ML24159A175
ML24159A175 | |
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: ML24159A175 (1) | |
Text
POW ER RANGE POSITIVE NEUTRON FLUX RATE TRIP
POW ER RANGE NEUTRON FLUX RATE TRIP (HIGH) SETTING PRESSURIZER HIGH PRESSURE TRIP MANUAL TRIP SAFETY INJECTION TRIP
SOURCE RANGE NEUTRON FLUX TRIP L O
HIGH INTERMEDIATE RANGE NEUTRON FLUX TRIP G I
C POW ER RANGE NEUTRON FLUX TRIP (LOW ) SETTING M A
UNDER-VOLTAGE T R
I REACTOR C
E TRIP TURBINE GENERATOR TRIP INTERLOCKS S BREAKERS REACTOR COOLANT PUMP BREAKER TRIP LOW REACTOR COOLANT FLOW TRIP PRESSURIZER LOW PRESSURE TRIP PRESSURIZER HIGH LEVEL TRIP
LOW -LOW STEAM GENERATOR W ATER LEVEL TRIP LOW FEEDW ATER FLOW TRIP T
TAVG OVERPOW ER FLUX DIFFERENCE RESET T TRIP FROM TOP AND BOTTOM LONG ION CHAMBERS T OVERTEMPERATURE TAVG T TRIP REACTOR COOLANT PRESSURE
Revision 21 Change
Description:
UCR-1852
AMERICAN ELECTRIC POWER
Title:
REACTOR PROTECTION SYSTEMS COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGM AN, MICHIGAN DWG. NO. UFSAR FIG 7.2-2 Sheet 1 of 1 16.5
K 2
K 1 3K
- 1. ANALOG CIRCUITRY IS USED FOR THE COMPARATOR NETWORK.
- 2. COMPARISON IS DONE FOR ALL CONTROL BANKS.
16.5 REVISED PER 98-UFSAR-375
REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE CONTROL ROD BANK INSERTION COOK NUCLEAR PLANT MONITOR NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 7.2-3 SH 1 of 1
Ch.
- Ch. IVCh. III
LT_ LT_ LT_
LP/ LS/ LP/ LP/LS/LS/
LQ LP/ LP/ LP/LQLQ
I/I I/I I/I Feedwater/Steam LD/ To Stm. Gen. Flow Mismatch LI_ Lev. Control LI_ LI_
LB-LB-Ch. I Ch.II
LB-LB-LB-LB-LB-LB-
LS/ LS/
- 1 2 3 4 Ch II I I II
Loop 1 shown, L2 L3 L4 Loop 2,3,4 Similar 2/3 2/3 2/2
P-14 Start MDAFP Trip Reactor
& Trip 2/4 Reactor Start TDAFP
Revision 17 Change
Description:
UCR-1181
AMERICAN ELECTRIC POWER
Title:
STEAM GENERATOR LEVEL PROTECTION COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. UFSAR FIG 7.2-8 Sheet 1 of 1
UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Chapter: 7 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 1
UFSAR Figure: 7.5-3A Change
Description:
UCR-2054, Rev. 0 Unit 1
Title:
Environmental Conditions Inside Containment - Main Steam Break (Unit 1)
UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Chapter: 7 UPDATED FINAL SAFETY ANALYSIS REPORT Sheet: 1 of 1
UFSAR Figure: 7.5-3B Change
Description:
UCR-2054, Rev. 0 Unit 2
Title:
Environmental Conditions Inside Containment - Main Steam Break (Unit 2)
REMOTE CONTROL PANEL I-CP-A
SOLENOID VALVE (TYP)
OTHER CONTAINMENT PACHMS HYDROGEN REACTOR AIR SAMPLES ANALYZER SAMPLING CONTAINMENT PANEL I-SP-A BUILDING
REMOTE CONTROL PANEL I-CP-B
CONTAINMENT SAMPLE ISOLATION VALVES PACHMS HYDROGEN ANALYZER SAMPLING PANEL I-SP-B
SAMPLE RETURN ISOLATION VALVES
FIGURE 7.8-1
SCHEMATIC DIAGRAM OF POST-ACCIDENT CONTAINMENT HYDROGEN MONITORING SYSTEM (PACHMS)
Revision 17 Change
Description:
UCR-1077
AMERICAN ELECTRIC POWER
Title:
SCHEMATIC DIAGRAM OF POST-ACCIDENT CONTAINMENT HYDROGEN COOK NUCLEAR PLANT MONITORING SYSTEM (PACHMS)
NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. UFSAR FIG 7.8-1 Sheet 1 of 1 17 REVISED PER UCR 1077 UNIT 1
REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE ARRANGEMENT OF POST-ACCIDENT SAMPLING EQUIPMENT IN COOK NUCLEAR PLANT SPRAY ADDITIVE TANK ROOM NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO.FSAR FIG. 7.8-2 SH 1 of 1 17 REVISED PER UCR 1077
UNIT NO. 1 POST-ACCIDENT CONT. HYDROGEN
FSAR FIG. 7.8 - 3 fsar-fig-7.8-4_21-2.dgn 3/7/2008 10:56:32 AM NOTES: Roof
- 1. UNIT NO. 1 SHOWN (UNIT NO. 2 OPPOSITE HAND) Elev.
- 2. REFERENCE FSAR FIG. 5.5-2A 681'-11"
17 REVISED PER UCR 1077 UNIT 1
REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE Plan Elevation of Containment (Elevation - 650'-0") Detailing Location COOK NUCLEAR PLANT of Hydrogen Monitoring Sample Ports ESR-1 & 7 NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 7.8-5 SH 1 of 1 ESR-3 (EAST)
17 REVISED PER UCR 1077 UNIT 1
REV. NO. DESCRIPTION REVISIONS AMERICAN ELECTRIC POWER TITLE Plan Elevation of Containment (Elevation 633'-0") Detailing COOK NUCLEAR PLANT Location of Hydrogen Monitoring Sample Ports ESR-3 & 4 NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 7.8-6 SH 1 of 1