ML25307A066
Text
fsar-fig-4.2-1_21-2.dgn 3/7/2008 10:18:39 AM UFSAR Revision 33.0
...\fsar-fig-4-2-1a_20.dgn 08/08/2005 11:42:17 AM UFSAR Revision 33.0
UFSAR Revision 33.0
UFSAR Revision 33.0
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 33.0
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 33.0
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 33.0
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 33.0
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 33.0
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
==33.0
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 33.0
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 33.0
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 33.0
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 33.0
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 33.0
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 33.0
D -cl
\
C
\
I# E
/
Unit 1
Reactor Vessel Stress Analysis:
Areas Examined FIGURE 4.3-1
- JUIY, 1982 UFSAR Revision 33.0
9 (INLET)
E (OUTLET)
Unit 1
Reactor Vessel Stress Analysis:
Details
- Upper FIGURE 4.3-2
- July, 1982 UFSAR Revision 33.0
Unit 1
Reactor Vessel Stress Analysis:
Details
- Lower FIGURE 4.3-3
- July, 1982 UFSAR Revision 33.0
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 33.0
Revision: 33.0 Change
Description:
UCR-2313 (fully replaced figure)
AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN
Title:
Surveillance Capsule Plan View - Unit 1 UFSAR Figure: 4.5-2 Sheet 1 of 1 Capsule Location Azimuth Last Irradiated T
40 12/24/1976 X
220 5/30/1980 Y
320 7/3/1982 U
140 3/18/1989 W
184 4/2/2022 S
4 7/14/1995 S
40 3/3/2010 S
4 3/22/2025 S
40 Current*
V 176 3/22/2025 V
140 Current Z
356 3/22/2025 Z
320 Current
- Capsule S is expected to be moved in 2031 270° 220° 184° 180° 176° 140° 320° 356° 0° 4° 40° 90° Reactor Vessel Thermal Shield Core Barrel Capsule Z Capsule S Capsule V UFSAR Revision 33.0
Revision: 33.0 Change
Description:
UCR-2313 (New Figure)
AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN
Title:
Surveillance Capsule Plan View - Unit 2 UFSAR Figure: 4.5-2A Sheet 1 of 1 Capsule Location Azimuth Last Irradiated T
40 10/19/1979 X
220 2/28/1986 Y
320 11/20/1982 U
140 2/22/1992 W
184 3/22/2024 W
220 Current S
4 3/22/2024 V
176 3/22/2024 V
140 Current Z
356 3/22/2024 Z
320 Current 270° 220° 184° 180° 176° 140° 320° 356° 0° 4° 40° 90° Reactor Vessel Thermal Shield Core Barrel Capsule Z Capsule W Capsule V UFSAR Revision 33.0
SPECIMEN GUIDE TO THERMAL SHIELD ATTACHMENT Figure 4,5-3
- July, 1982 UFSAR Revision 33.0