ML21125A522

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0 to Updated Final Safety Analysis Report, Chapter 14.3, Figures 14.3.1-1A to 14.3.3-8 (Unit 2)
ML21125A522
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 04/19/2021
From:
Indiana Michigan Power Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML21126A238 List: ... further results
References
AEP-NRC-2021-19
Download: ML21125A522 (64)


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*

NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.1-1K Sheet 1 of 1

  • 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

Title:

Pumped Safety Injection Flow Rate- Injection Phase AMERICAN ELECTRIC POWER - Faulted Loop CHG Spilling to RCS Pressure -

COOK NUCLAR PLANT Faulted Loop HHSI / RHR Spilling to Containment Pressure NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-2 Sheet 1 of 1 Unit 2

Revision: 24.0 Change

Description:

UCR-1966, Rev. 0

Title:

Pumped Safety Injection Flow Rate AMERICAN ELECTRIC POWER - Recirculation Phase -

COOK NUCLAR PLANT Faulted Loop Spilling to Reactor Coolant System Pressure NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.2-3 Sheet 1 of 1 Unit 2

Revision: 24.0 Change

Description:

UCR-1966, Rev. 0

Title:

Pumped Safety Injection Flow Rate -

AMERICAN ELECTRIC POWER Recirculation Phase - Faulted Loop Spilling to RCS Pressure COOK NUCLAR PLANT Faulted Loop HHSI / RHR Spilling to Containment Pressure NUCLEAR GENERATION GROUP 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 Clad 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

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

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

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

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

,A- SHELL STIFFNESS LOOP STIFmES 305 306 RPV HORIZONTAL SUPPORTS(4 PLACE5) c RPV h RPV VERTICAL SUPPORTS(4 PLACES)

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

3

,D WtR &mQRT 1S - ?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 &NodeHydrodynamic MS Element4 Not to Scale

.- Figure 14.3.3-6 Hydrodynamic Masses in Vessel/Barrel Downcomer Annulus

n FULL RfGIOH n

0 Wave Path for Depressurization ' Waves Enterrnq

- Figure 14.3.3-T RPV fnl8t Nozzle (Cold Leg) * .

u u

FUELREGION Figure 14.3.3-a Wave.Path for De@resruritation Waves Entering RPV Outlet Nozzle (Hot Leg).

July 1994