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