ML21125A522
Text
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1A
Title:
D.C. Cook Unit 2 Limiting Case Cladding Temperature at the PCT Elevation Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1B
Title:
D.C. Cook Unit 2 Limiting Case Break Flow Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1C
Title:
D.C. Cook Unit 2 Limiting Case Broken and Intact Loop Pump Void Fraction Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1D
Title:
D.C. Cook Unit 2 Limiting Case Hot Assembly Top of Core Vapor Flow Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1E
Title:
D.C. Cook Unit 2 Limiting Case Pressurizer Pressure Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1F
Title:
D.C. Cook Unit 2 Limiting PCT Lower Plenum Collapsed Liquid Level*
Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0
- 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).
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1G
Title:
D.C. Cook Unit 2 Limiting Case Vessel Fluid Mass Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1H
Title:
D.C. Cook Unit 2 Limiting Case Loop 2 Accumulator Flow Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1I
Title:
D.C. Cook Unit 2 Limiting Case Loop 2 Charging Safety Injection Flow Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1J
Title:
D.C. Cook Unit 2 Limiting Case Loop 2 RHR and HHSI Flow Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1K
Title:
D.C. Cook Unit 2 Limiting Case Core Average Channel Collapsed Liquid Level*
Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0
- The reference point for the downcomer liquid level is the bottom of the active fuel.
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1L
Title:
D.C. Cook Unit 2 Limiting Case Loop 2 Downcomer Collapsed Liquid Level*
Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0
- The reference point for the downcomer liquid level is the bottom of the vessel.
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1M
Title:
D.C. Cook Unit 2 Limiting Case PCT Location*
Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0
- The reference point for the PCT location is the bottom of the active fuel.
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-2
Title:
D.C. Cook Unit 2 BELOCA Analysis Axial Power Shape Operating Space Envelope Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-3
Title:
D.C. Cook Unit 2 Lower Bound Containment Pressure Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0 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.
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-4
Title:
D.C. Cook Unit 2 Containment Pressure*
Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0 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.
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-5
Title:
D.C. Cook Unit 2 Structural Heat Removal Rate Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-6
Title:
D.C. Cook Unit 2 Lower Compartment Structural Heat Removal Rate Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-7
Title:
D.C. Cook Unit 2 Heat Removal by Sump Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-8
Title:
D.C. Cook Unit 2 Heat Removal by Lower Compartment Spray Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0 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.
AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-9
Title:
D.C. Cook Unit 2 Containment Temperature*
Change
Description:
UCR-1974, Rev. 0 Sheet 1 of 1 Revision: 24.0 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".
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-1
Title:
Pumped Safety Injection Flow Rate-Injection Phase Faulted Loop Spilling to Reactor Coolant System Pressure Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-2
Title:
Pumped Safety Injection Flow Rate-Injection Phase
- Faulted Loop CHG Spilling to RCS Pressure -
Faulted Loop HHSI / RHR Spilling to Containment Pressure Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-3
Title:
Pumped Safety Injection Flow Rate
- Recirculation Phase -
Faulted Loop Spilling to Reactor Coolant System Pressure Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-4
Title:
Pumped Safety Injection Flow Rate -
Recirculation Phase - Faulted Loop Spilling to RCS Pressure Faulted Loop HHSI / RHR Spilling to Containment Pressure Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-5
Title:
Hot Rod Axial Power Shape Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-6
Title:
Reactor Coolant System Pressure 4-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-7
Title:
Core Mixture Level 4-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-8
Title:
Clad Temperature at Peak Clad Temperature Elevation (11.25 ft) 4-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-9
Title:
Vapor Mass Flow Rate Out of Top of Core inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-10
Title:
Clad Surface Heat Transfer Coefficient at Peak Clad Temperature Elevation inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-11
Title:
Fluid Temperature at Peak Clad Temperature Elevation inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-12
Title:
Total Break Flow and Safety Injection Flow 4-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-13
Title:
Total Reactor Coolant System Mass 4-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-14
Title:
Top of Core Vapor Temperature 4-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-15
Title:
Reactor Coolant System Pressure 1.5-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-16
Title:
Core Mixture Level 1.5-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-17
Title:
Top of Core Vapor Temperature 1.5-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-18
Title:
Reactor Coolant System Pressure 2-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-19
Title:
Core Mixture Level 2-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-20
Title:
Top of Core Vapor Temperature 2-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-21
Title:
Clad Temperature at Peak Clad Temperature Elevation (11.00 ft) inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-22
Title:
Reactor Coolant System Pressure 3-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-23
Title:
Core Mixture Level 3-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-24
Title:
Top of Core Vapor Temperature 3-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-25
Title:
Clad Temperature at Peak Clad Temperature Elevation (11.25 ft) inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-26
Title:
Reactor Coolant System Pressure 6-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-27 Tit le: Core Mixture Level 6-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-28 Tit le: Top of Core Vapor Temperature 6-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-29 Tit le: Reactor Coolant System Pressure 8.75-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-30 Tit le: Core Mixture Level 8.75-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
Unit 2 AMERICAN ELECTRIC POWER COOK NUCLAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-31 Tit le: Top of Core Vapor Temperature 8.75-inch Change
Description:
UCR-1966, Rev. 0 Sheet 1 of 1 Revision: 24.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 29.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.2-32a Unit: 2
Title:
Reactor Coolant System Pressure Upfiow Conversion 4-inch
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 29.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.2-32b Unit: 2
Title:
Core Mixture Level Upflow Conversion 4-inch
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 29.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.2-32c Unit: 2
Title:
Top of Core Vapor Temperature Upflow Conversion 4-inch
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 29.0 Chapter:
14 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
LOOP STIFmES NOZZLE AN0 VESSEL
,A-SHELL STIFFNESS 305 306 RPV HORIZONTAL SUPPORTS (4 PLACE RPV c
h RPV VERTICAL SUPPORTS (4 PLACES)
- 5)
Figure 14.3.3-3 RPv Support Model July 1994
.r i
mnt BrnntL FLANGE LOWRR cow PLATR Figure 14.3.3-4 Core Barrel Submo$el July 1994
amoR?
mLuuNs AU0 owoc Twts 1
NIL 3
, D 1S 18 1
f I
WtR &mQRT
?LlTE g?
I Figure 14.3.3-S Internals Submodel July 1994
V8SWl Thermal Shield
.Barrcl
.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