ML24159A220

From kanterella
Jump to navigation Jump to search
Updated Final Safety Analysis Report (Ufsar), Revision 32, Chapter 4, Figures
ML24159A220
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 05/30/2024
From:
Indiana Michigan Power Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML24159A261 List: ... further results
References
AEP-NRC-2024-20
Download: ML24159A220 (1)


Text

fsar-fig-4.2-1_21-2.dgn 3/7/2008 10:18:39 AM UFSAR Revision 32.0

...\\fsar-fig-4-2-1a_20.dgn 08/08/2005 11:42:17 AM UFSAR Revision 32.0

UFSAR Revision 32.0

UFSAR Revision 32.0

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 32.0

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 32.0

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 32.0

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 32.0

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 32.0

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

==32.0

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 32.0

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 32.0

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 32.0

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 32.0

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 32.0

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 32.0

D -cl

\\

C

\\

I# E

/

Unit 1

Reactor Vessel Stress Analysis:

Areas Examined FIGURE 4.3-1

JUIY, 1982 UFSAR Revision 32.0

9 (INLET)

E (OUTLET)

Unit 1

Reactor Vessel Stress Analysis:

Details

- Upper FIGURE 4.3-2

July, 1982 UFSAR Revision 32.0

Unit 1

Reactor Vessel Stress Analysis:

Details

- Lower FIGURE 4.3-3

July, 1982 UFSAR Revision 32.0

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 32.0

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 32.0

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

July, 1982 UFSAR Revision 32.0