ML24159A220: Difference between revisions

From kanterella
Jump to navigation Jump to search
StriderTol Bot insert
 
StriderTol Bot change
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:fsar-fig-4.2-1_21-2.dgn 3/7/2008 10:18:39 AM
{{#Wiki_filter: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


- SPRAY NOZZLE RELIEF SAFETY NOZZLE Ho22LE -
...\\fsar-fig-4-2-1a_20.dgn 08/08/2005 11:42:17 AM UFSAR Revision 32.0


- INSTRUMEWTATIOH HOZZLE
UFSAR Revision 32.0


LOWER MEAD
UFSAR Revision 32.0


HEATER SUPPORT PLATE /-
RELIEF Ho22LE HEATER SUPPORT PLATE  
-k II(STRUMEWTATIDW NOZZLE
-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


ELECTRICAL HEATER
Unit 2 Revision: 18 Change
 
L SUROE NOZZLE
 
PRESSURIZER FIGURE 4.2-3 July, 1982 Revision: 18 Change


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


==Title:==
==Title:==
Cook Unit 2 AMERICAN ELECTRIC POWER Repaired Steam Generator General Arrangement COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 4.2-4 Sheet 1 of 1
Cook Unit 2 Repaired Steam Generator General Arrangement UFSAR Revision 32.0
 
Unit 2 16.6 REVISED PER 99-UFSAR-1226
 
REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLEUNIT 1 MODEL 51R REPLACEMENT STEAM COOK NUCLEAR PLANT GENERATOR, GENERAL CONFIGURATION NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO.FSAR FIG. 4.2 - 4A SH 1 of 1 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 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 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 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
 
FLYWHEEL
 
UPPER RADIAL BEARING
 
THRUST BEARING THRUST BEARING OIL LIFT PUMP MOTOR SHAFT + MOTOR
 
MOTOR STATOR 9 MAIN LEAD CONDUIT BOX
 
LOVER RADIAL ASSEMBLY BEARING VAPOR LEAKAGE TO ATMOSPHERE NO. 2 INJECTIOW WATER LEAK OFF
 
PUMP SHAFT LOWER SEAL
 
MAIN FLANGE COOLING WATER INLET COOLING WATER OUTLET
 
RADIAL BEARING DISCHARGE NOZZLE ASSEMBLY THERMAL BARRIER AND HEAT EXCHANGER
 
SUCTION NOZZLE
 
REACTOR COOLANT PUVP FIGURE 4.2-5


July, 1982 REACTOR COOLANT PLJMP FLYWHEEL
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


75 in.
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


4.50in.
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


f
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


of s 8-318 in. Diameter wit!, 3 Keyways
==32.0


NOTE: The plates are bolted together with the bolts aligned
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


perpendicular to the planes of the plates.
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
FIGURE 4.2-6
: July, 1982 UFSAR Revision 32.0


July, 1982 c..,
C
C /
/
... c..
24 is 16 14 12 10 8
24
6' c.
 
c..
FLYWHEEL OD - 75 in.
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


is
500 400 300 200 100 0
 
4
16 TAN&NTIAL STRESS VS. FLYW'REE!, RADIUS
/
 
/
14.
j i
; _. 1 -
i
12 - OVERSPEED 10
\\I
 
.._ L. (____  
8
--.--A-j
 
: 1. j j
6'
__I -.I-.--
 
I--:
10 12 14 16 18 20 22 '24 26 28 30 32 34 RADIUS, in. Original FSAR figure 500
____! -i.--  
 
.L....!--I.-.L.-A.
..-.._ L. (____ --.--A-
4 1
\\I 4 ! / / j i i j 1. j j
I i-X.--j I
 
.j  
400
.. __.(  
 
-I  
300 __I -.I-.-- :.. ____ I--: ____! -i.--.L....!--I.-.L.-A. 4 1 I i-X.--j
.-+--.-.  
 
.I  
200
.-I  
 
---!,~---:i 0
I.j _ _.. __.( :- -I.-+--.-..I.-I ---!,~---:i.-
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
100
: July, 1982 UFSAR Revision 32.0
 
0 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 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 C
 
D -cl \\ \\ I# E
/
 
Unit 1 Reactor Vessel Stress Analysis: Areas Examined FIGURE 4.3-1 JUIY, 1982 9 (INLET)
 
-- E (OUTLET)
 
Unit 1 Reactor Vessel Stress Analysis:
Details - Upper FIGURE 4.3-2 July, 1982 Unit 1 Reactor Vessel Stress Analysis: Details - Lower
 
FIGURE 4.3-3 July, 1982 NOZZLE NOZZLE WELD WELD
 
WELD WELD


7 7 r-t- "CORE"
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


VESSE VESSE J J INTERMEDIATE INTERMEDIATE
D -cl
\\
C
\\
I# E
/
Unit 1
Reactor Vessel Stress Analysis:
Areas Examined FIGURE 4.3-1
: JUIY, 1982 UFSAR Revision 32.0


VESSEL A LOWER SHELL I
9 (INLET)
E (OUTLET)
Unit 1
Reactor Vessel Stress Analysis:
Details
- Upper FIGURE 4.3-2
: July, 1982 UFSAR Revision 32.0


0.030" STASNLESS SHEATH
Unit 1
Reactor Vessel Stress Analysis:
Details
- Lower FIGURE 4.3-3
: July, 1982 UFSAR Revision 32.0


.- CORE SPACERS HARPY SPECIMEN
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


SURVEILLANCE CAPSULE ELEVATION VIEW July, 1982 Figure 4.5-l Notes: Capsule W was moved back to the 4 degree location and renamed as S in March 2010 (U1C23).
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.
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.
Figure 4.5-2 is current as of March 2010. Figure 4.5-2A is superseded.


Revision: 23 Change
==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:==
== Description:==
UCR-1968
UCR-1968 Revision: 23 UFSAR Revision 32.0
 
AMERICAN ELECTRIC POWER
 
==Title:==
Surveillance Capsule Plan View
 
COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 4.5-2 Sheet 1 of 1 SPECIMEN GUIDE TO THERMAL SHIELD ATTACHMENT
 
Figure 4,5-3


July, 1982}}
SPECIMEN GUIDE TO THERMAL SHIELD ATTACHMENT Figure 4,5-3
: July, 1982 UFSAR Revision 32.0}}

Revision as of 18:03, 24 November 2024

Updated Final Safety Analysis Report (Ufsar), Revision 32, Chapter 4, Figures
ML24159A220
Person / Time
Site: Cook  
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