ML21125A543
Text
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT 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.
Change
Description:
UFSAR Figure: 14.1-1 Unit 1 UCR-2054, Rev. 0
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 Revised: 27.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT 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.
Change
Description:
UFSAR Figure: 14.1-2 Unit 1 UCR-2054, Rev. 0
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 Revised: 27.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT 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.
Change
Description:
UFSAR Figure: 14.1-3 Unit 1 UCR-2054, Rev. 0
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 Revised: 27.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 1 Change
Description:
UFSAR Figure: 14.1-3A Unit 1 UCR-2054, Rev. 0
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\
t 70 \,\
\\
\\
65
\1 Lh f \\
ov 55
\ \
50 1 \ \ SG Sderv 1 0
45 :
40 3s
- 8\ 'I- i ii \ 8 L I I
- 30 [
600 DONALD C.COOK NucLEAFtPLAKT UMTl OverpowCrAf 533.0'F 2250 psi*
.v r JULYi997
UFSAR Revision 30.0 Cook Nuclear Plant Unit 1 Normalized Negative Reactivity Insertion as a Function of Time Used for the Reactor Trip In Transient Safety Analysis 1 7 0.9 0.8 s
5 0.7 3 .
.2
$ 0.6 g . . . . . .
2 0.5 H .
- 0.4 5 . . ,
E .. . .. . . . . .. . . . .
is 0.3 . . . ._.
z ..__..... - . . . .. _.._._... . . . .
i .
0.2 ........... .-. ........... . . . . . .
............ .e. .......... a . . . . . a. . . . . . .
0.1 ..........
s.. ........... I . e . .
1 :*;
0 CI 0 0.4 0.8 1.2 1.6 2 2 t 2.8 3.2 Time After Rod Drop Begins (seconds)
Figure 14.1-5 Trip Reactivity vs. Rod Drop Time JULY1997
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 NuclearPowerand HocChannelHeat 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 -
750 -
z 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 Revision: 18.1 Change
Description:
UCR-1667
Title:
Nuclear Power vs. Time For The RCCA Withdrawal AMERICAN ELECTRIC POWER At Power Event, Full Power, 80 PCM/Sec. Insertion COOK NUCLEAR PLANT Rate Maximum Reactivity Feedback NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.2-1 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Pressurizer Pressure and Pressurizer Water Volume AMERICAN ELECTRIC POWER vs. Time For The RCCA Withdrawal At Power Event COOK NUCLEAR PLANT Full Power, 80 PCM/Sec. Insertion Rate Maximum NUCLEAR GENERATION GROUP Reactivity Feedback BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.2-2 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Core Average Temperature and DNBR vs. Time For AMERICAN ELECTRIC POWER The RCCA Withdrawal At Power Event, Full Power, COOK NUCLEAR PLANT 80 PCM/Sec. Insertion Rate Maximum Reactivity NUCLEAR GENERATION GROUP Feedback BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.2-3 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Nuclear Power vs. Time For The RCCA Withdrawal AMERICAN ELECTRIC POWER At Power Event, Full Power, 4 PCM/Sec. Insertion COOK NUCLEAR PLANT Rate Maximum Reactivity Feedback NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.2-4 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Pressurizer Pressure and Pressurizer Water Volume AMERICAN ELECTRIC POWER vs. Time For The RCCA Withdrawal At Power Event COOK NUCLEAR PLANT Full, Power, 4 PCM/Sec. Insertion Rate Maximum NUCLEAR GENERATION GROUP Reactivity Feedback BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.2-5 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Core Average Temperature and DNBR vs. Time For AMERICAN ELECTRIC POWER The RCCA Withdrawal At Power Event, Full Power, 4 COOK NUCLEAR PLANT PCM/Sec. Insertion Rate Maximum Reactivity NUCLEAR GENERATION GROUP Feedback BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.2-6 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Minimum DNBR vs. Reactivity Insertion Rate For The AMERICAN ELECTRIC POWER RCCA Withdrawal At Power Event, 100% Power COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.2-7 Sheet 1 of 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Minimum DNBR vs. Reactivity Insertion Rate For The AMERICAN ELECTRIC POWER RCCA Withdrawal At Power Event, 60% Power COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.2-8 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Minimum DNBR vs. Reactivity Insertion Rate For The AMERICAN ELECTRIC POWER RCCA Withdrawal At Power Event, 10% Power COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.2-9 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 UFSAR Revision 30.0 UFSAR Revision 30.0 0.00 I 3 4 6 8 10 Tme (s]
DONALDC.COOK NUCLEARPLANT UNIT1 FGURE 14.1.6-1 Total Core Flow vs. Time for Rx Coqletc Los Of Flow Event 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 Pressurevs. Tinx for The Compictc Loss Of Flow Event JULY1997
UFSAR Revision 30.0 1.6 E
6 left I
=
B E
2 08-Z5 3
u
= 0.4 -
nn + I I 0 V.
_ . m. 1 Heatfluxes are showniuafracuonofche DONALD C. COOK l
nomtnid average chatu)ei beu flux NUCLEAR PLANT UNIT1 FIGURE 14.1.6-3 Average and Hot ChannelHeat !Gxcs and DrUBR vs. Tim for rht CompleteLoss Of Flow Event JULY1997
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 LossOf Flow Event JULY 1997
UFSAR Revision 30.0 b
rjme [s]
DONALDC.COOK NUCLEARPLANT UNIT1 FIGURE 14.1b-5 Suclcar Power and Prtssuriztr Pressurevs. 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 channelheat flux FIGURE 14.1.6-6 Average and Hot Channel Heat Fluxes and DYBR vs. Time for tic Partial Loss Of Flow Event JULY1997
UFSAR Revision 30.0 4 b 8 IO Time [s]
4 6 8 10 Time [s]
DONALD C. COOK NUCLEAR PLANT UNIT 1 FIGURE 14.1A-7 Total Core now and FaultedLoop 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 Pressurevs. 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 IO Tme [s]
l Heat fluxes are shown as a fraction of the normnal average channel heat flux 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 Revision: 18.1 Change
Description:
UCR-1667
Title:
Nuclear Power and DNBR vs. Time For Loss of Load, AMERICAN ELECTRIC POWER Minimum Reactivity Feedback With Pressurizer COOK NUCLEAR PLANT Spray and PORVs NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-1 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Pressurizer Pressure and Pressurizer Water Volume AMERICAN ELECTRIC POWER vs. Time For Loss of Load, Minimum Reactivity COOK NUCLEAR PLANT Feedback With Pressurizer Spray and PORVS NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-2 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Vessel Average and Loop 1 Temperatures vs. Time AMERICAN ELECTRIC POWER For Loss of Load, Minimum Reactivity Feedback With COOK NUCLEAR PLANT Pressurizer Spray and PORVs NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-3 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Nuclear Power and DNBR vs. Time For Loss of Load, AMERICAN ELECTRIC POWER Maximum Reactivity Feedback With Pressurizer COOK NUCLEAR PLANT Spray and PORVs NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-4 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Pressurizer Pressure and Pressurizer Water Volume AMERICAN ELECTRIC POWER vs. Time For Loss of Load, Maximum Reactivity COOK NUCLEAR PLANT Feedback With Pressurizer Spray and PORVs NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-5 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Vessel Average and Loop 1 Temperatures vs. Time AMERICAN ELECTRIC POWER For Loss of Load, Maximum Reactivity Feedback COOK NUCLEAR PLANT With Pressurizer Spray and PORVs NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-6 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 UNIT 1 16.6 Revised per 99-UFSAR-1540 REV. Description NO Revision
Title:
Nuclear Power and DNBR vs. Time For Loss of Load, Minimum Reactivity Feedback Without Pressurizer Spray and PORVs DWG. NO. UFSAR FIG 14.1.8-7 SH 1 of 1
UFSAR Revision 30.0 UNIT 1 16.6 Revised per 99-UFSAR-1540 REV. NO Description Revision
Title:
Pressurizer Pressure and Pressurizer Volume vs. Time For Loss of Load, Minimum Reactivity Feedback Without Pressurizer Spray and PORVs DWG. NO. UFSAR FIG 14.1.8-8 SH 1 of 1
UFSAR Revision 30.0 UNIT 1 16.6 Revised per 99-UFSAR-1540 REV. NO Description Revision
Title:
Vessel Average and Loop 1 Temperatures vs. Time For Loss of Load, Minimum Reactivity Feedback Without Pressurizer Spray and PORVs DWG. NO. UFSAR FIG 14.1.8-9 SH 1 of 1
UFSAR Revision 30.0 UNIT 1 16.6 Revised per 99-UFSAR-1540 REV. NO Description Revision
Title:
Nuclear Power and DNBR vs. Time For Loss of Load, Maximum Reactivity Feedback Without Pressurizer Spray and PORVs DWG. NO. UFSAR FIG 14.1.8-10 SH 1 of 1
UFSAR Revision 30.0 UNIT 1 16.6 Revised per 99-UFSAR-1540 REV. NO Description Revision
Title:
Pressurizer Pressure and Pressurizer Water Volume vs. Time For Loss of Load, Maximum Reactivity Feedback Without Pressurizer Spray and PORVs DWG. NO. UFSAR FIG 14.1.8-11 SH 1 of 1
UFSAR Revision 30.0 UNIT 1 16.6 Revised per 99-UFSAR-1540 REV. NO Description Revision
Title:
Vessel Average and Loop 1 Temperatures vs. Time For Loss of Load, Maximum Reactivity Feedback Without Pressurizer Spray and PORVs DWG. NO. UFSAR FIG 14.1.8-12 SH 1 of 1
UFSAR Revision 30.0 UNIT 1 16.6 Revised per 99-UFSAR-1540 REV. NO Description Revision
Title:
Nuclear Power and Core Heat Flux vs. Time (Loss of Normal Feedwater)
DWG. NO. UFSAR FIG 14.1.9-1 SH 1 of 1
UFSAR Revision 30.0 UNIT 1 16.6 Revised per 99-UFSAR-1540 REV. NO Description Revision
Title:
Pressurizer Water Volume, Pressurizer Pressure and Loop Temperature vs. Time (Loss of Normal Feedwater)
DWG. NO. UFSAR FIG 14.1.9-2 SH 1 of 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Nuclear Power and Pressurizer Pressure vs. Time For AMERICAN ELECTRIC POWER Single Loop Feedwater Malfunction With Automatic COOK NUCLEAR PLANT Rod Control at Full Power NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.10-1 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Core Average Temperature and DNBR vs. Time For AMERICAN ELECTRIC POWER Single Loop Feedwater Malfunction With Automatic COOK NUCLEAR PLANT Rod Control at Full Power NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.10-2 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Nuclear Power and Pressurizer Pressure vs. Time For AMERICAN ELECTRIC POWER Single Loop Feedwater Malfunction With Manual Rod COOK NUCLEAR PLANT Control at Full Power NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.10-3 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Core Average Temperature and DNBR vs. Time For AMERICAN ELECTRIC POWER Single Loop Feedwater Malfunction With Manual Rod COOK NUCLEAR PLANT Control at Full Power NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.10-4 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Nuclear Power and Pressurizer Pressure vs. Time For AMERICAN ELECTRIC POWER Multi-Loop Feedwater Malfunction With Automatic COOK NUCLEAR PLANT Rod Control at Full Power NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.10-5 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Core Average Temperature and DNBR vs. Time For AMERICAN ELECTRIC POWER Multi-Loop Feedwater Malfunction With Automatic COOK NUCLEAR PLANT Rod Control at Full Power NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.10-6 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Nuclear Power and Pressurizer Pressure vs. Time For AMERICAN ELECTRIC POWER Multi-Loop Feedwater Malfunction With Manual Rod COOK NUCLEAR PLANT Control at Full Power NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.10-7 Sheet 1 of 1 Unit 1
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1667
Title:
Core Average Temperature and DNBR vs. Time For AMERICAN ELECTRIC POWER Multi-Loop Feedwater Malfunction With Automatic COOK NUCLEAR PLANT Rod Control at Full Power NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.10-8 Sheet 1 of 1 Unit 1
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 UNIT 1 16.6 Revised per 99-UFSAR-1540 REV. NO Description Revision
Title:
Nuclear Power and Core Flow vs. Time (Loss of Offsite Power)
DWG. NO. UFSAR FIG 14.1.12-1 SH 1 of 1
UFSAR Revision 30.0 UNIT 1 16.6 Revised per 99-UFSAR-1540 REV. NO Description Revision
Title:
Loop Temperature and Pressurizer Water Volume vs. Time (Loss of Offsite Power)
DWG. NO. UFSAR FIG 14.1.12-2 SH 1 of 1
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Chapter: 14 Sheet: 1 of 1 UPDATED FINAL SAFETY ANALYSIS REPORT 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.
Change
Description:
UFSAR Figure: 14.1.13-1 Unit 1 UCR-2122, Rev. 0
Title:
Cross Section - L.P. Turbine Rotor (Unit 2) (Shown without Blades)
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT 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.
Change
Description:
UFSAR Figure: 14.1.13-2 Unit 1 UCR-2122, Rev. 0
Title:
Stress in L-P Turbine Rotor Discs at 176% Speed
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT 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.
Change
Description:
UFSAR Figure: 14.1.13-3 Unit 1 UCR-2122, Rev. 0
Title:
Calculated Failure Speeds of L-P Turbine Rotor Discs
UFSAR Revision 30.0 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.
Revision: 24.0 Change
Description:
UCR-1977, Rev. 0
Title:
Sketch of Last Stage Region - L.P. Turbine Unit 1 UFSAR Figure: 14.1.13-4 Sheet 1 of 1 UNIT 1
UFSAR Revision 30.0 DONALD C. COOK NUCLEAR PLANT 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.
Revision: 24.0 Change
Description:
UCR-1977, Rev. 0
Title:
SKETCH OF THE LOW PRESSURE TURBINE UNIT 1 UFSAR Figure: 14.1.13-4a Sheet 1 of 1 UNIT 1
UFSAR Revision 30.0 INDIANA AND MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT 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.
Change
Description:
UFSAR Figure: 14.1.13-5 Unit 1 UCR-2122, Rev. 0
Title:
Sketch of Low Pressure Turbine Rotor and Casing Unit No. 2
UFSAR Revision 30.0 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)
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.
Revision: 24.0 Change
Description:
UCR-1977, Rev. 0
Title:
UNIT 1 TURBINE LAST STAGE WHEEL UFSAR Figure: 14.1.13-6 Sheet 1 of 1 UNIT 1