ML21194A377
| ML21194A377 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 06/22/2021 |
| From: | Ameren Missouri |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML21195A333 | List:
|
| References | |
| ULNRC-06673 | |
| Download: ML21194A377 (6) | |
Text
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CHKD. SUPV. APPD. 444 445 446 ~----(COOLING MONITOR 416 415 4 14 G I G-8) I MAL DLB N/A INCORP. G t-~
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TE TUBING BCB : OJ TE 118 021 TO ~ FROM PB-403D MP 97-1010 443A 'I--T ----2 TO TR-443 ( D-7) I 413A
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NOTE 1 MP 01-1 019A. REV. 27 DATE 100704
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& HV-B811A IM-22EJ01 ,F-7)
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--8 INCORPORATE VlW 2 ~
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~--1 I 'f'621 V008 L.C. MINOR CHANGE CARS-200503887.
~BG-183-BCA-2" I L ~6~T~~~p M-228803
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NOTE 5 I I~ [4]
'-._./SPARE \ ,....,.,.v4,...,7,-
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-NOTE 02-8 ~ ~
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- ..I CAR 201001930 ro y 7 y ?
~
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--1 8948D
~ M-22EM01 <
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= I I -@
M-22BB03 3 , (~) II -V288 8~D NOTE 17 I CVCS NORMAL ( G-2) EP-03-BCA-1 0" 02-BCA-1 0" IA-3) 1 413B 021 I (HIS\ QD,~ I BCB 83788 CHARGING - ~ ---(TY _TO 413K I m I B -2 ) SIS BORON s / -< M-22BG01 < 118 I IA-6) FROM OIL LIFT PUMP<,---- 021-+ 1 RCP BUS
--( UNDER-N u
m INJECT I ON 04-8CA-3' NOTE 1 BCA I BCB IF-B) "'~ N o"'" f- I I l_lle CONTROLS M-226603 I L FREQUENCY (OA\ V001 PRESSURIZER o:m TO CORE s~~s'> ~~ I
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_j I
~
REACTOR SAFETY INJECTION ACCUMULATOR
/EP- -
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r-L_---G
> M-22EP01 >-- 1 REACTOR
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DO o:- Of-oou N I w "'
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> M-22EPOI ~ TO~ I TY-413K ~ I COOLANT PUMP 39-BCA-10" w ~
IE- 2 ) IA-6) "-' D / I PBB01 cI Vl> 2 EP-06-BCA-10' TO CORE I PBB01B I
" D NOTES:
NOTE 6 w L__ _ _ _:,SU::.:,BCOOL I NG MONITOR NOTE 6
- 1. DRILLED RESTRICTION 31a" IN DIAMETER. POINT
~-- 3"x1 1; { RED.
AT WHICH QUALITY GROUP CLASSIFICATION IS
....--3"x1 1 ~'z" RED. 31 HIGH CHANGED FROM A TO B.
TE TE ENERGY TE TO CORE SIS BORON 2. SEE WESTINGHOUSE DRAWING 8756D37 SHT. 7. 430B 431B '-- ( SUBCQQLI NG SIS BORON 4218 SPARE
~/E MONITOR
) M~-:~2E~02 >--
INJECTION EM-86-BCA-1 I !z " 40-BCA-1 I \ INJECT I ON SPARE 3. SEE WESTINGHOUSE DRAWING 8756D37 SHT. 8.
~~E ~
- - - - - - - - V040 1;{
- 4. SEE WESTINGHOUSE DRAWING 8756D37 SHT. 9.
I \ BG-01-BCA-3" 54-BCA- 3" - y ~---~_I__AVG _ _ _ _ _2 26-BCA-6" SAFETY INJECTION s-----"T_---------1 ( NOTE 17 )
- 5. SEE WESTINGHOUSE DRAWING 8756D37 SHT. 10.
- 6. DETAILS OF REACTOR COOLANT PUMP MOTOR COOLING, eves LETDOWN <f 8-----@--_L-------------~
TD/431 ~--l NOTE 4 TO REACTOR CONTROL AND PROTECTION AND RESIDUAL 89498 HEAT REMOVAL PUMPS TO REACTOR CONTROL AND PROTECTION NOTE 3 I
--Y ~ ___ __[__ (TY\_ ~
~ ~
D/421E 37-BCA-2 " SEAL WATER INJECTION, AND INSTRUMENTATION AND CONTROLS ARE SHOWN ON M-22BB03. M-22BG01 _sc_s....,....sf-c_D _ I - - - @ - - - - " T _ _ _ _ _c' SYSTEM ~ M-22EM01 < SYSTEM S---I__AVG _ _ _ --@----~ 1 V028 7. RTD STRAPPED TO LINE. ( F -2 I 8. TYGON HOSE TO BE INSTALLED AT THESE CONNECTIONS EM-10-BCA-5" TO VENT PRESSURIZER DURING DRAINING AND FILLING.
---1~-t-11
~---------
3*{ I D) I \
~ -------8 V290 <t u
- 9. DELETED.
\ I I \
I MAIN STEAM
'" s 10. REFERENCE WESTINGHOUSE DRAWINGS 1145E01 SHT. I, NOTE 1 I I 1145EOI SHT. 2, AND 1145E01 SHT. 3.
SYSTEM 0 c --- 55-BCA-2" I I I I I I AB-02-DBB-~'- t M-22AB01 > f-I u m 11 . DELETED. c I I M-22EM01 III(TY\ ~ C-4 ) z
"'~ ~HB-37-8CD-2" 12. FOR P & ID LEGEND AND SYMBOLS SEE DRAWINGS VJ V0481 I I IE -2) I~-~-~-~ I I --"z o<t -
M-220101 THRU M-220104.
~_LTY'l__
of- o REACTOR 0 I I MAIN STEAM I I EM-13-BCA-6" I I I I u 00 ro I 3. DETAILS OF STEAM GENERATOR SECONDARY SIDE I I LA_~ I I SYSTEM PIPING AND CONTROLS ARE PROVIDED ON M-22AB01, COOLANT ~ ~~ I I N 00 DRAIN TANK I I
<M-22AB01 ~ ~;~~;~B-28~ I I
I I I 42-BCA-6 II I \ Ill~~ I N I M-22AE02, AND M-22BMOI. 8---- 2
<M-22HB01 f ~' o I C-7)
GENERATOR : ~II 1 ~-----l I \ SPARE [2]
~-----~ I I MAIN FEEDWATER SYSTEM I
1 4. A DIRECT READING DIGITAL PRESSURE INDICATOR IS CONNECTED TO THIS SAMPLE STATION, DOWN LINE AT THE NUCLEAR STREAM OF THE SAMPLE I I I I (8-81 HB-38-BCD-2" I EBB01 c I I
~ £TY'l_ I '----~
I I TE 420A1 I ~---~ I > M-22AE02 r-22-EBB-J_[;I' I 0 COOLER, FOR PURPOSES PRESSURIZER PRESSURE OF CALIBRATING THE INSTRUMENT CHANNELS.
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<t ~-~-1 I I
'-._./
I I I I C-4 I I 15. DELETED. u I I
'l'l LOOP NO. 3 /'"- NUCLEAR ~--l I [2] SPARE I I ~--~ n PRESSURIZER SAFETY & RELIEF VALVE DISCHARGE
~E n MAIN FEEDWATER SAMPLING I I .i:l 1 5.
LINE IS ANALYZED SO AS TO ASSURE THE
"'I SYSTEM SYSTEM ~EE ~E TE 42TlAz[2] @jE @E I STEAM ~I INTEGRITY OF THE PRESSURIZER RELIEF TANK
_ M-22AE02 >- AE-21-EBB-16"
----- <M-22SJ04 f---CIS~
V046 431A3 431A2 L~-\ 431AI 430A2
'-._./ '-._./ 421A1 421A2 421A3 L GENERATOR CD I n 00 DURING & FOLLOWING AN SSE.
1 C-7) TUBIN~~.,.SCB I I 1 0 SPARE SPARE ,-;;-]I I I 17. SG-AR-7: PEAK RECORDING ACCELEROMETER. TO BE I H-8) I I I TE L_Lj I I I I EBB01B I MOUNTED ON SURFACE OF HORIZONTAL PIPE SECTION. B NOTE 13 1 w0C1J0[1]0 III 431A3 431A2 431A1
~ _l[I]_l[2J_l[i]
( TE '\ 421A1 ( TE '\ 421A2 I421A3 TE \ NOTE 13 LOOP NO. 2 1 8. SEE WESTINGHOUSE DWG. 7250D64 SHT. 6, MCB ANNUNCIATOR IPAH-4551 IS PROVIDED FOR PZR HI PRESSURE PORV OPEN. 1 9. ASTS IAUXILIARY SHUTDOWN TRANSFER SIGNAL) IS B NOTE 1 NOTE 1 41-BCA-29"
-- r.o.-__,.-~...___NOT-E 1-~ I y~==r ===r=- r_ _---;--25_-_B_CA~9.: _I_.D_._ _ _ __,
NOTE 1 NOTE 1 NOTE 1 INITIATED AT RPII8B BY RP-HIS-3 WHICH TRANSFERS CONTROL TO THE AUXILIARY SHUTDOWN PANEL WHILE ISOLATING THE MAIN CONTROL BOARD CONTROLS AND INDICATION.
~
~----~----(TO RVLIS 20. PRT IS A SEISMICALLY QUALIFIED ASME SECTION VIII COMPONENT.
V057 V05B V036 V037 TE I~ TR I~----( TO CORE SUBCOOLING yoz1 21. THE INTERNALS OF THIS VALVE HAVE BEEN REMOVED IT] 433A -~- I 4 33 MON I TOR 2 [1] AND REPLACED WITH A STAINLESS STEEL PLUG. THE FT FT I 1 022 I [2] FT --, FT --, VALVE HAS BEEN TRANSFORMED TO A go* ELBOW. I' I' ' 435 436 425 424 I FROM ' - : R - TE-423B I TE I I I 22. DELETED. c- 423A i
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I --2 FROM TE -423B I D-3 l ( D-3) 423 022
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IT I L'---( SUBCOOLING TO CORE MONITOR
- 23. DELETED.
- 24. DELETED.
~
II
?022
~ 022 I
I ~-----~ I IG-71 n_l<l21
~I ~-----~ I 25. THE INTERNALS OF VALVE BB8949A HAVE BEEN REMOVED:
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~TI3BJ - - l 413 I
'--( TY-413J TO I H-1 )
7-@----------j ~I 425 I 6" CHECK VALVE BODY REMAINS IN SYSTEM. AS-BUILT CLASS 1 1 I I ~ 022
~--~ TY ~----j A
i-1 A TO TO DRAWN (DATE I
- @ L-------@----------2 LD FLOW REACTOR TRIP LO FLOW REACTOR TRIP s--------@-------J ~ :
N/A
'"'"' PIPING AND INSTRUMENTATION DIAGRAM 1 ~022 ----2 TO PAH-405D I G-1 )
~ To22l NIA REACTOR COOLANT SYSTEM
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SUPV. (DATEJ
~----j N/ A FSAR FIGURE 5. 1-1 SHEET L-------@-----------~ s-----------~-------J APPO. (DATEJ LOCATION CLASS FROM 020 I OPEN PORV N/A CALLAWAY PLANT TB-413M ~--- ----2 M-22BB02 I 0)
I G-2) LOC. F-8 UNION ELECTRIC COMPANY REV. ST. LOUIS. MD M-228801(0) 31 8 7 6 5 4 3 2 1
8 7 6 5 4 3 2 1 (0) 2:0882:2:-v-l REV. 21 DATE 041401 RLW CHKD. SUPV. APPD. DRAWN MAL OTW N/A INCORP. MP 00-1005 FCN-02 REV. DATE DRAWN 22 081501 RLW
~/81 CHKD. SUPV. APPD.
87-ECD-12" JHK JAM N/A H H INCORP. RFR-21330A REV. DATE DRAWN 23 oa3ooz RLW MODERATE HIGH HIGH MODERATE HIGH MODERATE CHKD. SUPV. APPD. r--1 ~ NOTE 7 co ENERGY ENERGY ENERGY ENERGY NOTE 7 ENERGY ENERGY NOTE 7 EWM TWS N/A I INCORP. R/E 0 u 1 _ f---..--.;;.96.;;.-..;H..;C.;;D_-.;.4_"- - - EJ -8 7 0 8 A RFR-22105A w I g; S OJ s TO TAH-464 VIA s FROM TB-466.465 co m N r I EJ-29-ECB-3" < RHR SUCTION
< REV.
24 DATE 082003
---~---@
INLOCK }- > HCD ECB - - - - - - - - - - - - - - - - - - - - M-22EJ01 DRAWN CHKD. SUPV. zs 0 R>x(TAH\ --~~- l TO TAH BCA ECD IG-71 RL W MAL TWS ECD BCA 801 OA 464 VIA ) - - - -~--, -2 BCA ECD ,---~-'V-~ INCORPORATE s INTERLOCK 0 I I 021 A o1s 1"(0) LOJ
~~--,----~9.;;.7-.;.H.;;C~D..;-..;4_"_ _ _ __,r---1~
MINOR CHANGE CAR 200305155
~021 ~021 I
r N REV. DATE I 80108 ,_....._ 80100 0 I 7 3"4" l.l IV I
~ I EJ-51-ECB-3" RHR SUCTION
< 25 051304 DRAWN CHKD. SUPV.
, FROM ZS-801 DB u i3 01 ~
l w --------------- M-22EJ01 RL W MAL RWW
---o I LOC. G-6 I TO ZA-8010 8010A I LOC. G-7 I TO ZA-8010 I
T ~ H_c_,o1::E'::c=s~ (c 7 J INCORPORATE
'"" I
'" ,--( ILOC.G-7 I w
Q > 1 ,~DJ 4"x3" RED. MP 89-1 035A I PARTIAL I 0 I 94-HCD-4" 1---i" BG-8121 G 018 "J FROM ZS-801 DC ILOC.G-51
~021 __ L__ @ "'m N HCD r'
I S BG-191-HCB-2" REACTOR COOLANT PUMP SEAL LEAKOFFS REV. 26 DATE 11 09 04 DRAWN CHKD. SUPV. TJC MAL TWS G 0 021 > -------------------- M-22BG01 m INCORPORATE C~:.,~_l_~_~-": ;,-.;.H.; ,C; ,:D. .;-.;.4. ;" 1_'~-~-D-1---------j_J-""i~"~f:-BG-8~~----~~G~~) 0 RFR-22941A. REV. DATE
. . ___ IE 3 I 27 080205 rn u
,_ w u
"'u m u rn u r r \ 125
,_/ eves DRAWN CHKD. SUPV.
s "' 0 w 0 w 0 0 s w 0 0 s
~- 3/{xl/{ RED. & FEMALE QUICK CONNECT 4"x3" RED.-~-
I BG-263-ECB-2"
< LETDOWN M-22BG01
< RL W MAL TWS INCORPORATE MINOR CHANGE u u u HCD ECB I H-2 I CAR 200503892
"' "' "' REV.
28 DATE 11 1 1 05
'co SAMPLE s DRAWN CHKD. SUPV.
I 0 CONNECTIONS RLW EWM SKC u cJ R/E INCORPORATE I MP 89-1035A co 00 NOTE
'"m N PIPE TUNNEL GASEOUS RADWASTE REV.
29 DATE 102508
> SYSTEM 3'4" 1 02-HCD-1" DRAWN CHKD. SUPV.
M-22HA03 RLW EWM LMR INCORPORATE
~ IF-21 MP 07-0007 241-HCD-1" REV. DATE
~KH-011-HBD- 3,4' NITROGEN SUPPL:J V413 30 091009 F V091 V094
'3------------< M-22KH01 IE-SI
< DRAWN CHKO. SUPV.
RLW TJC LMR INCORPORATE F 1 05-HCD-1 PCV HY AS (Hc\ AC 09-000063: RFR 200801863 8034 '~ ,---~ I 8045 REV. DATE 0 ri I 001 u I 31 050910
~(HCI\
I 0 u HV DRAWN CHKD. SUPV. I 8045 N I EWM RLW LMP 0 I V397 m m co 0 y-~ INCORPORATE 8037 CAR 201000409 0 I 001
> REACTOR MAKE-UP LOJ 021~ WATER 1"101 HS/ [i] DATE
,---~ tzD_ REV.
.....,_NOTE M-228L01 I A-2 I
~--
I I 10030 11 5 y --l 32 T JC MAL INCORP. 070710 DRAWN CHKD. SUPV. TWS 16 8L-29-HCD-3" I I I D-3 I I [2J I CAR 201001930 ACTION 1. HV I ZT AS 8157A 8157A EXCESS
- 249-HCC-4" LETDOWN 0~1S HX OUTLET
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I 8037 M-228G01 < u I 021~
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REV. 33 DATE 021611 m m s CTMT NORMAL SUMP M-22LF09 6 l _£01 DRAWN CHKD. SUPV. MAL TJC SKC INCORP. N
> "'u I D-5 I y-~ CAR 201011348.
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~
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- 1. DELETED. MAL RL W TWS INCORP.
RFR 22941A
- 2. SINGLE ALARM POINT FOR ALL FOUR 141 PUMPS.
- 3. RESTRICTION ORIFICE 3/8" DIAMETER. POINT AT WHICH QUALITY GROUP CLASSIFICATION IS CHANGED FROM "A" TO "B".
- 4. DELETED
- 5. REFERENCE WESTINGHOUSE DRAWING; 1145E02 SOOI.
- 6. DELETED.
- 7. DELETED.
- 8. THERMAL BARRIER COOLING COIL HAS INTERNAL PRESSURE DESIGN RATING OF 150 PSIA.
- 9. DELETED.
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\j ~
WATER INCORPORATE 2'=~~~~~---1~6~9lrH~B~C::4:" M 22EG03 1G-3 I ________________ _,:J1L {:"H fu ~ f-nu N ~ ¥ z; N
~ II ~-'>> -~3:J---~G.::1£.-..!:!~.:4..:
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~
> INCORP.
RFR-22941A
~22 0 1"(0) TO FAHL-25 (FSHL m
COMPONENT I VIA INTERLOCK COOLING WATER 0 M-22B803A I G-2 I 31 053 F I m I ~ >~~;zE;O:J~--~~~7~1~H~B£C~1~'~'----------------l_~~rflrc:Hir M 22EG03 / I FT 31 r;I II
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---1 q
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____ / / /
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/
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F.C. IB 2 I f-----------------------------~ ,tI ;:--- YT 73E
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.). 1 II ( D)
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I D I SEAL 1 I I /E I PT 151
--------@-oY L,-@-s _1 151 \
\
151 TO PAL-153 VIA INTERLOCK M-22BB03A ID-21
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~---~ ~ a~ N 179-BCA-2 "1 BG-171-BCB-Z"l CHARGING
~V 351C
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a; > w f-
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[1]6PHIS
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> PUMP
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TUBING 1/z" (0) l~ -r:;; rrl z** J ~ 15 ~
~
COMPONENT COOLING WATER L.:__j
> )- C....,--n-=,...-:!=...,..,------~,: n,2" r---M rJ"l~ ~ , 7 >
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,._ r " :::_ 1 1'11H---.
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- 185-CBC-3" 11
- I M-22EG03 1~-31 --------~~c~l 257-CBC,-1 1,, 180 C8C 3" i NOTE 8 i ' V~~~ I G-3 I THERMAL ~
BARRIER 7 258-CBC-1 1 ,~ 2 " COOLING ~ COIL .'. N N
< M-22LF09 IE 61 s:------------y L LF -893-HCD-1" .J"""
V184 HCD CBC B 038-BCA-27 1----. SEE M-228803 FOR NOTES. DO NOT ADD NOTES TO THIS DRAWING.
\-----
053-BCA-31"1IDI REACTOR COOLANT PUMP C I AS-BUILT CLASS 1 DRAWN N/A WATE I A I PBB01 c I CHKD. WATEJ PIPING AND INSTRUMENTATION DIAGRAM REACTOR COOLANT SYSTEM fi\ N/A SUPV. WA TE J N/A { FSAR FIGURE 5.1 I SHEET 3C) APPO. (OATEJ LOCATION CLASS CALLAWAY PLANT N/A UNION ELECTRIC COMPANY REV. ST. LOUIS. MD M-22BB03C(Q) 7 8 7 6 5 4 3 2 1
8 7 6 5 4 3 2 1 (0l0£088ZZ-~ ~ ~ REV. DATE DRAWN "I "I 0 012397 RLW CDUI UI
~
~o~ o~ CHKD. SUPV. APPD.
~--' --' DLBr AMR N/A
~cr<t CDO'<t
~
IW~ mw~ INITIAL ISSUE
.,-c-o
~
--'f--0 IZCD lzm PER
<t-m <t-m o-1 N
<tN o-1
<tN N
~ ~ RFR-17575A REV. DATE DRAWN NOTE 19 I
I I I f-->:0 1' I f-->:0 1' I IG>Y I I I TO F AHL -25 VIA INTERLOCK M-228803A I G-2 I 1 02069 RAM AMR N/A J HK CHKD. SUPV. APPD. H TO HIS-40 PS --/r>-R I I I I I I I INCORP. DEC-1403. M-228801 494 Y Gz1 I I LS 4788 LS 495D I I I FSHL REV. 2 DATE DRAWN 03319 DLBr I SEE NOTE 14 I TO YT-474Ec'---l - , I I I 36 053 CHKD. SUPV. APPD. I ~ RLW AMR N/A
~~~~~~~~~~~-
TE TO YT-474D(--\ I I I 485A f----~- \ I \ I I TO LAHL-4758 INCORP. VIA INTERLOCK j~ r-R DEC-1402. M-228803A I H-4 I ~
~---0----1~4~~8}------~
REV. DATE DRAWN 3 040898 MAL 31'{ ~) ~ '-..___.../ CHKD. SUPV. APPD. EWM JHK N/A
!zw \
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- z -~h\-SS~ I INCORP.
DEC-1501. s; :r: V ~ 36 COOLING REV. DATE DRAWN I <t ....l L N
>~WATER I f-CL 4 062598 RAM LD en zz o
Ol 0 m [;'Jl.J,' 187-HBC-4"V203 - - CHKD. SUPV. APPD.
..-- UV)
- J LL
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N
~ MOTOR AIR I B-3 I INCORPORATES I COOLER RFR-18922A
"' ~
REV. 5 DATE 020199 DRAWN DJB RCP "D II D m 1"(0) ~ SEE DRAWING M-228803 FOR NOTES. CHKD. SUPV. APPD. STANDPIPE COMPONENT I 1"(DJo m I DO NOT ADD NOTES TO THIS DRAWING. RAM AMR INCORPORATES N/ A G COOLING WATER RFR-19267A I SBB01 D I
~f---~~----o-r~3rr-"
REV. DATE DRAWN 186 HBC 4" ~
) M 22EG03 6 100899 RLW CHKD. SUPV. APPD.
IB-31 OJB AMR N/A MOTOR AIR TO FAHL-25 INCORPORATES COOLER ---~ VI A INTERLOCK MP 97-1008A. 3 M-228B03A IG-21 REV. DATE
~ 0 7 041905 1"(0) Ico 0
m 3"{(Vl 0 DRAWN CHKD. SUPV. MAL RL W TWS
~,+-.~ ~
COMPONENT I COOLING INCORP. RFR 22941A
)
WATER
~~~~~~------1~9~0lrH~B~C::4:"
M 22EG03 ________l________,~L
-(..f-1 runu~ f- \S I u V ~ ~
~
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~
S::i COMPONENT COOLING REV. 8 DATE 100710
~,' >V241 1 B- 3 I UPPER BRG COOLER 3"
U~" I' ~ HH-*c:.J-".,-----111
**:J-----------------7 EG-162-HBC-4" "
WATER M-22EG03
> DRAWN CHKD. SUPV.
T JC INCORP. MAL TWS 191-HBC-4 (Ll (8-3) CAR 201006760. TO FAHL-25
~22 0
m VI A INTERLOCK r:---t-'c'FS_HL COMPONENT I M-22BB03A IG-21 32 178 022 I COOLING WATER D m 053 F I R > M 22EG03 192 HBC 1" I FT 32
.,. ~7~~ IA-31 Z-178 f----,
LOWER BRG H'~ rLr--......, ri913,~HXBC3~'~," roN~' ~ SEG-163-HB~~~;ONENT
'I
~
021 COOLER ~ .., I \ \ ~ COOLING
~ V420 '> V242 WATER D
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/ YE YTIS
~-~----i~/ !--~~Kr~1~96~-~H~C~D-~3~/~4-"--------~~~~--------~~M~22~B~L~0~1~ / 474C 474C --
474
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~--_/ ~-- 4740@
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II LF-812-HC0-1"
~ ~------------------------------------7 M-22LF09 FROM FROM YE-4740 YE-474E CTMT. SUMP
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3,.{ ( v ) I D-3 I E FE 1 91 ~s fHY\ 81410 REACTOR COOLANT 7, F~ r" DRAIN TANK
< M-22HB01 !---!!~~-:.:~.£.~: r-------llf----------------~
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~ 81 41 0 N
> I SEAL 2 I m c~
~
H.~ 1" (DJ
..l TO F AH-194 VIA INTERLOCK M-22BB03A I 0-5 I I" TC&IVI TUBING
~----~~ D lrz"( V) I SEAL 1 I
-~~
------------~~------~ PT TO PAL-153 VIA INTERLOCK u .. Cr "'w "' TUBING
' 150 M-22BB03A I 0-2 I
_j li-~~ 11 t (v) 0
~
c~ ~-~+-.,....,vs" 0 0
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~ ( m
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N N TO HS-9 AND TI-9 VIA INTERLOCK
~V w M-228B03A IC-31 BG-173-BCB-Z"l CHARGING PUMP 351D
...J L. 0.
f-
~ BCB
.. I..BCA 't I
> M-22BG01 )- -
198-BCB-2 11
" 1 199-BCB-2" I I
I V20B V209 I A-3 I -,r=::----cc:-1 TT
~~~P-4ol
>--' LABYRINTH 3'4" I TC & VI SEAL I PI B
I I c 0 u TE m I2 EG-300-CBC-3" COMPONENT COOLING WATER 7 M-22EG03 IC 3 I PI 260-CBC-1 1 -'z" 4
< M-22LF09 L LF-891-HC0-1" __] ....
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56-BCA-21 l,..z" ( ID l
~ ---\
72-8CA-31"1IDI I 1------ .. - - _...J AS-BUILT CLASS 1 REACTOR COOLANT PUMP "D II DRAWN N/A WATE I A I PBB01 D I CHKD. WATEJ PIPING AND INSTRUMENTATION DIAGRAM N/A REACTOR COOLANT SYSTEM SUPV. WATE J FSAR FIGURE 5.1-1 SHEET 30 N/A APPD. (OATEJ LOCATION CLASS N/A CALLAWAY PLANT UNION ELECTRIC COMPANY M-22BB03D(Q) REV. ST. LOUIS. MD 8 8 7 6 5 4 3 2 1
8 I 7 6 5 4 I 3 2 1 ( 0) 17088ZZ-~ I NOTES REV. 4 DATE 212u91 DRAWN RL W CHKD. SUPV. APPD.
- 1. REFER TO NOTE 1 ON M-22BB01(Q).
RV CORE SUBCOOLING MONITOR DLBr T JM N/A
- 2. SEE WESTINGHOUSE PROCESS BLOCK DIAGRAMS-~ DWG. NO. 2326090 (4 SHEETS), AND REDRAWN FOR TIC JUNCT. PENE WESTINGHOUSE INSTALLATION SCHEMATIC. CLAR JTY TRAIN SEP. GRP. BOX NO.
TIC NUMBER TRATION NO. REV. DATE DRAWN
- 3. LIS-1311, 1312, 1321, AND 1322 ARE HYDRAULIC ISOLATORS WJTH A MALFUNCTION INDICATION.
5 o5o692 MAL 38 30 33 5 41 SPR 75 4. DELETED. CHKD. SUPV. APPD. (NOTE 10 l RLW T JM N/A 20 4LI 47 43 SPR 76
- 5. HYDRAULIC SENSORS. REDRAWN FOR H A BB04A " 6. LEVEL TRANSMITTER ELEVATION ABOVE HYDRAULIC ISOLATOR AND NEAR CONTAINMENT PENETRATION.
CLARITY. INCORP. 39 15 35 13 46 7 77 CMP 91-1016.
- 7. DELETED.
REV. DATE DRAWN 31 27 32 29 4 SPR 78 6 S8R (NOTE 151 8. FOR THERMOCOUPLE/CORE COOLING MONITOR SEE WESTINGHOUSE DRAWING 2332078. (5 SHEETSJ. 10993 CHKD. SUPV. APPD. 12 9. ONLY 53 OF THE 54 STUDS ARE REQUIRED TO BE TENSIONED TO ENSURE D-RING SEATING AND RLW DME N/A 37 9 17 (NOTE 1<1 J 36 II SPR 75 COMPLIANCE WITH THE ASME CODE STRESS CONCENTRATION FACTORS. INCORP. CMP 92-1028 24 23 19 50 25 22 18 76 10. 88TC0041 HAS BEEN ABANDONED IN PLACE. FCN 03. B 4 8B048 11 . THERMOCOUPLES TC 1 6 AND TC40 HAVE BEEN REMOVED FROM SERV 1 CE AND CAPPED WITH A 1/ 8" REV. DATE DRAWN 40 15 (NOTE 11 l (NOTE 11 l 14 34 I0 21 SPR 77 SWAGELDK TUBING CAP (REF. CMP 92-1028l. 7 101596 OJ8 CHKD. SUPV. APPD. 6 12. DELETED. RLW AMR N/A 26 2 8 28 3 {NOTE 1 3 l SPR 78 SEE TABLE ( H-8 l 13. THERMOCOUPLE TC6 HAS BEEN REMOVED FROM SERVICE AND CAPPED WITH A 1/e SWAGELOK INCORP. TUBING CAP. {REF. SOS 96-16641 CMP 95-1012 REV. DATE DRAWN
- 14. THERMOCOUPLE TC12 IS REMOVED FROM SERVICE AND CAPPED WITH A 8 103096 RLW 1/ 8" SWAGELOK TUBING CAP. {REF. SOS 96-1664 AND RFR-17473BJ CHKO. SUPV. APPD.
RV CORE SUBCOOLING MONITOR 15. THERMOCOUPLE TC29 IS NOT CONNECTED AT THE TRANSITION CABLE (18BS33AX - P4. N4. DJB AMR N/A (NOTE 8) I I THERMOCOUPLE/CORE COOLING MONITOR
~-------------------------,-----------
16 AND SH4l ASSEMBLY TWIN PIN CONNECTOR. REF.: SOS 99-2143 AND RFR-17473C.
- 16. QUALITY GROUP CLASSIFICATION IS CHANGED FROM "A" TO "B" AT THE 3/ 8" ADAPTOR
--, I NCORP.
RFR-10372C. REV. DATE DRAWN G TRAIN 1 I TRAIN FROM 1" PIPE TO ~~8 " TUBING. 9 01~197 RLW DISPLAY INSTRUMENTS FOR CONTROL A ~---------------------,----.----------- B CHKD. SUPV. APPD. DLBr AMR N/ A BOARD SECTION AND/OR OTHER CABINETS TIC 1 I TIC INCORP. JUNCT r------------------T-----~----~----------- I I JUNCT RFR-17473A. INSTRUMENT TAG NO. LOCATION BOX 1 I I BOX REV. DATE DRAWN 10 040198 RLW I I I
~------------------------------------- CHKD. SUPV. APPD.
UU-1390A RP081A ' DJB JHK N/A I INCORP. UU-13908 RP0818 [1] [1] RFR-18663A.
~~
~~IS REV. DATE DRAWN 11 040898 RL W TR-1390A RP081A ~ ~--8DD1 TR-13908 RP0818 NOTE 2 I
I I 021 Yoz1 I CHKO. SUPV. APPD. MAL JHK INCORP. N/A
't I I I RFR-174T3B.
TI-1390A TI-13908 RL022 RL022
~
TE i-----E33 214-BCB-1" zs 8001A s I HV 8001A HV 80D2A s I zs B002A REV. 12 DATE o1oso DRAWN RLW CHKD. SUPV. APPO. OJB AMR N/A SLOPE 1323 INCORP. TAL-1390A RK020 250-BCB-1 -:=::::J RFR-17473C.
~~~~~--------~----------------~MM~--------~~~----IVJ FC FC REV. DATE F
TALL-13908 RK020 13 022204 DRAWN CHKO. SUPV. TRAIN 8 0 0...J~ ~lVI RLW MAL SKC
---? M-22BB04
~~IS
~~--BOD1 INCORPORATE MINOR CHANGE NOTE 2 {E 3 J V233 I 021
~vZI CAR 200309298
't SLOPE ! REV. DATE
[1] ~, 8--j__ _ I I I 14 100704 I I I I DRAWN CHKD. SUPV. TE I I RLW MAL TWS 1313'-" INCORPORATE zs s HV HV s zs MINOR CHANGE 80016 80016 8D026 80028 CAR 200406193 TRAIN A SLOPE REV. DATE VENTIF ILL
~ 251-BCB-1 ~ 15 110904 DRAWN CHKD. SUPV.
FC FC MAL RLW TWS INCORP. RFR 22941A. TUBING.,I,. 8CB .. I,.TU8ING REV. DATE 16 102814 3-a" r ~1 3/8 11 TRAIN B FROM TOP OF RV DRAWN CHKD. SUPV. RLW MAL DME
-.....~ V41 4 I' INCORPORATE V416 ) M 228804 MP 10-0001 FCN-01 E
~[:~,~~~*--1[]~)1c}----~'*!f___________~_F_5__' __--,
FLUX THIMBLE INSERTION POINT
~ . ~ X 3 "
11 I' 8 /4 RED. TUBING BCA I~-~,.
----:-" I ~J-~3~~---~l~~j---~'*~f--,
SEE NOTE 16~ I" I n ~* i ~~~ 8016A 7
. * ,,,. \ I NOTE 2
~01~ ** v.LJ,...J.L7'---l L
't 1[1]
252-BCA-1 " / I" 1 .. [4] 0 St-L- TE 1 31 4 SEE NOTE 9 5 .. NOTE 5 NOTE
~21 ~21 I I
~---1 ~---8 "8
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,*..., o'ci
~ ~ ~
SEE NOTE 2 SEE NOTE 2
't 't D TRAIN A FROM SEAL TABLE TRAIN A M 228B04 ~--l r----8 IP-9~
M 22BB04 (D 4 J L -11 ISEAL TABLE I J-7 { D 61 TE I 32 gl----t----1 I
-E6 4}6I I I RBB01 I
~---~
NOTE 3 z
~P-591
~
I I
,--'L,\,'\ )-l<-s~..,~,*-**-r-~x*-~><-c-~-*---+~
NOTE 2 I
'*---*--->f---'>E-,*-*-*-*CJII <-\ 1312L I s 1-*--*~
*'---*--+--1 I
1 NOTE 3 Ll s 1---,---l<- 1322 3/, 6* I I I NOTE 3 I [Il I 0 rxAHl\ --J I I
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~~
qo
~
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I 002 2-- ~R ~ 406
----1~; ' ----,----),~-,
I I I 01 [2] 1318 FROM PT405 I 0 c
)-----,---~--{~ L---@
I I T3E28' TE ' 403 022 I r TD/1318 (B-7l I T0/1327 ~~ lu\)'--rr-.-r-r"f
~ ~
[1] TRAIN A TO PB403C ( M-22BB01 12-----1 I 1 I I 020
~-~ _l TE 1317 TRAIN B
( A-5) , __ l___ _j _ _ T_T ______ I I 8 118 _j@ TRAIN B 1'< TRAIN A I I 11'6] NOTE 2 PB ~B I TO CORE I 1_1_1__ ..1._I _ _ _ _ _ _ _ 1 __ PD/403 K/1317 4038 ~ 03- __ _j SU8COOLING2- py I I [1] I MONITOR 4~3Y 0 1 ~
~22 I ~
I 1 TO RVLIS2---_j ~ 022
~
I NOTE 2 I
,_l_ _________ _ E.fl_ tll_ I I 405 405 : TO PV8702A I ~-( ( M-22B801 l 1[1] !-c' TO CORE SUB- I I ( F- 4 l A 002 L ~(e[\ I COOLING MONITOR I I L _ _ _ --( TO Z-8701 C I I I ( M-22EJ01 l I~
I ( H-8 l I 118 1-,J TO PB405C I I I I M-22BB01 I TO PV8702B I I L __ s I I I H-1 I f-( TO RVLIS I I L...(' TO PR403 I l ________ TO HV8701 A 8. HV8701B (M-22EJ01 l (G-8, C-81 L L--2 (M-228801) l H-6 l TO Z-8702C B (C-31 - - - - - - ( { M-22BB01 l ( G-5 l AS-BUILT CLASS 1 DRAWN N/A (DATEI A
~'~"'""---~'""'"~" PIPING & INSTRUMENTATION DIAGRAM
'""* NIA '"'"' A REACTOR COOLANT SYSTEM N/A /16\ FSAR FIGURE 5.1 1 SHEET 4 REV.
16 8 I 7 I 6 I 5 If 4 I 3 I 2 I 1
CALLAWAY - SP NOTES TO FIGURE 5.1-2 Mode A Steady State Full Power Operation Pressure Temperature Flow Location Fluid (psig) (°F) gpm (1) lb/hr (2) Volume 1 Reactor 2,235.0 618.8 108,781 36.2040 - coolant 2 Reactor 2,233.7 618.8 108,781 36.2040 - coolant 3 Reactor 2,189.7 557.7 97,452 36.2040 - coolant 4 Reactor 2,186.1 557.7 97,453 36.2040 - coolant 5 Reactor 2,282.3 558.0 97,368 36.2065 - coolant 6 Reactor 2,281.0 558.0 97,361 36.2040 - coolant 10-15 Reactor See Loop #1 Specifications coolant 19-24 Reactor See Loop #1 Specifications coolant 28-33 Reactor See Loop #1 Specifications coolant 37 Reactor 2,282.3 558.0 1.0 0.00037 - coolant 38 Reactor 2,282.3 558.0 1.0 0.00037 - coolant 39 Reactor 2,282.3 558.0 2.0 0.00074 - coolant Rev. OL-14 12/04
CALLAWAY - SP NOTES TO FIGURE 5.1-2 (Sheet 2) Pressure Temperature Flow Location Fluid (psig) (°F) gpm (1) lb/hr (2) Volume 40 Steam 2,235.0 652.7 - - 720 41 Reactor 2,235.0 652.7 - - 1,080 coolant 42 Reactor 2,235.0 652.7 2.5 0.0007 - coolant 43 Reactor 2,235.0 652.7 2.5 0.0007 - coolant 44 Steam 2,235.0 652.7 0 0 - 45 Reactor 2,235.0 300 0 0 Minimize coolant 46 N2 3.0 120 0 0 - 47 Reactor 2,235.0 300 0 0 Minimize coolant 48 N2 3.0 120 0 0 - 49 N2 3.0 120 0 0 - 50 N2 3.0 120 - - 450 51 Pressurizer 3.0 120 - - 1,350 relief tank water 52 Steam/H2 2,235.0 559 0 0 - 53 Reactor 3.0 120 0 0 - coolant 54 Reactor 50 170 0 0 - coolant (1) At the conditions specified. 6 (2) X 10 . Rev. OL-14 12/04
000223-1 STEAM GENERATOR STEAM GENERATOR SIS Sl AND SIS Sl AND RHR PMPS RHR PMPS LOOP 2 LOOP 3 eves LETDOWN eves EMERGENCY LETDOWN REACTOR SIS Bl COOLANT PUMP PUMP RMWSRMW 31 LOOP 1 LOOP4 eves CHARGING WPS (L) RCDT HX STEAM GENERATOR WPS(L) RCDT PUMP 7 CONTAINMENT SUMP SIS Sl SIS Sl (SEE NOTES ON THE PUMPS PUMPS FOLLOWING PAGES) NOTES: REVOL-8 THIS DIAGRAM IS A SIMPLIFICATION OF THE SYSTEM INTENDED TO FACILIATE THE UNDERSTANDING OF THE PROCESS. FOR DETAILS OF THE PIPING, VALVES, INSTRUMENTATION, ETC. REFER TO THE ENGINEERING RHRS RHflS 11/95 FLOW DIAGRAM. REFER TO PROCESS FLOW DIAGRAM TABLES FOR THE CONDITIONS AT EACH NUMBERED POINT. PUMP 1 PUMP 2 CALLAWAY PLANT FIGURE 5.1-2 REACTOR COOLANT SYSTEM PROCESS FLOW DIAGRAM
0 21 1/8" 21 1/8"
-16" VENTSTACK
+
22" DIA. :r:
! I I
! 0 N
8 3/4" 6" EXTRUDED OUTLET
-28" (28.38 O.D.) Rev. OL-0 6/86 CALLAWAY PLANT FIGURE 5.2*1 8" - 300#
W/NECK R. F. FLANGE INSTALLATION DETAIL FOR THE MAIN 6" - 900# STEAM PRESSURE RELIEF DEVICES LG/NECK R.F. FLANGE
NOTE: THESE CURVES ARE BASED UPON A CONTINUOUS CONTAINMENT PURGE RATE OF 4000 CFM.
. 10
-* 8
... 4 w
z~
', I I
I COOLER CONDENSATE-SSW lOO"F, OUTSIDE AIR 97"f 10'~ RH
----------~r-~~~~~~~~~~~~~~--------~2 (35% EVAPORATION)
COOLER CONDENSATE-ESW lOO"F, OUTSIDE AIR 97~F 45% RH i U) z
~
(35% EVAPORATION)
- 0.3
*- 0.2 5
....... 0.1
.08
.06
.05 i *- .03 2
10 1 MIN 2 MIN 3 4 5 6 8 10 15 20 30 2HR 3HR 4HR 6HR 8HR 12HR 16HR3 MINIMUM TIME TO DETECT LEAKAGE CALLAWAY PLANT FIGURE 5.2 - 2 PRIMARY COOLANT LEAK DETECTION RESPONSE TIME REV OL-14 12/04
--=-
J FIGURE 5.3-l REACTOR VESSEL
BOLTS OR STUDS AND NUTS REV. OL-9 5/97 CALLAWAY PLANT FIGURE 5.4-1 REACTOR COOLANT CONTROLLED LEAKAGE PUMP
14113-5 600 500
-Q)
Ql Ll.. 400
- r tl) c..
z "'C s:: 300 ra "'C ra Q)
- r
-rc 0 1-200 100 Required Net Positive Suction Head 0 0 10 20 30 40 50 60 70 80 90 100 110 120 130 140 Flow (Thousands of GPM) Rev. OL-0 6/86 CALLAWAY PLANT FIGURE 5.4-2 REACTOR COOLANT PUMP ESTIMATED PERFORMANCE CHARACTERISTIC
Steam Outlet Nozzle
/ Secondary Manway Pressure Tap Level Tap Sampling Tap Feedwater Nozzle
---------- LeveiTap
/ Inspection Port (typ.)
6 Handholes Primary Manway REV. OL-15 5/06 CALLAWAY PLANT Primary Coolant Inlet Nozzle~ FIGURE 5.4-3 Areva Model 73/19T Steam Generator
CALLAWAY - SP Figure 5.4-4 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 5.4-5 Deleted REV. OL-15 5/06
CALLAWAY - SP Figure 5.4-6 Deleted REV. OL-15 5/06
IIICSIGTL.ai LOIP l <lllt~T UG 1 r <liltS HOT Ull'. L£G r /'CSs~*
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D t L- -- 9 ll.JNT.\INIIO(f~ _ ___J o<JTE 1 TI-llS OlofiQIMIII IS A SUI'ltflt.t.TUJII f7 M ,S'Tal, , , . _ , 'm (SEE NOTES ON THE FOLLOWING PAGES) f.fiCILITATI flo .,._,....,.!>>' lMl "'-EEl OF T11[ l"tl"lllli. WLWS. I~ATI ... £TC . e t l1) M
.III'TAIU Dll1.0.1115 FUJI 01~ - - l'D , . _ . ,.,. 0 1 -
r-.rs F1:Jt H. t'OGITICIIlT UD4 ~ ...,._ CALLAWAY PLANT FIGURE 5.4-8 RESIDUAL HEAT REMOVAL SYSTEM PROCESS FLOW DIAGRAM Rev. OL-0, 6/86
CALLAWAY - SP NOTES TO FIGURE 5.4-8 MODES OF OPERATION MODE A - INITIATION OF RHR OPERATION When the reactor coolant temperature and pressure are reduced below approximately 350°F and 400 psig, approximately 4 hours after reactor shutdown, the second phase of plant cooldown starts with the RHRS being placed in operation. Before starting the pumps, the inlet isolation valves are opened, the heat exchanger flow control valves are set at minimum flow, and the outlet valves are verified open. The automatic miniflow valves are open and remain so until the pump flow exceeds approximately 1,650 gpm (at 300°F) at which time they close. Should the pump flow drop below approximately 816 gpm (at 300°F), the miniflow valves open automatically. Startup of the RHRS includes a warmup period during which time reactor coolant flow through the heat exchangers is limited to minimize thermal shock on the RCS. The rate of heat removal from the reactor coolant is controlled manually by regulating the reactor coolant flow through the residual heat exchangers. The total flow is regulated automatically by control valves in the heat exchanger bypass line to maintain a constant total flow. The cooldown rate is limited to 100°F/hr, based on equipment stress limits and a 120°F maximum component cooling water temperature at the RHR heat exchanger inlet. MODE B - END CONDITIONS OF A NORMAL COOLDOWN This situation characterizes most of the RHRS operation. As the reactor coolant temperature decreases, the flow through the residual heat exchanger is increased until all of the flow is directed through the heat exchanger to obtain maximum cooling. Note: For the safeguards functions performed by the RHRS, refer to Section 6.3, ECCS. Rev. OL-14 12/04
CALLAWAY - SP NOTES TO FIGURE 5.4-8 (Sheet 2) VALVE ALIGNMENT CHART Valve No. Operational Mode A B 2 C C 3 C C 10 O O 11 O O 12 C C 13 C C 14 C C 15 C C 16 P C 17 P C 18 P O 19 P O 20 C C 21 C C 22 O O 23 O O 24 O O 26 O O O = Open C = Closed P = Partially Open Rev. OL-14 12/04
CALLAWAY - SP NOTES TO FIGURE 5.4-8 (Sheet 3) MODE A - INITIATION OF RHR OPERATION Pressure Temperature Flow Location Fluid (psig) (F) (gpm) (a) (lb/hr) 24 Reactor 400 350 3,800 1.60 x 106 coolant 25 " 407 350 3,800 1.60 x 106 26 " 542 350 3,800 1.60 x 106 27 " 541 350 1,259 0.56 x 106 31 " 539 140 1,259 0.56 x 106 29 " 496 350 2,541 1.13 x 106 32 " 496 280 3,800 1.69 x 106 28 " 480 280 3,690 1.64 x 106 19 Loop 4 " 404 280 1,992 0.885 x 106 19 Loop 3 " 419 280 1,698 0.755 x 106 34 " 400 350 3,800 1.69 x 106 35 " 407 350 3,800 1.69 x 106 36 " 542 350 3,800 1.69 x 106 37 " 541 350 1,259 0.56 x 106 41 " 539 140 1,259 0.56 x 106 39 " 496 350 2,541 1.13 x 106 42 " 496 280 3,800 1.69 x 106 38 " 479 280 3,910 1.74 x 106 20 Loop 1 " 404 280 1,955 0.87 x 106 20 Loop 2 " 404 280 1,955 0.87 x 106 (a) At reference conditions 350°F and 400 psig Rev. OL-14 12/04
CALLAWAY - SP NOTES TO FIGURE 5.4-8 (Sheet 4) MODE B - END CONDITIONS OF A NORMAL COOLDOWN Pressure Temperature Flow Location Fluid (psig) (F) (gpm) (a) (lb/hr) 24 Reactor 0 140 3,800 1.87 x 106 coolant 25 " 7 140 3,800 1.87 x 106 26 " 156 140 3,800 1.87 x 106 27 " 149 140 3,800 1.87 x 106 31 " 129 120 3,800 1.87 x 106 29 " 93 120 0 0 32 " 93 120 3,800 1.87 x 106 28 " 75 120 3,800 1.87 x 106 19 " 2 120 1,900 0.935 x 106 34 " 0 140 3,800 1.87 x 106 35 " 7 140 3,800 1.87 x 106 36 " 156 140 3,800 1.87 x 106 37 " 149 140 3,800 1.87 x 106 41 " 129 120 3,800 1.87 x 106 39 " 93 120 0 0 42 " 93 120 3,800 1.87 x 106 38 " 75 120 3,800 1.87 x 106 20 " 2 120 1,900 0.935 x 106 (a) At reference conditions 140°F and 0 psig. Rev. OL-14 12/04
-- \ LL. 0 350 Ql 300
- s
....IV ~
Q. 250 \ E
~ ....c: ~ 150 0
200 u 0 100 ' ' ' I
~
IV Ql 4 8 12 16 20 a: Time After Reactor Shutdown (Hours) CALLAWAY PLANT FIGURE SA-O NORMAL RESIDUAL HE'R' REMOVAL COOLDOWN REV. 1e 8114
0 350
\
~ 300
..,Ill
~
~ 250 a.
\
E
~.... 200 c -8150 Ill u ~Ill 100 I I I I I I I Ql a:: 4 8 12 16 20 24 28 32 Time After Reactor Shutdown (Hours)
CALLAWAY PLANT FIGURE 5.4-10 SINGLE RESIDUAL HEAT REMOVAL TRAIN COOLDOWN REV.16 9/14
SPRAY NOZZLE SAFETY NOZZLE UPPER HEAD INSTRUMENTATION NOZZLE LIFTING TRUNNION SHELL LOWER HEAD HEATER SUPPORT PLATE INSTRUMENTATION NOZZLE ELECTRICAL HEATER SUPPORT SKIRT SURGE NOZZLE Rev. OL-0 6/86 CALLAWAY PLANT FIGURE 5.4-ll PRESSURIZER
PRESSURIZER RELIEF VALVE DISCHARGE LINE CONNECTION SPRAY WATER INLET SAFETY HEADS VENT CONNECTION RHR SUCTION RELIEF VALVE DISCHARGE LINE CONNECTION SPARGER PIPE
-----.,r-
*1
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1 * \ _../. ~ VESSEL SUPPORT DRAIN CONNECTION VESSEL SUPPORT CALLAWAY PLANT FIGURE 5.4-12 PRESSURIZER RELIEF TANK REV. 1 3/09
1299~1 l RI=.ACTOR DET VI:SSEL SUPPORT (~ RFQ'D) PLAN VIEW G_ REACTOR DETAIL SECTION B @ oD REACTOR VESSEL Rev. OL-0 6/86 SECTION CALLAWAY PLANT FIGURE 5.4-13 REACTOR VESSEL SUPPORTS
13,557-34 UPPER LATERAL SUPPORT LIMIT STOP LOWER LATERAL SUPPORT WIDE FLANGE COLUMNS DIRECTION OF THERMAL EXPANSION REV. OL-15 5/06
*CALLAWAY PLANT FIGURE 5.4-14 STEAM GENERATOR SUPPORTS
12999 rCOLD LEG I TIE RODS CRO:S-OVER LEG WIDE FLANGE COLUMNS Rev. OL-0 6/86 CALLAWAY PLANT FIGURE 5.4-15 REACTOR COOLANT PUMP SUPPORT~
/~
- - - - SUPPORT SKIRT
( \1.---- PRESSURIZER SUPPORT FRAMING
,.1 T
~
r*, .. SHIELD WALL CONCRETE SLAB l . ~ ANCHOR BOLTS
.J I l r 1 PLAN AT SUPPORT SKIRT BOLT ( TYP.)
SUPPORT Rev. OL-0 FRAMING 6/86 CALLAWAY PLANT SECTION@ FIGURE 5.4-16 REACTOR BUILDING INTERNALS PRESSURIZER SUPPORTS
38lf2-5 PRESSURIZER SKIRT BEARING PLATE GROUT Rev. OL-0 6/86 CALLAWAY PLANT FIGURE 5.4-17 PRESSURIZER SUPPORTS
tl S.G. VERT. tl R.C. PUMP RUN PIPE CROSSOVER PIPE
~--SUPPORT DEACTIVATED BY REMOVAL OF SHIM PLATES
( CMP 03-1 011 ) CALLAWAY PLANT FIGURE 5.4- 18 CROSSOVER LEG RES1RAINT REV. OL-15 5/06
CALLAWAY - SP Figure 5.4-19 Deleted REV. OL-15 5/06
SADDLE AND SHIMS REMOVED _ _ _ _ _ ___J CALLAWAY PLANT FIGURE 5.4- 20 HOT LEG RESTRAINT REV. OL-15 5/06
(0) £<;;88£0-::> t REACTOR 3'-3~' TO WP 111'-o: 1 i-o* 1i-1 "TO q;
--+
t Rf:ACTOR BLDG T 0 I ~{'J a
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-~ 1 ALL DIMENSIONS GIVEN ARE IN COLD POSITION UN 0 2 MATERIAL FOR HU 1"' THICK COLLAR RING SHALL 8E ASTM A!>lfl
- ..N a J THE 1" THICK COLLAR RING AND BUILT UP FILLER MEMBERS SHALL
.... BEPOSTWELDHEATTAEATED 4 SURFACES WHICH RECEIVE SHIMS ANDIOA BEARING SHALL BE MACHINED TO THE DESIGN CONTOUR 5 SHIM AREA AS INDICATED ON THE DRAWING SHALL BE ~ROVIDED WITH NOT LESS THAN 50'110 OF THE BEARING AREA
;,_N 6 SHIM PlATES SHALL BE SHOP TACK WELDED TO THE ~UIL T UP FILLfA a MEMBER AFTER PAOPfAL Y ALIGNED
-,:. 7 THE RADIAL LOCATION tO A INSIDE RADIUS AT ANY POINT Of THE 1 THICK COLLAR RING SHALL NOT VARY FADM THE DESIGN RADIUS BY MORE THAN 1/B F
b 8 RESTRAINT ASSEMBUH SHALL BE SHOP PRE ASSEMBLED TO INSURE
-~ PROPER ALIGNMENT AND DELIVER TO SITE AS ONE UNIT FOR EACH
.J.i:{ .IQ .£... ~~A-~TQtL N 9 THE MAXIMUM ALLOWABLE GM AT THE SHIM OR BEARING SURFACES
-" SHALL B~ 1/1~" SHIMS MAY 8E ADDED BETWEEN THE OUTSIDE FACE Of THE INNER RING AND THE INSIDE FACE OF THE SPOKE TO MH_T
-"' THIS REQUIREMENT 10 THE FIELD MACHINED SHIMS SHJ.LL ACCOUNT FOR THE AS BUILT DIMENSIONS OF THE RESTRAINT RING THE INSIDE FACE OF THE INNER RING AND THE OUTSIDE DIAMETER OF TH( HOT AND COLD PIPES AT EACH LOCATION 12 THE OVTfR ~lNG SHALL 8E PAE5SEO AGAIN!.T THE COMPRESSII!oLE MATERIAL AS MUCH AS POSSIBLE TO PRE~ENl LEAKAGE OF PLAN AT EL 2014'-6' u THE AS*8UILT C0\.0 GAP AT SHIM.J MUST 8[.
AI 5MALI ER THAN lOR EOUAl TO) THE AS*BUIL T COLO GAP E AT SNIM *2 B) SMALLER THAN (OR [QUAL TO) THE AS*8VIlf COlD
~
GAP AT SHIM ... PLUS )J\6". TYPCB
/~***3LG SHEAR STUDS AT 300 (TYP)
SEC: CHART FOR II ' 0 0 q_: COLD GAPS OF SHIMS 1.0 J......l..: IU' 1'-4 31132" R
\'
/
~**x 3 LG SHEAR STUDS AT 30° (T'rP)
- ~B"x2" COMPRESSIBLE REFERENCE DRAWINGS C-OL2930 REACTOR BUILDING LINER PLATE REACTOR CAVITY WALL (REF) MATERIAL (ROOOFOAM IT BY GRACE & CO, OR I
;.j TYP D
~~~~~~1-o,.l~~~~t~l§ J----*--H~~tlt-+--.
EQUAL) (BY OWNER) MATERIAL RESPONSIBILITY 1 STEEL TO BE FURNISHED UNDER SPEC 10466-C202 INSULATION DETAIL 6 (SEE OWG M-05002) SSALE1"~1'-C1' - c TYPICAL COLD PIPE tri.. "x5"x2'-4"(SHIM) SECTION SCALI 1"*,.-0" A
- [ tfi f_,:}o"x3"x1'-8"l~OT PIPE) l, (SHIM) MACH AS 8
*;*3"x2'-4"(C0LD IPE)j REQ'D IN FIELD M.A'tH AS REQ'D IN FIELD- ....-----~ r 5/8~ ~ ~~~:: GAP(COLD POSITION)
I HOf PIPE ONLY
£1}4.< ~'x1'-10"1HOT PIPE)
It 1l-.4'x 4'x 2-6(COLD PIPE)
------~~~to 25 oe'!H01 PIPES)
B 23132'CCOLD PIPES) Rev. OL-0
~-'
6/86 TACK WELD CALLAWAY PLANT TY I . 1 ....
'*-2x 1~ xO *2 STOP Sli.R AT END FIGURE 5.4-21 HOT AND COLD LEG A LATERAL RESTRAINTS (C-038853(01-41 8 7 5 4 3 2 1 e'ov 1~ t;** SIZE}}