ML21214A323

301 SRO Written - Applicant Version

ML21214A323
Person / Time
Site:	Farley
Issue date:	08/02/2021
From:	NRC/RGN-III
To:
References
Download: ML21214A323 (109)

Text

ES-401 Site Specific SRO Written Examination Cover Sheet Form ES-401-8 U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date:

Facility/Unit: FARLEY 1 & 2 Region:

I II III IV Reactor Type: W CE BW GE Start Time:

Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80 percent overall, with 70 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80 percent to pass. You have 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> to complete the combined examination and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO-only portion.

Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicants Signature Results RO/SRO-Only/Total Examination Values ______ / ______ / ______ Points Applicants Score ______ / ______ / ______ Points Applicants Grade ______ / ______ / ______ Percent ML21214A323

1. Given the following:

Unit 1 Reactor startup is in progress per UOP-1.2, Startup of Unit from Hot Standby to Minimum Load.

Reactor Power is 13%.

The CONTROL ROD MOTION switch has just been released following a rod withdrawal.

Control rods continue to step out.

Subsequently:

The crew enters AOP-19.0, Rod Control Malfunction.

The ROD CONTROL BANK SELECTOR SWITCH (RCBSS) is placed in AUTO.

Control rods continue to step out.

TAVG -TREF deviation is +2°F and rising.

Which one of the following completes the statements below?

Operators are required to (1).

Without additional operator action, C-1, IR Hi Flux Rod Stop, (2) stop outward rod motion if the applicable setpoint is reached.

(1) monitor rod motion and ensure rod motion stops when Tavg and Tref are matched within 1°F (2) does NOT (1) manually Trip the Reactor (2) does NOT (1) monitor rod motion and ensure rod motion stops when Tavg and Tref are matched within 1°F (2) DOES (1) manually Trip the Reactor (2) DOES A.

B.

C.

D.

2. Given the following:

Unit 1 is at 100% power.

Which one of the following completes the statements below per TS 3.4.10, Pressurizer Safety Valves?

The purpose of the three Pressurizer Code Safety Valves is to ensure RCS pressure does not exceed (1).

When (2) Pressurizer Safety Valve(s) is (are) INOPERABLE, the Tech Spec completion time to restore operability is 15 minutes.

Do not apply Risk Informed Completion Time Program allowances (1)

(2) 2735 psig ONE 2735 psig TWO 2400 psig ONE 2400 psig TWO A.

B.

C.

D.

3. Given the following:

Unit 1 Reactor startup is in progress per UOP-1.2, Startup of Unit from Hot Standby to Minimum Load.

Reactor power is 4% and stable.

Subsequently:

Control Bank D rod H2 falls to the bottom of the core.

Rod H2 position has been confirmed.

Which one of the following completes the statements below?

Per AOP-19.0, Malfunction of Rod Control System, the operating crew (1) required to shutdown the Reactor.

From steady state to steady state, Shutdown Margin is (2) after Rod H2 falls to the bottom of the core.

(1)

(2)

IS NOT affected IS reduced is NOT NOT affected is NOT reduced A.

B.

C.

D.

4. Given the following:

Unit 1 is in MODE 3.

The Shutdown Banks are withdrawn.

Which one of the following completes the statements below in accordance with LCO 3.4.5, RCS Loops - MODE 3?

(1) RCS loop(s) is(are) required to be OPERABLE and in operation.

If no RCS loops are in operation, the Reactor Trip Breakers (2) required to be opened.

(1) TWO (2) are NOT (1) TWO (2) ARE (1) ONE (2) are NOT (1) ONE (2) ARE A.

B.

C.

D.

5. Given the following:

A manual Reactor Trip and Safety Injection was initiated on Unit 1.

At 10:00:

The following indications were available during diagnostics of EEP-0.0, Reactor Trip or Safety Injection:

- AFW flow is controlled at an equal value for all SGs to control RCS temperature.

- Containment pressure is 1.2 psig.

- All MSIVs are open.

At 10:45:

The crew has progressed through the actions of EEP-3.0, Steam Generator Tube Rupture and the following conditions exist:

- Containment pressure is 1.2 psig.

- Normal charging has been aligned.

- Pressurizer level is 67% and rising.

Which one of the following describes the required actions to minimize RCS to secondary leakage per EEP-3.0?

Reference Provided Reduce charging flow ONLY Reduce RCS pressure ONLY Turn on PRZR heaters ONLY Reduce RCS pressure and Reduce charging flow A.

B.

C.

D.

6. Which one of the following is one of the power supplies to Unit 1 LT-459A, PRZR LVL?

1A 120VAC Vital panel 1B 120VAC Vital panel 1C 120VAC Vital panel 1D 120VAC Vital panel A.

B.

C.

D.

7. Which one of the following completes the statement below?

MOV-8701B, 1C RCS LOOP TO 1A RHR PUMP, is powered from.

600V MCC 1U 600V MCC 1V 600V MCC 1F 600V MCC 1G A.

B.

C.

D.

8. Which one of the following completes the statements below?

An "S" signal (1) required to cause MOV-8811A and MOV-8812A, CTMT SUMP TO 1A RHR PUMP, to automatically open when RWST level lowers to 50,000 gal.

This automatic actuation (2) be reset at the MCB.

(1) is NOT (2) CAN (1) is NOT (2) can NOT (1) IS (2) CAN (1) IS (2) can NOT A.

B.

C.

D.

9. Given the following:

Unit 1 has experienced a Large Break LOCA.

ESP-1.3, Transfer to Cold Leg Recirculation, has been completed.

Subsequently:

The Shift Supervisor directs the OATC to perform ESP-1.4, Transfer to Simultaneous Cold and Hot Leg Recirculation and the following occurs:

- Power is lost to the 1G 4160V Bus and will not be restored for 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.

Which one of the following completes the statement below?

At the completion of ESP-1.4, the running LHSI pump will be aligned for (1) leg recirculation and the running HHSI pump will be aligned for (2) leg recirculation.

(1)

(2)

HOT COLD COLD COLD HOT HOT COLD HOT A.

B.

C.

D.

10. Per SOP-1.2, Reactor Coolant Pressure Relief System, which one of the following completes the statements below?

During normal operation, the PRT temperature should not exceed a maximum temperature of (1).

The alternate method to cooldown the PRT is using (2).

(1) 120°F (2) spray from RMWST and draining to the RCDT (1) 170°F (2) spray from RMWST and draining to the RCDT (1) 120°F (2) recirculation through the RCDT heat exchanger (1) 170°F (2) recirculation through the RCDT heat exchanger A.

B.

C.

D.

11. Given the following:

Unit 1 is at 100% power.

The Unit 1 'B' train Rx Trip Bypass breaker is closed.

The Unit 1 'B' train Rx Trip Breaker is open.

Subsequently:

A loss of the 'A' Train Auxiliary Building 125V DC Bus occurs.

The crew takes the MCB Reactor Trip handswitch to TRIP.

Which one of the following completes the statements below?

The 'A' train Rx trip breaker (1) be Open.

The 'B' train Bypass breaker (2) be Open.

(1)

(2) will NOT will NOT WILL will NOT WILL WILL will NOT WILL A.

B.

C.

D.

12. Given the following:

A Pressurizer steam space break has occurred on Unit 1.

Containment pressure has risen to 2 psig and is stable.

ESP-1.2, Post LOCA Cooldown and Depressurization, is in progress.

The operating crew is at the step to "Check if normal charging should be established."

- The 1A Charging pump is running.

- Subcooling requirements are met.

- Pressurizer level is 30% and rising.

Which one of the following completes the statements below?

Normal Charging (1) be established with current plant conditions.

Once normal Charging is established, the crew will re-initiate HHSI if subcooling cannot be maintained above (2).

(1) can NOT (2) 45°F (1) can NOT (2) 16°F (1) CAN (2) 45°F (1) CAN (2) 16°F A.

B.

C.

D.

13. Given the following:

Unit 1 is 100% power.

At 1000:

The On service CCW pump trips on overload.

At 1005:

A complete loss of offsite power occurs.

Which one of the following completes the statements below?

At 1000, the standby CCW pump (1) automatically start.

At 1006, the standby CCW pump (2) running.

(1)

(2) will NOT is NOT WILL is NOT will NOT IS WILL IS A.

B.

C.

D.

14. Given the following:

Unit 1 has experienced a small break LOCA.

ESP-1.2, Post LOCA Cooldown and Depressurization is in progress.

The following conditions are observed:

- Containment pressure is 1.5 psig.

- Both RHR pumps are running and aligned to the RWST.

- RCS pressure is 270 psig and stable.

Which one of the following completes the statements below?

Per ESP-1.2, The operating crew (1) required to stop both RHR pumps.

If stopped, the RHR pumps (2) automatically restart if RCS pressure subsequently begins to lower.

(1)

(2)

IS will NOT IS WILL is NOT will NOT is NOT WILL A.

B.

C.

D.

15. Given the following:

Unit 1 is in MODE 3.

STP-45.16, PORV Testing Below P11 / Auto SI Blocked is in progress.

RCS pressure is 1875 psig.

Subsequently:

PCV445A, PRZR PORV, handswitch is placed in the OPEN position.

Which one of the following completes the statements below?

With PCV-445A handswitch in the OPEN position, PCV-445A (1) automatically close with no further operator action.

The PRT rupture discs will rupture if the pressure in the PRT exceeds a minimum of (2).

(1)

(2)

WILL 100 psig will NOT 100 psig WILL 150 psig will NOT 150 psig A.

B.

C.

D.

16. What action(s) is(are) required during implementation of ECP-1.1, Loss of Emergency Coolant Recirculation, if the RWST level lowers to 4.5 feet?

Attempt to start a RCP.

Stop Containment Spray Pumps ONLY.

Stop all safeguards pumps taking suction from RWST.

Use the PORVs or SPRAYs to rapidly depressurize the RCS and inject the accumulators.

A.

B.

C.

D.

17. Which one of the following completes the statement below?

600V LCC 1N is the power supply for the Pressurizer Heater Group(s).

1A 1B 1C and 1D 1E A.

B.

C.

D.

18. Given the following:

Unit 1 is operating at 100% power.

All control rods are at 227 steps.

DRPI is aligned to MCC 1D breaker HDN6L, NORMAL power supply.

Subsequently:

A complete loss of all Offsite power occurs.

Which one of the following completes the statements below 5 minutes after the complete loss of all Offsite power?

Rod bottom lights are (1).

Rod Group step counters indicate (2).

(1)

(2) illuminated 227 steps illuminated 0 steps extinguished 227 steps extinguished 0 steps A.

B.

C.

D.

19. Given the following:

Unit 1 is at 100% power.

Which one of the following completes the statements below?

As RCS pressure lowers, the (1) trip setpoint lowers.

The Reactor trip selected above is designed to ensure the (2) is not exceeded.

1)

OPT

2) DNBR limit

1)

OPT

2) allowable heat generation rate (kW/ft) of the fuel

1)

OTT

2)

DNBR limit

1)

OTT

2) allowable heat generation rate (kW/ft) of the fuel A.

B.

C.

D.

20. Which one of the following completes the statements below?

The minimum number of Containment Pressure channels that must sense the HI-3 pressure setpoint to generate an automatic Containment Spray Actuation is (1).

The Containment Hi-3 bistables are a(n) (2) to actuate design to initiate a Containment Spray Actuation.

(1)

(2)

TWO DEENERGIZE TWO ENERGIZE THREE DEENERGIZE THREE ENERGIZE A.

B.

C.

D.

21. Which one of the following completes the statements below?

A loss of DRPI input to the plant computer (1) cause FF5, COMP ALARM ROD SEQ/DEV OR PR FLUX TILT, to alarm.

If the plant computer becomes INOPERABLE and cannot be restored for four hours, the operating crew (2) required to perform STP-37.0, Power Distribution Surveillance (Plant Computer Inoperable).

(1)

(2)

WILL is NOT WILL IS will NOT is NOT will NOT IS A.

B.

C.

D.

22. Given the following:

Unit 1 is operating at 6% power.

Subsequently the 1B RCP trips.

AOP-4.0, Loss of Reactor Coolant Flow, is in progress.

Which one of the following completes the statements below?

1B Loop Tavg will (1).

A Reactor Trip is required when any loop's Tavg lowers below a maximum of (2).

(1)

(2)

RISE 545°F RISE 541°F LOWER 545°F LOWER 541°F A.

B.

C.

D.

23. Given the following:

Unit 1 is operating at 100% power.

A short circuit occurs in PT-445, PRZR PRESS, instrument output.

Actual Pressurizer Pressure remains stable.

Which one of the following completes the statement below?

The use of will ensure that PT-445 will not input into the Reactor Protection System.

an isolation device a median signal selector an independent control channel a de-energize to actuate bistable A.

B.

C.

D.

24. Given the following:

ECP-0.0, Loss of all AC Power, is in progress on Unit 1.

The TSC has determined that core damage has occurred.

Several CETCs indicate a short circuit.

Which one of the following completes the statements below?

The CETCs experiencing a short circuit will indicate (1) temperature.

Per ECP-0.0, if the CETCs are inoperable, the operating crew will use (2) to determine if the Severe Accident Guidelines (SAG) are required to be entered.

(1) minimum (2) Thot (1) minimum (2) Tcold (1) maximum (2) Thot (1) maximum (2) Tcold A.

B.

C.

D.

25. Given the following:

Unit 1 was operating at 100% power with the following conditions:

- 1A is selected on the CTMT CLR FANS A TRN SEL SWITCH.

- All Containment Cooler fans are running in FAST speed.

At 1000 A Large Break LOCA occurred with the following conditions:

- Containment pressure reached 33 psig.

- A Dual Unit complete loss of Offsite power occurred.

- EEP-0, Reactor Trip or Safety Injection, is in progress.

At 1010 The 1A Containment Cooler fan tripped.

Which one of the following completes the statements below at 1010?

Per EEP-0, the operating crew will verify at least one Containment Cooler fan per train is running in (1) speed.

The 1B Containment Cooler (2) automatically start when the 1A Containment Cooler fan trips.

(1)

(2)

SLOW will NOT SLOW WILL FAST will NOT FAST WILL A.

B.

C.

D.

26. Given the following:

Unit 1 is operating at 100% power.

Subsequently:

A Feedwater break occurs in Containment and the following is observed:

- Containment Temperature is 175°F.

- Containment Pressure is 22 psig.

Which one of the following completes the statement below?

Each Containment cooler will have (1) Service water flow and the fan discharge will be through the (2).

(1)

(2) 800 gpm dropout plate 800 gpm ductwork 2000 gpm dropout plate 2000 gpm ductwork A.

B.

C.

D.

27. Given the following:

At 1000:

Unit 1 is operating at 100% power.

Charging flow is 70 gpm.

Letdown flow is 76 gpm.

Seal Injection Flow is 8 gpm per RCP.

RCP # 1 seal leakoff flow is 3 gpm per RCP.

At 1030:

LCV-459, LTDN LINE ISO, fails closed and cannot be reopened.

At 1045:

Unit 1 is operating at 100% power.

AOP-16.0, CVCS Malfunction is in progress.

Charging flow is 50 gpm.

Excess Letdown is in service and is at design flow rate.

Seal Injection Flow is 7gpm per RCP.

RCP # 1 seal leakoff flow is 3 gpm per RCP.

Which one of the following completes the statements below?

At 1000, the Pressurizer level was (1).

At 1045, per AOP-16.0, the operating crew is required to (2) Charging flow to maintain it on programmed level.

(1)

(2)

RISING LOWER RISING RAISE LOWERING LOWER LOWERING RAISE A.

B.

C.

D.

28. Given the following:

Unit 1 is in Mode 5 1B RHR train is in service in the cooldown mode.

1A RHR train is in standby for cooldown.

1C CCW pump is tagged out to have the motor rebuilt.

1B and 1A CCW pumps are both in operation.

Subsequently:

The 1A CCW pump trips.

Which one of the following completes the statements below?

AOP-9.0, Loss of Component Cooling Water, (1) applicable in the current Mode.

Per AOP-12.0, Residual Heat Removal System Malfunction, the operating crew (2) required to place the 1A RHR train in the cooldown mode.

(1)

(2)

IS is NOT IS IS is NOT is NOT is NOT IS A.

B.

C.

D.

29. Given the following:

Unit 1 is operating at 100%.

AOP-9.0, Loss of Component Cooling Water, is in progress.

RCP motor bearing temperatures reach 200°F.

Which one of the following completes the statement below per AOP-9.0?

The ON SERVICE train (1) affected A Reactor trip (2) required.

(1)

(2)

IS IS IS is NOT is NOT IS is NOT is NOT A.

B.

C.

D.

30. Which one of the following completes the statements below?

The 1A Containment Spray (CS) Pump is powered from the 4160V AC bus.

1A 1H 1K 1F A.

B.

C.

D.

31. Which one of the following completes the statements below during the performance of FRP-S.1, Response to Nuclear Power Generation/ATWT?

The reason(s) for tripping the Main Turbine during an ATWT is to (1).

The first verification that the Main Turbine has tripped will be to check Turbine (2) position on TSLB-2.

(1) raise RCS pressure to prevent void formation (2) Throttle Valve (1) raise RCS pressure to prevent void formation (2) Governor Valve (1) prevent an uncontrolled cooldown of the RCS (2) Throttle Valve (1) prevent an uncontrolled cooldown of the RCS (2) Governor Valve A.

B.

C.

D.

32. Given the following:

Unit 1 is in Mode 3.

The appropriate section of SOP-12.2, Containment Purge and Pre-access Filtration System has been completed.

Which one of the following completes the statements below?

The (1) supply and exhaust fans are running and discharging directly to the (2).

(1) Main Purge (2) main exhaust plenum (1) Main Purge (2) plant vent stack (1) Mini purge (2) main exhaust plenum (1) Mini purge (2) plant vent stack.

A.

B.

C.

D.

33. Given the following:

Unit 1 is operating at 100% power.

Which one of the following completes the statements below concerning the Spent Fuel Pool Cooling System for Unit 1?

The RWST is aligned to the (1) for Silica removal.

The RWST silica removal path will automatically isolate if RWST level lowers to a minimum of (2) gallons.

(1)

(2)

SFP Demineralizer 50,000 SFP Demineralizer 471,000 Boric Acid Recovery System (BARS) 50,000 Boric Acid Recovery System (BARS) 471,000 A.

B.

C.

D.

34. Given the following:

Unit 2 is at 85% reactor power and stable, holding for chemistry with the following conditions:

- Rod control is in MANUAL.

- Main FRV original positions are 68% open.

Subsequently:

A 50 MW step rise in load occurs.

Which one of the following predicts the final status of the Main Feed Regulating Valves (FRVs) position and SG water level?

The Main FRVs will return to a position of (1).

Each SG NR water level will return to (2).

(1)

(2) more than 68% open the original level 68% open the original level more than 68% open a level higher than the original level 68% open a level higher than the original level A.

B.

C.

D.

35. Given the following conditions on Unit 1:

At 1000:

Mode 6 with core off-load in progress.

Refueling Cavity level is 153 ft 6 in.

At 1015:

The Refueling Cavity level is lowering rapidly.

At 1030:

The Refueling Cavity level is stable.

Refueling Cavity level is 24 ft. above the Reactor Vessel Flange.

Which one of the following completes the statements below?

At 1015, AOP-30.0, Refueling Accident, (1) required to be entered.

LCO 3.9.6, Refueling Cavity Water Level, (2) required to be entered.

(1)

(2)

IS is NOT is NOT is NOT IS IS is NOT IS A.

B.

C.

D.

36. Given the following:

Unit 1 is in Mode 3 AOP-2.0, Steam Generator Tube Leak, is in progress due to a leak In the 1A SG.

The Control Room crew is preparing for an RCS cooldown.

1A MSIV and bypass valves are closed.

• 1A SG pressure is 1035 psig.

1B AND 1C SG pressures are 1005 psig.

Desired subcooling is 32°F.

Which one of the following completes the statements below?

The highest temperature that the RCS cooldown will be stopped at is (1).

Per AOP-2.0, the operating crew will use (2) to determine if cooldown is complete.

Reference Provided (1)

(2) 519°F Core exit T/C monitor 515°F Core exit T/C monitor 519°F RCS Hot Leg Temperature 515°F RCS Hot Leg Temperature A.

B.

C.

D.

37. Given the following:

• Unit 2 is performing the initial heatup of the RCS following a Refueling outage, with the following conditions:

- RCS temperature is 480°F.

- All MSIV's are closed.

- The Unit Operator is preparing to open the MSIV's per SOP-17.0, Main and Reheat Steam.

- ALL MSIV Bypass valves are open.

Which one of the following completes the statement below?

When warming up the Main Steam header, Main Steam header pressure should be monitored closely to prevent a.

Low Pressurizer Pressure Reactor Trip Low Steam Line pressure Safety Injection Steam Line Differential pressure Safety Injection High Steam Flow LO-LO Tavg Main Steam Line Isolation A.

B.

C.

D.

38. Given the following:

• Unit 1 is in Mode 3.

• RCS Tavg is being maintained at 520°F.

• RCS pressure is being maintained at 2235 psig.

The Steam Dumps are in service in the STM PRESS mode with the following conditions:

- The Steam Dump interlock Train A and B switches are in ON after both switches were taken to BYP INTLK and released.

- PK-464, STM HDR PRESS, is in AUTO.

Which one of the following describes the effect of PT-464, STM HDR PRESS, pressure transmitter failing high?

The RCS will experience a heat up transient which will continue until operator action is taken.

The RCS will experience a cooling transient which will continue until operator action is taken.

The RCS will experience a cooling transient which will be stopped by the automatic closure of the MSIVs on low Steam Generator pressure.

The RCS will experience a cooling transient which will be stopped by the automatic closure of the MSIVs due to a high steam flow condition coincident with LO LO Tavg.

A.

B.

C.

D.

39. Given the following:

Unit 1 is at 68% power and stable.

1. 4 Governor valve is closed and EH fluid is isolated to it.

1. 2 and #3 Governor valves are open and at 39%

Subsequently, the following indications are observed on the Turbine Control System-Operation Panel.

Which one of the following completes the statements below?

Opposed governor valve closure (1) occurred.

Per AOP-17.0, Turbine Load Reduction, the operating crew is required to (2).

(1) has NOT (2) trip the Reactor (1) has NOT (2) perform a rapid ramp to < 480 MW (1) HAS (2) trip the Reactor (1) HAS (2) perform a rapid ramp to < 480 MW A.

B.

C.

D.

40. Given the following:

Unit 2 is operating at 75% power.

Rod Control is in MANUAL.

Subsequently:

Lowering Main Condenser vacuum is observed and the following occurs:

- AOP-8.0, Partial Loss of Condenser Vacuum, is in progress.

- KK1, TURB COND VAC LO, is in alarm.

- Condenser vacuum is 3 psia and slowly degrading.

- Condenser Circ Water Outlet temperature is 90°F and stable.

- The unit is ramping down per AOP-17.1, Emergent Power Reduction.

- TAVG-TREF deviation is -4°F.

Which one of the following completes the statements below?

Per AOP-17.1, rods (2) allowed to be withdrawn to raise TAVG.

Per AOP-8.0, the operating crew will reduce Main Turbine load as necessary (1).

(1) are NOT (2) to maintain condenser pressure at or below the KK1 setpoint (1) ARE (2) to maintain condenser pressure at or below the KK1 setpoint (1) are NOT (2) to stabilize and hold condenser pressure at its current value (1) ARE (2) to stabilize and hold condenser pressure at its current value A.

B.

C.

D.

41. Given the following:

Unit 1 is at 100% power.

Subsequently:

A large feed header rupture occurs at the outlet of MOV-3232A, MFW to 1A SG STOP VLV.

Which one of the following completes the statements below?

Prior to the Reactor trip, RCS Tavg will (1).

The Reactor will automatically trip on (2).

Assume no operator action (1) RISE (2) Low Low SG Water Level (1) RISE (2) Low Steam Line pressure (1) LOWER (2) Low Low SG Water Level (1) LOWER (2) Low Steam Line pressure A.

B.

C.

D.

42. Given the following:

Unit 1 is operating at 100%.

Subsequently:

A complete loss of Offsite Power occurs.

ESP-0.2, Natural Circulation Cooldown to Prevent Reactor Vessel Head Steam Voiding, is in progress.

Which one of the following completes the statements below?

After the RCPs coast down, when natural circulation flow begins, loop T will (1).

Per ESP-0.2, the number of available (2) affects the required RCS subcooling that must be maintained during the natural circulation cooldown.

(1)

(2)

RISE Containment Coolers RISE CRDM Cooling fans LOWER Containment Coolers LOWER CRDM Cooling fans A.

B.

C.

D.

43. Given the following:

Unit 1 is operating at 100% power with the following conditions:

- A Steam leak occurs inside Containment.

- A manual Reactor trip was initiated.

- Tavg is 545°F.

Subsequently:

A Safety Injection is manually actuated.

Which one of the following completes the statements below?

The initial Feedwater Isolation was caused by (1).

After the Safety Injection, depressing the FW ISO RESET A and B TRN buttons (2) allow the FRVs to be reopened.

(1) the Safety Injection (2) WILL (1) the Safety Injection (2) will NOT (1) the P-4 signal with Lo Tavg (2) WILL (1) the P-4 signal with Lo Tavg (2) will NOT A.

B.

C.

D.

44. Given the following:

At 1000:

Unit 1 was operating at 100%

STP-22.12, Motor Driven Auxiliary Feedwater Check Valves Flow Verification, is in progress with the following conditions:

- 1A MDAFW pump is running.

- FI-3229, AFW Total Flow, reads 295 gpm.

- All MDAFW Pump FCV Handswitches are in MOD.

- MDAFWP Flow control valves are throttled as follows:

HIC-3227AA, MDAFWP TO 1A SG FLOW CONT - 81%

HIC-3227BA, MDAFWP TO 1B SG FLOW CONT - 0%

HIC-3227CA, MDAFWP TO 1C SG FLOW CONT - 0%

At 1002:

The 1A MDAFW pump trips.

At 1005:

Both SGFPs trip.

Which one of the following completes the statements below?

At 1002, the 1B MDAFW pump (1) automatically start.

At 1005, FCV-3227A, MDAFWPUMP TO STM GEN 1A, will (2) Open.

(1) WILL (2) go to 100%

(1) WILL (2) stay at 81%

(1) will NOT (2) go to 100%

(1) will NOT (2) stay at 81%

A.

B.

C.

D.

45. Given the following Unit 2 is at 38% power.

The 'A' Train is On Service.

STP-80.1, Diesel Generator 2B Operability Test, is in progress.

2B DG is running at full load on Unit 2.

Subsequently:

A loss of the B Train SW header occurs due to a rupture on the supply header resulting in the following conditions:

AOP-10.0, Loss of Train A or B Service Water, is implemented.

PI-3001A, SW TO CCW HX HDR PRESS, is 68 psig.

PI-3001B, SW TO CCW HX HDR PRESS, is 0 psig.

Which one of the following completes the statements below per AOP-10.0?

The operating crew (1) required to secure 2B DG.

The operating crew (2) required to start the 'A' train Charging pump.

(1)

(2)

IS IS IS is NOT is NOT IS is NOT is NOT A.

B.

C.

D.

46. Given the following:

DF13, 1H 4160 V bus tie to 1F 4160 V bus, tripped.

Service Water temperature is 70°F.

Which one of the following completes the statements below?

(1) automatically started as a direct result of this fault.

The 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> load limit for the Diesel Generator selected above is (2).

(1)

(2) 1-2A DG 4353 KW 1C DG 4353 KW 1-2A DG 3100KW 1C DG 3100 KW A.

B.

C.

D.

47. Given the following:

Unit 2 is operating at 25% power.

• 2A, 2B and 2C 4160V buses are being powered from the Startup Transformers.

Subsequently:

• 2A Startup Transformer becomes de-energized.

Which one of the following completes the statements below?

The (1) is(are) tripped.

An automatic Reactor trip (2) occur.

(1)

(2) 2A RCP WILL 2A RCP will NOT 2B and 2C RCPs WILL 2B and 2C RCPs will NOT A.

B.

C.

D.

48. Given the following:

Unit 1 is in MODE 3.

PC-3371A/B/C, 1A/B/C MS ATMOS REL VLV, are at 10% demand.

Breaker LA05, 1A 125V BATTERY (NORMAL), is tagged open for maintenance.

Subsequently:

A ground occurs on the 1A 125V DC bus and the following occurs:

- Breaker LA09, 1A BATTERY CHARGER (NORMAL), trips open.

Which one of the following completes the statements below?

The Main Steam Atmospheric Relief Valves (1) fail closed.

The Main Steam Atmospheric Relief Valves (2) be operated from the Lower Equipment Room.

(1)

(2)

WILL can NOT WILL CAN will NOT can NOT will NOT CAN A.

B.

C.

D.

49. Given the following:

Unit 1 has tripped due to a complete loss of Offsite power.

Which one of the following signals will trip the 1B Emergency Diesel Generator?

High Lube Oil temperature High Crankcase pressure Generator Phase Differential High Jacket Water temperature A.

B.

C.

D.

50. Given the following:

Unit 1 was operating at 100% power and the following occurs:

- The Fuel Oil Storage Tank (FOST) for 1-2A DG is empty.

- The Fuel Oil Day Tank for 1-2A DG is full.

Which one of the following completes the statement below?

With no operator action, the 1-2A DG will run at full load for.

2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 3 hours 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 24 hours A.

B.

C.

D.

51. Given the following:

Unit 1 is operating at 100%.

Subsequently:

A complete loss of Instrument Air has occurred.

Which one of the following completes the statements below?

SG NR levels will (1).

Per AOP-6.0, Loss of Instrument Air, the operating crew will align emergency air to the (2) using SOP-62.0, Emergency Air System.

(1) LOWER (2) MDAFW pump Flow Control Valves (1) RISE (2) MDAFW pump Flow Control Valves (1) LOWER (2) TDAFW pump Flow Control Valves (1) RISE (2) TDAFW pump Flow Control Valves A.

B.

C.

D.

52. Given the following:

Unit 1 has entered AOP-28.0, Control Room Accessibility.

The operating crew has manned the Hot Shutdown Panels (HSDP).

Which one of the following completes the statements below?

Per AOP-28.0, the operating crew will initially adjust HIK-122, CHG FLOW to (1).

If letdown automatically isolates, LCV-459 and LCV-460, LTDN LINE ISO, (2) be reopened from the HSDP.

(1)

(2) 50%

can NOT 50%

CAN 100%

can NOT 100%

CAN A.

B.

C.

D.

53. Given the following:

Unit 1 is operating at 100% when the following occurs:

- R-19, SGBD SAMPLE, fails HIGH.

Which one of the following completes the statements below?

If open, (1) valves will automatically close.

Per SOP-45.0, Radiation Monitoring System, the action required to obtain a sample of the SGs is to (2).

(1) HV-3328, HV-3329 AND HV-3330, STEAM GEN 1A/1B/1C SAMPLE ISO, (2) remove the INSTRUMENT power fuses for R-19 (1) HV-3328, HV-3329 AND HV-3330, STEAM GEN 1A/1B/1C SAMPLE ISO, (2) place the R-19 Operations Selector Switch in the RESET position (1) HV-3179A, 3180A, AND 3181A, STEAM GEN 1A/1B/1C LOWER BLOWDOWN, (2) remove the INSTRUMENT power fuses for R-19 (1) HV-3179A, 3180A, AND 3181A, STEAM GEN 1A/1B/1C LOWER

BLOWDOWN, (2) place the R-19 Operations Selector Switch in the RESET position A.

B.

C.

D.

54. Given the following:

At 1000:

Unit 1 is operating at 75% power.

FG5, GFFD SYS TRBL, is in alarm.

The GFFD indicates 1.2 x 105 cpm above background.

AOP-32.0, High Reactor Coolant Activity, is in progress.

Which one of the following completes the statements below at 1000?

A power reduction (1) required.

The instrumentation available per TS 3.3.3, Post Accident Monitoring (PAM)

Instrumentation is(are) (2).

(1) is NOT (2) R-27A and R-27B, Containment (High Range)

(1) is NOT (2) R-2, CTMT 155 FT (1) IS (2) R-27A and R-27B, Containment (High Range)

(1) IS (2) R-2, CTMT 155 FT A.

B.

C.

D.

55. Given the following:

Unit 1 is operating at 100% power.

'A' Train is On service.

At 1000:

PI-3001A, SW TO CCW HX HDR PRESS, indicates 40 psig.

At 1005:

The Outside SO reports an abnormal noise from the 1B SW pump.

The UO secures the 1B SW pump.

Which one of the following completes the statements below?

At 1000, AD4, SW PRESS A TRN LO, (1) in alarm.

In order to minimize SW loads on the affected train, AOP-10, Loss of Service Water, will direct isolating SW to (2).

(1) IS (2) Steam Generator Blowdown (1) IS (2) RCP Motor Air Coolers (1) is NOT (2) Steam Generator Blowdown (1) is NOT (2) RCP Motor Air Coolers A.

B.

C.

D.

56. Given the following:

Unit 1 is at 100% power.

Generator reactive load is currently at "0" MVARs.

ACC has notified the plant that system voltage problems require UNIT 1 to establish maximum allowable incoming reactive load (MVARS in).

Which one of the following completes the statements below?

The operator will (1) voltage to a establish the maximum allowable incoming reactive load.

Per UOP-3.1, Power Operation, the switch that will be used to establish the maximum allowable incoming reactive load is the (2) Voltage Adjust Switch.

(1)

(2)

RAISE Manual RAISE Auto LOWER Manual LOWER Auto A.

B.

C.

D.

57. Given the following:

MOV-514, 515, 516 AND 517, SW to TURB BLDG ISOs have inadvertently closed.

Which one of the following completes the statements below?

The Service Air Compressors (1) have cooling water supplied.

A back up source of cooling to the Condensate pumps (2) be aligned.

(1)

(2)

DO CAN DO can NOT do NOT CAN do NOT can NOT A.

B.

C.

D.

58. Which one of the following completes the statements below?

TCV-3083, LTDN HX CCW TEMP CONTROLLER, fails (1) on a loss of air.

This will result in adding (2) reactivity.

(1)

(2)

OPEN POSITIVE OPEN NEGATIVE CLOSED POSITIVE CLOSED NEGATIVE A.

B.

C.

D.

TV3083, LTDN HX COMPONENT COOLING WATER DISCH TCV

59. Given the following:

Unit 2 is at 100% power.

Containment average air temperature is 125°F.

Which one of the following completes the statements below?

A REQUIRED ACTION statement of LCO - 3.6.5 Containment Air Temperature, (1) required to be entered.

Per SOP-12.1, Containment Air Cooling System, MOV-3024A (B, C, D), EMER SW FROM 2A(2B, 2C, 2D) CTMT CLR VALVES, (2) be opened to lower Containment temperature.

(1)

(2)

IS can NOT IS CAN is NOT can NOT is NOT CAN A.

B.

C.

D.

60. Which one of the following completes the statements below Per NMP-OS-007-003, Plant Operating Orders?

(1) are Temporary instructions issued to plant operating personnel that address subjects NOT covered by existing plant operating procedures.

Night Orders and Standing Orders (2) deviate from plant design or regulatory documents.

(1)

(2)

Standing Orders CAN Standing Orders can NOT Night Orders CAN Night Orders can NOT A.

B.

C.

D.

61. Given the following:

Operations is preparing to rack out a circuit breaker The remote breaker racking tool is not available.

SOP-36.6, Circuit Breaker Racking Procedure, Attachment 1, Electrical Safety Checklist for OPS Activities, is being performed.

Which one of the following completes the statements below?

A second qualified individual (1) required to be at this activity.

Hearing protection (2) required for this activity.

(1)

(2) is NOT is NOT is NOT IS IS is NOT IS IS A.

B.

C.

D.

62. Unless otherwise directed by procedure, which one of the following completes the statements below per NMP-OS-007-001, Conduct of Operations Standards and Expectations?

Prior to manual operation, the power supply breaker to an MOV (1) required to be opened.

To throttle a manual valve, the valve is to be fully (2) then placed in the appropriate position.

(1)

(2) is NOT CLOSED is NOT OPENED IS CLOSED IS OPENED A.

B.

C.

D.

63. Unit 1 is operating at 100% power when the following occurs:

STP-4.1, 1A Charging Pump Quarterly Inservice Test, is in progress.

1A Charging pump failed to start when the handswitch was taken to START.

Which one of the following are the required actions per NMP-OS-007-001, General Instructions to Operations Personnel?

Write a condition report documenting the event and contact Maintenance.

Obtain Shift Manager's permission, take the handswitch to START a second time, and then write a condition report to document the event.

Rackout and perform a visual inspection of the circuit breaker and then write a condition report to document the event.

Take the handswitch to START a second time and then write a condition report to to document the event.

A.

B.

C.

D.

64. Which one of the following completes the statements below per the BASES of SL 2.1.1, Reactor Core Safety Limit (SL)?

Overheating of the fuel cladding is prevented by restricting fuel operation to within the (1) boiling region.

The proper functioning of the Reactor Protection System (RPS) and (2) prevents violation of the reactor core SLs.

(1)

(2) nucleate Main Steam Safety Valves nucleate Auxiliary Feedwater film Main Steam Safety Valves film Auxiliary Feedwater A.

B.

C.

D.

65. Which one of the following completes the statements below regarding access to the Dry Cask Storage Radiation Controlled Area (RCA)?

For routine access, the normal method for entry into the Dry Cask Storage RCA is (1) per FNP-0-AP-42.0, Radiological Protection Access Control.

Upon exiting the Dry Cask Storage RCA, the operator (2) required to be scanned via the main RCA exit whole body monitor per NMP-HP-302, Restricted Area Classification, Postings, and Access Control.

1) using an RCA access terminal

2)

IS

1) using an RCA access terminal

2) is NOT

1) manual log in via RP

2)

IS

1) manual log in via RP

2) is NOT A.

B.

C.

D.

66. You are assigned a task:

Your current TEDE is 1500 mrem.

Dose rate in the area you are required to work is 750 mr/hr.

Which one of the following is the maximum amount of time you can stay in the area without exceeding the FNP TEDE limit?

40 minutes 200 minutes 240 minutes 280 minutes A.

B.

C.

D.

67. Given the following:

The operating crew is performing the actions of AOP-29.0, Plant Fire.

The Fire Protection Water System is in use.

Which one of the following completes the statements below?

The operating crew is required to verify the (1) water system is aligned to the Fire Protection Water Storage Tanks.

If unable to maintain level in the Fire Protection Storage Tanks, then (2) Service Water is required to be aligned to the Fire Protection System.

(1)

(2)

SANITARY Unit 2 WELL Unit 2 SANITARY Unit 1 WELL Unit 1 A.

B.

C.

D.

68. Given the following:

ECP-0.0, Loss of All AC Power, is in progress on Unit 1.

The Shift Supervisor dispatches operators to minimize DC loads per

, Non Essential DC Loads.

Which one of the following completes the statement below?

One of the loads that will be de-energized by the operators is the (1).

Minimizing DC loads per Attachment 5 will extend the availability of the (2).

(1)

(2)

Waste Gas Panel MCB Indications Waste Gas Panel TDAFWP SPDS Computer System MCB Indications SPDS Computer System TDAFWP A.

B.

C.

D.

69. Given the following:

An ALERT has been declared on Unit 1.

The OATC has been directed to perform NMP-EP-142-F09, ALERT Public Address (PA) Announcement Script.

Which one of the following completes the statements below in accordance with NMP-EP-142-F09?

Emergency Response Personnel (1) required to report to their Emergency Response Facility.

The PA announcement for the ALERT is required to be repeated at a minimum of every (2) minutes.

(1)

(2) 0 ARE 15 minutes are NOT 15 minutes ARE 60 minutes are NOT 60 minutes A.

B.

C.

D.

70. Given the following:

ECP-1.2, LOCA Outside Containment, has been completed and the following is observed:

- RCS pressure is slowly lowering.

Subsequently:

A transition is made to ECP-1.1, Loss of Emergency Coolant Recirculation.

Which one of the following describes the reason that a transition was made to ECP-1.1?

To take additional actions to isolate the break.

To take appropriate actions to recover the plant after the break is isolated.

To take compensatory actions for lack of inventory in the Containment Sump.

To maximize SI flow to ensure core cooling and stabilize RCS pressure to maintain subcooling.

A.

B.

C.

D.

71. Given the following:

At 1000 A spurious Reactor trip has occurred on Unit 1.

FRP-H.1, Response to Loss of Secondary Heat Sink, is in progress.

The operating crew is attempting to establish Condensate flow to the SGs.

The UO is depressurizing the SGs.

At 1015 All SGs are at the required pressure per FRP-H.1.

SG WR levels are as follows:

- 1A SG: 29% and slowly lowering.

- 1B SG: 29% and slowly lowering.

- 1C SG: 29% and slowly lowering.

Which one of the following completes the statements below per FRP-H.1?

At 1000, the UO will prevent excessive opening of the Steam Dumps during the SG depressurization to (1).

At 1015, RCS Bleed and Feed criteria (2) met.

(1) prevent an automatic Main Steam Line isolation (2) is NOT (1) prevent an automatic Main Steam Line isolation (2) IS (1) prevent exceeding a 100°F in any 60 min cooldown rate (2) is NOT (1) prevent exceeding a 100°F in any 60 min cooldown rate (2) IS A.

B.

C.

D.

72. Given the following:

FRP-C.2, Response to Degraded Core Cooling, is in progress.

ECCS flow cannot be established.

The crew is depressurizing ALL Steam Generators to 160 psig.

The STA reports a RED condition on the Integrity CSF Status Tree.

Which one of the following completes the statements below?

The RED condition on the Integrity CSF Status Tree is due to (1).

FRP-P.1, Response to Imminent Pressurized Thermal Shock Conditions, is required to be entered (2).

(1) cooling down at the maximum attainable rate (2) immediately (1) Accumulators injecting (2) immediately (1) cooling down at the maximum attainable rate (2) upon completion of FRP-C.2 (1) Accumulators injecting (2) upon completion of FRP-C.2 A.

B.

C.

D.

73. Given the following:

Unit 1 is performing FRP-P.1, Response to Imminent Pressurized Thermal Shock Condition.

The crew has determined that a soak is required.

Which one of the following completes the statements below?

The operating crew is required to maintain RCS (1) stable for the duration of the soak.

The soak allows thermal gradients to be reduced, thus reducing corresponding (2) stresses on the Reactor vessel inner wall which are most limiting.

(1) temperature only (2) compressive (1) temperature and pressure (2) compressive (1) temperature only (2) tensile (1) temperature and pressure (2) tensile A.

B.

C.

D.

74. Given the following:

Unit 1 is in ESP-1.3, Transfer to Cold Leg Recirculation, and CS pumps are aligned to the containment sump.

Subsequently:

ECP-1.3, Loss of Emergency Coolant Recirculation Caused by Sump Blockage, has been entered.

Both Charging pumps have been secured.

• Both RHR pumps continue to have oscillating amps, discharge pressure and flow.

Which one of the following completes the statements below?

Per ECP-1.3, the operating crew is required to (1).

While in ECP-1.3, FRPs (2) required to be implemented.

(1) immediately secure both RHR pumps (2) are NOT (1) immediately secure both RHR pumps (2) ARE (1) reduce RHR flow by throttling FCV-605A(B), 1A(B) RHR HX BYP FLOW, for the 1A(B) RHR pump (2) are NOT (1) reduce RHR flow by throttling FCV-605A(B), 1A(B) RHR HX BYP FLOW, for the 1A(B) RHR pump (2) ARE A.

B.

C.

D.

75. Given the following:

ECP-2.1, Uncontrolled Depressurization of All Steam Generators, is in progress.

Containment pressure is 8 psig and rising.

AFW flow to each SG has been throttled to 20 gpm due to excessive plant cooldown.

Per ECP-2.1, which one of the following conditions would require raising AFW flow to more than 20 gpm?

RCS pressure is rising.

RCS subcooling is degrading.

A RED path occurs on Heat Sink.

RCS Hot leg temperatures are rising.

A.

B.

C.

D.

76. Which one of the following completes the statement below?

The BASES for reducing THERMAL POWER to less than or equal to 75%

in accordance with Tech Spec 3.1.4, Condition B, One rod not within alignment limits, REQUIRED ACTION B.2 is that it.

removes the requirement to determine QPTR minimizes the effect of a Control Rod ejection accident eliminates the requirement to re-evaluate specific accident analysis ensures local Linear Heat Rate increases will not exceed core design criteria A.

B.

C.

D.

77. Given the following:

Unit 1 is at 100% power.

1A RCP #1 Seal Leakoff is 7.5 gpm.

DC2, RCP #1 SEAL LKOF FLOW HI, is in alarm.

DA5, 1A RCP #2 SEAL LKOF HI, is clear.

RCDT level is stable.

1A RCP lower seal water bearing temperature has stabilized at 190°F.

1A RCP seal water outlet temperature has stabilized at 200°F.

Which one of the following completes the statements below?

A (1) is required per AOP-4.1, Abnormal Reactor Coolant Pump Seal Leakage, before securing the 1A RCP.

If it is determined that Seal Injection flow exceeds the limit of LCO 3.5.5 Seal Injection Flow, then the ECCS train may not be capable of delivering sufficient water following a (2).

1) normal Reactor Shutdown

2) Large Break LOCA ONLY

1) normal Reactor Shutdown

2) Large Break LOCA or adequate boration during a small break LOCA

1) Reactor trip

2) Large Break LOCA ONLY

1) Reactor trip

2) Large Break LOCA or adequate boration during a small break LOCA A.

B.

C.

D.

78. Given the following:

Unit 1 is in MODE 1 and performing STP-11.6, Residual Heat Removal Valves Inservice Test.

A time stroke of MOV-8889, RHR TO RCS HOT LEGS ISO, in the open direction has been performed.

Stroke times obtained were as follows:

- At 1000 First time stroke: 15.28 Secs

- At 1005 Second time stroke: 16.77 Secs Which one of the following completes the statements below?

MOV-8889 is (1).

The operating crew is required to (2).

Reference Provided (1) OPERABLE (2) have an analysis of the time stroke results performed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> to ensure that the stroke time represents acceptable valve operation (1) INOPERABLE (2) Initiate an ADMIN LCO until the valve can be stroked again.

(1) OPERABLE (2) have the deviation analyzed and update the Acceptable Stroke Time Range listed in the procedure within the next thirty (30) days (1) INOPERABLE (2) have MOV-8889 repaired or replaced A.

B.

C.

D.

79. Given the following:

Unit 1 is in MODE 3.

The Reactor trip breakers are open.

All RCPs are running.

PCV-444C, 1A LOOP SPRAY VLV, drifts open and becomes mechanically stuck.

Which one of the following completes the statements below per AOP-100, Instrumentation Malfunction?

The operating crew is required to secure the (1) RCP(s).

The operating crew (2) required to transition to AOP-4.0, Loss of Reactor Coolant Flow.

(1)

(2) 1A and 1B is NOT 1A and 1B IS only 1A is NOT only 1A IS A.

B.

C.

D.

80. Given the following:

Unit 1 has experienced a SB LOCA.

The operating crew was performing ESP-1.2, Post LOCA Cooldown and Depressurization.

The operating crew has not been able to establish any injection flow.

Subsequently:

The operating crew has transitioned to FRP-C.2, Response to Degraded Core Cooling, and the following conditions exist:

- SGs have just been depressurized to atmospheric pressure.

Which one of the following completes the statements below?

As downcomer voiding occurs, excore NI counts (1) rise.

When SI flow has been established and Core Cooling is restored, the operating crew is required to transition to (2).

(1) will NOT (2) ESP-1.2, Post LOCA Cooldown and Depressurization (1) WILL (2) ESP-1.2, Post LOCA Cooldown and Depressurization (1) will NOT (2) EEP-1, Loss of Reactor or Secondary Coolant (1) WILL (2) EEP-1, Loss of Reactor or Secondary Coolant A.

B.

C.

D.

81. Given the following:

Unit 1 is at 100% power.

PT-950, CTMT PRESS (Channel 1), was declared INOPERABLE.

Which one of the following completes the statements below?

The Safety Injection function coincidence (1) affected by the PT-950 malfunction.

Per Tech Spec 3.3.2, the REQUIRED ACTION is to place the PT-950 bistables in (2).

(1)

(2)

IS TRIP IS BYPASS is NOT TRIP is NOT BYPASS A.

B.

C.

D.

82. Given the following:

Unit 1 was operating at 60% power.

A ramp to 50% at 5 MW/min is in progress.

Subsequently:

A Pressurizer pressure malfunction occurs and RCS pressure lowers to 2200 psig.

AOP-100, Instrumentation Malfunction, is in progress.

Which one of the following completes the statements below?

A REQUIRED ACTION statement of LCO 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (1) required to be entered.

Per the BASES of LCO 3.4.1, during short term operational transients initiated below 100% power (2) margin to DNB exists.

(1) IS (2) MORE (1) IS (2) LESS (1) is NOT (2) MORE (1) is NOT (2) LESS A.

B.

C.

D.

as compared to transients initiated from 100% power.

83. Given the following:

Unit 1 is at 12% power.

LS/459Z, PRZR LVL CONT CH, is in the I/II (LT459/60) position.

Subsequently:

HA3, PRZR LVL LO HTRS OFF LTDN SEC, is in alarm.

HB2, PRZR LVL DEV LO, is in alarm.

LT-460, PRZR LVL, is 40% and rising.

LT-459, PRZR LVL, is 0%.

Which one of the following completes the statements below?

Per AOP-100, Instrumentation Malfunction, manual control of Charging (1) required.

Per the BASES of LCO 3.4.9, Pressurizer, the Pressurizer is required to be OPERABLE to (2).

(1) is NOT (2) preserve the steam space for pressure control (1) is NOT (2) provide protection against water relief through the Pressurizer Safety Valves (1) IS (2) preserve the steam space for pressure control (1) IS (2) provide protection against water relief through the Pressurizer Safety Valves A.

B.

C.

D.

84. Given the following:

FRP-S.1, Response to Nuclear Power Generation/ATWT, is in progress on Unit 1.

RCS pressure is 2350 psig and rising.

Subsequently:

Both PORV's have been manually opened and RCS pressure is lowering.

Which one of the following completes the statements below?

Per FRP-S.1, the PORV's are required to be manually closed when RCS pressure is below the maximum pressure of (1).

Per FRB-S.1, the reduction in pressure is required to (2).

Nomenclature: FRB-S.1, Farley Nuclear Plant Specific Background Document for FNP-1/2-FRP-S.1, Response to Nuclear Power Generation/ATWT (1)

(2) 2240 psig raise boron injection flowrate 2135 psig raise boron injection flowrate 2240 psig prevent excessive PORV cycling 2135 psig prevent excessive PORV cycling A.

B.

C.

D.

85. Given the following:

At 1000:

Unit 1 is performing EEP-3, Steam Generator Tube Rupture.

The operating crew is at the step to "Reduce RCS pressure using pressurizer PORV to minimize break flow and refill pressurizer."

At 1003:

PCV-445A, PRZR PORV, did not close.

MOV-8000A, PRZR PORV ISO, did not close.

RCS pressure continues to lower.

Which one of the following completes the statements below per EEP-3?

At 1000, the operating crew is required to stop the RCS depressurization when RCS subcooling reaches a minimum of (1) in the CETC mode.

At 1003, the operating crew will transition to (2).

(1) 45°F (2) ECP-3.3, SGTR Without Pressure Control (1) 45°F (2) ECP-3.1, SGTR With A loss of Reactor Coolant Subcooled Recovery Desired (1) 16°F (2) ECP-3.3, SGTR Without Pressure Control (1) 16°F (2) ECP-3.1, SGTR With A loss of Reactor Coolant Subcooled Recovery Desired A.

B.

C.

D.

86. Given the following:

ECP-0.0, Loss of All AC Power on Unit 1 is in progress.

The operating crew is performing the step "Perform ATTACHMENT 3, DEFEATING ESF EQUIPMENT AUTO START."

Subsequently, One train of emergency power has been restored.

The operating crew is as the step to "Select Recovery Procedure" and the following is observed:

- Subcooling is 28°F.

- Pressurizer level is 20% and rising.

- SI flow has not occurred.

Which one of the following completes the statements below?

The operating crew is required to transition to (1).

At the completion of the procedure selected above, the operating crew will transition to (2).

(1) ECP-0.1, Loss of All AC Power Without SI Required (2) EEP-0, Reactor Trip or Safety Injection (1) ECP-0.2, Loss of All AC Power With SI Required (2) EEP-1, Loss of Reactor or Secondary Coolant (1) ECP-0.1, Loss of All AC Power Without SI Required (2) ESP-0.2, Natural Circulation Cooldown to prevent Reactor Vessel Head Steam Voiding (1) ECP-0.2, Loss of All AC Power With SI Required (2) EEP-0, Reactor Trip or Safety Injection A.

B.

C.

D.

87. Given the following:

Unit 1 is at 100% power.

WD2, 1B INV FAULT, comes into alarm.

- 1B INVERTER EPB ammeter reads 0 amps.

- Local 1B INVERTER indications are:

BATTERY INPUT BKR tripped INVERTER OUTPUT BKR closed Bypass Source Powering Load light NOT lit BYPASS SOURCE AVAILABLE light lit Which one of the following completes the statements below?

Per ARP WD2, 1B INV FAULT, the operating crew will direct (1) to restore power to the 1B Vital panel.

Per LCO 3.8.9 Distribution System - Operating, when the 1B Vital Panel is aligned to the BYPASS source it is (2).

(1) depressing the BYPASS SOURCE TO LOAD pushbutton (2) OPERABLE (1) depressing the BYPASS SOURCE TO LOAD pushbutton (2) INOPERABLE (1) placing the MANUAL BYPASS switch to the BYPASS SOURCE TO LOAD position (2) OPERABLE (1) placing the MANUAL BYPASS switch to the BYPASS SOURCE TO LOAD position (2) INOPERABLE A.

B.

C.

D.

88. Given the following:

Unit 2 is performing the actions of ECP-0.0, Loss of All AC Power.

ACC has informed the plant that Offsite power will not be restored for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Which one of the following completes the statements below?

The operating crew is required to take local control of the TDAFW pump within a minimum of (1).

Per ECP-0.0, the operating crew will use the guidance of (2) to take local control of the TDAFW pump.

Nomenclature: SOP-22.0, Auxiliary Feedwater System (1)

(2) 90 minutes SOP-22.0 90 minutes ECP-0.0 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> SOP-22.0 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ECP-0.0 A.

B.

C.

D.

89. Given the following:

A spurious Reactor trip and Safety Injection occurred on Unit 1.

• FRP-H.1, Response to Loss of Secondary Heat Sink, is in progress.

The crew is attempting to restore SG level using a SGFP.

Subsequently:

The 1A SGFP has been started.

RCS Bleed and Feed requirements were not met.

SGNR Levels are as follows:

- 1A SG: 28% and rising

- 1B SG: 27% and rising

- 1C SG: 26% and rising Feedwater flow rate:

- 1A SG: 78 gpm and stable

- 1B SG: 74 gpm and stable

- 1C SG: 66 gpm and stable Which one of the following completes the statements below?

Implementation of FRP-H.1, Attachment 1, Main Feedwater Bypass Valves Automatic Closure Defeat, (1) required to open the Main Feedwater Bypass valves.

FRP-H.1 (2) be exited.

(1)

(2)

IS can NOT is NOT can NOT IS CAN is NOT CAN A.

B.

C.

D.

90. Given the following:

Unit 1 is in MODE 4.

A loss of Containment integrity occurs.

Which one of the following completes the statements below?

Entry into LCO 3.6.1, Containment, (1) required.

Per the BASES of LCO 3.6.1, Containment, LOCA and Rod Ejection Accident (2) two of the Design Basis Accidents that challenge Containment OPERABILITY.

(1)

(2) is NOT ARE IS ARE is NOT are NOT IS are NOT A.

B.

C.

D.

91. Given the following:

Unit 1 is operating at 100% power.

Circulating Water Canal has become clogged with debris from a storm.

Subsequently:

Main Condenser Vacuum is degrading.

The operating crew is ramping the Unit down per AOP-8.0, Partial Loss of Vacuum.

Condenser Circ Water outlet temperature is 120°F and slowly rising.

Which one of the following completes that statements below?

A Reactor trip is required when (1).

Per NMP-AD-031-GL02, Reportability Guidelines, the operating crew is required to notify the NRC within a maximum of (2) after the Reactor trip.

(1) Condenser Circ Water outlet temperature cannot be maintained < 120°F (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (1) a valid KK2, TURB COND VAC LO-LO, alarm actuates (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (1) Condenser Circ Water outlet temperature cannot be maintained < 120°F (2) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (1) a valid KK2, TURB COND VAC LO-LO, alarm actuates (2) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> A.

B.

C.

D.

92. Which one of the following completes the statements below?

The Fuel Handling Supervisor (1) permitted to serve as one of the two people required to verify the correct manipulation of fuel assemblies and inserts in the core.

The Refueling Manager (2) permitted to authorize the unlatching of a fuel assembly from the Manipulator Crane in the Reactor Vessel.

(1)

(2)

IS IS is NOT IS IS is NOT is NOT is NOT A.

B.

C.

D.

93. Which one of the following completes the statements below per UOP-4.0, General Outage Operations Guidance?

An intentional entry into a ORANGE condition on the Outage Defense in Depth Assessment must be approved by a minimum of the Shift Outage Manager and the (1).

An intentional entry into a RED condition on the Outage Defense in Depth Assessment (2) allowed.

(1)

(2)

Operations Director is NOT Operations Director IS Plant Manager is NOT Plant Manager IS A.

B.

C.

D.

94. Given the following:

A Non-urgent Temporary Configuration Change is going to be performed:

The Temporary Configuration Change props open the louvers on the 2C DG room.

The Temporary Configuration Change will remain in place for 180 days.

Which one of the following completes the statements below?

Per NMP-AD-010, 10 CFR 50.59 Screening and Evaluations, the Temporary Configuration Change (1) require a 10 CFR 50.59 evaluation.

The Shift Supervisor (2) give permission to install the approved Temporary Configuration Change.

(1)

(2)

DOES can NOT DOES CAN does NOT can NOT does NOT CAN A.

B.

C.

D.

DELETED

95. Which one of the following completes the statements below?

The lowest DOSE EQUIVALENT I-131 value that requires an entry in to LCO 3.4.16, RCS Specific Activity, is (1).

Per the bases of LCO 3.4.16, RCS Specific Activity, the required action to reduce RCS Tavg below 500 ºF is to reduce the risk of opening the (2).

(1)

(2) 0.8 µCi/gm Main Steam Safety Valves 0.8 µCi/gm SG Atmospheric Relief Valves 1.1 µCi/gm Main Steam Safety Valves 1.1 µCi/gm SG Atmospheric Relief Valves A.

B.

C.

D.

96. Given the following:

Unit 1 is at 100% power.

R-18, Waste Monitor Tank Pump Discharge, radiation monitor has been declared INOPERABLE due to failing low.

Per the ODCM, which one of the following will be required prior to releasing the #1 WMT?

The activity of a sample taken must be verified less than <1x10-7 µCi/ml.

Two independent samples of the #1 WMT must be taken and analyzed.

Chemistry must be able to take grab samples and analyze them for gross radioactivity (beta or gamma) at a minimum detectable concentration at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Chemistry must be able to take grab samples and analyze them for gross radioactivity (beta or gamma) at a minimum detectable concentration at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

A.

B.

C.

D.

97. Which one of the following describes the use of AOPs during the performance of Emergency Procedures in accordance with NMP-AP-005-GL01, Farley Transient Response Guidelines?

AOPs are not allowed to be used unless directed by the Emergency Procedure in progress.

AOPs may be performed during the performance of the Emergency Procedures based on operator judgment.

AOPs are only allowed to be performed in parallel with the Emergency Procedures if entry conditions are met.

Only AOPs listed in NMP-AP-005-GL01 are allowed to be used during the performance of the Emergency Procedures.

A.

B.

C.

D.

98. Which one of the following completes the statement below?

This highest priority Critical Safety Function is (1) because it (2).

(1) H - Heat Sink (2) prevents a SGTR due to tube overheating (1) H - Heat Sink (2) protects the fuel cladding through heat removal from the fuel (1) I - Inventory (2) ensures adequate RCS volume for effective decay heat removal (1) I - Inventory (2) ensures adequate RCS volume for effective pressure control A.

B.

C.

D.

99. Given the following:

Unit 1 has experienced a Loss of Offsite Power and is now performing a cooldown per ESP-0.2. The following conditions exist:

- RCS cold leg temperatures are 510°F.

- RCS hot leg temperatures are 545°F.

- RCS pressure is 1900 psig.

- 1A and 1B CRDM fans are running.

- RCPs 1A, 1B, and 1C are tripped and can NOT be restarted.

- CST level is 13.0 ft.

- AFW flow is 350 gpm.

- The 1A RCS Loop is inactive.

- RCS cooldown rate is the maximum allowed for an inactive loop.

- PZR level is stable at 25%.

- All RVLIS lights are dark (not illuminated).

The operating crew is at the step to "Check CST level adequate to remain in FNP-1-ESP-0.2."

Which one of the following completes the statements below?

The maximum cooldown rate for the given condition is (1).

The operating crew is required to (2).

Nomenclature: ESP-0.2, Natural Circulation Cooldown to Prevent Reactor Head Steam Voiding ESP-0.4, Natural Circulation Cooldown With Allowance For Reactor Vessel Head Steam Voiding (Without RVLIS)

Reference Provided (1) < 100°F in any 60 min period (2) transition to ESP-0.4 (2) < 25°F/hr (2) transition to ESP-0.4 (1) < 100°F in any 60 min period (2) remain in ESP-0.2 (1) < 25°F/hr (2) remain in ESP-0.2 A.

B.

C.

D.

100. Given the following:

• The operating crew is performing ESP-1.3, Transfer to Cold Leg Recirculation, on Unit 1.

The operating crew has just begun Step 7 "Align ECCS for cold leg recirculation."

The indications for containment sump level are as follows:

- LI-3594A, CTMT SUMP LVL, is reading 8.2 feet.

- LR-3594B, POST ACCIDENT CTMT WTR LVL, is reading 8.2 feet.

Which one of the following completes the statements below?

The operating crew (1) required to immediately transition to FRP Z.2.

The reason that FRP-Z.2 is entered is the concern for (2).

Nomenclature: FRP-Z.2, Response to CTMT Flooding (1) is NOT (2) damage to critical plant components necessary for plant recovery (1) IS (2) damage to critical plant components necessary for plant recovery (1) is NOT (2) reducing the boron concentration in the containment sump (1) IS (2) reducing the boron concentration in the containment sump A.

B.

C.

D.

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Residual Heat Removal Valves Inservice Test FNP-1-STP-11.6 FARLEY Version 44.2 Unit 1 Page 31 of 32 Printed 05/22/2019 at 12:43:00 TABLE 3 Page 1 of 1 Q1E11MOV8889 VALVE EXERCISE VALVE NUMBER DESCRIPTION ACTUAL STROKE TIME REFERENCE STROKE TIME ACCEPTABLE STROKE TIME RANGE MAXIMUM ALLOWABLE TIME CR NO. IF REQUIRED POSITION IND SAT INITIALS (2)

Q1E11MOV8889 RHR TO RCS HOT LEGS ISO 11.72 9.96 to 13.47 16 Sec.

(3)

Q1E11MOV8889 RHR TO RCS HOT LEGS ISO 11.72 9.96 to 13.47 16 Sec.

NOTE 2 Valve time while stroking open.

3 Valve time while stroking closed.

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Farley 2021-301 Written Answer Key

1. B

26. C

51. A

76. D

2. A

27. A

52. A

77. A

3. A

28. B

53. B

78. D

4. B

29. A

54. C

79. B

5. D

30. D

55. A

80. D

6. A

31. C

56. D

81. D

7. B

32. C

57. A

82. A

8. C

33. D

58. A

83. C

9. D

34. A

59. B

84. B

10. A

35. A

60. B

85. D

11. C

36. A

61. D

86. C

12. D

37. C

62. C

87. C

13. D

38. B

63. A

88. B

14. C

39. D

64. A

89. C

15. B

40. A

65. A

90. B

16. C

41. A

66. A

91. D

17. D

42. B

67. B

92. C

18. C

43. D

68. A

93. C

19. C

44. C

69. C

94. Deleted

20. B

45. A

70. C

95. A

21. B

46. D

71. A

96. B

22. D

47. C

72. D

97. B

23. C

48. B

73. D

98. B

24. A

49. C

74. C

99. B

25. A

50. C

75. D 100. A