ML24159A223

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Updated Final Safety Analysis Report (Ufsar), Revision 32, Chapter 7, Tables
ML24159A223
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 05/30/2024
From:
Indiana Michigan Power Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML24159A261 List: ... further results
References
AEP-NRC-2024-20
Download: ML24159A223 (1)
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IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 21.2 Table:

7.2-1 Page:

1 of 5 LIST OF REACTOR TRIPS AND ACTUATION MEANS OF: ENGINEERED SAFETY FEATURES, CONTAINMENT AND STEAM LINE ISOLATION & AUXILIARY FEEDWATER Initiator Coincidence Circuitry and Interlocks Comments Reactor Trip

1.

Manual 1/2, no interlocks

2.

Neutron flux (Power Range):

2A.

High neutron flux 2/4, low setpoint interlocked with P-10 High and low settings; manual block and automatic reset of low setting by P-10, Table 7.2-2 2B.

High positive neutron flux rate 2/4, no interlocks

3.

Overtemperature T 2/4, no interlocks

4.

Overpower T 2/4, no interlocks

5.

Low pressurizer pressure 2/4, interlocked with P-7

6.

High pressurizer pressure 2/4, no interlocks

7.

High pressurizer water level 2/3, interlocked with P-7

8.

Low reactor coolant flow 2/3 signals per loop, interlocked with P-7 and P-8 Blocked below P-7. Low flow in 1 loop permitted below P-8.

9.

Monitored electrical supply to reactor coolant pumps:

9A.

Undervoltage 2/4, interlocked with P-7 2/4 bus undervoltage signals will actuate a reactor trip (interlocked with P-7) and will also actuate the autostart of the turbine driven auxiliary feedwater pump (not interlocked with P-7).

9B.

Underfrequency 2/4, interlocked with P-7 2/4 underfrequency signals will actuate a reactor trip:

(interlocked with P-7).

UFSAR Revision 32.0

IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 21.2 Table:

7.2-1 Page:

2 of 5 LIST OF REACTOR TRIPS AND ACTUATION MEANS OF: ENGINEERED SAFETY FEATURES, CONTAINMENT AND STEAM LINE ISOLATION & AUXILIARY FEEDWATER Initiator Coincidence Circuitry and Interlocks Comments 9C.

Reactor coolant pump breaker position 2/4, interlocked with P-7 2/4 breakers open will cause a reactor trip above P-7.

Blocked below P-7.

10.

Safety injection signal Manual 1/2 panel switches (per train).

2/3 low pressurizer pressure.

2/3 high containment pressure.

2/3 differential steam line pressure signals of one line compared with the other three lines.

2/4 Low steam line pressure.

Trips main feedwater pumps. Closes feedwater control valves. Closes feedwater isolation valves. Initiates Phase A isolation. Actuation by pressurizer pressure may be manually blocked below P11 and is automatically unblocked above P-11.

2/3 high containment pressure actuates the Containment Air Recirculation Hydrogen Skimmer System Fans.

11.

Turbine-generator trip Interlocked with P-8 OR 4/4 stop valves closed signal interlocked P-8.

31 percent power (P-8)

12.

Low Feedwater Flow 1/2 steam/feedwater flow mismatch in coincidence with 1/2 low steam generator water level, per loop.

13.

Low-low steam generator water level 2/3, per loop

14.

Intermediate range neutron flux 1/2, manual block permitted by P-10 Manual block and automatic reset

15.

Source range neutron flux 1/2, manual block permitted by P-6, interlocked with P-10 Manual block and automatic reset Containment Isolation Actuation

16.

Containment pressure Same as Item 10 or 1/2 manual Actuates all non-essential process lines containment isolation trip valves. (Isolation Phase A)

Coincidence of 2/4 containment Hi-Hi pressure or 1/2 manual Actuates all remaining trip valves (except those required for operation of engineered safeguard system).

(Isolation Phase B)

UFSAR Revision 32.0

IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 21.2 Table:

7.2-1 Page:

3 of 5 LIST OF REACTOR TRIPS AND ACTUATION MEANS OF: ENGINEERED SAFETY FEATURES, CONTAINMENT AND STEAM LINE ISOLATION & AUXILIARY FEEDWATER Initiator Coincidence Circuitry and Interlocks Comments

17.

High containment activity 1/3 high activity signal, from containment area, air particulate, or noble gas monitors or manual initiation of Phase A or Phase B isolation Closes containment purge supply, exhaust ducts and all other necessary to isolate containment atmosphere.

(Containment Ventilation Isolation)

Engineering Safeguards Systems Actuation

18.

Safety injection signal See Item 10

19.

Containment spray signal Hi-Hi-containment pressure (2/4) or manual 1/1 (per train)

20.

NaOH addition Containment Spray Actuation Signal Steam Lines Isolation Actuation

21.

Steam flow High Steam flow (any 2 steam lines out of 4) coincident with low-low Tavg.

22.

Steamline Pressure 2/4 Low Steamline Pressure

23.

Containment pressure 2/4 Hi-Hi containment pressure signal

24.

Manual (per steam line) 1/1 per steam line (per train)

UFSAR Revision 32.0

IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 21.2 Table:

7.2-1 Page:

4 of 5 LIST OF REACTOR TRIPS AND ACTUATION MEANS OF: ENGINEERED SAFETY FEATURES, CONTAINMENT AND STEAM LINE ISOLATION & AUXILIARY FEEDWATER Initiator Coincidence Circuitry and Interlocks Comments Auxiliary Feedwater Actuation

24.

Turbine driven pump Coincidence of 2/3 low-low level in two steam generators or undervoltage on 2/4 RCP busses or 3/4 low feedwater flow coincident with power above 40% (AMSAC) or manual (local and remote) 2/3 high level in steam generator trips main feedwater pumps

25.

Motor driven pumps 2/3 low-low level in any steam generator: or trip of both main feedwater pumps, or safety injection signal, manual (local and remote); 3/4 low feedwaterflow coincident with power 40%

(AMSAC); or 2/3 per bus (T11A, T11D) to start pump; valve actuation or 2/3 per bus on 2 busses (T11A and T11B or T11C and T11D)

Main Feedwater Isolation

26.

Safety Injection See No. 10 Feedwater isolation signal closes main feedwater control valves (fast closure) and feedwater isolation valves. SI signal also trips main feedwater pumps which causes subsequent feedwater pump discharge valve closure.

27 Hi-Hi Steam Generator level.

2/3 high-high in 1/4 steam generators.

Feedwater isolation signal closes main feedwater control valves (fast closure) and feedwater isolation valves. Hi-Hi steam generator level signal also trips main feedwater pumps which causes subsequent feedwater pump discharge valve closure.

UFSAR Revision 32.0

IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 21.2 Table:

7.2-1 Page:

5 of 5 LIST OF REACTOR TRIPS AND ACTUATION MEANS OF: ENGINEERED SAFETY FEATURES, CONTAINMENT AND STEAM LINE ISOLATION & AUXILIARY FEEDWATER Initiator Coincidence Circuitry and Interlocks Comments 28 Reactor Trip Reactor Trip coincident with low Tavg.

(Interlock P-4, see Table 7.2-2)

Feedwater isolation signal closes main feedwater control valves (fast closure) and feedwater isolation valves.

Interlock P-4 signal also trips main feedwater pumps which causes subsequent feedwater pump discharge valve closure UFSAR Revision 32.0

IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 21.2 Table:

7.2-2 Page:

1 of 4 INTERLOCK CIRCUITS Note: Where applicable setpoints can be found in the Technical Specifications for each unit, or in appropriate engineering documents.

Designation Derivation Function P-4 1/2 Reactor trip breakers and its corresponding bypass breaker open Actuates main turbine trip.

Initiates feedwater isolation on Tavg below setpoint.

Actuates main feedwater pump trip.

Blocks re-actuation of safety injection after manual reset of safety injection actuation signal.

P-6 1/2 Intermediate range neutron flux above setpoint Allows manual block of source range reactor trip.

P-6 Reset 2/2 Intermediate range neutron flux below reset point Prevents or defeats the manual block of source range reactor trip.

P-7 Enabled by P-10 or P 2/4 Power range neutron flux channels above setpoint (P-10) or 1/2 turbine first stage pressure above setpoint (P-13)

Permits reactor trip when any of the following conditions are sensed:

Greater than one loop reactor coolant flow low Greater than one reactor coolant pump breaker open Reactor coolant pump bus undervoltage or underfrequency Pressurizer low pressure Pressurizer high level P-7 Reset P-10 reset and P-13 reset Prevents or defeats the reactor trip when any of the following conditions are sensed:

Greater than one loop reactor coolant flow low Greater than one reactor coolant pump breaker open Reactor coolant pump bus undervoltage or underfrequency Pressurizer low pressure Pressurizer high level UFSAR Revision 32.0

IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 21.2 Table:

7.2-2 Page:

2 of 4 INTERLOCK CIRCUITS Note: Where applicable setpoints can be found in the Technical Specifications for each unit, or in appropriate engineering documents.

Designation Derivation Function P-8 2/4 power range channels above setpoint Prevents or defeats the automatic block of reactor trip on low coolant flow condition in a single loop.

Permits reactor trip when the Turbine Trip condition is sensed.

P-8 Reset 3/4 NIS power range channels below reset point Permits the automatic block of reactor trip on low flow in a single loop.

Prevents or defeats the reactor trip when the Turbine Trip condition is sensed.

P-10 2/4 power range neutron flux channels above setpoint Inputs to P-7 permissive.

Permits the manual block of reactor trip on:

Intermediate range high neutron flux level.

Power range channel low setpoint high neutron flux level.

Permits manual block of intermediate range channel rod stop.

Permits automatic block of source range channel trip.

P-10 Reset 3/4 power range channels below reset point Prevents or defeats the manual block of reactor trip on:

Intermediate range channel high neutron flux level.

Power range channel low setpoint high neutron flux level.

Prevents or defeats the manual block of intermediate range channel rod stop.

P-11 2/3 pressurizer pressure below setpoint Permits manual block of safety injection actuation on low pressurizer pressure.

P-11 Reset 2/3 pressurizer pressure above reset point Prevents or defeats manual block of safety injection actuation on low pressurizer pressure.

P-12 2/4 Tavg channels below setpoint Permits manual block of safety injection on low steam line pressure.

Permits or causes steam line isolation on high steam line flow.

Blocks condenser steam dump.

UFSAR Revision 32.0

IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 21.2 Table:

7.2-2 Page:

3 of 4 INTERLOCK CIRCUITS Note: Where applicable setpoints can be found in the Technical Specifications for each unit, or in appropriate engineering documents.

Designation Derivation Function P-12 Reset 3/4 Tavg channels above reset point Prevents or defeats manual block of safety injection on low steam line pressure.

Prevents or defeats steam line isolation on high steam flow.

Permits condenser steam dump.

P-13 1/2 turbine first stage pressure channel above setpoint Inputs to P-7.

P-13 Reset 2/2 turbine first stage pressure below reset point Inputs to P-7.

P-14 2/3 hi-hi steam generator level (any steam generator) greater than or equal to setpoint Permits the initiation of:

Feedwater isolation Main feedwater pump trip.

Main turbine trip.

P-14 Reset 2/3 hi-hi steam generator level (any steam generator) less than or equal to reset point Prevents or defeats initiation of:

Feedwater isolation.

Main feedwater pump trip.

Min turbine trip.

C-1 1/2 Intermediate range neutron flux above setpoint Blocks automatic and manual control rod withdrawal.

May be manually blocked above P-10.

Automatically unblocked below P-10.

C-2 1/4 Power range neutron flux above setpoint Blocks automatic and manual control rod withdrawal.

C-3 2/4 Overtemperature Delta T above setpoint Blocks automatic and manual control rod withdrawal.

Actuates turbine runback via load reference.

C-4 2/4 overpower Delta T channels above setpoint Blocks automatic and manual rod withdrawal and initiates turbine runback C-5 Turbine impulse pressure equivalent below setpoint Blocks automatic rod withdrawal UFSAR Revision 32.0

IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 21.2 Table:

7.2-2 Page:

4 of 4 INTERLOCK CIRCUITS Note: Where applicable setpoints can be found in the Technical Specifications for each unit, or in appropriate engineering documents.

Designation Derivation Function C-7A, C-B 1/1 Time Derivative (absolute value) of turbine First Stage pressure (decrease only) above setpoint Makes steam dump valves available for either tripping or modulation.

C-8 2/3 Turbine Emergency Trip Fluid pressure below setpoint or 4/4 stop valves closed Blocks steam dump control via load rejection T avg controller.

2/3 Turbine emergency trip fluid pressure above setpoint or 4/4 stop valves not closed Blocks steam dump control via turbine trip T avg controller.

C-9 Any condenser vacuum above setpoint or All circulation water pump breakers open or Loss of CRID II Power Blocks steam dump to condenser.

C-11 Control Bank D demand signal above withdrawal limit setpoint Blocks automatic control rod withdrawal.

C-20 2/2 Turbine first stage pressure high Defeats the block of AMSAC.

UFSAR Revision 32.0

IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.1 Table:

7.2-3 Page:

1 of 1 ROD STOPS Rod Stop Designation Rod Motion Blocked Nuclear Overpower

a. Intermediate Range C-1 Automatic and manual withdrawal
b. Power Range C-2 Automatic and manual withdrawal High T:
a. Over-temperature C-3 Automatic and manual withdrawal
b. Over-power C-4 Automatic and manual withdrawal Turbine Power:
a. Low Demand C-5 Automatic withdrawal
b. High Demand C-11 Automatic withdrawal See Table 7.2-2 for more detail.

May be manually overridden above interlock P-10.

Automatically re-instated below interlock P-10.

UFSAR Revision 32.0

IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision:

17 Table:

7.2-4 Page:

1 of 1 SYMBOLS AND ABBREVIATIONS TL Channel in Test Warning Lamp

  • L Test Lamp L/L Lead/Lag Unit I/I Signal Isolator
  • P/

Test Point

  • D/

Computer Input

  • S/

Test Switch

  • T_

Transmitter

  • Q_

Power Supply

  • I-Indicator De-energize (trip) on signal set point
  • B-Signal Monitor (Bistable)
  • B-
  • B-Signal Monitor (Bistable)

De-energize (trip) on signal set point Energize (trip) on signal set point Signal Monitor (Bistable)

ABBREVIATIONS DNBR Departure from nucleate boiling ratio TH Reactor Coolant Hot Leg temperature TC Reactor Coolant Cold Leg temperature Tavg (TH+TC (per loop)

T TH - TC (per loop)

AUCT Auctioneered (highest)

LVDT Linear Variable Differential Transformer (position sensor)

Ch.

Protection channel S. I.

Safety Injection MDAFP Motor Driven Auxiliary Feedwater Pump TDAFP Turbine Driven Auxiliary Feedwater Pump CIA Containment Isolation Phase "A" CIB Containment Isolation Phase "B" CVI Containment Ventilation Isolation FWI Feedwater Isolation SLI Steam Line Isolation CTS Containment Spray WR Rec.

Wide Range Recorder NR Rec.

Narrow Range Recorder

  • =P=Pressure Channel
  • =L=Level Channel UFSAR Revision 32.0

IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.2 Table:

7.2-5 Page:

1 of 2 PROCESS CONTROL BLOCK DIAGRAM DRAWING INDEX Item #

Function Drawing #

Drawing Title 1

Index 2

Reactor Coolant Flow Protection Set I 99010 Reactor Coolant Flow Loops 1,2,3,4 3

Reactor Coolant Flow Protection Set II 99010 Reactor Coolant Flow Loops 1,2,3,4 4

Reactor Coolant Flow Protection Set III 99010 Reactor Coolant Flow Loops 1,2,3,4 5

Wide-Range Reactor Coolant Temp. (Hot Leg)

Control 99029 Wide Range Reactor Coolant Temp &

Press 6

Wide-Range Reactor Coolant Temp. (Cold Leg)

Control 99029 Wide Range Reactor Coolant Temp &

Press 7

Loop 1 T/AVG Protection Set I 99001 Reactor Coolant Delta T Protection Channel 1 8

Loop 2 T/AVG Protection Set II 99002 Reactor Coolant Delta T Protection Channel 2 9

Loop 3 T/AVG Protection Set III 99003 Reactor Coolant Delta T Protection Channel 3 10 Loop 4 T/AVG Protection Set IV 99004 Reactor Coolant Delta T Protection Channel 4 11 Pressurizer Levels Protection Set I, II, III 99031 Pressurizer, RWST, & Condensate Storage Tank Levels 12 Pressurizer Pressure Protection Set I Thru IV 99022 Pressurizer Pressure CH 1,2, & 3 13 Pressurizer Pressure Protection Set I Thru IV 99034 Stm Gen Hdr Press Ch 3,4 Pressurizer Pressure Ch 4& Lower Containment Press Channel 4 14 Steam Generators 1 & 2 Mismatch Protection Set I 99012 Steam Generator 1 & 2 Mismatch Channel 1 15 Steam Generators 3 & 4 Mismatch Protection Set I 99014 Steam Generators 3 & 4 Mismatch Channel 1 16 Steam Generators 1 & 3 Mismatch Protection Set II 99015 Steam Generators 1 & 3 Mismatch Channel 2 17 Steam Generators 2 & 4 Mismatch Protection Set II 99013 Steam Generator 2 & 4 Mismatch Channel 2 18 Steam Generator Levels Protection Set I, II 99032 Steam Generator Level Channel 1 & 2 19 Turbine Impulse Chamber Pressure Protection Set I, II 99033 Upper & Lower Containment Ch.

1,2,3 & Turbine Impulse Ch. 1, 2 Pressure 20 Steam Generator Levels Protection Set III 99018 Steam Generator level Channel 3 21 Steam Generator Levels Protection Set IV 99019 Steam Generator level Channel 4 UFSAR Revision 32.0

IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.2 Table:

7.2-5 Page:

2 of 2 PROCESS CONTROL BLOCK DIAGRAM DRAWING INDEX Item #

Function Drawing #

Drawing Title 22 Steam Pressures Protection Set III, IV 99034 Stm Gen Hdr Press Ch. 3,4 Pressurizer Pressure Ch. 4 & Lower Containment Press Channel 4 23 None 24 Rod Control Control 99007 Rod Control 25 Rod Control Control 99007 Rod Control 26 Steam Dump Feed Pump Speed Control Control 99008 Steam Dump, Turbine & Feed Pump Control 27 Pressurizer Pressure Control Control 99023 Prz pressure Control 28 Pressurizer Level Control Control 99024 Pressurizer Level Control System 29 Volume Control Tank Level Control Control 99027 RWST, CST and VCT Level 30 Boric Acid Blend Control Control 99061 Boric Acid and Primary Water 31 Rod Insertion Limit Control 99006 Rod Insertion Limits 32 T/Auctioneered T Deviation Alarms Control 99005 Tavg & T/Auctioneered Tavg & T Deviation Alarms 33 TAVG/Auctioneered TAVG Deviation Alarms Control 99005 Tavg & T/Auctioneered Tavg & T Deviation Alarms 34 Steam Generator Level Control Control 99016 Steam Generators 1,2 & 3 Level Control System 35 Steam Generator Level Control Control 99017 S. G. #4 Level Control 36 Steam Generator Level (Wide Range)

Control 99020 Steam Pressure & Wide Range S.G.

Level 37 T & T - S.P. Recording Control 99001 Reactor Coolant Delta T Protection Channel 1 UFSAR Revision 32.0

IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 21.2 Table:

7.2-6 Page:

1 of 1 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES1 Functional Unit Response Time 1

Power Range, Neutron Flux (High and Low setpoint)

Less than or equal to 0.5 seconds 2 2

Overtemperature T For Unit 1, see Table 14.1-2 (2)

For Unit 2, see Table 14.1.0-4(2) 3 Overpower T For Unit 1, see Table 14.1-2 For Unit 2, see Table 14.1.0-4 4

Pressurizer Pressure - Low Less than or equal to 2.0 seconds 5

Pressurizer Pressure - High Less than or equal to 2.0 seconds 6

Pressurizer Water Level - High Less than or equal to 2.0 seconds 7

Loss of Flow - Single Loop (Above P-8)

Less than or equal to 1.0 seconds 8

Loss of Flow - Two Loops (Above P-7 and below P-8)

Less than or equal to 1.0 seconds

9.

Steam Generator Water Level -Low-Low Less than or equal to 2.0 seconds 10 Undervoltage - Reactor Coolant Pumps Less than or equal to 1.5 seconds 11 Underfrequency - Reactor Coolant Pumps Less than or equal to 0.6 seconds 1 Response times previously in Technical Specifications 4.3.1.1.3 as documented in Reference 19.

2 Neutron detectors are exempt from response time testing. Response time of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in the channel.

UFSAR Revision 32.0

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

7.2-7 Page:

1 of 3 Engineered Safety Feature Actuation System Response Times1 Initiating Signal and Function Response Time In Seconds

1.

Containment Pressure - High

a. Safety Injection (ECCS)

Less than or equal to 27.02 / 27.03

b. Reactor Trip (from SI)

Less than or equal to 3.0

c. Essential Service Water System Less than or equal to 47.04
d. Containment Air Recirculation Fan Greater than or equal to 270.0 and less than or equal to 300.0 [Unit 1];

Greater than or equal to 108.0 and less than or equal to 132.0 [Unit 2]

e. Feedline Isolation Less than or equal to 44
2.

Pressurizer Pressure - Low

a. Safety Injection (ECCS)

Less than or equal to 27.02 / 27.03

b. Reactor Trip (from SI)

Less than or equal to 3.0

c. Feedwater Isolation Less than or equal to 8.0
d. Essential Service Water Less than or equal to 47. 04 1 Response times previously in Technical Specifications 4.3.2.1.3 as documented in Reference 19.

2 Diesel generator starting and sequence loading delays NOT included. Offsite power available. Response time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps. Sequential transfer of charging pump suction from the VCT to the RWST (RWST valves open, then VCT valves close) is included.

3 Diesel generator starting and sequence loading delays included. Response time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging, SI and RHR pumps. Sequential transfer of charging pump suction from the VCT to the RWST (RWST valves open, then VCT valves close) is NOT included. For Unit 1 only, an additional allowance of 20 sec. is provided from the LOCA analysis (47.0 seconds total).

4 Essential Service Water System is implicitly assumed available for safety injection and containment spray pump operability in addition to heat exchangers ultimate heat sink.

UFSAR Revision 32.0

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

7.2-7 Page:

2 of 3 Engineered Safety Feature Actuation System Response Times1 Initiating Signal and Function Response Time In Seconds

3.

Steam Line Pressure - Low

a. Safety Injection (ECCS)

Less than or equal to 27.02 / 37.05

b. Reactor Trip (from SI)

Less than or equal to 3.0

c. Feedwater Isolation Less than or equal to 8.0
d. Steam Line Isolation Less than or equal to 11.0
4.

Containment Pressure - High-High

a. Containment Spray Greater than or equal to 244.0 and less than or equal to 300.0 [Unit 1];

Less than or equal to 45.0 [Unit 2]

b. Steam Line Isolation Less than or equal to 11.0
5.

Steam Generator Water Level -High - High

a. Turbine Trip Less than or equal to 2.5
b. Feedwater Isolation Less than or equal to 11.0
6.

Steam Generator Water Level-Low - Low

a. Motor Driven Auxiliary Feedwater Pumps Less than or equal to 60.0
b. Turbine Driven Auxiliary Feedwater Pumps Less than or equal to 60.0 5 Diesel generator starting and sequence loading delays included. Response time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps. Sequential transfer of charging pump suction from the VCT to the RWST (RWST valves open, then VCT valves close) is included.

UFSAR Revision 32.0

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

7.2-7 Page:

3 of 3 Engineered Safety Feature Actuation System Response Times1 Initiating Signal and Function Response Time In Seconds

7.

4160 volt Emergency Bus Loss of Voltage

a. Motor Driven Auxiliary Feedwater Pumps Less than or equal to 60.0
8.

Loss of Main Feedwater Pumps

a. Motor Driven Auxiliary Feedwater Pumps Less than or equal to 60.0
9.

Reactor Coolant Bus Undervoltage

a. Turbine Driven Auxiliary Feedwater Pumps Less than or equal to 60.0 UFSAR Revision 32.0

IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 21.2 Table:

7.5-1 Page:

1 of 1 PROCESS INSTRUMENTATION FOR RPS & ESF ACTUATION Parameter Quantity Sensor Type Protect./Safeguards Use Taps Reactor Coolant Temperature 16 RTD T trips, Tavg permissives Installed in thermowells Pressurizer Pressure 4

Transmitter Hi/Lo pressure trips, Safety Injection 3 (top level), one shared Pressurizer Level 3

P Transmitter Reactor Trip 3 (top level), 3 (bottom level)

Steam Flow 8

P Transmitter Mismatch Trip, Safety Injection 1 pair each Feedwater Flow 8

P Transmitter Mismatch Trip 1 pair each Steam Pressure 12 Transmitter Safety Injection 1 each Steam Generator Level 12 P Transmitter Mismatch Trip, Low Level Trip 1 pair each Reactor Coolant Flow 12 P Transmitter Low Flow Trip 1 High press shared/loop, 1 Low press each Containment Pressure 4

Transmitter Safety Injection (3), Containment Spray (4) 4 Turbine 1st Stage Pressure 2

Transmitter Set Point Programs, Turbine Power permissives 1 each UFSAR Revision 32.0

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7.5-2 Page:

1 of 2 ENGINEERED SAFETY FEATURES EQUIPMENT EXPOSED TO HARSH ENVIRONMENT Equipment Quantity Inside Containment Outside Containment Operating Mode LOCA or MSLB Design Operating Duration Miscellaneous Containment Air Recirculation/

Hydrogen Skimmer Fan 2

X Approximately 2 minutes after 2/3 hi containment pressure.

1 Year Safeguards Equipment Power, Control and Instrument Cable X

X As required by equipment serviced As required by equipment serviced Valves Containment Isolation 34 14 20 2 open, 8 remain as is, 2 switch & 22 close Various ECCS Process 40 8

32 14 remain as is, 6 close & 20 switch Various Other ESF Process 38 8

30 16 open, 9 remain as is, 4 close & 9 switch Various UFSAR Revision 32.0

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2 of 2 ENGINEERED SAFETY FEATURES EQUIPMENT EXPOSED TO HARSH ENVIRONMENT Equipment Quantity Inside Containment Outside Containment Initiate LOCA or MSLB Monitor Design Operating Duration Instrumentation Auxillary Feedwater Flow 4

X X

4 Months Containment Pressure 4

X X

X X

4 Months Main Feedwater Flow 2/Stm. Gen.

X X

1 Minute Main Steam Flow 2/Stm. Gen.

X X

1 Minute Main Steam Pressure 3/Stm. Gen.

X X

X 4 Months Pressurizer Level 3

X X

4 Months Pressurizer Pressure 3

1 X

X X

X X

X X

4 Months 1 Minute Wide Range Reactor Coolant Pressure 2

X X

4 Months Narrow Range Reactor Coolant Temperature 2/Loop X

X X

1 Minute Wide Range Reactor Coolant Temperature 2/Loop X

X 4 Months Steam Generator Narrow Range Level 3/Stm. Gen.

X X

X 4 Months Containment Water Level 8

X X

4 Months Includes a redundant pair of overlapping level monitors and a redundant pair of level switches.

UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page:

1 of 51 Last Revised: 30.0 TYPE "A" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location A-1 Verify ECCS Flow Prior to Manual Stop of Reactor Coolant Pumps Flow in HPI System (Centrifugal Charging Pump Flow)

IFI-51 IFI-52 IFI-53 IFI-54 0 to 110% design flow 0-200 GPM Control Room Panel SIS A-2 Manual Trip of RC pumps based on RCS pressure RCS Pressure (wide range)

NPS-110 NPS 111 MR-13 0-3000 psig 0-3000 psig Control Room Panel SIS Control Room Panel RHR for MR-13 A-3 Not used A-4 Not used A-5 Not used A-6 Not used UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page:

2 of 51 Last Revised: 30.0 TYPE "A" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location A-7 Determination of required core exit temperature by SG pressure S/G Pressure MPP-210 MPP-211 MPP-212 MPP-220 MPP-221 MPP-222 MPP-230 MPP-231 MPP-232 MPP-240 MPP-241 MPP-242 From atmospheric pressure to 20% above the lowest safety valve setting 0-1200 psig Control Room Panel SG A-8 Determination of Adverse Containment Containment Water Level NLI-320 NLI-321 NLI-330 NLI-331 NLI-340 NLI-341 599-3 to 614 elevation (Containment floor to max flood level) 602'-2 3/4" to 613'-0" Control Room Panel RHR UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page:

3 of 51 Last Revised: 30.0 TYPE "A" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location A-9 Manual reduction of ECCS Flow (secondary heat sink capability)

S/G Level Narrow Range BLP-110 BLP-111 BLP-112 BLP-120 BLP-121 BLP-122 BLP-130 BLP-131 BLP-132 BLP-140 BLP-141 BLP-142 From below 1st stage separator to 2nd stage separator From below 1st stage separator to 2nd stage separator Control Room Panel SG A-10 Manual Reduction of ECCS Flow Pressurizer Level NLP-151 NLP-152 NLP-153 Top to Bottom 0-100% (96% of indicated volume)

Control Room Panel PRZ A-11 Not used UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

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4 of 51 Last Revised: 30.0 TYPE "A" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location A-12 Determination of adverse containment Containment Area Radiation Monitor High Range VRA-1310 VRA-1410 for U1 VRA-2310 VRA-2410 for U2 1 R/Hr to 1 x 107 R/Hr 1 R/Hr to 1 x 107 R/Hr Control Room Panel RMS-CT A-13 Manually establish or trip containment spray Containment Pressure (narrow range)

PPP-300 PPP-301 PPP-302 PPP-303

-5 to design pressure

-5 to +12 psig Control Room Panel SPY A-14 Not used UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page:

5 of 51 Last Revised: 30.0 TYPE "A" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location A-15 Manual reduction of ECCS Flow (Secondary heat sink capability)

Auxiliary Feedwater Flow FFI-210 FFI-220 FFI-230 FFI-240 0-110 % design flow 0 to 250 x 103 PPH Control Room Panel SG A-16 Manual transfer to cold leg recirculation in low level in RWST RWST Level ILS-950 ILS-951 MR-36 for ILS-950 Essentially Top (bottom of overflow) to Bottom (bottom of safety injection pipe)

(100% of total volume)

Essentially Top (bottom of overflow) to Bottom (bottom of safety injection pipe)

(100% of total volume)

Control Room Panel Spy for MR-36 Control Room Panel BA for ILS-951 UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page:

6 of 51 Last Revised: 30.0 TYPE "A" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location A-17 Manual trip or reduction of Pressurizer Spray and ECCS flow Degrees subcooling Inputs are received from variables A-2, A-25, A-38, and A-39 for Hot and Cold Leg Variables 200F subcooling to 35F superheat 425F subcooling to 75F superheat Control Room Panel BA A-18 Not used A-19 Not used A-20 Not used A-21 Not used A-22 Not used A-23 Not used A-24 Not used UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page:

7 of 51 Last Revised: 30.0 TYPE "A" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location A-25 Manual reduction of ECCS Flow Core Exit Temp SG-30 and SG-31 for TC 1-65 1 200 - 2300F 200 - 2300F Control Room Panel FI TC Readings Monitored By PPC and Recorders A-26 Not used A-27 Not used A-28 Manual Trip of RCPs CCP Breaker status Unit 1 & 2 101-TD7 (Pump PP-50E) by BKR T11D7 101-TA8 (Pump PP-50W) by BKR T11A8 Open/Close Open/Close Control Room Panel BA 1 Technical Specifications (Unit 1-3.3.3.8 and Unit 2-3.3.3.6) require two TCs per channel per quadrant minimum.

UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page:

8 of 51 Last Revised: 30.0 TYPE "A" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location A-29 Manual Trip of RCPs SI pump breaker status Unit 1 & 2 101-TD5 (Pump PP-26N) by BKR T11D5 101-TA1 (Pump PP-26S) by BKR T11A1 Open/Close Open/Close Control Room Panel SIS A-30 Not used A-31 Not used A-32 Not used A-33 Not used A-34 Manual trip of RCPs Safety Injection Pump Flow IFI-260 IFI-266 0-500 gpm 0-500 gpm Control Room Panel SIS A-35 Not used A-36 Not used UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page:

9 of 51 Last Revised: 30.0 TYPE "A" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location A-37 Not used A-38 RCS Cold Leg water temperature RCS Cold Leg water temperature MR-9 and MR-11 for NTR-210 NTR-230 50-400F 0-700F Control Room Panel DTU A-39 Core Cooling RCS Hot Leg water temperature MR-9 and MR-11 for NTR-110 NTR-130 50-700F 0-700F Control Room Panel DTU UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 10 of 51 Last Revised: 30.0 TYPE "A" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location A-40 Post-Accident Sampling Containment Containment Hydrogen concentration PAS-H2-A-CRI and PAS-H2-B-CRI for ESR-1, ESR-2, ESR-3, ESR-4, ESR-5, ESR-6, ESR-7, ESR-8, ESR-9 0 to 30 volume % for ice-condenser type containment 0-30 volume %

Control Room Panel IV A-41 CCW flow to ESF system CCW Pump Breaker Status (101-TD3) PP-10E by BKR T11D3 (101-TA7) PP-10W by BKR T11A7 Open/Close Open/Close Control Room Panel CCW UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 11 of 51 Last Revised: 30.0 TYPE "A" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location A-42 Determination of excessive fouling or blockage of recirculation sump strainers Containment Recirculation Sump Water Level NLI-300 NLI-301 Above/Below Vortex Limit Control Room Panel RHR UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 12 of 51 Last Revised: 30.0 TYPE "B" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location B-1 Reactivity Control Neutron Flux NRI-21 NRI-23 10-6 to 100% power 10-8 to 200% power Control Room Panel NIS B-2 Reactivity Control (continued)

Control Rod Position CA1-8 (U1), CB1-4 (U1)

CA1-4 (U2), CB1-8 (U2)

CC1-8 CD1-9 SA1-8 SB1-8 SC1-4 SD1-4 Full In or Not Full In Full In or Not Full In Control Room Panel RC UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 13 of 51 Last Revised: 30.0 TYPE "B" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location B-3 Reactivity Control (continued)

RCS soluble Boron concentration NSX-101 NSX-103 0-6000 ppm Diluted = 375-10000 ppm Undiluted = 0.375-10000 ppm NA B-4 Reactivity Control (continued)

See Item A-38 RCS Cold Leg water temperature 50-400F 0-700F B-5 Core Cooling See Item A-39 RCS Hot Leg water temperature 50-700F 0-700F UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 14 of 51 Last Revised: 30.0 TYPE "B" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location B-6 Core Cooling (continued)

See Items A-38 and B-4 RCS Cold Leg water temperature 50-700F 0-700F B-7 Core Cooling (continued)

See Item A-2 RCS Pressure 0-3000 psig 0-3000 psig B-8 Core Cooling (continued)

See Item A-25 Core exit temperature SG-30 and SG-31 for TC 1-65 200-2300F 200-2300F UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 15 of 51 Last Revised: 30.0 TYPE "B" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location B-9 Core Cooling (continued)

Coolant Inventory RVLIS NLI-110 NLI-111 NLI-120 NLI-121 NLI-130 NLI-131 Bottom of hot leg to top of vessel Bottom of hot leg to top of vessel Top of head vent piping to bottom of vessel (100% of volume)

Control Room Panel SIS B-10 Core Cooling (continued)

See item A-17 Degrees Subcooling UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 16 of 51 Last Revised: 30.0 TYPE "B" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location B-11 Maintaining RCS Integrity See Item A-2 RCS Pressure 0-3000 psig 0-3000 psig B-12 Maintaining RCS Integrity (continued)

See Item A-8 Containment sump water level NLA-310 NLI-311 5895 to 5998 (bottom of sump to containment floor)

Control Room Panel RHR B-13 Maintaining RCS Integrity (continued)

Containment pressure (wide range)

PPA-310 PPA-312 0 to design pressure (psig)

-5 to +36 psig Control Room Panel SPY UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 17 of 51 Last Revised: 30.0 TYPE "B" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location B-14 Maintaining Containment Integrity Containment Isolation valve position (excluding check valves)

See Table 5.4-1 Closed-not closed Closed-not closed Control Room Panel IV, Panel BA, Panel SIS, Panel SPY B-15 Maintaining Containment Integrity (continued)

See Items A-13 & B-13 Containment pressure

-5 psig to design pressure

-5 to +12 psig (A-13) or

-5 to +36 psig (B-13)

UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 18 of 51 Last Revised: 30.0 TYPE "C" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location C-1 Fuel Cladding See Item A-25 Core Exit Temperature SG-30 and SG-31 for TC 1-65 200-2300F 200-2300F C-2 Fuel Cladding (continued)

Radioactive Concentration or Radiation Level in Circulating Primary Coolant NSX-101 NSX-103 1/2 Tech Spec limit to 100 times Tech Spec limit Equipment capable of measuring 1 Ci/ml to 10 Ci/ml NA UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 19 of 51 Last Revised: 30.0 TYPE "C" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location C-3 Fuel Cladding (continued)

See Item C-2 Analysis of Primary Coolant (gamma spectrum) 10 Ci/ml to 10Ci/ml or TID-14844 source term in coolant volume Equipment capable of measuring 1 Ci/ml to 10 Ci/ml C-4 Reactor Coolant pressure boundary See Item A-2 RCS Pressure 0-3000 psig 0-3000 psig UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 20 of 51 Last Revised: 30.0 TYPE "C" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location C-5 Reactor Coolant pressure boundary (continued)

See items A-13 & B-13 Containment Pressure

-5 psig to design pressure

-5 to +12 psig (A-13) or

-5 to +36 psig (B-13)

C-6 Reactor Coolant pressure boundary (continued)

See Items A-8 & B-12 Containment Sump Water Level See Items A-8 & B-12 See Items A-8 & B-12 UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 21 of 51 Last Revised: 30.0 TYPE "C" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location C-7 Reactor Coolant pressure boundary (continued)

See Item A-12 Containment Area Radiation 1 R/Hr to 1 x 104 R/Hr 1 R/Hr to 1 x 107 R/Hr C-8 Reactor Coolant pressure boundary (continued)

Effluent Radioactivity-Noble Gas effluent from condenser air removal system exhaust SRA-1900 for Unit 1 SRA-2900 for Unit 2 1 x 10-6 to 1 x 10-2

µCi/cc 9x10-7 to 9x104 µCi/cc (Minimum Range)

Control Room FFC Panel C-9 Containment See Item A-2 RCS Pressure 0-3000 psig 0-3000 psig UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 22 of 51 Last Revised: 30.0 TYPE "C" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location C-10 Containment (continued)

See Item A-40 Containment Hydrogen Concentration PAS-H2-A-CRI and PAS-H2-B-CRI for ESR 1 through 9 0 to 30 volume % for ice-condenser type containment 0-30 volume %

C-11 Containment (continued)

See Items A-13 & B-13 Containment Pressure

-5 psig pressure to 3 times design pressure for concrete containment

-5 to +12 psig (A-13) or

-5 to +36 psig (B-13)

UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 23 of 51 Last Revised: 30.0 TYPE "C" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location C-12 Containment (continued)

Containment Effluent Radioactivity Noble Gases from identified release points VRS-1500 for Unit 1 VRS-2500 for Unit 2 1 x 10-6 to 1 x 10-2 Ci/cc 9x10-7 to 9x104 Ci/cc (Minimum Range)

Control Room FFC Panel C-13 Containment (continued)

See Item C-12 Effluent Radioactivity Noble Gases (from buildings or areas where penetrations and hatches are located, eg,) secondary containment and AUX buildings that are in direct contact with primary containment UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 24 of 51 Last Revised: 30.0 TYPE "D" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location D-1 RHR System RHR System Flow IFI-310 IFI-320 (0-1500 GPM)

IFI-311 IFI-321 (1500-5000 GPM) 0 to 110% design flow 0-1500 GPM 1500-5000 GPM Control Room Panel RHR D-2 RHR System (continued)

RHR Heat Exchanger Outlet Temperature ITI-310 ITI-320 40-350F 0-400F Control Room Plant Process Computer (PPC)

UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 25 of 51 Last Revised: 30.0 TYPE "D" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location D-3a SI System Accumulator Tank Level ILA-110 ILA-120 ILA-130 ILA-140 (Wide Range)

ILA-111 ILA-121 ILA-131 ILA-141 (Narrow Range) 10 to 90% volume Wide Range 4.148 to 120.8 or 300 to 1000 cubic ft (52% of total volume)

Narrow Range 104.15 to 129.15 or 900 to 1050 cubic ft (7.5% of total volume)

Control Room Panel SIS D-3b SI System (continued)

Accumulator Tank Pressure IPA-110 IPA-111 IPA-120 IPA-121 IPA-130 IPA-131 IPA-140 IPA-141 0 to 750 psig 0-700 psig Control Room Panel SIS UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 26 of 51 Last Revised: 30.0 TYPE "D" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location D-4 SI System (continued)

Accumulator Tank Isolation Valve Position IMO-110 IMO-120 IMO-130 IMO-140 Closed or Open Closed or Open Control Room Panel SIS D-5 SI System (continued)

See Item D-24 Boric Acid Charging Flow QFI-200 0 to 110% design flow 0-200 GPM D-6 SI System (continued)

See Item A-1 Flow in HPI System IFI-51 IFI-52 IFI-53 IFI-54 0 to 110% design flow 0-200 GPM UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 27 of 51 Last Revised: 30.0 TYPE "D" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location D-7 SI System (continued)

See Item D-1 Flow in LPI System 0 to 110% design flow 0-1500 GPM 1500-5000 GPM D-8 SI System (continued)

See Item A-16 RWST Level Top to Bottom Essentially Top (bottom of overflow) to Bottom (bottom of safety injection pipe)

(100% of total volume)

UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 28 of 51 Last Revised: 30.0 TYPE "D" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location D-9 Primary Coolant System RCP Status RCP-1 for PP-45-1 RCP-2 for PP-45-2 RCP-3 for PP-45-3 RCP-4 for PP-45-4 Motor Current 0-1200 A Control Room Panel RCP D-10 Primary Coolant System (continued)

Primary System Safety Relief Valve Flow QR-107A QR-107B QR-107 C QR-107D NA NA Control Room Panel RC D-11 Primary Coolant System (continued)

See Item A-10 Pressurizer Level Top to Bottom 0-100%

(96% of indicated volume)

UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 29 of 51 Last Revised: 30.0 TYPE "D" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location D-12 Primary Coolant System (continued)

Pressurizer Heater Status Group A1, A2, A3 C1, C2, C3 On/Off On/Off Control Room Panel PRZ D-13 Primary Coolant System (continued)

Quench Tank Level NLA-351 Top to Bottom 7 above tank bottom to 7 below tank top Control Room Panel PRZ D-14 Primary Coolant System (continued)

Quench Tank Temperature NTA-351 50-750F 50-750F Control Room Panel PRZ UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 30 of 51 Last Revised: 30.0 TYPE "D" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location D-14a Primary Coolant System (continued)

Quench Tank Pressure NPA-351 0 to design pressure

-10 to 100 psig Control Room Panel PRZ D-15a Secondary System (Steam Generator)

S/G Level (wide range)

BLI-110 BLI-120 BLI-130 BLI-140 From tube sheet to separators From 12 above tube sheet to separators Control Room Panel SG UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 31 of 51 Last Revised: 30.0 TYPE "D" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location D-15b Secondary System (Steam Generator)

(continued)

See Item A-7 S/G Pressure From atmospheric pressure to 20% above the lowest safety valve setting 0-1200 psig D-16a Secondary System (Steam Generator)

(continued)

See Item D-16b Safety/Relief Valve Positions UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 32 of 51 Last Revised: 30.0 TYPE "D" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location D-16b Secondary System (Steam Generator)

(continued)

Main Steam Flow MFC-110 MFC-111 MFC-120 MFC-121 MFC-130 MFC-131 MFC-140 MFC-141 NA 0-4 x 106 PPH Control Room Panel SG D-17 Secondary System (Steam Generator)

(continued)

Main Feedwater Flow FFC-210 FFC-211 FFC-220 FFC-221 FFC-230 FFC-231 FFC-240 FFC-241 0 to 110% design flow 0-4 x 106 PPH Control Room Panel SG D-18 Auxiliary Feedwater System See Item A-15 Aux Feedwater Flow 0 to 110% design flow 0 to 250 x 103 PPH UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 33 of 51 Last Revised: 30.0 TYPE "D" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location D-19 Auxiliary Feedwater System (continued)

Condensate Storage Tank Level CLI-113 CLI-114 CLR-110 CLR-111 MR-49 for CLR-110 CLR-111 Plant specific Essentially top to bottom (95% total volume)

Control Room Panel CP D-20 Containment Cooling System Containment Spray Flow IFI-330 IFI-331 (upper containment)

(0-2500 GPM)

PP-9E PP-9W (On/Off) 0 to 110% design flow 0-2500 GPM On/Off Control Room Panel SPY D-21 Containment Cooling System (continued)

Heat Removal by Containment Heat Removal System D.C. Cook does not have this type of system and therefore it does not apply UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 34 of 51 Last Revised: 30.0 TYPE "D" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location D-22 Containment Cooling System (continued)

Containment Atmosphere Temperature SG-18 for ETR-11 ETR-12 ETR-13 ETR-14 ETR-15 ETR-16 ETR-17 ETR-18 ETR-19 ETR-20 ETR-21 ETR-22 ETR-23 ETR-24 ETR-25 ETR-26 and ETR-27 40-400F 0-400F Control Room Aux Relay Panel A-15 D-23 Containment Cooling System (continued)

Containment Sump Water Temperature MR-14 and MR-15 for ITR-311 and ITR-321 50 to 250F 50 to 400F Control Room Panel RHR UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 35 of 51 Last Revised: 30.0 TYPE "D" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location D-24 Chemical and Volume Control System Makeup Flow - In QFI-200 0 to 110% design flow 0-200 GPM Control Room Panel BA D-25 Chemical and Volume Control System (continued)

Letdown Flow - Out QFI-301 0 to 110% design flow 0-200 GPM Control Room Panel BA and Panel HSD D-26 Chemical and Volume Control System (continued)

Volume Control Tank Level QLC-451 QLC-452 Top to Bottom Essentially top to bottom (65% of total volume)

Control Room Panel BA UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 36 of 51 Last Revised: 30.0 TYPE "D" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location D-27 Cooling Water System CCW Water Temperature to ESF System SG-10 for CTR-410 CTR-415 CTR-420 CTR-425 40-200F 0-200F Control Room Panel ESW D-28 Cooling Water System (continued)

CCW Flow to ESF System CFI-410 CFI-420 (0-10000 GPM)

CFI-419 CFI-429 (0-6000 GPM) 0 to 110% design flow 0-10000 GPM 0-6000 GPM Control Room Panel CCW D-29 Rad Waste System High Level Radioactive Liquid Tank Level 12-RLS-255 12-RLS-256 Top to Bottom Essentially top to bottom (84% of total volume)

Panel WDS UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 37 of 51 Last Revised: 30.0 TYPE "D" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location D-30 Rad Waste System (continued)

Radioactive Gas Holdup Tank Pressure 12-MR-58 and 12-MR-59 for 12-RPC-310 12-RPC-320 12-RPC-330 12-RPC-340 12-RPC-350 12-RPC-360 12-RPC-370 12-RPC-380 0 to 150% design pressure 0-250 psig Panel WDS D-31 Ventilation System Emergency Ventilation Damper Position VCR-201 VCR-202 VCR-203 VCR-204 VCR-205 VCR-206 VCR-207 Open/Closed Open/Closed Control Room Panel IV VCR-207 on Control Room Panel SPY UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 38 of 51 Last Revised: 30.0 TYPE "D" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location D-32a Status of Standby Power and Other Energy Sources Important to Safety Diesel Generator Status DGAB-AM-1-REM DGCD-AM-1-REM DGAB-AM-2-REM DGCD-AM-2-REM DGAB-AM-3-REM DGCD-AM-3-REM Plant Specific 0-800 A Control Room Panel SA D-32b Status of Standby Power and Other Energy Sources Important to Safety (continued) 4Kv Safety Related Power Systems Status Bus T11A, T11B, T11C, T11D for Unit 1 Bus T21A, T21B, T21C, T21D for Unit 2 Plant Specific 0-150 V Control Room Panel SA UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 39 of 51 Last Revised: 30.0 TYPE "D" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location D-32c Status of Standby Power and Other Energy Sources Important to Safety (continued) 250 Vdc Battery Power System Status BATT-AB-REM-VM BATT-CD-REM-VM Plant Specific 0-300 V Control Room Panel SA D-32d Status of Standby Power and Other Energy Sources Important to Safety (continued) 120 Vac Safety Related Power System Status Channel I, II, III, IV CRID-1-VM CRID-2-VM CRID-3-VM CRID-4-VM Plant Specific 0-150 V Control Room Panel SA UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 40 of 51 Last Revised: 30.0 TYPE "D" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location D-32e Status of Standby Power and Other Energy Sources Important to Safety (continued)

Instrument Air Status XPI-100 (0-150 psig)

XPI-50 (0-100 psig)

XPI-20 (0-60 psig)

XPI-85 (0-160 psig)

Plant Specific Control Room Panel SV UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 41 of 51 Last Revised: 30.0 TYPE "E" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location E-1 Containment Radiation See Item A-12 Containment Area Radiation Monitor High Range 1 R/Hr to 1 x 107 R/Hr 1 R/Hr to 1 x 107 R/Hr UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 42 of 51 Last Revised: 30.0 TYPE "E" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location E-2 Area Radiation Radiation Exposure Rate (inside buildings or where areas of access are required to service equipment important to safety)

ERA-7303 ERA-7304 ERA-7305 ERA-7306 ERA-7307 ERA-7308 ERA-7403 ERA-7404 ERA-7504 ERA-7507 ERA-7508 ERA-7601 ERA-7602 ERA-7603 ERA-7604 ERA-7605 ERA-8303 ERA-8304 ERA-8305 ERA-8306 ERA-8307 ERA-8308 ERA-8403 ERS-7401 ERS-8401 1 x 10-1 R/Hr to 1 x 104 R/Hr Equipment installed is capable of monitoring within the range Control Room FFC Panel UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 43 of 51 Last Revised: 30.0 TYPE "E" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location E-3a Noble Gases and Vent Flow Rate See Item E-3e Containment or Purge Effluent E-3b Noble Gases and Vent Flow Rate (continued)

See Item E-3e Reactor Shield Building Annulus E-3c Noble Gases and Vent Flow Rate (continued)

See Item E-3e Aux Building UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 44 of 51 Last Revised: 30.0 TYPE "E" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location E-3d Noble Gases and Vent Flow Rate (continued)

Condenser Air Removal System Exhaust SRA-1900 for Unit 1 SRA-2900 for Unit 2 SFR-401 (0-250 scfm only) 1 x 10-6 to 1 x 105 Ci/cc 0 to 110% vent design flow 9 x 10-7 to 9 x 104 Ci/cc (Minimum Range) 0-250 scfm Control Room FFC Panel UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 45 of 51 Last Revised: 30.0 TYPE "E" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location E-3e Noble Gases and Vent Flow Rate (continued)

Common Plant Vent VRS-1500 for Unit 1 VRS-2500 for Unit 2 VFR-315 (0-200k scfm only) 1 x 10-6 to 1 x 103 Ci/cc 0 to 110% vent design flow 9 x 10-7 to 9 x 104 Ci/cc (Minimum Range) 0-200k scfm Control Room FFC Panel UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 46 of 51 Last Revised: 30.0 TYPE "E" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location E-3f Noble Gases and Vent Flow Rate (continued)

Vent from S/G Safety Relief Valves MRA-1600, MRA-1700 (Unit 1)

MRA-2600,MRA-2700 (Unit 2) 1 x 10-1 to 1 x 103 Ci/cc 0.1 to 100 Ci/cc2 Control Room FFC Panel 2 This is the minimum sensitivity of the instrument for normal operation, to follow the course of an accident, and/or take protective actions. Values of the instrument above or below this minimum sensitivity range are acceptable.

UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 47 of 51 Last Revised: 30.0 TYPE "E" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location E-3g Noble Gases and Vent Flow Rate (continued)

Other Identified Release Points SRA-1800 (Unit 1)

SRA-2800 (Unit 2)

SFR-201 (0-4500 scfm only) 1 x 10-6 to 1 x 102 Ci/cc 0 to 110% vent design flow 1x10-7 to 1x105 Ci/cc (SRA-1800) 1x10-7 to 1x105 Ci/cc (SRA-2800)

(Minimum Range)

Unit 1 = 0-1500 scfm Unit 2 = 0-4500 scfm Control Room FFC Panel UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 48 of 51 Last Revised: 30.0 TYPE "E" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location E-4 Particulates and Halogens See Item E-3e All Identified Release Points (except S/G safety relief valves and condenser air removal system exhaust) sampling and onsite analysis 1 x 10-3 to 1 x 102 Ci/cc 0 to 110% vent design flow E-5a Environmental Radiation and Radioactivity Airborne Radioactivity and Particulates Sampling and Analysis (portable)

NA 1 x 10-9 to 1 x 103 Ci/cc 1 x 10-9 to 1 x 10-3 Ci/cc (minimum)

UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 49 of 51 Last Revised: 30.0 TYPE "E" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location E-5b Environmental Radiation and Radioactivity (continued)

Plant and Environmental Radiation (portable)

NA 1 x 10-3 to 1 x 104 R/hr photons 1 x 10-3 to 1 x 104 Rads/hr Beta radiations and low-energy photons Gamma 1 x 10-3 to 1 x 104 R/hr Beta / low energy gamma 1 x 10-3 to 1 x 104 Rad/hr UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 50 of 51 Last Revised: 30.0 TYPE "E" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location E-5c Environmental Radiation and Radioactivity (continued)

Plant and Environmental Radioactivity (portable)

NA Isotopic analysis Isotopic analysis E-6 Meteorology Wind Direction EFR-410 EFR-412 EFR-413 EFR-414 0-360 degrees 0-360 degrees Control Room Plant Process Computer (PPC)

E-7 Meteorology (continued)

Wind Speed EFR-400 EFR-404 EFR-402 EFR-403 0-100 MPH 0-125 MPH Control Room Plant Process Computer (PPC)

UFSAR Revision 32.0

INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 30.0 Table:

7.8-1 Page: 51 of 51 Last Revised: 30.0 TYPE "E" VARIABLES PROVIDED THE OPERATOR FOR MANUAL FUNCTIONS DURING AND FOLLOWING AN ACCIDENT Item No.

Purpose Variable Tag No.

Range Reg Guide 1.97 Value Installed Value Display Location E-8 Meteorology (continued)

Estimation of Atmospheric Stability ETR-400 ETR-402 ETR-403 ETQ-401

-5C to +10C per 50 meter intervals

-30 to 50 C Control Room Plant Process Computer (PPC)

E-9a Line Item Deleted E-9b Line Item Deleted E-9c Line Item Deleted E-9d Line Item Deleted E-9f Line Item Deleted E-9g Line Item Deleted E-9h Line Item Deleted E-10a Line Item Deleted E-10b Line Item Deleted E-10c Line Item Deleted UFSAR Revision 32.0

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