ML21125A546

0 to Updated Final Safety Analysis Report, Chapter 14.2, Figures 14.2.5-1 to 14.2.8-8 (Unit 2)

ML21125A546
Person / Time
Site:	Cook
Issue date:	04/19/2021
From:	Indiana Michigan Power Co
To:	Office of Nuclear Reactor Regulation
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ML21126A238	List: AEP-NRC-2021-19, 0 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary ML21125A456 ML21125A457 ML21125A472 ML21125A473 ML21125A475 ML21125A482 ML21125A486 ML21125A487 ML21125A488 ML21125A493 ML21125A498 ML21125A499 ML21125A500 ML21125A501 ML21125A502 ML21125A503 ML21125A505 ML21125A508 ML21125A509 ML21125A510 ML21125A512 ML21125A514 ML21125A517 ML21125A518 ML21125A520 ML21125A521 ML21125A522 ML21125A524 ML21125A525 ML21125A526 ML21125A527 ML21125A529 ML21125A533 ML21125A534 ML21125A535 ML21125A537 ML21125A538 ML21125A539 ML21125A540 ML21125A542 ML21125A543 ML21125A545 ML21125A546 ML21125A547 ML21125A548 ML21125A550 ML21125A554 ML21125A557 ML21125A558 ... further results
References
AEP-NRC-2021-19
Download: ML21125A546 (16)

Text

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 29.0 Chapter:

14 Sheet:

1 of 1 UFSAR Figure: 14.2.5-1 Unit: 2

Title:

Variation of Reactivity with Core Temperature at 1050 psla for the End of Life Rodded Core with One Control Rod Assembly Stuck (Assumes Zero Power)

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: 14.2.5-2 Unit: 2

Title:

Doppler Power Feedback for Steam Line Break UFSAR Revision 30.0

=i n

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o-RCS PRESSURE (PSIA)

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7 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: 14.2.5-4 Unit: 2

Title:

Steam Line Break DER Inside Containment with Power Nuclear Power and Core Heat Flux Versus Time 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: 14.2.5-5 Unit: 2

Title:

Steam Line Break DER Inside Containment with Power Core Average Temperature, RCS Pressure, and Pressurizer Water Volume Versus Time 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: 14.2.5-6 Unit: 2

Title:

Steam Line Break DER Inside Containment with Power Reactivity and Core Boron Concentration Versus Time UFSAR Revision 30.0

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July 1991 UFSAR Revision 30.0

1600.

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102 10 Figure 14.2.8-2 Feedline Break with Power Pressurizer Pressure and Pressurizer Water Volume Versus Time UNIT 2

July 1991 UFSAR Revision 30.0

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l 1400.

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I.3 IO Figure 14.2.8-4 Feedline Break with Power Steam Generator Mass and Steam Generator Pressure Versus Time UNIT 2

July 1991 UFSAR Revision 30.0

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100 IO 100 IO' 102 103 IO' TlR@

csttt 14.2.8-5 Feedline Break without Power Nuclear Power and Care Heat Flux Versus lime UNIT 2 July 1991 UFSAR Revision 30.0

PRESSURIZCR Vf-iICR VOLUtlf lCUBlC FCEI)

PRCSSURIZCR PRCSSURE IPSIfkI UFSAR Revision 30.0

bb0.

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Figure 14.2.8-7 Feedline Break without Power Faulted and Non-faulted Loop Temperatures Versus Time UNIT 2

UFSAR Revision 30.0

INTACT 5

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1400.

1200.

1000.

000.

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INTACT 100 101 102 103 IO txne 1sct1 Figure 14.2.8-8 Feedline Break without Power Steam Generator Mass and Steam Generator Pressure Versus Time UNIT 2 July 1991 UFSAR Revision 30.0