ML24159A190
| ML24159A190 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/30/2024 |
| From: | Indiana Michigan Power Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML24159A261 | List:
|
| References | |
| AEP-NRC-2024-20 | |
| Download: ML24159A190 (1) | |
Text
UFSAR Revision 32.0
INDIANA AND MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 1
Note: O peration at an RCS pressure of 2 10 0 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 NO P / NO T program. H ence, this figure has been maintained for completeness.
UFSAR Figure: 14.1-1 Change
Description:
UCR-2 0 5 4, Rev. 0 Unit 1
Title:
Illustration of O vertemperature and O verpower T roction Nonal avg = 7 6.3°F - Nominal P ressure = 2 10 0 psia UFSAR Revision 32.0
INDIANA AND MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 1
Note: O peration at an RCS pressure of 2 10 0 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 NO P / NO T program. H ence, this figure has been maintained for completeness.
UFSAR Figure: 14.1-2 Change
Description:
UCR-2 0 5 4, Rev. 0 Unit 1
Title:
Illustration of O vertemperature and O verpower T roction Nonal avg = 5 3.0°F - Nominal P ressure = 2 10 0 psia UFSAR Revision 32.0
INDIANA AND MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 1
Note: O peration at an RCS pressure of 2 10 0 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 NO P / NO T program. H ence, this figure has been maintained for completeness.
UFSAR Figure: 14.1-3 Change
Description:
UCR-2 0 5 4, Rev. 0 Unit 1
Title:
Illustration of O vertemperature and O verpower T roction Nonal avg = 7 6.3°F - Nominal P ressure = 2 2 5 0 psia UFSAR Revision 32.0
INDIANA AND MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 1
UFSAR Figure: 14.1-3 A Change
Description:
UCR-2 0 5 4, Rev. 0 Unit 1
Title:
Illustration of O vertemperature and O verpower T roction Nonal avg = 7 5.4°F - Nominal P ressure = 2 2 5 0 psia 80 r,\\.............
75 1 \\
\\ t
70 \\, \\ \\ \\
65 \\ \\ \\ 1 \\
Lh \\ f ov
55
\\ \\ 1 \\ \\ SG Sderv 1 50
0
45 :
40
3s I i ii \\ I
- 8 : 8 30 [ L \\ 'I-600
_. DONALD C. COOK NucLEAFtPLAKT UMTl
OverpowCrAf 533.0'F 2250 psi*
.v r
. JULY i997 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.......
.......... s............. I. e..
0.1.....
1 :*;
CI 0
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
JULY 1997
= 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 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 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 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 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 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 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 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 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
Unit 1 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 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
0.0 I 0 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 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 1.6
E lef t I 6 = B E 2 08-
5 Z 3 u = 0.4 -
nn + I V. 0 I
l Heat fluxes are shown i _. m. 1 uafracuonofche nomtnid average chatu)ei beu flux 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 UNIT 1
16.6 Revised per 99-UFSAR-1540 REV. NO Description
Revision
Title:
V essel 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 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 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 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 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 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 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 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 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 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 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 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 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 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
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 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 32.0
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) B rown B overi 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 -1 Change
Description:
1 UCR-2 12 2, Rev. 0 Unit
Title:
Cross Section - L.P. Turbine Rotor (Unit 2) (Shown without B lades)
UFSAR Revision 32.0
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) B rown B overi 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 Fi gure: 14.1.13 -2 Change
Description:
UCR-2 12 2, Rev. 0 Unit 1
Title:
Stress in L -P Turbine Rotor Discs at 176% Speed UFSAR Revision 32.0
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) B rown B overi 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 Fi gure: 14.1.13 -3 Change
Description:
UCR-2 12 2, Rev. 0 Unit 1
Title:
Calculated Failure Speeds of L -P Turbine Rotor Discs UFSAR Revision 32.0
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:
Sk et c h of Las t St age Regi on - L.P. Tu r b i n e Un i t 1
UFSAR Figure: 14.1.13-4 Sheet 1 of 1
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 P ower, 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
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) B rown B overi 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 Fi gure: 14.1.13 -5 Change
Description:
UCR-2 12 2, Rev. 0 Unit 1
Title:
Sk etch of L ow P ressure Turbine Rotor and Casing Unit No. 2 UFSAR Revision 32.0
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
UN IT 1