ML21125A514

0 to Updated Final Safety Analysis Report, Chapter 7, Figures

ML21125A514
Person / Time
Site:	Cook
Issue date:	04/19/2021
From:	Indiana Michigan Power Co
To:	Office of Nuclear Reactor Regulation
Shared Package
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References
AEP-NRC-2021-19
Download: ML21125A514 (22)

Text

I I

LOG C

M ATR CES OVERTEMPERATURE T TRIP LOW-LOW STEAM GENERATOR WATER LEVEL TRIP LOW FEEDWATER FLOW TRIP TAVG T

REACTOR COOLANT PRESSURE OVERPOWER T TRIP T

TAVG FLUX DIFFERENCE RESET FROM TOP AND BOTTOM LONG ION CHAMBERS INTERLOCKS REACTOR TRIP BREAKERS LOW REACTOR COOLANT FLOW TRIP TURBINE GENERATOR TRIP REACTOR COOLANT PUMP BREAKER TRIP PRESSURIZER LOW PRESSURE TRIP PRESSURIZER HIGH LEVEL TRIP SOURCE RANGE NEUTRON FLUX TRIP HIGH INTERMEDIATE RANGE NEUTRON FLUX TRIP POWER RANGE NEUTRON FLUX TRIP (LOW) SETTING UNDER-VOLTAGE PRESSURIZER HIGH PRESSURE TRIP POWER RANGE POSITIVE NEUTRON FLUX RATE TRIP MANUAL TRIP SAFETY INJECTION TRIP POWER RANGE NEUTRON FLUX RATE TRIP (HIGH) SETTING Revision 21 Change

Description:

UCR-1852 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. UFSAR FIG 7.2-2 Sheet 1 of 1

Title:

REACTOR PROTECTION SYSTEMS UFSAR Revision 30.0

REVISED PER 98-UFSAR-375 CONTROL ROD BANK INSERTION MONITOR FSAR FIG. 7.2-3 SH 1 of 1 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REV. NO.

DESCRIPTION REVISIONS TITLE DWG. NO.

K 2 K 1 3

K

1. ANALOG CIRCUITRY IS USED FOR THE COMPARATOR NETWORK.

2. COMPARISON IS DONE FOR ALL CONTROL BANKS.

16.5 16.5 UFSAR Revision 30.0

UFSAR Revision 30.0

UFSAR Revision 30.0

UFSAR Revision 30.0

UFSAR Revision 30.0 UFSAR Revision 30.0

Revision 17 Change

Description:

UCR-1181 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. UFSAR FIG 7.2-8 Sheet 1 of 1

Title:

STEAM GENERATOR LEVEL PROTECTION LB-LB-LL LL LB-LL LT_

LI_

I/I 2/3 Start TDAFP 2/4 L2 L3 L4 Start MDAFP

& Trip Reactor Feedwater/Steam Flow Mismatch LB-LB-LS/

LL LL LS/

LB-LL LS/

LT_

LI_

LQ LS/

I/I Ch. I Trip Reactor 2/2 LD/

I/I LB-LB-LL LL LT_

LI_

LP/

LQ Ch.II 2/3 P-14 To Stm. Gen.

Lev. Control 1 2 3 4 II I I II Loop 1 shown, Loop 2,3,4 Similar Ch Ch.

• Ch. IV Ch. III LQ LS/

LS/

LP/

LP/

LS/

LS/

LS/

LS/

LS/

LP/

LP/

LP/

UFSAR Revision 30.0

UFSAR Revision 30.0

UFSAR Revision 30.0

UFSAR Revision 30.0

UFSAR Revision 30.0 UFSAR Revision 30.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:

7 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 30.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Chapter:

7 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)

UFSAR Revision 30.0

UFSAR Revision 30.0

t v

. _ i,.

UFSAR Revision 30.0

UFSAR Revision 30.0

PACHMS HYDROGEN ANALYZER SAMPLING PANEL I-SP-B REMOTE CONTROL PANEL I-CP-B PACHMS HYDROGEN ANALYZER SAMPLING PANEL I-SP-A REMOTE CONTROL PANEL I-CP-A SOLENOID VALVE (TYP)

CONTAINMENT SAMPLE ISOLATION VALVES OTHER CONTAINMENT AIR SAMPLES REACTOR CONTAINMENT BUILDING SCHEMATIC DIAGRAM OF POST-ACCIDENT CONTAINMENT HYDROGEN MONITORING SYSTEM (PACHMS)

FIGURE 7.8-1 SAMPLE RETURN ISOLATION VALVES Revision 17 Change

Description:

UCR-1077 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN DWG. NO. UFSAR FIG 7.8-1 Sheet 1 of 1

Title:

SCHEMATIC DIAGRAM OF POST-ACCIDENT CONTAINMENT HYDROGEN MONITORING SYSTEM (PACHMS)

UFSAR Revision 30.0

FSAR FIG. 7.8-2 ARRANGEMENT OF POST-ACCIDENT SAMPLING EQUIPMENT IN SPRAY ADDITIVE TANK ROOM REVISED PER UCR 1077 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN 17 REV. NO.

DESCRIPTION REVISIONS DWG. NO.

TITLE SH 1 of 1 UNIT 1 UFSAR Revision 30.0

UNIT NO. 1 POST-ACCIDENT CONT. HYDROGEN FSAR FIG. 7.8 - 3 REVISED PER UCR 1077 17 FSAR FIG. 7.8 - 3 UFSAR Revision 30.0

fsar-fig-7.8-4_21-2.dgn 3/7/2008 10:56:32 AM UFSAR Revision

==30.0

DESCRIPTION==

TITLE REVISIONS DWG. NO.

NOTES:

1. UNIT NO. 1 SHOWN (UNIT NO. 2 OPPOSITE HAND)

2. REFERENCE FSAR FIG. 5.5-2A AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN REVISED PER UCR 1077 REV. NO.

17 Plan Elevation of Containment (Elevation - 650'-0") Detailing Location of Hydrogen Monitoring Sample Ports ESR-1 & 7 FSAR FIG. 7.8-5 SH 1 of 1 UNIT 1 Roof Elev.

681'-11" UFSAR Revision 30.0

FSAR FIG. 7.8-6 Plan Elevation of Containment (Elevation 633'-0") Detailing Location of Hydrogen Monitoring Sample Ports ESR-3 & 4 REVISED PER UCR 1077 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN 17 REV. NO.

DWG. NO.

DESCRIPTION REVISIONS TITLE UNIT 1 SH 1 of 1 ESR-3 (EAST)

UFSAR Revision 30.0