ML21125A564

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0 to Updated Final Safety Analysis Report, Chapter 4, Figures
ML21125A564
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 04/19/2021
From:
Indiana Michigan Power Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML21126A238 List: ... further results
References
AEP-NRC-2021-19
Download: ML21125A564 (22)
v • d • e


Text

fsar-fig-4.2-1_21-2.dgn 3/7/2008 10:18:39 AM UFSAR Revision 30.0

+

5 6

7 8

9

+

A B

THRUST BEAR\\t,JG UPPEI', ~ LOWEf' SHOE (TYP)

LOWER OIL RC:!:f nR UPPEP. ~ w RADIAL e, T~RU BEARl.r(i~ (T REACTOR COOLANT PUMP CSEE SK "D-3" ON FIG. 4. 2-lA)

TO REACTOR COOLANT DRAIN TANK SE~

FIG. ll,1-1 e>--

QLA REACTOR COOLANT PUMP

<SEE SK "D-3" ON FIG. 4. 2-lAl QTQ IMR 1MB TO REACTOR COOLANT DRAIN TANK SEE FIG. ll. 1-1 IGS069' A

B QTQ NVA C

ALTERNATE CHARGING LINE. SEE FIG. 9.2-1 LOOP '2 D

FROM EMERGENCY CORE COOLING SYS BORON IN..ECTION TANK DISCHARGE. SEE FIG. 6.2-1 FROM RESIDUAL HEAT REMOVAL & SAFETY INJECTION SYSTEMS. SEE FIG. 6. 2-IA F

REACTOR VESSEL FLANGE SEAL LEAK-OFF TO REACTOR COOLANT DRAIN TANK. SEE FIG. ll. 1-1 I

F.O.

G FROM ACCUMULATOR TANKS. SEE FIG. 6. 2-lA OTA.

TELLrALE 1,... '"'""" '"

COOLING SYSTEM.

SEE FIG. 6.2-1------._. ---411----

E CM I 3

4 S

6 7

G H

TO EXCESSIVE LETDO LINE. SEE FIG. 9.2-LO.

J I(

SPRAY LINE TO PREC:SURIZER. SEE SK irG-9" ON SH.AM GE:.NE:.RATOR FIG. 4. 2-IA 3i&INCH 4 H

FROM RESIDUAL HEAT REMOVAL & SAFETY INJECTION SYSTEMS.

SEE FIG. 6.2-IA PRESSURIZER S~RGE LINE. SEE SK G-9" ON FIG. 4,2-IA7 12 16 J

5TE:AM uE.NE.RATOR NO.?,

LO O P 3 L

TO REACTOR COOLANT DRAIN TANK SEE

~

FIG. ll.1-1 ---

OLA TO REACTOR COOLANT

/

DRAIN TANK SEE__..,,.,.

FIG. ll. 1-1 30 L

M NV OllSCQt,Jt,JfCT FLAt,JC,c~ (TYP)

N 0

\\TO UPPER COl.ffAlt,JMENT

\\ 1/0LUME.

........ ~

1MB 1MB QT INCHES REACTOR COOLANT PUMP CSEE SK. "D-3" ON FIG. 4. 2-lA)

ORIFICE COUPLING (T'IP)

REACTOR HEAD VENT

REFERENCES:

REACTOR VESSEL

~

TO LETDOWN LINE SEE FIG. 9. 2-1 NVA REACTOR COOLANT PUMP

<SEE SK '1D-3" ON FIG. 4.2-lAl CONNECTION

~

FOR REFUELING WATER LEVEL MEASURE M

OP-I <21-5121 NOTE A:

DIGITAL METAL IMPACT MONITORING SENSOR LOCATIONS:

REACTOR VESSEL 2 SENSORS ON R.V. HD.

2 SENSORS ON R.V. LOWER HD.

INSTRUMENT GUIDE TUBES s

STEM, GEN. 'S 1, 2, 3 AND 4 I SENSOR ABOVE TUBE SHEET I SENSOR BELOW TUBE SHEET lIDIE....B_;

SYSTEM LINEUP SHOWN FOR NORMAL OPERATION. VALVE POSITIONS ARE NOT GOVERNED BY THE UFSAR FIGURES BUT RATHER BY STATION PROCEDURES

<EXCEPT VALVES WITH LOCKED OR SEALED,AND FAILURE POSITIONS AS INDICATED).

DATE ND.

DESCRIPTION REVISIONS

FILENAME, fsar-lig--1.2-1 21-2.d~n raster file : fsar-fi -4.2-1 21-2.cit APPD

-THIS DltAIIINO 11 THI! ~ltTY 01' THI! AMERICAN ELECTRIC POWER SERVICE CORP. AND 11 LCIAIED uPOII CONDITION THAT II IS NOT TO !E AEPRCIDUCED 7

OR COPIED. IN WHDLE OR IN PART* QR USED Fmt Fl.R-8 NISHINO IWCIRMATION 10 ANY PERSON VITH0UT T...

VRITTEN COldEIIT OF THIE AEP SERVICE CORP.

  • DR FDR ANY PI.RPOSE DETRIMENIAL TO IHIEIR INIERl:SI, AMJ IS TO BE AETUUED I.PON REIIUEST" INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT FIG. 4.2-1 NECH CHI*

AEP SERVICE CORP.

1 RIVERSIDE PlAZA COLUMBUS, OH 43215 0

9

...\\fsar-fig-4-2-1a_20.dgn 08/08/2005 11:42:17 AM UFSAR Revision 30.0 I

+

4 s

6 7

8 9

+

IGS06!i4 A

B l:J 'if $ :J "ON "SMC i I f Hi:.AT HEAT EXCH. SAFETY DISCH..

SEE FIG. S.2-1

,.-r FROM NI TR.OGEN V ~(t.~-JT~tH n A

t

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y std l

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(ll Lil

_.J G

.,....a H

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L TO VOLUME CONTROL TA.MC SEE FIG. 9.2-1

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DRAI~J FROM 0 z F--~--- ' FRO !vi

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llKAIN TANK. SEE FIG~ !L 1-1

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l*----i~l:J-------------------------*-----------------------------""~~

___ I TEMP. HOSE CONN. FOR CHARGING PUMP SUCTION SAFETY V ~i vr nTSf:H.

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P05T ACC.iDENT VENT OP-1 C2)-512iiA VALVE: POS!T!ON0ARE NOT

~nVFRl"-JFn RV THF l JFSAR 20 REVISED PER UCR-1712.

DATE NO.

DESCRIPTION REVISIONS

FILENAME, fsar-fig-4-2-la 20.dgn (roster file): fsar-fig--4-2-la 20.tif APPD.

"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-NISHING INFORMATION TO ANY PERSON WITHOUT THE WRITTEN CONSENT OF THE AEP SERVICE CORP.,OR FOR ANY PURPOSE DETRIMENTAL TO THEIR INTEREST, AND IS TO Bli: Rli:TUANli:D UPON Rli:01.Ai:ST" INDIANA MICHIGAN POWER COMPANY DONALD C. COOK BRIDGMAN NUCLEAR PLANT REACTOR COOLANT UNIT NO. I OR 2 SHEET 2 OF 2 MICHIGAN DWG. NO. FSAR FIG. 4.2-1A MECH SIR AEP SERVICE CORP.

1 RIVERSIDE PLAZA COLUMBUS. OH 43215 0

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J REACTOR VESSEL SCHEMATIC FIGURE 4*. 2-2 July, 1982 f

(

(

UFSAR Revision 30.0 rtJ-"'*"""~

t) 4~~.1 "'M-=~==-------------------------i

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I I REACTOR VESSEL SCHEMATIC FIGURE 4.2-2A July, 1982

UFSAR Revision 30.0 RELi EF HOZZLE--

SPRAY NOZZLE 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

Unit 2 Revision: 18 Change

Description:

UCR-1649 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 4.2-4 Sheet 1 of 1

Title:

Cook Unit 2 Repaired Steam Generator General Arrangement UFSAR Revision 30.0 EXISTING UPPER SHELL AND INTERNALS NEW l'EEDWATER RING I INCONEL J-NOZZl.ES FORGED TRANSITION CONE TW0-4" INSPECTION PORTS SIS QUA. TREFOIL TUBE SUPPORT PLATES FORGED STUB BARREL TUH LANE BLOCKS ENHANCED 8LOW00WN

~~£~~~~

THREE SETS OF AVB'S

--..i~.J.I.. ~~~~-- INCREASED ROW 1 U-BENC RADIUS; ROWS 1*9 U*IEND lli!i-.,l,,j~i,,Mi,,+--1 STRESS RELIEF INCONEL 980 TT TUBING SIS OCTAFOIL FLOW OISTRIBUTION BAFFLE

"""-s1x-1* ACCESS PORTS MODEL 51 F STEAM GENERATOR

,3

FSAR FIG. 4.2 - 4A UNIT 1 MODEL 51R REPLACEMENT STEAM GENERATOR, GENERAL CONFIGURATION DESCRIPTION REV. NO.

AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO.

REVISIONS TITLE 16.6 REVISED PER 99-UFSAR-1226 SH 1 of 1 UFSAR Revision 30.0 Modular Secondary Separators Pnmary Separators Pnmary Deck Rec1rculabon Connection Tubesheet Steam

~Outlet b='":::A I ~~"":::Jl Nozzle I

\\

11 Steam Orum

~~Manway tr-___- Existing Steam Drum Feedwater U

Header 1-111111--- I Flat Bar Ubend Restraints Shell Cone Handhole Lattice Gnd Tube Support (typical)

Lower Shell Handhole Tube sheet Handhole Slowdown Nozzle Pnmary Head Pnmary Manway

FSAR FIG. 4.2-4B UNIT 1 MODEL 51R REPLACEMENT STEAM GENERATOR, STEAM DRUM ARRANGEMENT DESCRIPTION REV. NO.

AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO.

REVISIONS TITLE 16.6 REVISED PER 99-UFSAR-1226 SH 1 of 1 UFSAR Revision 30.0 11 I 1 Pnmary Separators I I I I 11_ Normal Water Lev~---

_______ JI 1 I 1;J'~=====i==~

Feedwater Nozzle

---H--+-- Feedwater Ring

FSAR FIG. 4.2-4C UNIT 1 MODEL 51R REPLACEMENT STEAM GENERATOR, PRIMARY AND SECONDARY SEPARATORS DESCRIPTION REV. NO.

AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO.

REVISIONS TITLE 16.6 REVISED PER 99-UFSAR-1226 SH 1 of 1 UFSAR Revision 30.0 11""""::;:;;~;;:-~t-----Byposs Holes L~::§@::i./1_11----i Sccondocy Separator Woter Secondocy Comportment lnlersloge Space

~\\.:L-----Rctoining Up

~~+------Relum Cyfsnder Perforations Primacy Separator Relurn Cylinder Riser

{length varies depencfltlg on lhe cpplt::alion)

~----oroin line Separolor Deck

FSAR FIG. 4.2 - 4D UNIT 1 MODEL 51R REPLACEMENT STEAM GENERATOR, B&W LATTICE GRID TUBE SUPPORT DESCRIPTION REV. NO.

AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO.

REVISIONS TITLE 16.6 REVISED PER 99-UFSAR-1226 SH 1 of 1 UFSAR Revision

==30.0

DESCRIPTION==

REV. NO.

REVISIONS FSAR FIG. 4.2 - 4E UNIT 1 MODEL 51R REPLACEMENT STEAM GENERATOR, TUBESHEET BLOWDOWN CONFIGURATION AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO.

TITLE SH 1 of 1 REVISED PER 99-UFSAR-1226 16.6 UFSAR Revision 30.0

UFSAR Revision 30.0 FLYWHEEL UPPER RADIAL BEARING THRUST BEARING MOTOR SHAFT MOTOR STATOR MAIN LEAD CONDUIT BOX LO~ER RADIAL BEARING VAPOR LEAKAGE TO ATMOSPHERE NO. 2 INJECTION WATER LEAK OFF PUMP SHAFT COO LI NG WATER INLET DISCHARGE NOZZLE SUCTION NOZZLE THRUST BEARING 01 L LI FT PUMP

+ MOTOR MOTOR UNIT

,\\SSEMBL Y UPPER SE~L HOUSING NO. I SEAL LEAK OFF LOWER SEAL HOUSING MAIN FLANGE COOLING WATER OUTLET RADIAL BEARING ASSEMBLY THERMAL BARRIER AND HEAT EXCHANGER CASING IMPELLER REACTOR COOLANT PUMP FIGURE 4.2-5 July, 1982

UFSAR Revision 30.0 REACTOR COOLANT PUMP FLYWHEEL I

1s in.

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

UFSAR Revision 30.0 24 _,,_ ___________ ;__ ______ ;.;._ _______________

~

0...

M 22 20 is 16 14 g:

12 8

6 4

2 0

4

"\\

"--mrtls 4.1875 in.

6 8

10 12 FLYWHEEL OD* 75 in.

TANGENTIAL STRESS VS. FLYWHEEL RADIUS 1

--- 1500 RPM - OVERSPEED 1200 RPM 14 16 18 20 22 26 28 30 32 34 36 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 500 FOR Mn-Mo STEEL l,j:,:;',-:-TH?1*r;. )I

_'I,

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200 H++i~~~~-++-l+tt-+~~4414..,1 150 l+++H-l+ffl~+-t~~M""-++-ri...

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450 490 A.

550 L:::..

550 A533B, Class l 475 to 540 0

600 A302B Numbers 1 through 37 ( SEL ATT/1CHED SHEETS 1 RAGIATION INDUCED INCREASE IN TRANSITION TEMPERATURE FOR Mn-Mo STEEL FIGURE 4.2-9 July, 1982

UFSAR Revision 30.0 I'

D...,

Unit l I

\\

F Reactor Vessel Stress Analysis:

Areas Examined FIGURE

4. 3-1 E

I.....

/

July, 1982

UFSAR Revision 30.0

....ll. (INLET) l_ (OUTLET)

Unit l Reactor V essel St ress An 1 Details -

a ysis:

Upper J

FIGURE uly, 1982 4.3-2

UFSAR Revision 30.0

) ) ) ) ) ) )) ) ) ) ) )) ) ) ) ) ) ) ) ) ) )

I!...

1/

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THE !'OI::TS CIR.CL'.:::) IN t::E SK:~'!.'~! 1::'.S ~:~!'R::S:~r: 'i:.':T ~:':-:;::,Fi. Lr,r r** !'"' /,.YD GEm:2:?..Y OF TEE AREAS OF DISCON'!'INUIT: A~~D/OR S7RE3S r.n?-:r.-r.~:"."'1}.:':0:--!.

Unit 1 Reactor Vessel Stress Analysis:

Details -

Lower FIGURE 4. 3-3 July, 1982

UFSAR Revision 30.0 NOZZLE WELD WELD VESSE INTERMEDIAT SHELL 32 5/8" CAPSUL WELD VESSEL LOWER SHELL 0

"CORE" CL

,.;;t

+

,.;;t

..-4 CL

0. 030" STAINLESS SHEATH

=

1.,.. CORE llc:-T-C::111~=::::.:....-spAcERS

....i....-t'::~'-;-:~".".l---.r.HARPy SPECIMEN

~-----WELD SURVEILLANCE CAPSULE ELEVATION VIEW Figure 4.5-1 July, 1982

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.

Title:

Surveillance Capsule Plan View Sheet 1 of 1 UFSAR Figure: 4.5-2 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN Change

Description:

UCR-1968 Revision: 23 UFSAR Revision 30.0

,~" ****...

VESSEL\\

I 'l:f

  • /~

'loo j

I 180° THERMAL SHIELD

/

UFSAR Revision 30.0

CAPSULE

SPECIMEN GUIDE SPECIMEN GUIDE TO THERMAL SHIELD ATTACHMENT Figure 4,. 5-3 July, 1982

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