ML24159A177
| ML24159A177 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/30/2024 |
| From: | Indiana Michigan Power Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML24159A261 | List:
|
| References | |
| AEP-NRC-2024-20 | |
| Download: ML24159A177 (1) | |
Text
Revision: 23 Change
Description:
UCR-1969
Title:
Variation of Reactivity with Core Temperature at 1050 psia AMERICAN ELECTRIC POWER for the End of Life Rodded Core with One Control Rod COOK NUCLEAR PLANT Assembly Stuck (Zero Power) for the Steamline Break NUCLEAR GENERATION GROUP Double Ended Rupture Event BRIDGMAN, MICHIGAN Sheet 1 of 1 UFSAR Figure: 14.2.5-1
UN IT 1 Revision: 23 Change
Description:
UCR-1969
Title:
Doppler Power Feedback for the Steamline Break AMERICAN ELECTRIC POWER Double Ended Rupture Event COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN Sheet 1 of 1 UFSAR Figure: 14.2.5-2
UN IT 1 moo
400,...,...... I...... 1,..
\\
\\
n I 0 5 10 15 20 25 30 35 40 45 50 Cold Leg Safety injection [Ibmkec]
DONAWC.COOK NUCLEARPLANT UNIT1
FIGURE 14.2.5-3
Safety Injection Flow Supplied By One Charging Pump For The Suamhnc Break Double Ended Ruprurc Event JULY 1997 Revision: 23 Change
Description:
UCR-1969
Title:
Nuclear Power and Core Heat Flux vs. Time for the AMERICAN ELECTRIC POWER Steamline Break Double Ended Rupture Event COOK NUCLEAR PLANT [Downstream of the Flow Restrictor with Offsite Power Available]
NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN Sheet 1 of 1 UFSAR Figure: 14.2.5-4
UN IT 1 Revision: 23 Change
Description:
UCR-1969
Title:
Core Average Temperature and RCS Pressure vs. Time AMERICAN ELECTRIC POWER for the Steamline Break Double Ended Rupture Event COOK NUCLEAR PLANT [Downstream of the Flow Restrictor with Offsite Power Available]
NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN Sheet 1 of 1 UFSAR Figure: 14.2.5-5
UN IT 1 Revision: 23 Change
Description:
UCR-1969
Title:
Pressurizer Water Volume vs. Time for the Steamline AMERICAN ELECTRIC POWER Break Double Ended Rupture Event COOK NUCLEAR PLANT [Downstream of the Flow Restrictor with Offsite Power Available]
NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN Sheet 1 of 1 UFSAR Figure: 14.2.5-6
UN IT 1 Revision: 23 Change
Description:
UCR-1969
Title:
Reactivity and Core Boron Concentration vs. Time for AMERICAN ELECTRIC POWER the Steamline Break Double Ended Rupture Event COOK NUCLEAR PLANT [Downstream of the Flow Restrictor with Offsite Power Available]
NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN Sheet 1 of 1 UFSAR Figure: 14.2.5-7
INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 1
UFSAR Figure: 14.2.5-8 Change
Description:
UCR-2054, Rev. 0 Unit 1
Title:
N uclear Power and Core Heat Flux vs Time for the Rupture of a Steam Pipe from Hot Full Power Event -
(0.89 ft2 Break, Largest Break Size to Trip on OPT)
UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 1
UFSAR Figure: 14.2.5-9 Change
Description:
UCR-2054, Rev. 0 Unit 1
Title:
Pressurizer Pressure and M ix ture V olume vs Time for the Rupture of a Steam Pipe from Hot Full Power Event - (0.89 ft2 Break, Largest Break Size to Trip on OPT)
UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 1
UFSAR Figure: 14.2.5-10 Change
Description:
UCR-2054, Rev. 0 Unit 1
Title:
V essel I nlet Temperature and SG Pressure vs Time for the Rupture of a Steam Pipe from Hot Full P o wer Event - (0.89 ft2 Break, Largest Break Size to Trip on OPT)
UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Chapter: 14 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 1
UFSAR Figure: 14.2.5-11 Change
Description:
UCR-2054, Rev. 0 Unit 1
Title:
Loop Steam Flow and Tnal vse for theuprefameromot Fuowerven -
(0.t2 Break,gtreakioripnP T)
DONALD C. COOK NucLEARPuNT UNIT1
FIGURE 14.26 1 Nudur Power vs.Tim For TIE Rod Ejection Evenf Hot Zero Power. EIKI Of Life
JULY 1997
- II Fuel Centdim
DONALD C. COOK NUCLEARPLANT UNIT1
FIGURE 14.2.62 Fuel CeatatiDt, Fuel Avenge, and Clad Outer Surfrce Tc~ vs.Trmc For l-be Rod I Ejection Evmt, Hot Zero Power, End Of Lik JULY 1997 DONALD C. COOK NIT-PLANT L UNlTl
Nuclear Power vs.Tim For Tk Rod Ejection Event.
Hot FuIl Power, End Of Life
JULY 1997 I
clad outer surfpa
DONALDCCOOK Nu-m r - UNIT1
FIGURE 14.264 cIentm+, F\\wl Avenge, and cladoutcrsurf~T~ m.Time For Tbc Rod Ejectioa Event, Hot Full Power, End Oftife
JULY 1997