ML21125A570
Text
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:
14 Sheet:
1 of 1 The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new limiting case. See Section 14.3.1.6.2 and Figure 14.3.1-1AA for more information.
UFSAR Figure: 14.3.1-1A Change
Description:
UCR-2054, Rev. 0 Unit 1
Title:
D. C. Cook Unit 1 Limiting Case Cladding Temperature at the PCT Elevation UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1AA Change
Description:
UCR-2054, Rev. 0 Unit 1
Title:
D. C. Cook Unit 1 Limiting Case Cladding Temperature at the PCT Elevation for the Return to RCS NOP/NOT Evaluation UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:
14 Sheet:
1 of 1 The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new limiting case. See Section 14.3.1.6.2 and Figure 14.3.1-1BA for more information.
UFSAR Figure: 14.3.1-1B Change
Description:
UCR-2054, Rev. 0 Unit 1
Title:
D. C. Cook Unit 1 Limiting Case Vessel Side Break Flow UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1BA Change
Description:
UCR-2054, Rev. 0 Unit 1
Title:
D. C. Cook Unit 1 Limiting Case Vessel Side Break Flow for the Return to RCS NOP/NOT Evaluation UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:
14 Sheet:
1 of 1 The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new limiting case. See Section 14.3.1.6.2 and Figure 14.3.1-1CA for more information.
UFSAR Figure: 14.3.1-1C Change
Description:
UCR-2054, Rev. 0 Unit 1
Title:
D. C. Cook Unit 1 Limiting Case Pump Side Break Flow UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1CA Change
Description:
UCR-2054, Rev. 0 Unit 1
Title:
D. C. Cook Unit 1 Limiting Case Pump Side Break Flow for the Return to RCS NOP/NOT Evaluation UFSAR Revision 30.0
INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised:
28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1D Change
Description:
UCR-2178, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting Case Broken and Intact Loop Pump Void Fraction The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new limiting case. See Section 14.3.1.6.2 and Figure 14.3.1-1Da for more information.
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1Da Change
Description:
UCR-2178, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting Case Broken and Intact Loop Pump Void Fraction for the Return to RCS NOP/NOT Evaluation (Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1E Change
Description:
UCR-2178, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting Case Hot Assembly Top of Core Vapor Flow The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new limiting case. See Section 14.3.1.6.2 and Figure 14.3.1-1Ea for more information.
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1Ea Change
Description:
UCR-2178, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting Case Hot Assembly Top of Core Vapor Flow for the Return to RCS NOP/NOT Evaluation (Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1F Change
Description:
UCR-2178, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting Case Pressurizer Pressure The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new limiting case. See Section 14.3.1.6.2 and Figure 14.3.1-1Fa for more information.
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1Fa Change
Description:
UCR-2178, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting Case Pressurizer Pressure for the Return to RCS NOP/NOT Evaluation (Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1G Change
Description:
UCR-2178, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting PCT Lower Plenum Collapsed Liquid Level
- The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new limiting case. See Section 14.3.1.6.2 and Figure 14.3.1-1Ga for more information.
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 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)
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1Ga Change
Description:
UCR-2178, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting PCT Lower Plenum Collapsed Liquid Level for the Return to RCS NOP/NOT Evaluation *
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 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).
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1H Change
Description:
UCR-2178, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting Case Vessel Fluid Mass The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new limiting case. See Section 14.3.1.6.2 and Figure 14.3.1-1Ha for more information.
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1Ha Change
Description:
UCR-2178, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting Case Vessel Fluid Mass for the Return to RCS NOP/NOT Evaluation (Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1I Change
Description:
UCR-2179, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting Case Loop 2 Accumulator Flow The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new limiting case. See Section 14.3.1.6.2 and Figure 14.3.1-1Ia for more information.
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1Ia Change
Description:
UCR-2179, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting Case Loop 2 Accumulator Flow for the Return to RCS NOP/NOT Evaluation (Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1J Change
Description:
UCR-2179, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting Case Loop 2 Charging Safety Injection Flow The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new limiting case. See Section 14.3.1.6.2 and Figure 14.3.1-1Ja for more information.
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1Ja Change
Description:
UCR-2179, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting Case Loop 2 Charging Safety Injection Flow for the Return to RCS NOP/NOT Evaluation (Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1K Change
Description:
UCR-2179, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting Case Loop 2 RHR and HHSI Flow The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new limiting case. See Section 14.3.1.6.2 and Figure 14.3.1-1Ka for more information.
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1Ka Change
Description:
UCR-2179, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting Case Loop 2 RHR and HHSI Flow for the Return to RCS NOP/NOT Evaluation (Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1L Change
Description:
UCR-2179, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting Case Core Average Channel Collapsed Liquid Level
- The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new limiting case. See Section 14.3.1.6.2 and Figure 14.3.1-1La for more information.
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
- The reference point for the collapsed liquid level is the bottom of the active fuel.
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1La Change
Description:
UCR-2179, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting Case Core Average Channel Collapsed Lipid Level or the Return to RCS NOP/NOT Evaluation*
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
- The reference point for the collapsed liquid level is the bottom of the active fuel.
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1M Change
Description:
UCR-2179, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting Case Loop 2 Downcomer Collapsed Liquid Level
- The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new limiting case. See Section 14.3.1.6.2 and Figure 14.3.1-1Ma for more information.
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
- The reference point for the downcomer liquid level is the bottom of the vessel.
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1Ma Change
Description:
UCR-2179, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting Case Loop 2 Downcomer Collapsed Liquid Level for the Return to RCS NOP/NOT Evaluation*
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
- The reference point for the downcomer liquid level is the bottom of the vessel.
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1N Change
Description:
UCR-2180, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting Case PCT Location
- The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new limiting case. See Section 14.3.1.6.2 and Figure 14.3.1-1Na for more information.
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
- The reference point for the PCT Location is the bottom of the active fuel.
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-1Na Change
Description:
UCR-2180, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Limiting Case PCT Location for the Return to RCS NOP/NOT Evaluation *
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
- The reference point for the PCT location is the bottom of the active fuel.
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-2 Change
Description:
UCR-2180, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 BELOCA Analysis Axial Power Shape Operating Space Envelope PBOT = integrated power fraction in the bottom third of the core PMID = integrated power fraction in the middle third of the core (Revision 23.0 l Change
Description:
UCR-1947, Rev. 0)
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-3 Change
Description:
UCR-2180, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Lower Bound Containment Pressure The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new LOTIC2 containment backpressure. See Section 14.3.1.6.2 and Figure 13.3.1-3a for more information.
It is noted that the error identified in Section 14.3.1.6.1 was corrected in the updated LOTIC2 containment backpressure calculation in Section 14.3.1.6.2.
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
Due to errors identified with the LOTIC2 containment backpressure calculation, an evaluation was performed assuming a revised initial CTS temperature. See Section 14.3.1.6.1 for more information.
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 (Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Figure: 14.3.1-3a Change
Description:
UCR-2180, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Lower Bound Containment Pressure for the Return to RCS NOP/NOT Evaluation UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-4 Change
Description:
UCR-2180, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Containment Pressure
- The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new LOTIC2 containment backpressure. See Section 14.3.1.6.2 and Figure 14.3.1-4a for more information. It is noted that the error identified in Section 14.3.1.6.1 was corrected in the updated LOTIC2 containment backpressure calculation in Section 14.3.1.6.2.
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
- The lower compartment trace in the plot is identical to the LOTIC2 trace in Figure 14.3.1-3.
Due to errors identified with the LOTIC2 containment backpressure calculation, an evaluation was performed assuming a revised initial CTS temperature. See section 14.3.1.6.1 for more information.
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-4a Change
Description:
UCR-2180, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Containment Pressure for the Return to RCS NOP/NOT Evaluation *
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
- The lower compartment in the plot is identical to the LOTIC2 trace in Figure 14.3.1-3a.
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-5 Change
Description:
UCR-2180, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Structural Heat Removal Rate The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new LOTIC2 containment backpressure. See Section 14.3.1.6.2 and Figure 13.3.1-5a for more information.
It is noted that the error identified in Section 14.3.1.6.1 was corrected in the updated LOTIC2 containment backpressure calculation in Section 14.3.1.6.2.
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 (Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Figure: 14.3.1-5a Change
Description:
UCR-2180, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Structural Heat Removal Rate for the Return to RCS NOP/NOT Evaluation UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-6 Change
Description:
UCR-2180, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Lower Compartment Structural Heat Removal Rate The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new LOTIC2 containment backpressure. See Section 14.3.1.6.2 and Figure 13.3.1-6a for more information. It is noted that the error identified in Section 14.3.1.6.1 was corrected in the updated LOTIC2 containment backpressure calculation in Section 14.3.1.6.2.
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 (Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Figure: 14.3.1-6a Change
Description:
UCR-2181, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Lower Compartment Structural Heat Removal Rate for the Return to RCS NOP/NOT Evaluation UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-7 Change
Description:
UCR-2181, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Heat Removal by Sump The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new LOTIC2 containment backpressure. See Section 14.3.1.6.2 and Figure 14.3.1-7a for more information. It is noted that the error identified in Section 14.3.1.6.1 was corrected in the updated LOTIC2 containment backpressure calculation in Section 14.3.1.6.2.
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 (Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Figure: 14.3.1-7a Change
Description:
UCR-2181, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Heat Removal by Sump for the Return to RCS NOP/NOT Evaluation UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-8 Change
Description:
UCR-2181, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Heat Removal by Lower Compartment Spray The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new LOTIC2 containment backpressure. See Section 14.3.1.6.2 and Figure 14.3.1-8a for more information. It is noted that the error identified in Section 14.3.1.6.1 was corrected in the updated LOTIC2 containment backpressure calculation in Section 14.3.1.6.2.
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
Due to errors identified with the LOTIC2 containment backpressure calculation, an evaluation was performed assuming a revised initial CTS temperature. See section 14.3.1.6.1 for more information.
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 (Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
UFSAR Figure: 14.3.1-8a Change
Description:
UCR-2181, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Heat Removal by Lower Compartment Spray for the Return to RCS NOP/NOT Evaluation UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-9 Change
Description:
UCR-2181, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Containment Temperatures
- The evaluation for the return to NOP/NOT conditions and fuel TCD calculated a new LOTIC2 containment backpressure. See Section 14.3.1.6.2 and Figure 14.3.1-9a for more information. It is noted that the error identified in Section 14.3.1.6.1 was corrected in the updated LOTIC2 containment backpressure calculation in Section 14.3.1.6.2.
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
- Note that the Upper Compartment Temperature pictured is Air Temperature, while the Lower Compartment Temperature pictured is Steam Temperature.
Due to errors identified with the LOTIC2 containment backpressure calculation, an evaluation was performed assuming a revised initial CTS temperature. See section 14.3.1.6.1 for more information.
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 28.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.1-9a Change
Description:
UCR-2181, Rev. 0 Unit 1
Title:
D.C. Cook Unit 1 Containment Temperatures for the Return to RCS NOP/NOT Evaluation *
(Revision 27.0 l Change
Description:
UCR-2054, Rev. 0)
- Note that the Upper Compartment Temperature pictured is Air Temperature, while the Lower Compartment Temperature pictured is Steam Temperature.
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-1 Change
Description:
UCR-2001, Rev. 0
Title:
Pumped Safety Injection Flow Rate - Injection Phase Faulted Loop Spilling to Reactor Coolant Pressure Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-2 Change
Description:
UCR-2001, Rev. 0
Title:
Pumped Safety Injection Flow Rate - Injection Phase-Faulted Loop CHG Spilling to RCS Pressure - Faulted Loop HHSI/RHR Spilling to Containment Pressure Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-3 Change
Description:
UCR-2001, Rev. 0
Title:
Pumped Safety Injection Flow Rate - Recirculation Phase Faulted Loop Spilling to Reactor Coolant System Pressure Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-4 Change
Description:
UCR-2001, Rev. 0
Title:
Pumped Safety Injection Flow Rate - Recirculation Phase - Faulted Loop CHG Spilling to RCS Pressure - Faulted Loop HHSI/RHR Spilling to Containment Pressure Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-5 Change
Description:
UCR-2001, Rev. 0
Title:
Hot Rod Axial Power Shape Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-6 Change
Description:
UCR-2001, Rev. 0
Title:
Reactor Coolant System Pressure - 3.25-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-7 Change
Description:
UCR-2001, Rev. 0
Title:
Core Mixture Level - 3.25-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-8 Change
Description:
UCR-2001, Rev. 0
Title:
Clad Temperature at Peak Clad Temperature Elevation (11.75 ft) 3.25-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-9 Change
Description:
UCR-2001, Rev. 0
Title:
Vapor Mass Flow Rate Out of Top of Core 3.25-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-10 Change
Description:
UCR-2001, Rev. 0
Title:
Clad Surface Heat Transfer Coefficient at Peak Clad Temperature Elevation 3.25-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-11 Change
Description:
UCR-2001, Rev. 0
Title:
Fluid Temperature at Peak Clad Temperature Elevation 3.25-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-12 Change
Description:
UCR-2001, Rev. 0
Title:
Total Break Flow and Safety Injection Flow 3.25-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-13 Change
Description:
UCR-2001, Rev. 0
Title:
Total Reactor Coolant System Mass 3.25-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-14 Change
Description:
UCR-2001, Rev. 0
Title:
Top of Core Vapor Temperature 3.25-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-15 Change
Description:
UCR-2001, Rev. 0
Title:
Reactor Coolant System Pressure 1.5-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-16 Change
Description:
UCR-2001, Rev. 0
Title:
Core Mixture Level 1.5-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-17 Change
Description:
UCR-2001, Rev. 0
Title:
Top of Core Vapor Temperature 1.5-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-18 Change
Description:
UCR-2001, Rev. 0
Title:
Reactor Coolant System Pressure 2-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
UFSAR Figure: 14.3.2-19 Change
Description:
UCR-2001, Rev. 0
Title:
Core Mixture Level 2-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-20 Change
Description:
UCR-2001, Rev. 0
Title:
Top of Core Vapor Temperature 2-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-21 Change
Description:
UCR-2001, Rev. 0
Title:
Clad Temperature at Peak Clad Temperature Elevation (11.00 ft) 2-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-22 Change
Description:
UCR-2001, Rev. 0
Title:
Reactor Coolant System Pressure 2.5-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-23 Change
Description:
UCR-2001, Rev. 0
Title:
Core Mixture Level 2.5-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-24 Change
Description:
UCR-2001, Rev. 0
Title:
Top of Core Vapor Temperature 2.5-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-25 Change
Description:
UCR-2001, Rev. 0
Title:
Clad Temperature at Peak Clad Temperature Elevation (11.5 ft) 2.5-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-26 Change
Description:
UCR-2001, Rev. 0
Title:
Reactor Coolant System Pressure 2.75-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-27 Change
Description:
UCR-2001, Rev. 0
Title:
Core Mixture Level 2.75-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-28 Change
Description:
UCR-2001, Rev. 0
Title:
Top of Core Vapor Temperature 2.75-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-29 Change
Description:
UCR-2001, Rev. 0
Title:
Clad Temperature at Peak Clad Temperature Elevation (11.5 ft) 2.75-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-30 Change
Description:
UCR-2001, Rev. 0
Title:
Reactor Coolant System Pressure 3-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-31 Change
Description:
UCR-2001, Rev. 0
Title:
Core Mixture Level 3-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-32 Change
Description:
UCR-2001, Rev. 0
Title:
Top of Core Vapor Temperature 3-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-33 Change
Description:
UCR-2001, Rev. 0
Title:
Clad Temperature at Peak Clad Temperature Elevation (11.75 ft) 3-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-34 Change
Description:
UCR-2001, Rev. 0
Title:
Reactor Coolant System Pressure 3.5-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-35 Change
Description:
UCR-2001, Rev. 0
Title:
Core Mixture Level 3.5-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-36 Change
Description:
UCR-2001, Rev. 0
Title:
Top of Core Vapor Temperature 3.5-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-37 Change
Description:
UCR-2001, Rev. 0
Title:
Clad Temperature at Peak Clad Temperature Elevation (11.75 ft) 3.5-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-38 Change
Description:
UCR-2001, Rev. 0
Title:
Reactor Coolant System Pressure 3.75-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-39 Change
Description:
UCR-2001, Rev. 0
Title:
Core Mixture Level 3.75-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-40 Change
Description:
UCR-2001, Rev. 0
Title:
Top of Core Vapor Temperature 3.75-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-41 Change
Description:
UCR-2001, Rev. 0
Title:
Clad Temperature at Peak Clad Temperature Elevation (11.5 ft) 3.75-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-42 Change
Description:
UCR-2001, Rev. 0
Title:
Reactor Coolant System Pressure 4-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-43 Change
Description:
UCR-2001, Rev. 0
Title:
Core Mixture Level 4-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-44 Change
Description:
UCR-2001, Rev. 0
Title:
Top of Core Vapor Temperature 4-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-45 Change
Description:
UCR-2001, Rev. 0
Title:
Clad Temperature at Peak Clad Temperature Elevation (11.25 ft) 4-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-46 Change
Description:
UCR-2001, Rev. 0
Title:
Reactor Coolant System Pressure 6-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-47 Change
Description:
UCR-2001, Rev. 0
Title:
Core Mixture Level 6-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-48 Change
Description:
UCR-2001, Rev. 0
Title:
Top of Core Vapor Temperature 6-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-49 Change
Description:
UCR-2001, Rev. 0
Title:
Clad Temperature at Peak Clad Temperature Elevation (11.00 ft) 6-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-50 Change
Description:
UCR-2001, Rev. 0
Title:
Reactor Coolant System Pressure 8.75-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-51 Change
Description:
UCR-2001, Rev. 0
Title:
Core Mixture Level 8.75-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Chapter:
14.3 Sheet:
1 of 1 UFSAR Figure: 14.3.2-52 Change
Description:
UCR-2001, Rev. 0
Title:
Top of Core Vapor Temperature 8.75-inch Unit: 1 Last Revised: Revision 25.0 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 29.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.2-53 Unit 1
Title:
Reactor Coolant System Pressure Upflow Configuration 3.0-inch UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 29.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.2-54 Unit 1
Title:
Core Mixture Level Upflow Configuration 3.0-inch UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 29.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.2-55 Unit 1
Title:
Top of Core Vapor Temperature Upflow Configuration 3.0-inch UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 29.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.2-56 Unit 1
Title:
Cladding Temperature at PCT Elevation (8500 MWD/MTU) Upflow Configuration 3.0-inch UFSAR Revision 30.0
P L
m N
STEAM PARIIAL PRESSURE, PSIA 0
ul 0
u, 8
G I
I I
I 1
I I
1 I
I 2
vl 0
cn 0
AIR PARTIAL PRESSURE, PSIA UFSAR Revision 30.0
PEAK COMPRESSION PRESSURE (PSIG) ul ul u
b b
ul U
QD ln b
UFSAR Revision 30.0
Figure 14.3.4-3 L'pper Compartment Compression Pressure versus Energy Release for Tests a:
110% and 200% of Initial DBA Blowdown Rate hi:
1 l&.3.4-164 July 1992 UFSAR Revision 30.0
16.4 REVISED PER 99-UFSAR-0956 Ice Melted versus Energy Release for Tests at Different Blowdown Rates FSAR FIG. 14.3.4-4 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
UNIT 1 TEST AT 14 % INITIAL MHA BLOWDOWN RATE TESTS BETWEEN 110 % AND 200 % INITIAL MHA BLOWDOWN RATE ICE MELTED, %
ENERGY RELEASE % OF REACTOR COOLANT SYSTEM RELEASE UFSAR Revision 30.0
16.4 REVISED PER 99-UFSAR-956 Upper Compartment Peak Compression Pressure versus Blowdown Rate for Tests with 185 % Energy Release FSAR FIG. 14.3.4-5 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.
DESCRIPTION REVISIONS TITLE DWG. NO.
COMPRESSION PEAK PRESSURE (PSIG) 10 8
6 4
2 0
INITIAL BLOWDOWN RATE, % OF MHA 0
25 50 75 100 125 150 175 200 UNIT 1 UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.4-6 Change
Description:
UCR-2087, Rev. 0 UCR-2138, Rev. 0 Unit: 1
Title:
LOCA Containment Integrity Containment Pressure Note 1: Figure 14.3.4-6 is a representative plot of the D. C. Cook LOCA pressure transient.
The actual plot will be slightly lower. The current peak pressure is calculated to be 11.16 psig +0.27 psig as described in Section 14.3.4.1.3.1.3 (U1).
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.4-6A Change
Description:
UCR-2087, Rev. 0 UCR-2138, Rev. 0 Unit: 1
Title:
LOCA Containment Integrity (Composite) Containment Pressure Note 2: Figure 14.3.4-6A is a representative plot of the D. C. Cook LOCA pressure transient. The actual plot will peak slightly lower.
Note 1: This peak pressure is increased by 0.27 psi described in Section 14.3.4.1.3.1.3.
The peak composite pressure is 10.37 psig.
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.4-7 Change
Description:
UCR-2087, Rev. 0 UCR-2138, Rev. 0 Unit: 1
Title:
LOCA Containment Integrity Upper Compartment Temperature Note 1: Figure 14.3.4-7 is a representative plot of the D. C. Cook LOCA temperature transient.
The actual plot will peak slightly lower.
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.4-8 Change
Description:
UCR-2087, Rev. 0 UCR-2138, Rev. 0 Unit: 1
Title:
LOCA Containment Integrity Lower Compartment Temperature Note 2: Figure 14.3.4-8 is a representative plot of the D. C. Cook LOCA temperature transient.
The actual plot will peak slightly lower.
Note 1: Peak Temperature = 232.2°F.
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.4-9 Change
Description:
UCR-2087, Rev. 0 UCR-2138, Rev. 0 Unit: 1
Title:
LOCA Containment Integrity Containment Sump Temperature Transient Note 1: Figure 14.3.4-9 is a representative plot of the D. C. Cook LOCA containment sump temperature transient. The actual transient will vary slightly.
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.4-10 Change
Description:
UCR-2087, Rev. 0 UCR-2138, Rev. 0 Unit: 1
Title:
LOCA Containment Integrity Ice Melt Transient Note 1: Figure 14.3.4-10 is a representative plot of the D. C. Cook LOCA ice melt transient.
The actual plot will vary slightly.
UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.4-11 Change
Description:
UCR-2054, Rev. 0 Unit 1
Title:
30% of 3327 MWt NSSS Power, 1.4 ft2 Double-Ended Rupture, MSIV Failure, Compartment Temperatures UFSAR Revision 30.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:
14 Sheet:
1 of 1 UFSAR Figure: 14.3.4-12 Change
Description:
UCR-2054, Rev. 0 Unit 1
Title:
100.34% of 3327 MWt NSSS Power, 0.865 ft2 Split Break, MSIV Failure, Compartment Temperatures UFSAR Revision 30.0
400 300 2CQ LOO 5.3 L
/
- b.
- b.
-a maa A
Host Severe Small Break
-a at3011 Power
-\\
(0.942 ft2)
AEP's (0.942 ft2) 3A soa TIME (SEC) i
- sa Figure 14.3.4-13 Worst Break-Lower Compartment Temperature Comparison Unit 1
14.3.4-174 Julv 1003 UFSAR Revision 30.0
400 200 250 100
/ 0.60 ft2 TIME (SEC)
Figure 14.3.4-14 Upper Compartment Temperature (30%
Power Level)
Unit 1
14.3.4-17s July 1992 UFSAR Revision 30.0
4.3 2.3 6.3
\\
0.60 ft2 6.3 300
- suo, TIME (SEC)
Figure 14.3.4-15 Lower Compartment Pressure (30%
Power Level)
Unit 1
14.3.4-176 July 1992 UFSAR Revision 30.0
so0 TIME (SEC)
LOO0 Unit 1
Figure 14.3.4-16 Lower Compartment Temperature (30%
Power Level) 14.3.4-177 July 1992 UFSAR Revision 30.0
Acoo Unit 1
Sull Break at 30x Payer (Q.942 ft
)
Figure
- 14. 3.4.
?oa TIME (SEC) 7 Worst Break-Lover Compartment Temperature Comparison Generic Analysis l&.3.&-178 July 1992 UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-18 Sheet 1 of 1
Title:
Cook Unit 1 & 2 TMD Model Plan At Equipment Rooms Elevation FAN COMPARTMENT PR 2
3 1
6 4
5 27 S.G.
S.G.
S.G.
P 31 FAN COMPARTMENT ACC P
P P
ACC S.G.
ACC ACC GATE 33 29 INSTR. ROOM UPPER COMPARTMENT A
A 25 UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-19 Sheet 1 of 1
Title:
Cook Unit 1 & 2 TMD Model Containment Section View 25 UPPER COMPARTMENT 25 25 34 9
8 7
40 33 25 30 32 26, 28 REFUELING CANAL Top Deck Doors Intermediate Deck Doors GATE Section "A-A" 39, 38, 37, 36, 35 23, 20, 17, 14, 11 24, 21, 18, 15, 12 22, 19, 16, 13, 10 45, 44, 43, 42, 41 1, 2, 3, 4, 5 & 6 27, 29, 31 UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-20 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Plan View at Ice Condenser Elevation Ice Condenser Compartments S.G.
44, 19, 20, 21, 38 PR 2
3 1
6 4
5 45, 22, 23, 24, 39 43, 16, 17,18, 37 42, 13, 14, 15, 36 40, 7, 8, 9, 34 41, 10, 11, 12, 35 S.G.
S.G.
S.G.
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-21 Sheet 1 of 1
Title:
Cook Unit 1 & 2 TMD Model Layout of Containment Shell 29 9
34 35 36 37 38 39 25 26 28 30 32 27 31 25 25 40 41 42 43 44 45 7
10 13 16 19 22 8
11 14 17 20 23 12 15 18 21 24 UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-22 Sheet 1 of 1
Title:
Steam Generator Enclosure Above Elevation 665 ft.
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-23 Sheet 1 of 1
Title:
Steam Generator Enclosure Below Elevation 665 ft.
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-24 Sheet 1 of 2
Title:
Steam Generator Enclosure Cut-Open View of the Steam Generator Enclosure UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-24 Sheet 2 of 2
Title:
Schematic of the Cook Unit 1 & 2 9 Node TMD Steam Generator Enclosure Model SG 62 SG SG SG 58 57 59 56 63 60 61 58 59 50 54 47 51 48 52 53 49 Loop Compartment No. 3 Loop Compartment No. 2 Loop Compartment No. 1 55 56 63 62 60 61 57 52 51 48 47 49 54 53 50 46 Loop Compartment No. 3 Loop Compartment No. 2 Loop Compartment No. 1 A
A Elevation A - A UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-25 Sheet 1 of 1
Title:
Schematic of the Cook Unit 1 & 2 9 Node TMD Steam Generator Enclosure Model 63 62 59 58 57 56 60 61 47 48 49 50 54 53 52 51 55 46 3
2 1
1 - 3 Loop Compartments 46 - 54 Steam Generator Enclosure A 55 - 63 Steam Generator Enclosure B UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-26 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Pressurizer Enclosure TMD Model Noding Network 49 48 47 48 49 46 UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-27 Sheet 1 of 1
Title:
Cook Unit 1 & 2 TMD Model with Pressurizer Enclosure Nodalization Network 25 29 4
43 33 16 17 18 37 5
3 1
47 48 49 46 30 42 13 14 15 36 41 44 40 45 2
10 11 12 35 7
8 9
34 6
22 24 23 39 19 20 21 38 28 26 32 31 27 UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-28 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Fan / Accumulator Room TMD Model Plan at Equipment Rooms Elevation FAN COMPARTMENT PR 2
3 1
6 4
5 55 S.G.
S.G.
S.G.
P 31 FAN COMPARTMENT ACC P
P P
ACC S.G.
ACC ACC GATE 33 29 INSTR. ROOM UPPER COMPARTMENT A
A 25 27 54 56 57 UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-29 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Fan / Accumulator Room TMD Model Layout of Containment Shell 29 9
34 35 36 37 38 39 25 26 28 30 32 31 25 25 40 41 42 43 44 45 7
10 13 16 19 22 8
11 14 17 20 23 12 15 18 21 24 57 56 55 54 27 UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-30 Sheet 1 of 1
Title:
Cook Unit 1 & 2 TMD Model with Fan / Accumulator Room Nodalization Network 25 29 4
43 33 16 17 18 37 5
3 1
52 48 49 53 30 42 13 14 15 36 41 44 40 45 2
10 11 12 35 7
8 9
34 6
22 24 23 39 19 20 21 38 28 26 32 31 55 50 47 46 51 27 54 56 57 UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-31 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Loop Subcompartment TMD Model Nodalization Network 25 29 4
43 33 16 17 18 37 5
3 1
52 48 49 53 30 42 13 14 15 36 41 44 40 45 2
10 11 12 35 7
8 9
34 6
22 24 23 39 19 20 21 38 28 26 32 31 27 50 47 46 51 UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-32 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Reactor Cavity Subcompartment TMD Model Containment Section View 51 46 38 2
53 4
Thru 37 3
52 UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-33 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Reactor Cavity Subcompartment TMD Model Layout of Reactor Vessel Annulus Elements 32 37 8 13 18 21 23 25 27 29 36 17 7
12 33 14 11 9
34 15 5
10 35 16 6
11 43 42 41 40 44 39 1
45 44 31 20 26 24 22 28 30 19 3
Break Location 338 293 270 247 224.5 202 158 113 67 22 338 Circumference (Degrees)
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-34 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Reactor Cavity Subcompartment TMD Model Nodalization Network 2
32 37 29 36 7
8 12 13 17 18 21 23 27 25 30 33 34 4
9 14 5
10 15 19 22 24 26 28 35 6
11 16 20 52 42 38 59 60 3
58 31 61 62 43 41 40 39 44 1
45 46 50 49 56 57 51 53 47 54 48 55 UFSAR Revision 30.0
Revision: 19.3 Change
Description:
UCR-1748 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-35 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Steam Line Break
( P55-25 )
This Figure is representative and should not be used as input in other analyses.
UFSAR Revision 30.0
Revision: 19.3 Change
Description:
UCR-1748 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-36 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Steam Line Break
( P56-25 )
This Figure is representative and should not be used as input in other analyses.
UFSAR Revision 30.0
Revision: 19.3 Change
Description:
UCR-1748 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-37 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Steam Line Break
( P57-25 )
This Figure is representative and should not be used as input in other analyses.
UFSAR Revision 30.0
Revision: 19.3 Change
Description:
UCR-1748 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-38 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Steam Line Break
( P58-25 )
This Figure is representative and should not be used as input in other analyses.
UFSAR Revision 30.0
Revision: 19.3 Change
Description:
UCR-1748 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-39 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Steam Line Break
( P59-25 )
This Figure is representative and should not be used as input in other analyses.
UFSAR Revision 30.0
Revision: 19.3 Change
Description:
UCR-1748 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-40 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Steam Line Break
( P60-25 )
This Figure is representative and should not be used as input in other analyses.
UFSAR Revision 30.0
Revision: 19.3 Change
Description:
UCR-1748 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-41 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Steam Line Break
( P61-25 )
This Figure is representative and should not be used as input in other analyses.
UFSAR Revision 30.0
Revision: 19.3 Change
Description:
UCR-1748 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-42 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Steam Line Break
( P62-25 )
This Figure is representative and should not be used as input in other analyses.
UFSAR Revision 30.0
Revision: 19.3 Change
Description:
UCR-1748 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-43 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Steam Line Break
( P63-25 )
This Figure is representative and should not be used as input in other analyses.
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-44 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Steam Line Break
( P55-46 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-45 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Steam Line Break
( P56-47 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-46 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Steam Line Break
( P57-48 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-47 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Steam Line Break
( P60-51 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-48 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Steam Line Break
( P61-52 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-49 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Steam Line Break
( P56-58 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-50 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Steam Line Break
( P57-59 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-51 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Steam Line Break
( P60-62 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-52 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Steam Line Break
( P61-63 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-53 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Feedwater Line Break
( P55-25 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-54 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Feedwater Line Break
( P56-25 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-55 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Feedwater Line Break
( P57-25 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-56 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Feedwater Line Break
( P58-25 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-57 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Feedwater Line Break
( P59-25 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-58 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Feedwater Line Break
( P60-25 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-59 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Feedwater Line Break
( P61-25 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-60 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Feedwater Line Break
( P62-25 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-61 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Feedwater Line Break
( P63-25 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-62 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Feedwater Line Break
( P55-46 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-63 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Feedwater Line Break
( P56-47 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-64 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Feedwater Line Break
( P57-48 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-65 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Feedwater Line Break
( P60-51 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-66 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Feedwater Line Break
( P61-52 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-67 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Feedwater Line Break
( P56-58 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-68 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Feedwater Line Break
( P57-59 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-69 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Feedwater Line Break
( P60-62 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-70 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Differential Pressure Time History Steam Generator Enclosure Feedwater Line Break
( P61-63 )
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-71 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Pressure Time History Upper Compartment Element 25 Spray Line Break (When using this curve, the pressure time history should be increased by 10%.)
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-72 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Pressure Time History Pressurizer Enclosure Element 46 Spray Line Break (When using this curve, the pressure time history should be increased by 10%.)
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-73 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Pressure Time History Pressurizer Enclosure Element 47 Spray Line Break (When using this curve, the pressure time history should be increased by 10%.)
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-74 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Pressurizer Time History Pressurizer Enclosure Element 48 Spray Line Break (When using this curve, the pressure time history should be increased by 10%.)
UFSAR Revision 30.0
Unit 1 Revision: 17.1 Change
Description:
UCR-850 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.3.4-75 Sheet 1 of 1
Title:
Cook Unit 1 & 2 Pressure Time History Pressurizer Enclosure Element 49 Spray Line Break (When using this curve, the pressure time history should be increased by 10%.)
UFSAR Revision 30.0