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
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: ML21125A514 (22)

Text

UFSAR Revision 30.0 POWER RANGE POSITIVE NEUTRON FLUX RATE TRIP POWER 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 POWER RANGE NEUTRON FLUX TRIP (LOW) SETTING M A

T UNDER-VOLTAGE R I

C REACTOR 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 WATER LEVEL TRIP LOW FEEDWATER FLOW TRIP T

TAVG OVERPOWER 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 BRIDGMAN, MICHIGAN DWG. NO. UFSAR FIG 7.2-2 Sheet 1 of 1

UFSAR Revision 30.0 16.5 K

2 K K 1 3

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 TITLE AMERICAN ELECTRIC POWER CONTROL ROD BANK INSERTION COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP MONITOR BRIDGMAN, MICHIGAN DWG. NO. FSAR FIG. 7.2-3 SH 1 of 1

UFSAR Revision 30.0 UFSAR Revision 30.0 UFSAR Revision 30.0 UFSAR Revision 30.0 UFSAR Revision 30.0

UFSAR Revision 30.0 Ch.

• Ch. III Ch. IV LT_ LT_ LT_

LP/ LS/ LP/ LS/ LP/ LS/

LQ LP/ LQ LP/ LQ LP/

I/I I/I I/I Feedwater/Steam To Stm. Gen.

LD/ Flow Mismatch Lev. Control LI_ LI_ LI_

LB- LB-Ch. I Ch.II LB- LB- LB- LB- LB- LB-LS/ LS/

LL LL LS/ LS/ LS/ LS/ LS/ LS/

LL LL LL LL LL LL

• 1 2 3 4 Ch II I I II Loop 1 shown, 2/3 2/3 L2 L3 L4 2/2 Loop 2,3,4 Similar 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 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 Revised: 27.0 D. C. COOK NUCLEAR PLANT Chapter: 7 Sheet: 1 of 1 UPDATED FINAL SAFETY ANALYSIS REPORT Change

Description:

UFSAR Figure: 7.5-3A Unit 1 UCR-2054, Rev. 0

Title:

Environmental Conditions Inside Containment - Main Steam Break (Unit 1)

UFSAR Revision 30.0 INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Chapter: 7 Sheet: 1 of 1 UPDATED FINAL SAFETY ANALYSIS REPORT Change

Description:

UFSAR Figure: 7.5-3B Unit 2 UCR-2054, Rev. 0

Title:

Environmental Conditions Inside Containment - Main Steam Break (Unit 2)

UFSAR Revision 30.0 t

v

. _ i, .

.. UFSAR Revision 30.0

UFSAR Revision 30.0 UFSAR Revision 30.0 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

UFSAR Revision 30.0 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

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

1. UNIT NO. 1 SHOWN (UNIT NO. 2 OPPOSITE HAND) 681'-11"

2. REFERENCE FSAR FIG. 5.5- 2A 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

UFSAR Revision 30.0 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