROMETRIC CONDENSER CND-27

VACUUM -TANK --TNK-27

r-,--~-~--,-~-------_. w '@f >If + w >If 1 3-45E714-6 r .l ,.Pi...S, '--.----+--'--, )..!Q_ / ' ~ .... /~ / '~ - . 111-28 ~ (HS\ ("j:jS\9-3 {HS\_ _______ ... ::;-- p:-3

71-29C ~A 71-29B \

'-[ ___ 't-:.-:. .___, --=--=--=--=--=--=-~9/\ 7-2.=38

.CC / YJC-...

~-- l!l PMP-29

x x '------+,.--------~~-----t~ TO CRW

f ==~ :==1 I FCV FCV I 71-7A 71-7B

I I I

I .3-45E714-6

I I L I 25-30-,

.3-47E3847-5.G7

: 3-47E3847-5.G7 ~=7 y~0_-4-5-E6-2-6-_4~ I L-~-..---_,....!-,

Zl-71-7AA~:@: :®:!~: +---l ~l~IC :&i:-r---ili-~-j

R I©/ R * ZI-71-7BA / ' '~ ....

0-45E626-1

9-3 9-3 MIMIC

7

5 4

I I 1-_J ,...,..., Y.!:<1'@" /~~,

(HS l 71-31C '----'

TO MAIN CONDENSER ** 9-3

MIMIC

- -J~3-_4_s_E s_2_s-_2~ r ~~_o_-•_5_E_62_6_-_1 _,

-l I LOGIC 8 I 9-3 9-3 r- 3-45E626-2 RESET ~s

I .---~ ! RCIC AUTO ISOL _"J;{ ~ ~...,loc1CARESET----4')6z. IL-71-51B

.....__,,, ~IL-71-51A

9 _3 r-l o-•5E626-1 I ~ l _ RCI£...!!:!I.!]AT~N ~--T"°SEAL-IN RESET

.....__,,, Y}:t IL-71-52 9-.3 )!Y,

@ ' {~~~A~u~~o~~~-f~~TION '----' I

L -j 3-45E626-2

9-47 (IT\_ (TR\ ~ ~24 73~10 ~

9-47 (IT\_ __ (TR\ --- LOG ~47 73~11 A71047

9-47 (IT\_ (TR\ ~ ~48 73~12 ~

(£)-,-@:3 I ::r.< 25-32 ~--~ Xl-71-44 I ,....,..._,..,..,.,..,...--.., L_____ 3-45E626-2

0-45E626-4

©---@;-~ @:-3

I , 25-32 ~---ill' XI-71-23 I / ' ,....,--.,-,,,.,..,..,.-.,.-.., L_____ 3-45E626-2

0-45E626-4

@--~-~ @:-3

I 25-32 ~---0: XI-71-45 I .--------.., L_____ 3-45E626-3

©--~-~ @:-3 I ~25-32

0-45E626-4

COMPANION DRAWINGS: 1-47E610-71-1 2-47E610-71-1

3

~-- A XI-71-46 I / L------1 0-45E626-4

THE UNID ARE NOT DEPICTED. FOR ADDITIONAL GUIDANCE, REFER TO NEDP-4. EXAMPLE: MEL UNID DRAWING UNID

BFN-0-SHV-018-0502 SHV-18-502 BFN-1-HS-031-0160A HS-31-160A BFN-2-PT-003-0204C PT-3-204C

13. FLEX HosEf ll'lJ'I~ TO BE INSTALLED FOR TESTING PURPOSES ONLY. REFERENCE DRAWiNGS: MEL .......................... INSTRUMENT TABULATIONS 3-47E610-1-1A ................ CONTROL DIAGRAM-MAIN SYSTEM 0-47E610-2-2 ................. CONTROL DIAGRAM-CONDENSATE SYSTEM 3-47E610-3-1 ................. CONTROL DIAGRAM-REACTOR FEEDWATER 3-47E610-69-1 ................ CONTROL DIAGRAM-REACTOR WATER CLEANUP 2-47E611-71-4 ................ LOGIC DIAGRAM-RCIC 0-47E800-1 ................... FLOW DIAGRAM-GENERAL PLANT SYSTEM 0-47E800-2 ................... MECHANICAL SYMBOLS~ FLOW DIAGRAM

INDEX 3-47E610-73-1 ................ HPCI SYSTEM 3-47E813-1 ................... FLOW DIAGRAM-RCIC SYSTEM 3-45E779-12 .................. WIRING DIAGRAM-480V SHUTDOWN

AUXILIARY POWER SCHEMATIC DIAGRAM 3-45E714-5,-6 ................ WIRING DIAGRAM-250V MOV BOARD 1C

SCHEMATIC DIAGRAM 0-45E626-1 .-4 ................ WIRING DIAGRAM-RCIC SCHEMATIC DIAGRAM 3-45E626-2,-3 ................ WIRING DIAGRAM-RCIC SCHEMATIC DIAGRAM 0-47E610-12-1 ................ CONTROL DIAGRAM-AUXILIARY BOILER 3-45E620-2.-3 ................ KEY DIAGRAM-ANNUNCIATOR SYSTEM 3-47E811-1 ................... FLOW DIAGRAM-RHR SYSTEM 3-45N3654-1 .................. WIRING DIAGRAM-UNIT CONTROL BOARDS

PANEL 9-21. SH 1 3-45W670-SERIES .............. WIRING DIAGRAM ECCS

GE DRAWINGS: 729E652, SH 1 THRU 4 .... FUNCTIONAL CONTROL

TERRY TURBINE CO. DIAGRAMS-RCIC C-883-X ................. RCIC TURBINE GOVERNOR

NASH ENGR CO. CONTROL SYSTEM D-14-1365 ............... RCIC BAROMETRIC CONDENSER

AMENDMENT 26 POWERHOUSE UNIT 3

BROWNS FERRY FINAL SAFETY

NUCLEAR PLANT ANALYSIS REPORT

REACTOR CORE ISOLATION COOLING SYSTEM

MECHANICAL CONTROL DIAGRAM FIGURE 4.7-ld

H

G

F

E

D

c

B

A

Page 5: Browns Ferry Nuclear Plant Updated Final Safety Analysis ... · 090~ ~-£ ~93lt-z v'-1 ls i i 1 reactor ---< 8" 2-47e818-1,c7 c--,,--'ps i /'. 71.:.!a f...--1 pdt \.'---~~--" ps primary

"'"".wf.~·

-:r ... \l.o ............... ---

AMENDMENT 27

BROWNS fERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT

REACTOR CORE I SOLATION COOLING SYSTEM

MECHANI CAL CONTROL DIAGRAM

FIGURE 4. 7-le

Page 6: Browns Ferry Nuclear Plant Updated Final Safety Analysis ... · 090~ ~-£ ~93lt-z v'-1 ls i i 1 reactor ---< 8" 2-47e818-1,c7 c--,,--'ps i /'. 71.:.!a f...--1 pdt \.'---~~--" ps primary

8 7 5 2

AMENDMENT 27 I"'OEIIHOUSE UNIT1

BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT

H

B

REACt~L 1~~E S~~~Q liON A MECHANICAL CONTROL DIAGRAM

FIGURE +. 7-1f

Page 7: Browns Ferry Nuclear Plant Updated Final Safety Analysis ... · 090~ ~-£ ~93lt-z v'-1 ls i i 1 reactor ---< 8" 2-47e818-1,c7 c--,,--'ps i /'. 71.:.!a f...--1 pdt \.'---~~--" ps primary

BFN-22

Figures 4.7-2a through 4.7-2h (Deleted by Amendment 22)