ML21125A564
Text
UFSAR Revision 30.0 A B F G H J I( L M N 0 THRUST BEAR\t,JG UPPEI', ~ LOWEf' SHOE (TYP)
REACTOR VESSEL FLANGE SEAL LEAK-OFF TO LOWER OIL RC:!:f nR UPPEP. ~ w REACTOR COOLANT RADIAL e, T~RU DRAIN TANK. SEE BEARl.r(i~ (T FIG. ll. 1-1 I
NV \TO UPPER COl.ffAlt,JMENT
\ 1/0LUME.
OllSCQt,Jt,JfCT FROM ACCUMULATOR TANKS. SEE
~ _ ........~
FLAt,JC,c~ (TYP)
FIG. 6. 2-lA REACTOR REACTOR COOLANT PUMP
+ COOLANT PUMP CSEE SK "D-3" ON TO EXCESSIVE LETDO LINE. SEE FIG. 9.2-CSEE SK. "D-3" ON FIG. 4. 2-lA)
FIG. 4. 2-lA)
ALTERNATE CHARGING LINE. SEE FIG. 9.2-1 LO.
OTA.
SPRAY LINE TO ORIFICE PREC:SURIZER. SEE SH.AM GE:.NE:.RATOR COUPLING (T'IP)
FROM EMERGENCY F.O. SK irG-9" ON CORE COOLING SYS FIG. 4. 2-IA BORON IN..ECTION TANK DISCHARGE. SEE TELLrALE FIG. 6.2-1 REACTOR HEAD VENT
REFERENCES:
OP-I <21-5121 REACTOR VESSEL NOTE A:
DIGITAL METAL IMPACT MONITORING SENSOR LOCATIONS:
REACTOR VESSEL 2 SENSORS ON R.V. HD.
2 SENSORS ON R.V. LOWER HD.
5 INSTRUMENT GUIDE TUBES s 1MB 5TE:AM uE.NE.RATOR STEM, GEN. 'S 1, 2, 3 AND 4 TO REACTOR COOLANT I SENSOR ABOVE TUBE SHEET DRAIN TANK SEE 1MB I SENSOR BELOW TUBE SHEET TO REACTOR COOLANT FIG. ll.1 - - ~ TO LETDOWN LINE lIDIE....B_;
DRAIN TANK S E ~ SEE FIG. 9. 2-1 SYSTEM LINEUP SHOWN FOR NORMAL FIG. ll,1-1 FROM RESIDUAL HEAT FROM RESIDUAL HEAT REMOVAL &SAFETY REMOVAL &SAFETY OPERATION. VALVE POSITIONS ARE NOT INJECTION SYSTEMS. SEE INJECTION SYSTEMS. GOVERNED BY THE UFSAR FIGURES BUT FIG. 6. 2-IA SEE FIG. 6.2-IA RATHER BY STATION PROCEDURES NO.?, <EXCEPT VALVES WITH LOCKED OR 6 PRESSURIZER S~RGE SEALED,AND FAILURE POSITIONS AS &
LINE. SEE SK G-9" ON INDICATED).
FIG. 4,2-IA7 QTQ e>--
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COOLING SYSTEM.
SEE FIG. 6.2-1------._.
OLA NVA DATE ND. DESCRIPTION REVISIONS FILENAME, fsar-lig--1.2-1 21-2.d~n APPD raster file : fsar-fi -4.2-1 21-2.cit
-THIS DltAIIINO 11 THI! ~ltTY 01' THI! AMERICAN ELECTRIC POWER SERVICE CORP. AND 11 LCIAIED REACTOR uPOII CONDITION THAT II IS NOT TO !E AEPRCIDUCED 8 REACTOR COOLANT1 PUMP OR COPIED. IN WHDLE OR IN PART* QR USED Fmt Fl.R- 8 COOLANT PUMP <SEE SK ' D-3" ON NISHINO IWCIRMATION 10 ANY PERSON VITH0UT T...
VRITTEN COldEIIT OF THIE AEP SERVICE CORP.
- DR
<SEE SK "D-3" ON FIG. 4.2-lAl FDR ANY PI.RPOSE DETRIMENIAL TO IHIEIR INIERl:SI, FIG. 4. 2-lAl AMJ IS TO BE AETUUED I.PON REIIUEST" INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT 9 LOOP '2 LO O P 3 9 IMR FIG. 4.2-1 1MB NECH TO REACTOR COOLANT TO REACTOR COOLANT / CONNECTION CHI*
DRAIN TANK SEE -- DRAIN TANK SEE__..,,.,. ~ FOR REFUELING WATER FIG. ll. 1 - -
- FIG. ll. 1-1 LEVEL MEASURE AEP SERVICE CORP.
1 RIVERSIDE PlAZA COLUMBUS, OH 43215
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.,,._~.,,._,,,a "TI-IIS DRAWING IS THE PROPERTY OF THE AMERICAN ELECTRIC POWER SERVICE CORP. 1,,..0 IS LOANED UPON CONDITION THAT IT IS NOT TO BE REPROOUCED OR: COPIED, IN WHOLE OR: IN PART, OR: USED FOR FUR- 8 i 11
' ~_;;=---:::--~ ~--' NISHING INFORMATION TO ANY PERSON WITHOUT THE WRITTEN CONSENT OF THE AEP SERVICE CORP. ,OR
\ , FOR ANY PURPOSE DETRIMENTAL TO THEIR INTEREST, HO\.E PROV\OED7 FROM RE.ACTOR LOOP '-._./ AND IS TO Bli: Rli:TUANli:D UPON Rli:01.Ai:ST" COOLANT LOOP SEE FIG, 4.2-1 INDIANA MICHIGAN POWER COMPANY l ' DONALD C. COOK
\ \ BRIDGMAN NUCLEAR PLANT MICHIGAN
~0 REACTOR COOLANT Oi--
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FIG. 11. 1-1 AEP SERVICE CORP.
1 RIVERSIDE PLAZA COLUMBUS. OH 43215
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FIGURE 4*. 2-2 July, 1982
UFSAR Revision 30.0 rtJ-"'*"""~
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..,...,- ".3B,.34 47 ~o - ~ ~ FIGURE 4.2-2A July, 1982
UFSAR Revision 30.0 SPRAY NOZZLE RELi EF HOZZLE-- SAFETY NOZZLE MAHWAY UPPER HEAD INSTRUMENTATION HOZZLE LIFTING TRUHHION SHELL LOWER HEAD INSTRUMENTATION NOZZLE ELECTRICAL HEATER SUPPORT SKIRT SURGE NOZZLE PRESSURIZER FIGURE 4.2-3 July, 1982
UFSAR Revision 30.0 EXISTING UPPER SHELL AND INTERNALS NEW l'EEDWATER RING I INCONEL J-NOZZl.ES
~~£~~~~ THREE SETS OF AVB'S FORGED TRANSITION CONE
--..i~.J.I..~~~~-- INCREASED ROW 1 U-BENC TW0-4" INSPECTION PORTS : RADIUS; ROWS 1*9 U*IEND lli!i-.,l,,j~i,,Mi,,+--1 STRESS RELIEF SIS QUA. TREFOIL TUBE SUPPORT PLATES INCONEL 980 TT TUBING SIS OCTAFOIL FLOW FORGED STUB BARREL OISTRIBUTION BAFFLE TUH LANE BLOCKS
"""- s1x-1* ACCESS PORTS ENHANCED 8LOW00WN MODEL 51 F STEAM GENERATOR
,3 Revision: 18 Change
Description:
UCR-1649
Title:
Cook Unit 2 AMERICAN ELECTRIC POWER Repaired Steam Generator General Arrangement COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN Sheet 1 of 1 UFSAR Figure: 4.2-4 Unit 2
UFSAR Revision 30.0 Steam Modular ~Outlet Secondary b='":::A I ~~"":::Jl Nozzle Separators ,., I , \
11 Steam Orum
~~Manway Pnmary Separators tr-___- Existing Steam Drum Feedwater U Header Pnmary 111111--- I Deck Flat Bar Ubend Restraints Rec1rculabon Shell Cone Connection Handhole Lattice Gnd Tube Support (typical)
Lower Shell Handhole Tube sheet Handhole Slowdown Nozzle Tubesheet Pnmary Head Pnmary Manway 16.6 REVISED PER 99-UFSAR-1226 REV. NO. DESCRIPTION REVISIONS TITLE AMERICAN ELECTRIC POWER UNIT 1 MODEL 51R REPLACEMENT STEAM COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP GENERATOR, GENERAL CONFIGURATION BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 4.2 - 4A SH 1 of 1
UFSAR Revision 30.0 Pnmary Separators 11 II I1 II 1
1_ Normal Water Lev~--- _______ JI 1I Feedwater 1;J'~=====i==~ Nozzle
---H--+-- Feedwater Ring 16.6 REVISED PER 99-UFSAR-1226 REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE UNIT 1 MODEL 51R REPLACEMENT STEAM GENERATOR, COOK NUCLEAR PLANT STEAM DRUM ARRANGEMENT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 4.2-4B SH 1 of 1
UFSAR Revision 30.0 11""""::;:;;~;;:-~t-----Byposs Holes L~::§@::i./1_11----i Sccondocy Separator Secondocy Comportment lnlersloge Space
~\.:L-----Rctoining Up
~~+------Relum Cyfsnder Perforations Primacy Separator Woter Relurn Cylinder Riser
{length varies depencfltlg on lhe cpplt::alion)
~----oroin line Separolor Deck 16.6 REVISED PER 99-UFSAR-1226 REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE UNIT 1 MODEL 51R REPLACEMENT STEAM GENERATOR, COOK NUCLEAR PLANT PRIMARY AND SECONDARY SEPARATORS NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 4.2-4C SH 1 of 1
UFSAR Revision 30.0 16.6 REVISED PER 99-UFSAR-1226 REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE UNIT 1 MODEL 51R REPLACEMENT STEAM GENERATOR, B&W COOK NUCLEAR PLANT LATTICE GRID TUBE SUPPORT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 4.2 - 4D SH 1 of 1
UFSAR Revision 30.0 16.6 REVISED PER 99-UFSAR-1226 REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE UNIT 1 MODEL 51R REPLACEMENT STEAM GENERATOR, COOK NUCLEAR PLANT TUBESHEET BLOWDOWN CONFIGURATION NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 4.2 - 4E SH 1 of 1
UFSAR Revision 30.0 FLYWHEEL UPPER RADIAL BEARING THRUST BEARING THRUST BEARING 01 L LI FT PUMP MOTOR SHAFT + MOTOR MOTOR STATOR MAIN LEAD CONDUIT BOX MOTOR UNIT LO~ER RADIAL ,\SSEMBL Y BEARING VAPOR LEAKAGE UPPER SE~L TO ATMOSPHERE HOUSING NO. 2 INJECTION WATER LEAK OFF NO. I SEAL LEAK OFF PUMP SHAFT LOWER SEAL HOUSING MAIN FLANGE COO LI NG WATER INLET COOLING WATER OUTLET RADIAL BEARING DISCHARGE NOZZLE ASSEMBLY THERMAL BARRIER AND HEAT EXCHANGER CASING SUCTION NOZZLE IMPELLER REACTOR COOLANT PUMP FIGURE 4.2-5 July, 1982
UFSAR Revision 30.0 REACTOR COOLANT PUMP FLYWHEEL 1s in. I I
J_______.....,___ ___,. 7.5: in, f 65in. T LBore of"' 8-3/8 in. Diameter wit1. 3 Keyways NOTE: The plates are bolted together with the bolts aligned perpendicular to the planes of the plates.
FIGURE 4. 2-6 July, 1982
24 _,,__ _ _ _ _ _ _ _ _ _ _;___ _ _ UFSAR Revision
_ _ _;.;._____ 30.0
_ _ _ _ _ _ _ _ _ _ ___,;._ _ _ _ _ ~
22 FLYWHEEL OD* 75 in.
20 is 16 TANGENTIAL STRESS VS. FLYWHEEL RADIUS 0
14 M ... _. --
.... 1 g: 12 - - - 1500 RPM - OVERSPEED 8
6 4 "--mrtls 1200 RPM 4.1875 in.
2 0
4 6 8 10 12 14 16 18 20 22 26 28 30 32 34 36
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RADIUS, in. Original FSAR figure
UFSAR Revision 30.0 500 400 300 200 100 0
0 10 20 30 40 50 60 70 80 90 100 110 FLOW - THOUSANDS OF GPM REACTOR COOLANT PUMP PERFORMANCE CHARACTERISTICS FIGURE 4.2-8 July, 1982
UFSAR Revision 30.0 TR FOR Mn-Mo STEEL 500 l,j:,:;':
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- 475 to 540 RAGIATION INDUCED INCREASE IN 0 600 A302B TRANSITION TEMPERATURE FOR Mn-Mo Numbers 1 through 37 ( SEL ATT/1CHED SHEETS 1 STEEL FIGURE 4.2-9 July, 1982
UFSAR Revision 30.0 D ...,I' I
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Unit l Reactor Vessel Stress Analysis: Areas Examined FIGURE 4. 3-1 July, 1982
UFSAR Revision 30.0
....ll. (INLET) l_ (OUTLET)
Unit l Reactor Vessel St ress An 1 Detail s - a ysis:
Upper J FIGURE 4.3-2 uly, 1982
UFSAR Revision 30.0
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Unit 1 Reactor Vessel Stress Analysis: Details - Lower FIGURE 4. 3-3 July, 1982
UFSAR Revision 30.0 NOZZLE WELD 0
WELD "CORE" VESSE INTERMEDIAT SHELL
,.;;t
+
,.;;t CL ..-4 32 5/8" CAPSUL WELD CL VESSEL LOWER SHELL
- 0. 030" STAINLESS SHEATH
= ---- --1. ,.. CORE llc:-T-C::111~=::::.:....-spAcERS
....i....-t'::~'-;-:~".".l---.r.HARPy SPECIMEN
~-- ---W ELD SURVEILLANCE CAPSULE ELEVATION VIEW July , 1982 Figu re 4.5-1
UFSAR Revision 30.0
,~" ...
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THERMAL SHIELD
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I 180° Notes: Capsule W was moved back to the 4 degree location and renamed as S in March 2010 (U1C23).
Capsule S was renamed as W at the 184 degree location.
Figure 4.5-2 is current as of March 2010. Figure 4.5-2A is superseded.
Revision: 23 Change
Description:
UCR-1968
Title:
Surveillance Capsule Plan View AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 4.5-2 Sheet 1 of 1
UFSAR Revision 30.0
- - - - CAPSULE
- - - - SPECIMEN GUIDE SPECIMEN GUIDE TO THERMAL SHIELD ATTACHMENT Figure 4 ,. 5-3 July, 1982