ML22340A194

1 to Updated Final Safety Analysis Report, Chapter 4, Figures

ML22340A194
Person / Time
Site:	Cook
Issue date:	11/30/2022
From:	Indiana Michigan Power Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML22340A137	List: AEP-NRC-2022-62, 1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1) ML22340A128 ML22340A129 ML22340A131 ML22340A132 ML22340A133 ML22340A134 ML22340A135 ML22340A136 ML22340A138 ML22340A139 ML22340A141 ML22340A142 ML22340A143 ML22340A144 ML22340A145 ML22340A146 ML22340A147 ML22340A148 ML22340A149 ML22340A150 ML22340A151 ML22340A152 ML22340A153 ML22340A154 ML22340A155 ML22340A156 ML22340A157 ML22340A158 ML22340A159 ML22340A160 ML22340A161 ML22340A162 ML22340A163 ML22340A164 ML22340A165 ML22340A166 ML22340A167 ML22340A168 ML22340A169 ML22340A170 ML22340A171 ML22340A172 ML22340A173 ML22340A174 ML22340A175 ML22340A176 ML22340A177 ML22340A178 ML22340A179 ... further results
References
AEP-NRC-2022-62
Download: ML22340A194 (1)

Text

fsar-fig-4.2-1_21-2.dgn 3/7/2008 10:18:39 AM UFSAR Revision 31.0

...\\fsar-fig-4-2-1a_20.dgn 08/08/2005 11:42:17 AM UFSAR Revision 31.0

UFSAR Revision 31.0

UFSAR Revision 31.0

RELIEF Ho22LE HEATER SUPPORT PLATE

-k

- SPRAY NOZZLE SAFETY NOZZLE INSTRUMEWTATIOH HOZZLE

/-

LOWER MEAD II(STRUMEWTATIDW NOZZLE ELECTRICAL HEATER L

SUROE NOZZLE PRESSURIZER FIGURE 4.2-3

July, 1982 UFSAR Revision 31.0

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 31.0

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 31.0

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 31.0

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 31.0

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

==31.0

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 31.0

FLYWHEEL UPPER RADIAL BEARING THRUST BEARING MOTOR SHAFT MOTOR STATOR 9

THRUST BEARING OIL LIFT PUMP

+ MOTOR MAIN LEAD CONDUIT BOX LOVER RADIAL ASSEMBLY BEARING VAPOR LEAKAGE TO ATMOSPHERE NO.

2 INJECTIOW WATER LEAK OFF PUMP SHAFT COOLING WATER INLET LOWER SEAL MAIN FLANGE COOLING WATER OUTLET RADIAL BEARING DISCHARGE NOZZLE ASSEMBLY THERMAL BARRIER AND HEAT EXCHANGER SUCTION NOZZLE REACTOR COOLANT PUVP FIGURE 4.2-5

July, 1982 UFSAR Revision 31.0

REACTOR COOLANT PLJMP FLYWHEEL 4.50in.

f 75 in.

of s 8-318 in.

Diameter wit!,

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 31.0

C

/

24 is 16 14 12 10 8

6' c.

c..

FLYWHEEL OD - 75 in.

TAN&NTIAL STRESS VS. FLYW'REE!,

RADIUS 1 -

- OVERSPEED 10 12 14 16 18 20 22

'24 26 28 30 32 34 RADIUS, in.

Original FSAR figure UFSAR Revision 31.0

500 400 300 200 100 0

4

/

/

j i

i

\\I

.._ L. (____

--.--A-j

1. j j

__I -.I-.--

I--:

____! -i.--

.L....!--I.-.L.-A.

4 1

I i-X.--j I

.j

.. __.(

-I

.-+--.-.

.I

.-I

---!,~---:i 0

10 20 30 40 50 60 70 80 90 100 110 8

FLOW - THOUSANDS OF CPM REACTOR COOLANT PUMP PERFORMANCE CHARACTERISTICS FIGURE 4.2-8

July, 1982 UFSAR Revision 31.0

INTEGRATED

?iEUTHON

EXPCSUAE, neOtron#

per cq cm

>I Mov Code Temp.,

OF 0

450 n

490 A

550 A

550 A5338, Class I

v 475 to 540 Q

600 A302B lir~i,f;iTIG&

INDUCED INCREASE IN Th'XS!TION TEMPERATURE FOR Mn-Mo Numbers 1 through 37 (Sk:E AT;I\\CtiEC 5kfEETs\\

STEEL FIGURE 4.2-9

July, 1982 UFSAR Revision 31.0

D -cl

\\

C

\\

I# E

/

Unit 1

Reactor Vessel Stress Analysis:

Areas Examined FIGURE 4.3-1

JUIY, 1982 UFSAR Revision 31.0

9 (INLET)

E (OUTLET)

Unit 1

Reactor Vessel Stress Analysis:

Details

- Upper FIGURE 4.3-2

July, 1982 UFSAR Revision 31.0

Unit 1

Reactor Vessel Stress Analysis:

Details

- Lower FIGURE 4.3-3

July, 1982 UFSAR Revision 31.0

NOZZLE NOZZLE WELD WELD 7 7 WELD WELD VESSE VESSE J J INTERMEDIATE INTERMEDIATE VESSEL A LOWER SHELL I

r-t-

"CORE" 0.030" STASNLESS CORE SPACERS HARPY SPECIMEN SHEATH SURVEILLANCE CAPSULE ELEVATION VIEW

July, 1982 Figure 4.5-l UFSAR Revision 31.0

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 31.0

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

July, 1982 UFSAR Revision 31.0