ML24159A205
| ML24159A205 | |
| 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: ML24159A205 (1) | |
Text
Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 Limiting Case COOK NUCLAR PLANT Cladding Temperature at the PCT Elevation NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1A Sheet 1 of 1 Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 Limiting Case COOK NUCLAR PLANT Break Flow NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1B Sheet 1 of 1 Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 Limiting Case COOK NUCLAR PLANT Broken and Intact Loop Pump Void Fraction NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1C Sheet 1 of 1 Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 Limiting Case COOK NUCLAR PLANT Hot Assembly Top of Core Vapor Flow NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1D Sheet 1 of 1 Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 Limiting Case COOK NUCLAR PLANT Pressurizer Pressure NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1E Sheet 1 of 1
- The reference point for the lower plenum liquid level is the bottom of the vessel (10.1 feet below the bottom of the active fuel).
Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 Limiting PCT COOK NUCLAR PLANT Lower Plenum Collapsed Liquid Level*
NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1F Sheet 1 of 1 Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 Limiting Case COOK NUCLAR PLANT Vessel Fluid Mass NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1G Sheet 1 of 1 Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 Limiting Case COOK NUCLAR PLANT Loop 2 Accumulator Flow NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1H Sheet 1 of 1 Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 Limiting Case COOK NUCLAR PLANT Loop 2 Charging Safety Injection Flow NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1I Sheet 1 of 1 Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 Limiting Case COOK NUCLAR PLANT Loop 2 RHR and HHSI Flow NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1J Sheet 1 of 1
- The reference point for the downcomer liquid level is the bottom of the active fuel.
Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 Limiting Case COOK NUCLAR PLANT Core Average Channel Collapsed Liquid Level
- The reference point for the downcomer liquid level is the bottom of the vessel.
Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 Limiting Case COOK NUCLAR PLANT Loop 2 Downcomer Collapsed Liquid Level*
NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1L Sheet 1 of 1
- The reference point for the PCT location is the bottom of the active fuel.
Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 Limiting Case COOK NUCLAR PLANT PCT Location*
NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1M Sheet 1 of 1 Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 BELOCA Analysis COOK NUCLAR PLANT Axial Power Shape Operating Space Envelope NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-2 Sheet 1 of 1 Notes:
- 1. Due to errors identified with the LOTIC2 containment backpressure calculation, an evaluation was performed assuming a revised initial CTS temperature. See Section 14.3.1.5 for more information.
Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 COOK NUCLAR PLANT Lower Bound Containment Pressure NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-3 Sheet 1 of 1 Notes:
- 1. Due to errors identified with the LOTIC2 containment backpressure calculation, an evaluation was performed assuming a revised initial CTS temperature. See Section 14.3.1.5 for more information.
- The lower compartment trace in the plot is identical to the LOTIC2 trace in Figure 14.3.1-3.
Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 COOK NUCLAR PLANT Containment Pressure*
NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-4 Sheet 1 of 1 Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 COOK NUCLAR PLANT Structural Heat Removal Rate NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-5 Sheet 1 of 1 Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 Lower Compartment COOK NUCLAR PLANT Structural Heat Removal Rate NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-6 Sheet 1 of 1 Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 COOK NUCLAR PLANT Heat Removal by Sump NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-7 Sheet 1 of 1 Notes:
- 1. Due to errors identified with the LOTIC2 containment backpressure calculation, an evaluation was performed assuming a revised initial CTS temperature. See Section 14.3.1.5 for more information.
Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 COOK NUCLAR PLANT Heat Removal by Lower Compartment Spray NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-8 Sheet 1 of 1 Notes:
- 1. Due to errors identified with the LOTIC2 containment backpressure calculation, an evaluation was performed assuming a revised initial CTS temperature. See Section 14.3.1.5 for more information.
- Note that Upper Compartment Temperature pictured is "Air Temperature", while the Lower Compartment Temperature pictured is "Steam Temperature".
Revision: 24.0 Change
Description:
UCR-1974, Rev. 0
AMERICAN ELECTRIC POWER
Title:
D.C. Cook Unit 2 COOK NUCLAR PLANT Containment Temperature*
NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-9 Sheet 1 of 1 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Pumped Safety Injection Flow Rate-Injection Phase COOK NUCLAR PLANT Faulted Loop Spilling to Reactor Coolant System Pressure NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-1 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Pumped Safety Injection Flow Rate-Injection Phase COOK NUCLAR PLANT - Faulted Loop CHG Spilling to RCS Pressure -
NUCLEAR GENERATION GROUP Faulted Loop HHSI / RHR Spilling to Containment Pressure
BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-2 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Pumped Safety Injection Flow Rate COOK NUCLAR PLANT - Recirculation Phase -
NUCLEAR GENERATION GROUP Faulted Loop Spilling to Reactor Coolant System Pressure
BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-3 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Pumped Safety Injection Flow Rate -
COOK NUCLAR PLANT Recirculation Phase - Faulted Loop Spilling to RCS Pressure NUCLEAR GENERATION GROUP Faulted Loop HHSI / RHR Spilling to Containment Pressure
BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-4 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Hot Rod Axial Power Shape COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-5 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Reactor Coolant System Pressure COOK NUCLAR PLANT 4-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-6 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Core Mixture Level COOK NUCLAR PLANT 4-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-7 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Clad Temperature at Peak Clad COOK NUCLAR PLANT Temperature Elevation (11.25 ft) 4-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-8 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Vapor Mass Flow Rate COOK NUCLAR PLANT Out of Top of Core inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-9 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Clad Surface Heat Transfer Coefficient COOK NUCLAR PLANT at Peak Clad Temperature Elevation inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-10 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Fluid Temperature COOK NUCLAR PLANT at Peak Clad Temperature Elevation inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-11 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Total Break Flow and Safety Injection Flow COOK NUCLAR PLANT 4-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-12 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Total Reactor Coolant System Mass COOK NUCLAR PLANT 4-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-13 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Top of Core Vapor Temperature COOK NUCLAR PLANT 4-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-14 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Reactor Coolant System Pressure COOK NUCLAR PLANT 1.5-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-15 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Core Mixture Level COOK NUCLAR PLANT 1.5-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-16 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Top of Core Vapor Temperature COOK NUCLAR PLANT 1.5-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-17 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Reactor Coolant System Pressure COOK NUCLAR PLANT 2-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-18 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Core Mixture Level COOK NUCLAR PLANT 2-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-19 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Top of Core Vapor Temperature COOK NUCLAR PLANT 2-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-20 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Clad Temperature at Peak Cl ad COOK NUCLAR PLANT Temperature Elevation (11.00 ft) inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-21 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Reactor Coolant System Pressure COOK NUCLAR PLANT 3-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-22 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Core Mixture Level COOK NUCLAR PLANT 3-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-23 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Top of Core Vapor Temperature COOK NUCLAR PLANT 3-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-24 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Clad Temperature at Peak Clad COOK NUCLAR PLANT Temperature Elevation (11.25 ft) inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-25 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER
Title:
Reactor Coolant System Pressure COOK NUCLAR PLANT 6-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-26 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER Tit le: Core Mixture Level COOK NUCLAR PLANT 6-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-27 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER Tit le: Top of Core Vapor Temperature COOK NUCLAR PLANT 6-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-28 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER Tit le: Reactor Coolant System Pressure COOK NUCLAR PLANT 8.75-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-29 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER Tit le: Core Mixture Level COOK NUCLAR PLANT 8.75-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-30 Sheet 1 of 1
Unit 2 Revision: 24.0 Change
Description:
UCR-1966, Rev. 0
AMERICAN ELECTRIC POWER Tit le: Top of Core Vapor Temperature COOK NUCLAR PLANT 8.75-inch NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-31 Sheet 1 of 1
Unit 2 UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revised: 29.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 1
UFSAR Figure: 14.3.2-32a Unit: 2
Title:
Reactor Coolant Sy stem Pressure Upfiow Conversion 4-inch UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revised: 29.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 1
UFSAR Figure: 14.3.2-32b Unit: 2
Title:
Core Mix ture Level Upflow Conversion 4-inch UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revised: 29.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 1
UFSAR Figure: 14.3.2-32c Unit: 2
Title:
Top of Core V apor Temperature Upflow Conversion 4-inch UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revised: 29.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 1
UFSAR Figure: 14.3.2-32d Unit: 2
Title:
Clad Temperature at Peak Clad Temperature Elevation (11.50 ft) Upflow Conversion 4-inch Figure 14.3.3-1 Loop Layout and Global Cqordinates July 1994 Figure 14.3.3-2 RPV Shell Submodel
1..1., 1aaL NOZZLE AN0 VESSEL LOOP STIFmES,A-SHELL STIFFNESS
305 306 RPV HORIZONTAL SUPPORTS (4 PLACE 5)
RPV c h RPV VERTICAL SUPPORTS (4 PLACES)
Figure 14.3.3-3 RPv Support Model July 1994
.r i
mnt BrnntL
- FLANGE
- PLATR LOWRR cow
Figure 14.3.3-4 Core Barrel Submo$el
July 1994 3
, D 1S WtR &mQRT
- ?LlTE
amoR?
mLuuNs AU0 owoc Twts
1
18
1 I
f
NIL g?.
I
Figure 14.3.3-S Internals Submodel
July 1994 V8SWl Thermal.Barrcl Shield
.O &Node Hydrodynamic MS Element4 Not to Scale
.- Figure 14.3.3-6 Hydrodynamic Masses in Vessel/Barrel Downcomer Annulus n
FULL RfGIOH
n
0
- Figure 14.3.3-T Wave Path for Depressurization Waves Enterrnq RPV fnl8t Nozzle (Cold Leg) ' *.
u FUEL REGION u
Figure 14.3.3-a Wave.Path for De@resruritation Waves Entering RPV Outlet Nozzle (Hot Leg).
July 1994