ML21125A543
Text
INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:
14 Sheet:
1 of 1 Note: Operation at an RCS pressure of 2100 psia is no longer supported by the safety analyses; however, some safety analyses performed at reduced RCS pressure and temperature conditions were evaluated and demonstrated to remain bounding for the Return to RCS NOP/NOT program. Hence, this figure has been maintained for completeness.
UFSAR Figure: 14.1-1 Change
Description:
UCR-2054, Rev. 0 Unit 1
Title:
Illustration of Overtemperature and Overpower T Protection Nominal Tavg = 576.3°F - Nominal Pressure = 2100 psia UFSAR Revision 30.0
INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:
14 Sheet:
1 of 1 Note: Operation at an RCS pressure of 2100 psia is no longer supported by the safety analyses; however, some safety analyses performed at reduced RCS pressure and temperature conditions were evaluated and demonstrated to remain bounding for the Return to RCS NOP/NOT program. Hence, this figure has been maintained for completeness.
UFSAR Figure: 14.1-2 Change
Description:
UCR-2054, Rev. 0 Unit 1
Title:
Illustration of Overtemperature and Overpower T Protection Nominal Tavg = 553.0°F - Nominal Pressure = 2100 psia UFSAR Revision 30.0
INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:
14 Sheet:
1 of 1 Note: Operation at an RCS pressure of 2100 psia is no longer supported by the safety analyses; however, some safety analyses performed at reduced RCS pressure and temperature conditions were evaluated and demonstrated to remain bounding for the Return to RCS NOP/NOT program. Hence, this figure has been maintained for completeness.
UFSAR Figure: 14.1-3 Change
Description:
UCR-2054, Rev. 0 Unit 1
Title:
Illustration of Overtemperature and Overpower T Protection Nominal Tavg = 576.3°F - Nominal Pressure = 2250 psia UFSAR Revision 30.0
INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.1-3A Change
Description:
UCR-2054, Rev. 0 Unit 1
Title:
Illustration of Overtemperature and Overpower T Protection Nominal Tavg = 575.4°F - Nominal Pressure = 2250 psia UFSAR Revision 30.0
80 r,\\.............
\\
75 1 f
\\ t 70
\\, \\ \\ \\
65
\\ \\ \\ 1 \\
Lh
\\
ov 55 50 45 40 3s 30
\\
\\
1
\\
\\
SG Sderv 1
0
[
- 8 I
i ii
\\
I 8
L
\\
'I-600 DONALD C. COOK NucLEAFtPLAKT UMTl OverpowCrAf 533.0'F 2250 psi*
.v r
JULY i997 UFSAR Revision 30.0
1 0.9 0.8 s
5 0.7 3
.2 0.6 g
2 H
0.5 0.4
.- 5 E
is 0.3 z
0.2 0.1 0
CI Cook Nuclear Plant Unit 1 Normalized Negative Reactivity Insertion as a Function of Time Used for the Reactor Trip In Transient Safety Analysis 7
i
.e.
a s..
I 0
0.4 0.8 1.2 1.6 2
2
- a.
e 1
t 2.8 3.2 Time After Rod Drop Begins (seconds)
Figure 14.1-5 Trip Reactivity vs. Rod Drop Time JULY 1997 UFSAR Revision 30.0
03
=
t.-
5 c
0.4 d
d 0.3 0.0 lime [s]
DONALD C. COOK NucLEARPLANT UNIT1 FIGURE 14.1.1-I Nuclear Power and Hoc Channel Heat Flux vs. Tii For he Rod Whdmwal From Subcriticd Event JULY 1997 UFSAR Revision 30.0
0 5
IO I5 20 25 lrns (s]
800 -
z 750 -
e DONALDC.COOK NUCLEARPLANT UNIT1 FIGURE 14.1.1-2 Fuel Avenge aod Clad Tanpcratu~~ vs. Trm For The Rod Wubdrawal From Subcritical Event JULY 1997 UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.2-1 Sheet 1 of 1
Title:
Nuclear Power vs. Time For The RCCA Withdrawal At Power Event, Full Power, 80 PCM/Sec. Insertion Rate Maximum Reactivity Feedback UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.2-2 Sheet 1 of 1
Title:
Pressurizer Pressure and Pressurizer Water Volume vs. Time For The RCCA Withdrawal At Power Event Full Power, 80 PCM/Sec. Insertion Rate Maximum Reactivity Feedback UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.2-3 Sheet 1 of 1
Title:
Core Average Temperature and DNBR vs. Time For The RCCA Withdrawal At Power Event, Full Power, 80 PCM/Sec. Insertion Rate Maximum Reactivity Feedback UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.2-4 Sheet 1 of 1
Title:
Nuclear Power vs. Time For The RCCA Withdrawal At Power Event, Full Power, 4 PCM/Sec. Insertion Rate Maximum Reactivity Feedback UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.2-5 Sheet 1 of 1
Title:
Pressurizer Pressure and Pressurizer Water Volume vs. Time For The RCCA Withdrawal At Power Event Full, Power, 4 PCM/Sec. Insertion Rate Maximum Reactivity Feedback UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.2-6 Sheet 1 of 1
Title:
Core Average Temperature and DNBR vs. Time For The RCCA Withdrawal At Power Event, Full Power, 4 PCM/Sec. Insertion Rate Maximum Reactivity Feedback UFSAR Revision 30.0
Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.2-7 Sheet 1 of 1
Title:
Minimum DNBR vs. Reactivity Insertion Rate For The RCCA Withdrawal At Power Event, 100% Power UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.2-8 Sheet 1 of 1
Title:
Minimum DNBR vs. Reactivity Insertion Rate For The RCCA Withdrawal At Power Event, 60% Power UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.2-9 Sheet 1 of 1
Title:
Minimum DNBR vs. Reactivity Insertion Rate For The RCCA Withdrawal At Power Event, 10% Power UFSAR Revision 30.0
UFSAR Revision 30.0
UFSAR Revision 30.0
DONALDC.COOK NUCLEARPLANT UNIT1 FGURE 14.1.6-1 Total Core Flow vs. Time for Rx Coqletc Los Of Flow Event 0.0 I
0 3
4 6
8 10 Tme (s]
JULY 1997 UFSAR Revision 30.0
0 4
6 8
IO Time [s]
0 2
4 6
8 IO Tme [s]
DONALDC.COOK NUCLEARPLANT UNIT1 FIGURE 14. I.62 Nuclear Power and Ressurizcr Pressure vs. Tinx for The Compictc Loss Of Flow Event JULY 1997 UFSAR Revision 30.0
I 1.6 E lef t 6 =
B E
2 08-5 Z
3 u = 0.4 -
nn +
I V.
0 l Heat fluxes are shown i
- m.
1 uafracuonofche nomtnid average chatu)ei beu flux I
DONALD C. COOK NUCLEAR PLANT UNIT1 FIGURE 14.1.6-3 Average and Hot Channel Heat !Gxcs and DrUBR vs. Tim for rht Complete Loss Of Flow Event JULY 1997 UFSAR Revision 30.0
r Tme [s]
0.0 L 0
2 4
6 8
IO Tme (s]
DONALD C. COOK NUCLEAR PLANT UNIT 1 FIGURE 14.1.6-4 Total Core Row and Faulted Loop Flow vs. Tie for The Pamal Loss Of Flow Event JULY 1997 UFSAR Revision 30.0
b rjme [s]
DONALDC.COOK NUCLEARPLANT UNIT1
/
FIGURE 14.1 b-5 Suclcar Power and Prtssuriztr Pressure vs. Tinr for The Partial Loss Of Flow Event I
JULY 1997 UFSAR Revision 30.0
0.0 i 0
2 4
6 8
10 Tme [s]
0 2
4 6
8
-lime [s]
l Hear fluxes are shown as a fraction of the nominal average channel heat flux FIGURE 14.1.6-6 Average and Hot Channel Heat Fluxes and DYBR vs. Time for tic Partial Loss Of Flow Event JULY 1997 UFSAR Revision 30.0
4 b
8 IO Time [s]
4 6
8 10 Time [s]
DONALD C. COOK NUCLEAR PLANT UNIT 1 FIGURE 14.1 A-7 Total Core now and Faulted Loop Flow vs. Tii For The Locked Rotor Event JULY 1997 UFSAR Revision 30.0
lime [s]
4 6
8 Time [s]
DONALDC.COOK NUCLEAR PLANT UNIT1 RGURE 14.1.6-8 Nuclear Power and RCS Pressure vs. Time For The bckd Rotor Event JULY 1997 UFSAR Revision 30.0
0.0 0
2 4
6 8
IO rrne
[s]
2 4
6 l Heat fluxes are shown as a fraction of the normnal average channel heat flux Tme
[s]
IO FIGURE 14.1.6-9 Average and Hot Channel Heat Fluxes vs. Time and Clad Inner Tempcraturr vs. Time For The Locked Rotor Event JULY 1997 UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-1 Sheet 1 of 1
Title:
Nuclear Power and DNBR vs. Time For Loss of Load, Minimum Reactivity Feedback With Pressurizer Spray and PORVs UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-2 Sheet 1 of 1
Title:
Pressurizer Pressure and Pressurizer Water Volume vs. Time For Loss of Load, Minimum Reactivity Feedback With Pressurizer Spray and PORVS UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-3 Sheet 1 of 1
Title:
Vessel Average and Loop 1 Temperatures vs. Time For Loss of Load, Minimum Reactivity Feedback With Pressurizer Spray and PORVs UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-4 Sheet 1 of 1
Title:
Nuclear Power and DNBR vs. Time For Loss of Load, Maximum Reactivity Feedback With Pressurizer Spray and PORVs UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-5 Sheet 1 of 1
Title:
Pressurizer Pressure and Pressurizer Water Volume vs. Time For Loss of Load, Maximum Reactivity Feedback With Pressurizer Spray and PORVs UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-6 Sheet 1 of 1
Title:
Vessel Average and Loop 1 Temperatures vs. Time For Loss of Load, Maximum Reactivity Feedback With Pressurizer Spray and PORVs UFSAR Revision 30.0
16.6 Description Revised per 99-UFSAR-1540 Revision REV.
NO DWG. NO. UFSAR FIG 14.1.8-7 SH 1 of 1
Title:
Nuclear Power and DNBR vs. Time For Loss of Load, Minimum Reactivity Feedback Without Pressurizer Spray and PORVs UNIT 1 UFSAR Revision 30.0
16.6 Description Revised per 99-UFSAR-1540 Revision REV. NO DWG. NO. UFSAR FIG 14.1.8-8 SH 1 of 1
Title:
Pressurizer Pressure and Pressurizer Volume vs. Time For Loss of Load, Minimum Reactivity Feedback Without Pressurizer Spray and PORVs UNIT 1 UFSAR Revision 30.0
16.6 Description Revised per 99-UFSAR-1540 Revision REV. NO DWG. NO. UFSAR FIG 14.1.8-9 SH 1 of 1
Title:
Vessel Average and Loop 1 Temperatures vs. Time For Loss of Load, Minimum Reactivity Feedback Without Pressurizer Spray and PORVs UNIT 1 UFSAR Revision 30.0
16.6 Description Revised per 99-UFSAR-1540 Revision REV. NO DWG. NO. UFSAR FIG 14.1.8-10 SH 1 of 1
Title:
Nuclear Power and DNBR vs. Time For Loss of Load, Maximum Reactivity Feedback Without Pressurizer Spray and PORVs UNIT 1 UFSAR Revision 30.0
16.6 Description Revised per 99-UFSAR-1540 Revision REV. NO DWG. NO. UFSAR FIG 14.1.8-11 SH 1 of 1
Title:
Pressurizer Pressure and Pressurizer Water Volume vs. Time For Loss of Load, Maximum Reactivity Feedback Without Pressurizer Spray and PORVs UNIT 1 UFSAR Revision 30.0
16.6 Description Revised per 99-UFSAR-1540 Revision REV. NO DWG. NO. UFSAR FIG 14.1.8-12 SH 1 of 1
Title:
Vessel Average and Loop 1 Temperatures vs. Time For Loss of Load, Maximum Reactivity Feedback Without Pressurizer Spray and PORVs UNIT 1 UFSAR Revision 30.0
16.6 Description Revised per 99-UFSAR-1540 Revision REV. NO DWG. NO. UFSAR FIG 14.1.9-1 SH 1 of 1
Title:
Nuclear Power and Core Heat Flux vs. Time (Loss of Normal Feedwater)
UNIT 1 UFSAR Revision 30.0
16.6 Description Revised per 99-UFSAR-1540 Revision REV. NO DWG. NO. UFSAR FIG 14.1.9-2 SH 1 of 1
Title:
Pressurizer Water Volume, Pressurizer Pressure and Loop Temperature vs. Time (Loss of Normal Feedwater)
UNIT 1 UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.10-1 Sheet 1 of 1
Title:
Nuclear Power and Pressurizer Pressure vs. Time For Single Loop Feedwater Malfunction With Automatic Rod Control at Full Power UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.10-2 Sheet 1 of 1
Title:
Core Average Temperature and DNBR vs. Time For Single Loop Feedwater Malfunction With Automatic Rod Control at Full Power UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.10-3 Sheet 1 of 1
Title:
Nuclear Power and Pressurizer Pressure vs. Time For Single Loop Feedwater Malfunction With Manual Rod Control at Full Power UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.10-4 Sheet 1 of 1
Title:
Core Average Temperature and DNBR vs. Time For Single Loop Feedwater Malfunction With Manual Rod Control at Full Power UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.10-5 Sheet 1 of 1
Title:
Nuclear Power and Pressurizer Pressure vs. Time For Multi-Loop Feedwater Malfunction With Automatic Rod Control at Full Power UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.10-6 Sheet 1 of 1
Title:
Core Average Temperature and DNBR vs. Time For Multi-Loop Feedwater Malfunction With Automatic Rod Control at Full Power UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.10-7 Sheet 1 of 1
Title:
Nuclear Power and Pressurizer Pressure vs. Time For Multi-Loop Feedwater Malfunction With Manual Rod Control at Full Power UFSAR Revision 30.0
Unit 1 Revision: 18.1 Change
Description:
UCR-1667 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.10-8 Sheet 1 of 1
Title:
Core Average Temperature and DNBR vs. Time For Multi-Loop Feedwater Malfunction With Automatic Rod Control at Full Power UFSAR Revision 30.0
UFSAR Revision 30.0
UFSAR Revision 30.0
UFSAR Revision 30.0
UFSAR Revision 30.0
UFSAR Revision 30.0
UFSAR Revision 30.0
UFSAR Revision 30.0
UFSAR Revision 30.0
16.6 Description Revised per 99-UFSAR-1540 Revision REV. NO DWG. NO. UFSAR FIG 14.1.12-1 SH 1 of 1
Title:
Nuclear Power and Core Flow vs. Time (Loss of Offsite Power)
UNIT 1 UFSAR Revision 30.0
16.6 Description Revised per 99-UFSAR-1540 Revision REV. NO DWG. NO. UFSAR FIG 14.1.12-2 SH 1 of 1
Title:
Loop Temperature and Pressurizer Water Volume vs. Time (Loss of Offsite Power)
UNIT 1 UFSAR Revision 30.0
INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.1.13-1 Change
Description:
UCR-2122, Rev. 0 Unit 1
Title:
Cross Section - L.P. Turbine Rotor (Unit 2) (Shown without Blades)
This information is still provided for the (removed) Brown Boveri low-pressure turbines, as this information is part of the potential missile evaluations that are included in structural design criteria as shown in Table 5.1-1.
UFSAR Revision 30.0
INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.1.13-2 Change
Description:
UCR-2122, Rev. 0 Unit 1
Title:
Stress in L-P Turbine Rotor Discs at 176% Speed This information is still provided for the (removed) Brown Boveri low-pressure turbines, as this information is part of the potential missile evaluations that are included in structural design criteria as shown in Table 5.1-1.
UFSAR Revision 30.0
INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.1.13-3 Change
Description:
UCR-2122, Rev. 0 Unit 1
Title:
Calculated Failure Speeds of L-P Turbine Rotor Discs This information is still provided for the (removed) Brown Boveri low-pressure turbines, as this information is part of the potential missile evaluations that are included in structural design criteria as shown in Table 5.1-1.
UFSAR Revision 30.0
UNIT 1 Revision: 24.0 Change
Description:
UCR-1977, Rev. 0 UFSAR Figure: 14.1.13-4 Sheet 1 of 1
Title:
Sketch of Last Stage Region - L.P. Turbine Unit 1 This information is still provided for the (removed) General Electric low-pressure turbines, as this is the analysis that bounds other Unit 1 rotating elements. This figure is for the (removed) General Electric low-pressure turbines.
UFSAR Revision 30.0
UNIT 1 Revision: 24.0 Change
Description:
UCR-1977, Rev. 0 UFSAR Figure: 14.1.13-4a Sheet 1 of 1
Title:
SKETCH OF THE LOW PRESSURE TURBINE UNIT 1 This figure shows the Unit 1 low pressure turbine retro-fitted with the low pressure turbine manufactured by Alstom Power, Inc. It is typical for all three low pressure turbines.
DONALD C. COOK NUCLEAR PLANT SKETCH OF THE LOW PRESSURE TURBINE UNIT 1 UFSAR Revision 30.0
INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 This information is still provided for the (removed) Brown Boveri low-pressure turbines, as this information is part of the potential missile evaluations that are included in structural design criteria as shown in Table 5.1-1.
UFSAR Figure: 14.1.13-5 Change
Description:
UCR-2122, Rev. 0 Unit 1
Title:
Sketch of Low Pressure Turbine Rotor and Casing Unit No. 2 UFSAR Revision 30.0
UNIT 1 Revision: 24.0 Change
Description:
UCR-1977, Rev. 0 UFSAR Figure: 14.1.13-6 Sheet 1 of 1
Title:
UNIT 1 TURBINE LAST STAGE WHEEL This information is still provided for the (removed) General Electric low-pressure turbines, as this is the analysis that bounds other Unit 1 rotating elements. This figure is for the (removed) General Electric low-pressure turbines.
DONALD C. COOK NUCLEAR PLANT UNIT 1 TURBINE LAST STAGE WHEEL KINETIC ENERGY OF 120º FRAGMENT AFTER INNER CASING IMPACT 43" WHEEL, ZERO RESTITUTION, CASE "C" SECOND PHASE IMPACT (RING IN PARTICLES)