ML22161A939

From kanterella
Jump to navigation Jump to search
301 Exam Report Items, RO Written Exam
ML22161A939
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 06/10/2022
From:
NRC/RGN-II
To:
Tennessee Valley Authority
References
Download: ML22161A939 (77)
v • d • e


Text

ILT 2204 Written Exam 1

1.

4 KV Shutdown Board ___________ is the NORMAL power supply to the A Fire Pump.

A. A B. B C. C D. D ML22161A939

ILT 2204 Written Exam 2

2.

Unit 3 is operating at 100% RTP when the following plant conditions occur:

  • Control Room abandonment has been directed due to toxic gas in the Control Room In accordance with 3-AOI-100-2, Control Room Abandonment, the IMMEDIATE ACTION to insert a Reactor SCRAM will be performed from Panel.

A. 3-9-5 B. 3-9-15 C. 3-9-17 D. 3-25-32

ILT 2204 Written Exam 3

3.

Unit 2 was operating at 95% RTP with the following plant conditions:

  • Reactor Feedwater Pump 2C has just been secured for maintenance An event then occurs which results in an automatic Reactor SCRAM.
  • Reactor Water Level reached (-) 15 inches before recovering to the normal band Given the conditions above and in accordance with 2-OI-3, Reactor Feedwater System, Reactor Feedwater Pump (RFP), (1) will control Reactor Water Level in automatic while the other RFP Turbine will runback to (2) rpm.

A. (1) 2A (2) 480 B. (1) 2A (2) 600 C. (1) 2B (2) 480 D. (1) 2B (2) 600

ILT 2204 Written Exam 4

4.

Unit 2 is operating at 100% RTP.

Which ONE of the following plant transients will cause the APRM Operator Display Assemblies (ODAs) to AUTOMATICALLY display the Oscillation Power Range Monitor (OPRM) Bargraph Screens?

A. Recirc Pump 2A trip B. Inadvertent HPCI injection C. Control Rod drifting into the core D. Feedwater Heater 2A1 Extraction Steam isolation

ILT 2204 Written Exam 5

5.

Unit 2 is operating at 100% RTP when the following conditions occur:

  • REACTOR WATER LEVEL ABNORMAL (2-9-5A, Window 8) alarms Given the above conditions and in accordance with 2-OI-68, Reactor Recirculation System, the Recirc Pump _________ limiter will be enforcing.

A. 28%

B. 58%

C. 75%

D. 90%

8 REACTOR WATER LEVEL ABNORMAL 2-LA-3-53

ILT 2204 Written Exam 6

6.

Unit 1 has suffered an Anticipated Transient Without SCRAM (ATWS) with the following indications:

Given the indications above, SLC Squib Valve (1) is open and the time to reach Hot Shutdown Boron Weight is (2) compared to the time with both squib valves open.

A. (1) A (2) longer B. (1) A (2) the same C. (1) B (2) longer D. (1) B (2) the same

ILT 2204 Written Exam 7

7.

In accordance with OPDP-1, Conduct of Operations, the BFN Reactor Controls Area is defined as Panels 9-3 through (1) and when the Reactor is operating at 100%

RTP, the OATC (2) REQUIRED to notify the NUSO prior to leaving the Reactor Controls Area.

A. (1) 9-8 (2) is B. (1) 9-8 (2) is NOT C. (1) 9-54 (2) is D. (1) 9-54 (2) is NOT

ILT 2204 Written Exam 8

8.

Unit 3 is operating at 100% RTP when the following conditions occur:

  • Loss of Offsite Power
  • 3B EDG mechanically fails
  • Reactor Water Level lowers to (-) 130 inches Given the conditions above, 3B RHR Pump (1) automatically start and 3C RHR Pump (2) automatically start.

A. (1) will NOT (2) will B. (1) will NOT (2) will NOT C. (1) will (2) will D. (1) will (2) will NOT

ILT 2204 Written Exam 9

9.

Unit 2 is operating at 100% RTP with the following plant conditions:

  • ECCS ANALOG TRIP UNIT TROUBLE (2-9-3E, Window 30) alarms
  • A malfunction causes a failure of Division 1 ECCS ATU Inverter Which ONE of the following accurately describes the effects of this loss on the HPCI AND RCIC Systems?

HPCI is (1) and RCIC is (2).

A. (1) OPERABLE (2) OPERABLE B. (1) OPERABLE (2) INOPERABLE C. (1) INOPERABLE (2) OPERABLE D. (1) INOPERABLE (2) INOPERABLE 30 ECCS ANALOG TRIP UNIT TROUBLE 2-XA-71-60

ILT 2204 Written Exam 10

10.

Unit 1 is operating at 100% RTP when the following conditions occur:

  • Lowest Reactor Water Level was (-) 38 inches
  • Drywell Pressure is 3.2 psig
  • Current Reactor Water Level is (+) 10 inches Given the conditions above, Reactor Pressure can be controlled using __________.

Note: 1-EOI Appendix-8B, Reopening MSIVs/Bypass Valve Operation 1-EOI Appendix-11C, Alternate RPV Pressure Control Systems HPCI Test Mode 1-EOI Appendix-11F, Alternate RPV Pressure Control Systems, RFPT on Minimum Flow 1-EOI Appendix-11E, Alternate RPV Pressure Control Systems, RWCU System Recirc/Blowdown Mode A. 1-EOI Appendix-11C B. 1-EOI Appendix-11F C. 1-EOI Appendix-11E D. 1-EOI Appendix-8B

ILT 2204 Written Exam 11

11.

In accordance with 1-OI-71, Reactor Core Isolation Cooling System, the RCIC MINIMUM speed is (1) and maintaining turbine speed above this limit is accomplished (2).

A. (1) 2100 rpm (2) MANUALLY by the Operator B. (1) 2100 rpm (2) AUTOMATICALLY by an electrical speed clamp C. (1) 2400 rpm (2) MANUALLY by the Operator D. (1) 2400 rpm (2) AUTOMATICALLY by an electrical speed clamp

ILT 2204 Written Exam 12

12.

Unit 2 is in MODE 2 with the following conditions:

  • A Reactor startup is in progress
  • An Instrument Mechanic (IM) places 2-HS-92-7-41A, IRM A Channel A INOP/INHIBIT switch in the STANDBY position Given the conditions above, the IMs actions will result in a (1) SCRAM.

In accordance with 2-OI-92A, Intermediate Range Monitors, IRM A bypass operations are performed on Panel (2).

A. (1) full (2) 9-5 AND 9-12 B. (1) full (2) 9-5 C. (1) half (2) 9-5 AND 9-12 D. (1) half (2) 9-5

ILT 2204 Written Exam 13

13.

Unit 1 is operating at 100% RTP. The Instrument Mechanics (IMs) are setting up to perform maintenance in the Auxiliary Instrument Room, when a PCIS Group 6 Isolation occurs.

Given the conditions above, the Drywell Blowers (1) running and the Drywell (2) be vented via the NORMAL vent path in accordance with 1-AOI-64-1, Drywell Pressure and/or Temperature High, or Excessive Leakage Into Drywell.

A. (1) are (2) can B. (1) are (2) can NOT C. (1) are NOT (2) can D. (1) are NOT (2) can NOT

ILT 2204 Written Exam 14

14.

A Unit 3 Reactor Startup is in progress, when the Operator observes the following:

  • SRM DOWNSCALE, (3-9-5A, Window 6), alarms
  • SRM HIGH/INOP, (3-9-5A, Window 13) alarms
  • IRM CH A, C, E, G HI-HI/INOP, (3-9-5A, Window 33), alarms Given the conditions above, which ONE of the following power sources, if lost, would cause these failures?

A. 24VDC Power Distribution Panel B. 125VDC Power Distribution Panel C. 120VAC RPS Power Supply Distribution Panel D. 120VAC Instrument and Control Power Distribution Panel 6

SRM DOWNSCALE 33 IRM CH A, C, E, G HI-HI/INOP

ILT 2204 Written Exam 15

15.

All three Units are operating at 100% RTP when the following conditions occur:

  • A Loss of Offsite Power occurs
  • B Emergency Diesel Generator (EDG) fails to start Given the conditions above, in accordance with 0-AOI-57-1A, Loss of Offsite Power (161 and 500 KV)/ Station Blackout, the minimum action(s) required to re-energize the affected 480V Distribution Board(s) is to transfer 480V Shutdown Board (1) to alternate.

The respective board (2) be manually transferred from Main Control Room (MCR)

Panel 9-8.

A. (1) 1B (2) can B. (1) 1B (2) can NOT C. (1) 2A (2) can D. (1) 2A (2) can NOT

ILT 2204 Written Exam 16

16.

Unit 2 was operating at 100% RTP when an event occurred resulting in the following conditions:

  • Drywell Temperature is 255 ºF and rising
  • Suppression Pool Water Level is 15 feet
  • 480V RMOV BD 2B is de-energized due to a fault Given the conditions above, Drywell Sprays will be initiated on RHR Loop (1).

Drywell Temperature indication is monitored on Panel(s) (2).

A. (1) I (2) 9-3 OR 9-4 B. (1) I (2) 9-3 ONLY C. (1) II (2) 9-3 OR 9-4 D. (1) II (2) 9-3 ONLY

ILT 2204 Written Exam 17

17.

Unit 1 was operating at 100% RTP when events occurred resulting in the following conditions:

  • Drywell Pressure reached 2.5 psig
  • A fire has been reported in the Unit 1 Reactor Building
  • 0-AOI-26-1, Fire Response, has been entered In accordance with the AOI, the Assistant Unit Operators (AUOs) will INITIALLY report to (1) and smoke is currently being removed by (2).

A. (1) their assigned Control Room (2) Reactor Zone Ventilation B. (1) their assigned Control Room (2) Standby Gas Treatment Fans C. (1) the Incident Commander (2) Reactor Zone Ventilation D. (1) the Incident Commander (2) Standby Gas Treatment Fans

ILT 2204 Written Exam 18

18.

An event has occurred on Unit 2, requiring the use of Standby Gas Treatment (SGT)

System, with the following conditions:

  • SGT TRAIN C FILTER BANK TEMP HIGH (2-9-3B, Window 25) alarms
  • The Outside AUO reports that SGT C charcoal filter temperature is 150 F Given the conditions above, the SGT decay heat removal mode (1) initiated and the carbon bed filters (2) designed to remove iodine.

A. (1) is automatically (2) are B. (1) is automatically (2) are NOT C. (1) must be manually (2) are D. (1) must be manually (2) are NOT 25 SGT TRAIN C FILTER BANK TEMP HIGH 2-TA-65-63

ILT 2204 Written Exam 19

19.

Unit 2 is operating at 100% RTP with the following conditions:

  • Traversing Incore Probe (TIP) operations are in progress
  • Area Radiation Monitor 2-RI-90-22A, TIP ROOM EL 565 REACTOR BLDG alarms Given the conditions above, a PCIS Group 8 Isolation (1) occur and EOI entry (2) required.

A. (1) will (2) is NOT B. (1) will (2) is C. (1) will NOT (2) is NOT D. (1) will NOT (2) is

ILT 2204 Written Exam 20

20.

The Limiting Condition for Operations (LCO) statement for Unit 2 Anticipated Transient Without SCRAM Recirculation Pump Trip (ATWS - RPT) Instrumentation, LCO 3.3.4.2, requires OPERABILITY of the function for Reactor Vessel Water Level at (1) and Reactor Steam Dome Pressure at (2).

A. (1) (-) 45 inches (2) 1073 psig B. (1) (-) 45 inches (2) 1162 psig C. (1) (-) 122 inches (2) 1073 psig D. (1) (-) 122 inches (2) 1162 psig

ILT 2204 Written Exam 21

21.

Unit 1 is operating at 100% RTP when a Control Air leak develops, resulting in the following conditions:

  • SERVICE AIR CROSSTIE VALVE OPEN (1-9-20B, Window 30) alarms
  • Control Air Pressure is 69 psig and slowly lowering Given the conditions above and in accordance with the appropriate Alarm Response Procedure, 0-FCV-33-1, SERVICE AIR CROSSTIE VALVE opened at (1) Control Air Pressure.

A manual Reactor SCRAM is required if Control Air Pressure continues to lower to less than (2) as indicated by 1-PI-32-20 on Panel 1-9-20 in accordance with 0-AOI-32-1, Loss of Control and Service Air Compressors.

A. (1) 70 psig (2) 55 psig B. (1) 70 psig (2) 66 psig C. (1) 85 psig (2) 55 psig D. (1) 85 psig (2) 66 psig 30 SERVICE AIR XTIE VLV OPEN 0-PA-33-1A/1

ILT 2204 Written Exam 22

22.

Unit 2 is in MODE 4 when the following conditions occur:

  • 2B and 2D RHR Pumps are in service
  • 480V Shutdown Board 2B trips Given the conditions above, 2-FCV-74-67, RHR SYSTEM II INBOARD INJECTION VALVE, (1) AUTOMATICALLY close and the running RHR Pumps are (2) tripped.

A. (1) will (2) manually B. (1) will (2) automatically C. (1) will NOT (2) manually D. (1) will NOT (2) automatically

ILT 2204 Written Exam 23

23.

Unit 2 was operating at 100% Rated Thermal Power (RTP) when the following conditions occurred:

  • 2-FI-68-48, JET PUMP FLOW for RECIRC LOOP B indicates less than 40 x 106 lbm/hr Given the conditions above, in accordance with 2-AOI-68-1, Recirc Pump Trip / Core Flow Decrease, Core Flow must be (1) to ensure accurate indication is provided and the Operator is required to insert Control Rods to less than (2) loadline.

A. (1) lowered (2) 67%

B. (1) lowered (2) 74%

C. (1) raised (2) 67%

D. (1) raised (2) 74%

ILT 2204 Written Exam 24

24.

Unit 1 was operating at 100% RTP when an event occurred resulting in the following conditions:

  • Suppression Pool Water Temperature is 150 °F and rising
  • Suppression Chamber Pressure is 3 psig and rising
  • SRVs are being cycled for Reactor Pressure Control
  • Suppression Pool Water Level is 13 feet and lowering Given the conditions above, the (1) will be uncovered FIRST.

(2) will be more effective at mitigating the CURRENT Heat Capacity limitations of Primary Containment.

A. (1) HPCI Turbine exhaust (2) Suppression Chamber Sprays B. (1) HPCI Turbine exhaust (2) Suppression Pool Cooling C. (1) Downcomer opening (2) Suppression Chamber Sprays D. (1) Downcomer opening (2) Suppression Pool Cooling

ILT 2204 Written Exam 25

25.

To place Suppression Pool Cooling in service, which ONE of the following correctly identifies which RHRSW Pumps are available to provide cooling for RHR Heat Exchangers?

RHRSW Pumps (1) supply cooling water to RHR Loop (2) heat exchangers.

A. (1) B1 and B2 ONLY (2) II ONLY B. (1) B1 and B2 ONLY (2) I and II C. (1) B1, B2 and D1, D2 (2) II ONLY D. (1) B1, B2 and D1, D2 (2) I and II

ILT 2204 Written Exam 26

26.

When Unit 3 Safety Relief Valve (SRV) solenoids experience an undervoltage condition on the normal power supply, the transfer to the alternate power supply (1).

ALTERNATE electrical power for Unit 3 SRV Solenoids, where available, is supplied from 250 VDC (2).

A. (1) occurs automatically (2) RMOV Boards ONLY B. (1) occurs automatically (2) RMOV Boards and Battery Boards C. (1) must be performed manually (2) RMOV Boards ONLY D. (1) must be performed manually (2) RMOV Boards and Battery Boards

ILT 2204 Written Exam 27

27.

Unit 2 is operating at 100% RTP when an event occurred resulting in the following conditions:

At 0400:

  • Suppression Pool Water Level is (-) 3 inches and rising at 1 inch per hour Given the conditions above, the EARLIEST time that Technical Specification (Tech Spec) 3.6.2.2, Suppression Pool Water Level limit will be reached is (1) and 2-EOI-2, Primary Containment Control entry (2) be required for Suppression Pool Water Level.

A. (1) 0515 (2) will NOT B. (1) 0515 (2) will C. (1) 0615 (2) will NOT D. (1) 0615 (2) will

ILT 2204 Written Exam 28

28.

Unit 3 is in MODE 5 when an event occurs resulting in the following:

  • All Refueling Zone radiation monitors indicate 69 mR/hr
  • All Reactor Zone radiation monitors indicate 73 mR/hr Given the conditions above, the Unit 3 Ventilation System isolates (1) Zone Ventilation System(s) to limit the (2).

A. (1) ONLY the Reactor (2) release of fission products to the environment B. (1) ONLY the Reactor (2) spread of contamination within Secondary Containment C. (1) the Refueling AND Reactor (2) release of fission products to the environment D. (1) the Refueling AND Reactor (2) spread of contamination within Secondary Containment

ILT 2204 Written Exam 29

29.

In accordance with EOI-1A, ATWS RPV Control and the associated EOI Program Manual, Standby Liquid Control (SLC) injection is required BEFORE Suppression Pool Temperature rises to a MINIMUM of (1) in order to (2).

A. (1) 110 °F (2) preclude Emergency Depressurization B. (1) 110 °F (2) prevent Thermal Hydraulic Instabilities (THI)

C. (1) 120 °F (2) preclude Emergency Depressurization D. (1) 120 °F (2) prevent Thermal Hydraulic Instabilities (THI)

ILT 2204 Written Exam 30

30.

Unit 2 is operating at 100% RTP, with the following plant conditions:

  • HPCI is operating for a surveillance as follows:

o 2-FCV-73-35, HPCI PUMP CST TEST VALVE, is THROTTLED OPEN o 2-FCV-73-36, HPCI/RCIC CST TEST VALVE, is OPEN o 2-FCV-73-44, HPCI PUMP INJECTION VALVE, is CLOSED

  • An event occurs resulting in a Reactor SCRAM
  • Reactor Water Level indicates (-) 50 inches Given the conditions above, which ONE of the following completes the statements below?

2-FCV-73-36, HPCI/RCIC CST TEST VALVE will (1).

2-FCV-73-44, HPCI PUMP INJECTION VALVE will (2).

A. (1) remain OPEN (2) travel OPEN B. (1) remain OPEN (2) remain CLOSED C. (1) travel CLOSED (2) travel OPEN D. (1) travel CLOSED (2) remain CLOSED

ILT 2204 Written Exam 31

31.

Unit 3 was operating at 100% RTP when HPCI initiates and injects on an invalid signal.

Given the conditions above, Reactor Power as monitored on the Average Power Range Monitors (APRMs) on Panel 3-9-5 will (1) and INDICATED Total Steam Flow on Panel 3-9-5 will (2).

A. (1) rise (2) rise B. (1) rise (2) lower C. (1) lower (2) rise D. (1) lower (2) lower

ILT 2204 Written Exam 32

32.

Preparations are underway to place Unit 2 in Cold Shutdown following a SCRAM when the following occurs:

  • Reactor Water Level then lowered to 0 inches Given the conditions above, SDC (1) isolate.

In accordance with 2-OI-74, Residual Heat Removal System (RHR), the normal Cold Shutdown Reactor Water Level band is maintained to prevent (2).

A. (1) will (2) thermal stratification B. (1) will (2) jet pump cavitation C. (1) will NOT (2) thermal stratification D. (1) will NOT (2) jet pump cavitation

ILT 2204 Written Exam 33

33.

In accordance with 2-OI-75, Core Spray System automatic interlocks, when system flow reaches the SETPOINT of (1) gpm, 2-FCV-75-9(37), CORE SPRAY SYS I(II)

MINIMUM FLOW VALVEs OPEN and will CLOSE when system flow reaches the SETPOINT of (2).

A. (1) 900 gpm (2) 2600 gpm B. (1) 900 gpm (2) 5800 gpm C. (1) 2200 gpm (2) 2600 gpm D. (1) 2200 gpm (2) 5800 gpm

ILT 2204 Written Exam 34

34.

Unit 1 was operating at 100% RTP when an event occurred, resulting in the following conditions:

A manual SCRAM was inserted, ALL Control Rods are in MAIN STEAM LINE RADIATION HIGH-HIGH, (1-9-3A, Window 27) is sealed in OFFGAS AVERAGE ANNUAL RELEASE RATE EXCEEDED, (1-9-4C, Window 27) is sealed in Given the conditions above, Main Steam Isolation Valves (MSIVs) require closure based on actions contained within Alarm Response Procedure (ARP) (1), Window 27.

The MAIN STEAM LINE RADIATION HIGH-HIGH alarms at radiation levels of (2) normal full power background.

A. (1) 1-9-3A (2) 1.5 x B. (1) 1-9-3A (2) 3.0 x C. (1) 1-9-4C (2) 1.5 x D. (1) 1-9-4C (2) 3.0 x 27 OG AVG ANNUAL RELEASE LIMIT EXCEEDED 1-RA-90-157C

ILT 2204 Written Exam 35

35.

In accordance with 1-OI-99, Reactor Protection System (RPS), which ONE of the following completes the statements below?

The Generator Load Reject Turbine Control Valve (TCV) Fast Closure RPS SCRAM signal is automatically bypassed at (1) RTP.

The pressure switch on either TCV 1 or 3 will send a trip signal to RPS Trip System (2).

A. (1) 50%

(2) A B. (1) 50%

(2) B C. (1) 5%

(2) A D. (1) 5%

(2) B

ILT 2204 Written Exam 36

36.

Unit 3 is operating at 80% RTP with the following conditions:

  • The Transmission System Operator (TOp) notified the Shift Manager (SM) that the 500 KV System voltage is 542 KV
  • Grid frequency is 60.03 Hz
  • Unit 3 Main Generator Reactive Load is 53 MVARs outgoing
  • 0-AOI-57-1E, Grid Instability has been entered by all Units Given the conditions above, which ONE of the following identifies how to restore to normal limits in accordance with 0-AOI-57-1E?

A. Raise Reactive Power using the Voltage Regulator.

B. Lower Reactive Power using the Voltage Regulator.

C. Raise Reactor Power by approximately 1% / minute using Recirculation Flow.

D. Lower Reactor Power by approximately 1% / minute using Recirculation Flow.

ILT 2204 Written Exam 37

37.

Unit 2 is operating at 100% RTP when 2-RM-90-265A, Off-Gas Post-Treatment Radiation Monitor, fails UPSCALE.

One minute after the given conditions above, 2-FCV-66-28, Off-Gas System Isolation Valve, (1) AUTOMATICALLY close.

If directed to manually restrain the 2-FCV-66-28, Off-Gas System Isolation Valve, the AUO will be dispatched to the (2).

A. (1) will (2) Turbine Building B. (1) will (2) Off Gas Stack C. (1) will NOT (2) Turbine Building D. (1) will NOT (2) Off Gas Stack

ILT 2204 Written Exam 38

38.

Unit 1 was operating at 100% RTP when the following conditions occur:

  • OATC reports Reactor Power is 8% following the SCRAM
  • Plant conditions require Emergency Depressurization In accordance with EOIs, ADS (1) required to be inhibited.

In accordance with the EOI Program Manual, once directed to open 6 ADS Main Steam Relief Valves (SRV) for Emergency Depressurization, the Reactor Operator will open (2) additional SRVs.

A. (1) is (2) 5 B. (1) is (2) 6 C. (1) is NOT (2) 5 D. (1) is NOT (2) 6

ILT 2204 Written Exam 39

39.

Given the following conditions:

  • A LOCA has occurred on Unit 2
  • Control Bay Ventilation has isolated

CREV is designed to maintain Control Room differential pressure (2) to limit the spread of radioactive contamination.

A. (1) will (2) positive B. (1) will (2) negative C. (1) will NOT (2) positive D. (1) will NOT (2) negative

ILT 2204 Written Exam 40

40.

Unit 2 is operating at 100% RTP and the HPCI System surveillance test was started.

A seismic event occurs that results in a HPCI steam leak with the following conditions:

  • 250V RMOV BOARD 2A de-energized
  • HPCI room temperature is 190 °F and rising
  • Highest steam rate achieved was 160% of rated flow Given the above conditions, HPCI received a PCIS Isolation signal from high (1).

BOTH 2-FCV-73-2, HPCI STEAM LINE INBOARD ISOLATION VALVE AND 2-FCV-73-3, HPCI STEAM LINE OUTBOARD ISOLATION VALVE (2) close on the PCIS isolation signal.

A. (1) temperature (2) will B. (1) temperature (2) will NOT C. (1) steam flow rate (2) will D. (1) steam flow rate (2) will NOT

ILT 2204 Written Exam 41

41.

Unit 1 is operating at 100% RTP.

Given the condition above and pertaining to End-of-Cycle Recirculation Pump Trips (EOC-RPT), the NORMAL plant configuration of 1-HS-099-5A-S14A and 1-HS-099-5A-S14B, RECIRC PUMP TRIP (RPT) LOGIC A/B TEST SWITCHES in the Aux Instrument Room, are in the (1) position.

IF the above switches are in the NORMAL position, THEN a Recirculation Pump trip will occur as a result of the (2) Valves being less than 90% open.

A. (1) NORMAL (2) Turbine Stop B. (1) NORMAL (2) Turbine Control C. (1) OUT OF SERVICE (2) Turbine Stop D. (1) OUT OF SERVICE (2) Turbine Control

ILT 2204 Written Exam 42

42.

Unit 1 is operating at 95% RTP with NO equipment out of service.

While HPCI testing is in progress, 1-EOI-2, Primary Containment Control entry is required upon first reaching (1) Suppression Pool Temperature.

When 1-EOI-2 is entered on high Suppression Pool Temperature, the Operator is required to place (2) loop(s) of Suppression Pool Cooling in service.

A. (1) 95 °F (2) ONLY 1 B. (1) 95 °F (2) ALL available C. (1) 105 °F (2) ONLY 1 D. (1) 105 °F (2) ALL available

ILT 2204 Written Exam 43

43.

Unit 3 is in MODE 2 with the following plant conditions:

  • SRM B is bypassed due to excessive noise and spiking
  • All IRMs are on Range 3 Subsequently, SRM A fails HIGH and has been declared INOPERABLE.

Given the conditions above and in accordance with 3-OI-92, Source Range Monitors, a Control Rod Block (1) occur and more than one SRM (2) be bypassed by a Control Room Operator.

A. (1) will (2) will B. (1) will (2) will NOT C. (1) will NOT (2) will D. (1) will NOT (2) will NOT

ILT 2204 Written Exam 44

44.

Unit 3 is operating at 100% RTP with the following conditions:

  • RFWCS INPUT FAILURE (3-9-6C, Window 14) alarms
  • The OATC reports 3-FI-3-78A, FW LINE A FLOW on Panel 3-9-5 indicates UPSCALE Given the conditions above, 3-FI-3-78A, FW LINE A FLOW (1) automatically bypass.

Once FW LINE A FLOW is bypassed, Feedwater Level Control will be in (2) element control.

A. (1) will (2) three B. (1) will (2) single C. (1) will NOT (2) three D. (1) will NOT (2) single 14 RFWCS INPUT FAILURE 3-LA-46-5D

ILT 2204 Written Exam 45

45.

Unit 1 and Unit 2 are operating at 100% RTP with the following conditions:

  • Unit 1 has RHR Loop I in Suppression Pool Cooling
  • Unit 2 has RHR Loop I in Suppression Pool Cooling
  • 250V Shutdown Battery A de-energizes due to a fault Given the conditions above, RHR Pump(s) (1) control power is(are) affected by this failure.

The affected 4KV Shutdown Board breaker(s) control power is provided by a(an)

(2) source.

A. (1) 1A ONLY (2) DC B. (1) 1A ONLY (2) AC C. (1) 1A AND 2A (2) DC D. (1) 1A AND 2A (2) AC

ILT 2204 Written Exam 46

46.

The following conditions exist on Unit 3:

  • 3-HS-99-5A-S1, REACTOR MODE SWITCH is in REFUEL
  • The Refueling Bridge Operator grappled a fuel bundle and raised it full up
  • The fuel bundle was then moved towards the Reactor Core As the Refueling Bridge moves towards the Reactor Core, it (1) the Core AND a Control Rod Block (2) occur.

A. (1) continues over (2) will B. (1) continues over (2) will NOT C. (1) stops before it reaches (2) will D. (1) stops before it reaches (2) will NOT

ILT 2204 Written Exam 47

47.

Unit 1 suffered a LOCA with the following condition:

  • Suppression Pool Temperature is 200 °F In accordance with EOI Curve 3, Heat Capacity Temp Limit (HCTL), the REQUIRED ACTION area is entered if Reactor Pressure reaches (1) when Suppression Pool Level is (2).

[REFERENCE PROVIDED]

A. (1) 500 psig (2) 14 feet B. (1) 500 psig (2) 15 feet C. (1) 700 psig (2) 14 feet D. (1) 700 psig (2) 15 feet

ILT 2204 Written Exam 48

48.

What effect does moderator temperature have on the ability of boron to shut down the Reactor, if any?

A. At lower moderator temperatures, less boron is needed.

B. At higher moderator temperatures, less boron is needed.

C. At higher moderator temperatures, more boron is needed.

D. Moderator temperature has no effect on the amount of boron needed.

ILT 2204 Written Exam 49

49.

Unit 2 is operating at 100% RTP with the following plant conditions:

  • 2A Reactor Building Closed Cooling Water (RBCCW) Pump is tagged for bearing replacement
  • The Spare RBCCW Pump 1C is aligned to Unit 2
  • 'A' EDG is supplying its 4KV Shutdown Board as the only source Subsequently, a steam line break inside containment occurs, causing Drywell Pressure to reach 3.0 psig and Reactor Pressure to lower to 440 psig.

Note: NO Operator actions have been taken.

Given the above conditions, 2B RBCCW pump restarts in (1) and 60 seconds later, 1C RBCCW pump (2) running.

A. (1) 40 seconds (2) is NOT B. (1) 40 seconds (2) is C. (1) 43 seconds (2) is NOT D. (1) 43 seconds (2) is

ILT 2204 Written Exam 50

50.

Unit 2 is operating at 100% RTP when a Control Air leak develops, resulting in the following indication:

Given the indication, which ONE of the following identifies the correct plant status in accordance with 0-AOI-32-1, Loss of Control and Service Air Compressors?

A. 0-FCV-33-1, SERVICE AIR CROSSTIE VALVE, is CLOSED B. 2-PCV-032-3901, CONTROL AIR CROSSTIE, is CLOSED C. 2-FCV-2-130, CONDENSATE DEMIN BYP VALVE, is OPEN D. OUTBOARD MAIN STEAM ISOLATION VALVES are CLOSED

ILT 2204 Written Exam 51

51.

In accordance with OPDP-1, Conduct of Operations, a plant announcement (1) required prior to starting A2 RHRSW Pump.

In accordance with 0-OI-23, Residual Heat Removal Service Water System, after starting A2 RHRSW Pump, a minimum flow of (2) is required to prevent pump damage.

A. (1) is (2) 1350 gpm B. (1) is (2) 1700 gpm C. (1) is NOT (2) 1350 gpm D. (1) is NOT (2) 1700 gpm

ILT 2204 Written Exam 52

52.

Unit 2 is operating at 100% RTP, when the following conditions occur:

  • PANEL 2-9-9 CABINET 1, 2, 3, or 6 CONTROL POWER TRANSFER (2-9-7A, Window 15) alarms
  • RPIS INOPERABLE (2-9-5A, Window 35) alarms Given the conditions above, the power supply to (1) has tripped.

During the failure, movement of Control Rods can be accomplished by (2).

A. (1) Unit Preferred, Panel 2-9-9 Cabinet 6 (2) SCRAM ONLY B. (1) Unit Preferred, Panel 2-9-9 Cabinet 6 (2) SCRAM OR 2-HS-85-48, CRD CONTROL SWITCH C. (1) I & C A, Panel 2-9-9 Cabinet 2 (2) SCRAM ONLY D. (1) I & C A, Panel 2-9-9 Cabinet 2 (2) SCRAM OR 2-HS-85-48, CRD CONTROL SWITCH 15 PANEL 9-9 CABINET 1,2,3 OR 6 CONTROL POWER TRANSFER 35 RPIS INOPERABLE

ILT 2204 Written Exam 53

53.

In accordance with 2-OI-85, Control Rod Drive System, Rod Worth Minimizer (RWM) is manually bypassed using a (1) switch.

RWM will automatically bypass when Total (2) is (are) greater than 22%.

A. (1) keylock (2) Feedwater Flow ONLY B. (1) keylock (2) Feedwater AND Steam Flow C. (1) pushbutton (2) Feedwater Flow ONLY D. (1) pushbutton (2) Feedwater AND Steam Flow

ILT 2204 Written Exam 54

54.

Unit 3 is in MODE 3 with Loop I RHR in Shutdown Cooling when the following conditions occur:

  • A Drywell leak occurs
  • Drywell Pressure rises to 2.7 psig
  • Reactor Pressure is 105 psig In accordance with the appropriate ARP, (1) automatically closed when Reactor Pressure reached (2).

Note: 3-FCV-74-47, RHR SHUTDOWN COOLING SUCTION OUTBOARD ISOLATION VALVE 3-FCV-74-48, RHR SHUTDOWN COOLING SUCTION INBOARD ISOLATION VALVE A. (1) ONLY 3-FCV-74-47 (2) 95 psig B. (1) ONLY 3-FCV-74-47 (2) 100 psig C. (1) 3-FCV-74-47 AND 3-FCV-74-48 (2) 95 psig D. (1) 3-FCV-74-47 AND 3-FCV-74-48 (2) 100 psig 32 RHR SYS I/II DISCH OR SD CLG HDR PRESS HIGH 3-PA-74-51

ILT 2204 Written Exam 55

55.

In accordance with 0-OI-39, CO2 System, the initiation of CO2 into the EDG rooms is (1).

If the CO2 System has initiated in an EDG room, then the respective EDG (2) receive an automatic trip signal.

A. (1) automatic ONLY (2) does B. (1) automatic ONLY (2) does NOT C. (1) automatic OR manual (2) does D. (1) automatic OR manual (2) does NOT

ILT 2204 Written Exam 56

56.

The Drywell to Suppression Chamber Vacuum Breakers will automatically open when differential pressure reaches a maximum of (1) (Drywell Pressure relative to Suppression Chamber Pressure).

Drywell to Suppression Chamber Vacuum Breaker position can be monitored on Panel (2).

A. (1) 0.5 psid (2) 2-9-3 B. (1) 0.5 psid (2) 2-9-4 C. (1) 0.25 psid (2) 2-9-3 D. (1) 0.25 psid (2) 2-9-4

ILT 2204 Written Exam 57

57.

Unit 2 is operating at 100% RTP with the following plant conditions:

  • Reactor Water Level is (-) 75 inches and lowering
  • Reactor Pressure is 350 psig and lowering
  • Drywell Pressure is 13 psig and lowering
  • Suppression Chamber Pressure is 14 psig and lowering Subsequently:
  • 2-XS-74-122, RHR SYSTEM I LPCI 2/3 CORE HEIGHT OVERRIDE has been placed in MANUAL OVERRIDE
  • 2-XS-74-121, RHR SYS I CONTAINMENT SPRAY/COOLING VALVE SELECT has been placed in SELECT The RHR Loop I Containment Spray Valves will AUTOMATICALLY close when A. RPV Level drops below (-) 122 inches B. RPV Level drops below (-) 183 inches C. Drywell Pressure drops below 1.96 psig D. Suppression Chamber Pressure drops below 1.96 psig

ILT 2204 Written Exam 58

58.

A trip of 4KV Shutdown Board (1) would cause a loss of 1B Fuel Pool Cooling Pump.

The MINIMUM Fuel Pool Temperature which requires entry into 1-EOI-3, Secondary Containment Control, is (2).

A. (1) B (2) 125 F B. (1) B (2) 150 F C. (1) C (2) 125 F D. (1) C (2) 150 F

ILT 2204 Written Exam 59

59.

Unit 2 is performing a startup at 30% RTP when an event occurs resulting in the following conditions:

  • Reactor Water Level peaked at (+) 50 inches
  • All Reactor Feedwater Pump Turbines (RFPTs) tripped Given the conditions above and in accordance with 2-OI-3, Reactor Feedwater System, the RFPTs tripped due to (1).

Subsequently, conditions were restored to normal. In order to meet a RFP start permissive, the respective (2) valve must be OPEN.

A. (1) High Reactor Water Level (2) discharge B. (1) High Reactor Water Level (2) suction C. (1) Low Main Condenser Vacuum (2) discharge D. (1) Low Main Condenser Vacuum (2) suction

ILT 2204 Written Exam 60

60.

Unit 1 is operating at 100% RTP when the following conditions occur:

  • NO Operator actions have been taken Given the conditions above and in accordance with 1-AOI-70-1, Loss of Reactor Building Closed Cooling Water, the Operator will IMMEDIATELY (1) and ENSURE 1-FCV-70-48, RBCCW SECTIONALIZING VALVE automatically (2).

A. (1) secure RWCU pumps (2) closed B. (1) secure RWCU pumps (2) opened C. (1) start the spare RBCCW pump (2) closed D. (1) start the spare RBCCW pump (2) opened 12 RBCCW PUMP DISCH. HDR PRESS LOW 1-PA-70-15

ILT 2204 Written Exam 61

61.

Unit 2 is operating at 100% RTP when the following occurs:

An annunciator with an invalid input has been disabled in accordance with OPDP-4, Annunciator Disablement.

The annunciator window is required to be flagged with a (1) magnetic border and a narrative log entry (2) required to made.

A. (1) white (2) is NOT B. (1) white (2) is C. (1) blue (2) is NOT D. (1) blue (2) is

ILT 2204 Written Exam 62

62.

Unit 1 was operating at 100% RTP when an event resulted in the following conditions:

  • Reactor Pressure peaked at 1300 psig
  • Reactor Water Level indicates (-) 170 inches Given the conditions above, the Tech Spec Safety Limit for (1) has been violated.

The REQUIRED ACTION is to restore within the Reactor Safety Limit and insert ALL insertable Control Rods within (2).

A. (1) Reactor Pressure (2) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> B. (1) Reactor Pressure (2) 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> C. (1) Reactor Water Level (2) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> D. (1) Reactor Water Level (2) 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />

ILT 2204 Written Exam 63

63.

In accordance with the PC Pressure leg of 2-EOI-2, Primary Containment Control and the associated Bases, Suppression Chamber Sprays are initiated to prevent (1) when Primary Containment Pressure cannot be maintained below (2).

A. (1) chugging in the downcomers (2) 1.96 psig B. (1) chugging in the downcomers (2) 2.45 psig C. (1) over-pressurizing the Suppression Chamber (2) 1.96 psig D. (1) over-pressurizing the Suppression Chamber (2) 2.45 psig

ILT 2204 Written Exam 64

64.

Unit 1 was conducting a Refueling Outage when the following conditions occurred:

  • Bridge Operator lowered a fuel assembly into the Reactor Core
  • Unexpected criticality is observed in the Main Control Room Given the above conditions, in accordance with 1-AOI-79-2, Inadvertent Criticality During Incore Fuel Movements, the Bridge Operator is required to IMMEDIATELY __________.

A. ISOLATE RWCU B. STOP the CRD Pump C. START an SLC Pump D. REMOVE the fuel assembly from the Reactor Core

ILT 2204 Written Exam 65

65.

In accordance with NPG-SPP-22.206, Verification Program, (1) verification is used for a locked throttle valve, and activities involving radiation exposure of greater than 10 mrem Total Effective Dose Equivalent (TEDE) (2) be exempted from verification requirements.

A. (1) concurrent (2) can B. (1) concurrent (2) can NOT C. (1) independent (2) can D. (1) independent (2) can NOT

ILT 2204 Written Exam 66

66.

Unit 1 is operating at 100% RTP.

Isolating Extraction Steam to the 1A1 Feedwater Heater will cause Reactor Core Thermal Power to (1) and steam cycle efficiency will (2).

A. (1) lower (2) rise B. (1) lower (2) lower C. (1) rise (2) rise D. (1) rise (2) lower

ILT 2204 Written Exam 67

67.

Which ONE of the following sets of conditions satisfies the Tech Spec definition of MODE 3?

A. A Reactor SCRAM has just occurred. The MODE SWITCH is in SHUTDOWN.

Moderator Temperature is 480 ºF. The MSlVs are closed.

B. The Reactor is shutdown. The MODE SWITCH is in START&HOT STBY. Moderator Temperature is 180 ºF. All Control Rods are fully inserted.

C. Preparations are in progress for a Reactor Startup. The MODE SWITCH is in SHUTDOWN. Moderator Temperature is 135 ºF. All Control Rods are fully inserted.

D. The Reactor is shutdown. The MODE SWITCH is in REFUEL. Moderator Temperature is 140 ºF. All Reactor Vessel Head Closure Bolts are NOT fully tensioned.

ILT 2204 Written Exam 68

68.

Unit 1 is operating at 100% RTP.

In an operating cooling water system, a higher stagnant fluid film thickness (1) the rate of heat transfer.

Stable film boiling is (2) efficient than nucleate boiling.

A. (1) raises (2) more B. (1) raises (2) less C. (1) lowers (2) more D. (1) lowers (2) less

ILT 2204 Written Exam 69

69.

A demineralizer works on the principle of mechanical (1).

A result of proper Radwaste and Condensate demineralizer operation on water with ionic impurities is that the exiting water will always have a (2) conductivity.

A. (1) filtration ONLY (2) lower B. (1) filtration ONLY (2) higher C. (1) AND chemical filtration (2) lower D. (1) AND chemical filtration (2) higher

ILT 2204 Written Exam 70

70.

In accordance with 0-OI-57C, 208V/120V AC Electrical System, Unit Preferred is operating in a normal lineup.

Using the 120VAC Distribution diagram, determine the correct answers below.

The attached diagram is specifically representative of (1) with Unit Preferred normally powered from the 480V RMOV Board, through the (2).

[REFERENCE PROVIDED]

A. (1) Unit 1 (2) rectifier/inverter, static switch AND breaker 1001 B. (1) Unit 1 (2) regulating transformer AND breaker 1002 C. (1) Unit 2 (2) rectifier/inverter, static switch AND breaker 1001 D. (1) Unit 2 (2) regulating transformer AND breaker 1002

ILT 2204 Written Exam 71

71.

In a comparison between a delayed neutron and a prompt neutron produced from the same fission event, the delayed neutron is more likely to _________.

A. leak out of the core B. fission a U-238 nucleus C. fission a Pu-240 nucleus D. become a thermal neutron

ILT 2204 Written Exam 72

72.

Referring to the drawing of effective neutron multiplication factor (keff) versus Core Age, which ONE of the following completes the statement below?

The major cause for the change in keff from point 3 to point 4 is the.

A. depletion of fuel B. depletion of Control Rods C. burnout of burnable poisons D. burnout of fission product poisons

ILT 2204 Written Exam 73

73.

Unit 1 has inserted a Reactor SCRAM with the following conditions:

  • Reactor Pressure is 885 psig
  • The NUSO has directed a cooldown using SRVs
  • The BOP has opened one SRV Given the conditions above, the tail pipe temperature for the open SRV will be approximately (1).

In accordance with Tech Spec 3.4.9, the MAXIMUM cooldown rate allowed is (2) per hour.

[REFERENCE PROVIDED]

A. (1) 200 °F (2) 90 °F B. (1) 200 °F (2) 100 °F C. (1) 300 °F (2) 90 °F D. (1) 300 °F (2) 100 °F

ILT 2204 Written Exam 74

74.

Unit 2 is operating at 100% RTP with the following conditions:

  • 250V REACTOR MOV BOARD 2B UNDERVOLTAGE (2-9-8C, Window 11) alarms
  • NO Operator actions have been taken Given the conditions above, 250V DC RMOV Board 2B provides (1) to its respective ECCS Analog Trip Unit (ATU) AND (2) ECCS ATU is de-energized.

A. (1) ONLY backup power supply (2) Division I, Panel 2-9-81 B. (1) ONLY backup power supply (2) Division II, Panel 2-9-82 C. (1) BOTH the normal AND backup power supply (2) Division I, Panel 2-9-81 D. (1) BOTH the normal AND backup power supply (2) Division II, Panel 2-9-82 11 250V REACTOR MOV BD 2B UV 2-EA-57-100

ILT 2204 Written Exam 75

75.

Control Rods that are located at position (1) in the Reactor Core are considered shallow.

The radial flux response to withdrawing a shallow Control Rod located at the PERIPHERY of the Core is based on a (2) fuel-moderator ratio.

A. (1) 10 (2) higher B. (1) 10 (2) lower C. (1) 40 (2) higher D. (1) 40 (2) lower

BFN ILT 2204 RO References as of 01/31/2022 REFERENCE PROVIDED to candidate (Verify ALL (1) hr / immediately are redacted)

05. REACTOR WATER LEVEL ABNORMAL (2-9-5A, Window 8)
06. 1-HS-63-6A, SLC Pump 1A/1B Pump/light indications and 1-ZI-63-8A/B, SLC Valve A/B Continuity lights and 1-IL-63-11, SLC Flow light indication
09. ECCS ANALOG TRIP UNIT TROUBLE (2-9-3E, Window 30)
14. SRM DOWNSCALE, (3-9-5A, Window 6), SRM HIGH/INOP, (3-9-5A, Window 13),

IRM CH A, C, E, G HI-HI/INOP, (3-9-5A, Window 33)

18. SGT TRAIN C FILTER BANK TEMP HIGH (2-9-3B, Window 25)
21. SERVICE AIR CROSSTIE VALVE OPEN (1-9-20B, Window 30)
34. MAIN STEAM LINE RADIATION HIGH-HIGH, (1-9-3A, Window 27),

OFFGAS AVERAGE ANNUAL RELEASE RATE EXCEEDED, (1-9-4C, Window 27)

37. OFFGAS POST TREATMENT RADIATION HIGH-HIGH, (2-9-4C, Window 34),

OFFGAS POST TREATMENT RADIATION MONITOR HI-HI-HI/INOP, (2-9-4C, Window 35)

44. RFWCS INPUT FAILURE (3-9-6C, Window 14)
47. 1-EOI Curve 3, Heat Capacity Temp Limit (HCTL)
50. Panel 2-9-20, 2-PI-32-88, Control Air Pressure
52. PANEL 2-9-9 CABINET 1, 2, 3, or 6 CONTROL POWER TRANSFER (2-9-7A, Window 15), RPIS INOPERABLE (2-9-5A, Window 35)
54. RHR SYS I/II DISCHARGE OR SHUTDOWN COOLING HEADER PRESSURE HIGH (3-9-3E, Window 32)
60. RBCCW PUMP DISCHARGE HEADER PRESSURE LOW (1-9-4C, Window 12)
70. Excerpt from 0-OI-57C, 208V/120V AC Elect Syst, Attachment 2 (Pg 1 of 1) Vital 120V AC Distribution diagram
72. keff vs. Core Age Graph
73. Steam Tables with Mollier Diagram
74. 250V REACTOR MOV BOARD 2B UNDERVOLTAGE (2-9-8C, Window 11)

Signature:

Date:

Name:

§ Do NOT make any stray marks on the page.

§ No credit will be given for improper marks.

Q If Side 2 is used, fill in ID on both sides.

@ G G Q Q G G Q Q Q Q

@ @ © © @ © ©

@ @ © @ © ©

© © ©

©©©©©©

@ @ © 9 @ ©

@©@©@@@

@ @ © @ © @

© © © 0 ©

© © © © O ©

@ © @ @ @ ©

© © ©

@ @ © @ @ © ©

© ©

© © © 4

Q C

G Q

Q Q

G C

Q G

/

Q

©©©©©

@@@0@

@ @ © © ©

@@@©@©

©

@@@@©

@ @ © O © ©

@ @ © @ ©

@ @ © © @ ©

© © ©

@@©@©@©©

©©©©©0©©

©

©

\\

C O C Q r g O Q J Q Q Q © @ C @. 3 Q O Q

C Q

V Q

Q 6

/

H

\\

Q Q

/

\\

@ © @ @ @ © ©

©©©©

@ @ © @ ©

© © 0 © ©

© © © 0 © ©

© © © ©

© © © ©

© 0 © ©

© © © 0 © ©

@ @ @ @ © 0 @

@ @ © © @ 0 @ © Q

Q O

Q O

Q D

O Q

V O

U m

Q Z

g

?

O 12 11

@ © © @ @ O © ©

© © © 0 © ©

@ @ @ @ @ © ©

@ @ © © 0 ©

@©©@©@©©

© © ©

@ © @ @ 0 @ ©

@ @ @ © @ © ©

© © © © © © 9 © © © LXROTESTT'V' Response Form LXR-20020

§ Mark responses darkly and fill completely.

Q Erase unwanted marks clearly.

§ Use black ink only.

©

© C

C C

C 5

C C

© C

C

@ C. C. @. C. @ C C @ C P Q C C. O C C @

Q

© O

O O

O

Q Q

C

©

©

§ O

© 9

3 3

6 V

© O

O O

Q C

O

©

©

©

©

© F Q O O O C O § C @ C @ @ C C C Q @ E C g E @. C @ Q.

T 9

O O

O C

Q C

C C

O C

C K

0 A

C C

C C

Q O

A K

A O

x

\\

E 7

6 6

77 Test: ILT 22054 ma ExAM Class:

Instructor:

READ CAREFULLY!

OK NOT OK 0

$ 6 9 Q @ D @ L O O O D C C O C § © @ O ©. @ "i @ @ < ©.

Q C C @ C C @ C D C @ @ @ @ @ C C @ D C O O O © § O D O O © Q O O @ O C O © O © © O O D © O O © D © C C O O © O A @ @ 0 0 0 © @ O O @ O O D © F @ @ O O O C C O O O @ @ O. @ O C O C T O D U O A O ~ O @ O @ @ O @ C @. @

Q C p l O u O O O O O O O O 123456739mnuwmmmnwwmm 4

um w

@@©@"$n

©

©

© © O @ W

© © © m

© O @ O O C O ( O O O O © O O C O O O C O O O O O

©

©

@ 0 9 0 0 \\ ( O J ? ) 3 @ @ O @ O O C O O O O O C C § @ O Q O C

@ © © @

O O O O © © © \\ < w O O O © O O O O O O O C O G 0 0 0 0 0 0 0 3 0 0

©

©

©

©

©

@ @ @ ©

© © © © C

O O

O O

Q O

E O

O O

Q M

O O

O

© O

O O

O O

O O

© O

O O

Q O

O

O O

E O O O © 9 © Q A L O O O O O O S O 3 E @ O Q O O Q

@ 0 J @ © @ O "v b i Q O © © © © § C O O O O O E E

@ @ © © @ @ © @ C 9 8 C Q C C § § © E G C O C Q © § O C C Q C G

© @ @ G Q J @ @ @ @ E O A @ C O C O @ Q $ @ C E C @ O C @

_ _ _ _ _ _ - - - _ _ _ _ _ _ _ } _ _

Retrieved from "https://kanterella.com/w/index.php?title=ML22161A939&oldid=3794932"