Text

DC Cook, 2010 Initial License Exam, Written Exam
	ML102220150
Person / Time
Site:	Cook
Issue date:	06/21/2010
From:	; Division of Reactor Safety III
To:	; Indiana & Michigan Electric Co
References
	Download: ML102220150 (100)
	v • d • e

Cook 2010 NRC Examination

1. `Given the following conditions on Unit 2:

The crew is responding to a Reactor Trip and has transitioned to 2-OHP-4023-ES-0.1, Reactor Trip Response, from 2-OHP-4023-E-0, Reactor Trip or Safety Injection.

Following the transition the crew notes the following conditions:

o RCS Pressure is 2100 psig and lowering o 2-NRV-152, indicating lights show an intermediate position Which ONE of the following describes the actions the operator should take to address these conditions:

A. Close 2-NMO-152, PORV Block Valve, to stop discharge into the PRT.

B. Open Pressurizer Spray valves to depressurize the RCS and limit the loss of Reactor Coolant.

C. Turn on all Pressurizer Heaters to maintain RCS pressure.

D. Isolate air to containment to fail the Pressurizer PORV closed and stop the RCS mass loss.

Page 1 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

2. Given the following conditions on Unit 2:

A reactor trip and safety injection have occurred.

The crew is responding to a Small Break Loss of Coolant Accident (LOCA).

All Reactor Coolant Pumps are tripped.

The crew is depressurizing the Reactor Coolant System (RCS) in accordance with Step 13 of 2-OHP-4023-ES-1.2, Post LOCA Cooldown and Depressurization.

A PORV is being used to depressurize the RCS.

As the depressurization occurs, which one of the following describes the expected trend of pressurizer level and the adverse operating condition that may initially occur as a result?

A. Lowering Pressurizer Level; Uncovering Pressurizer heaters.

B. Rising Pressurizer Level; Water solid conditions in the RCS and Pressurizer.

C. Rising Pressurizer Level; Upper head region voiding may occur.

D. Lowering Pressurizer Level; Upper head region voiding may occur.

Page 2 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

3. Given the following conditions on Unit 1:

A Large Break LOCA has occured.

Safety Injection has actuated.

Which ONE of the following describes:

1) how the Centrifugal Charging Pump suction swaps to the RWST when a Safety Injection is initiated

-AND-

2) how the CHARGING PUMP SUCTION swapover to the containment sump is completed in accordance with 1-OHP-4023-ES-1.3, Transfer to Cold Leg Recirculation?

Note: VCT valves = QMO-451/QMO-452 RWST valves = IMO-910/IMO-911 A. 1) The VCT valves will start to close AFTER one of the RWST valves have traveled to the full open position.

2) The RWST valves will AUTOMATICALLY close after IMO-340, Charging Pp Suction from East RHR Hx has been opened.

B. 1) The VCT valves will start to close AFTER one of the RWST valves have traveled to the full open position.

2) The RWST valves will be MANUALLY closed after IMO-340, Charging Pp Suction from East RHR Hx has been opened.

C. 1) The VCT valves will start to close AS SOON AS one of the RWST valves start to open.

2) The RWST valves will AUTOMATICALLY close after IMO-340, Charging Pp Suction from East RHR Hx has been opened.

D. 1) The VCT valves will start to close AS SOON AS one of the RWST valves start to open.

2) The RWST valves will be MANUALLY closed after IMO-340, Charging Pp Suction from East RHR Hx has been opened.

Page 3 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

4. Given the following conditions on Unit 2:

Unit tripped from 29% power.

RCP 21 breaker tripped open when the busses swapped.

Which one of the following describes the response of Thot and Tcold in Loop 1?

A. Tcold rises to approximately equal Thot.

B. Thot lowers to approximately equal Tcold.

C. Tcold lowers, Thot remains approximately stable.

D. Thot rises, Tcold remains approximately stable.

Page 4 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

5. Given the following conditions on Unit 2:

Reactor Coolant System (RCS) is in mid-loop condition

The following indications are fluctuating on the running Residual Heat Removal (RHR): amps, flow, and discharge pressure Which ONE of the following statements is correct regarding the standby RHR pump?

The standby RHR Pump should:

A. NOT be immediately started because air entrainment could cause a loss of both RHR trains.

B. be immediately started because following a loss of RHR flow, an RCS pressurization may occur precluding gravity feed makeup.

C. be immediately started because under certain loss of RHR conditions, core uncovery or core voiding can occur within 15 to 20 minutes.

D. NOT be immediately started because starting an idle RHR pump under mid-loop conditions could cause an unacceptable reduction in reactor shutdown margin.

Page 5 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

6. Given the following conditions on Unit 1:

Unit is operating at 100% power

1-NPP-151, PZR Press Channel 1, fails high

The operator has taken manual control of Pressurizer pressure control and stabilized pressure at 2085 psig.

Following completion of the procedure for response to a malfunction of a pressurizer pressure instrument, what will be the status of the CVCS/Charging system?

The ______ CCP will be INOPERABLE with the associated emergency leakoff valve deenergized in the ______ position.

A. East; open B. East; closed C. West; open D. West; closed Page 6 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

7. Given the following conditions on Unit 2:

The operators are implementing 2-OHP-4023-FR-S.1, Response to Nuclear Power Generation/ATWS

Both Reactor Trip Breakers remain closed.

The operators have completed steps of 2-OHP-4023-FR-S.1 through opening the MG Set output Breakers to shutdown the reactor.

Which ONE of the following describes the impact and potential consequences of the Reactor Trip Breakers remaining closed?

A. main steam line isolation signal will NOT occur to prevent excessive reactivity during the trip due to rapid RCS cooldown.

B. feedwater isolation signal will NOT actuate to prevent excessive reactor coolant system cooldown from the overfeeding of the steam generators.

C. main generator trip signal will NOT be generated preventing transfer of busses to reserve feed.

D. feedwater flow conservation signal will NOT occur to ensure equal distribution of water to the steam generators.

Page 7 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

8. Given the following conditions on Unit 1:

The Unit is operating at 75% power with all systems in automatic.

Main Turbine DCS is in "MW IN" in preparation for turbine valve testing.

Condenser vacuum is lowering.

Assuming no action has been taken by the crew, which ONE of the following describes the response of the rod control system to this event?

Control rods will automatically:

A. insert due to the rise in Tavg from the rise in steam flow.

B. insert due to the rise in Tavg from the lowering in steam flow.

C. withdraw due to the drop in Tavg from the rise in steam flow.

D. withdraw due to the a drop in Tavg from the lowering steam flow.

Page 8 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

9. Given the following conditions on Unit 1:

Unit 1 was operating at 100% power when a condensate system transient caused both Main FW pumps to trip.

The turbine and reactor failed to trip automatically.

In accordance with the immediate actions of 1-OHP-4023-FR-S.1, Response to Nuclear Power Generation/ATWS, the operators will:

1. Manually trip the Reactor, if it fails to trip insert control rods.

2. Manually actuate AMSAC.

3. Manually trip the Turbine, if it fails to trip, then runback the turbine.

Which ONE of the following describes the bases for these immediate actions in 1-OHP-4023-FR-S.1?

The safeguards systems are designed assuming that the only heat being added to the RCS is from _____________ . For an ATWS event with a loss of normal feedwater, a Turbine trip within 30 seconds will _____________________ .

A. fission product decay and RCP heat; prevent challenging the Pressurizer PORV's.

B. fission product decay and RCP heat; maintain S/G inventory.

C. 5% power; maintain S/G inventory.

D. 5% power; prevent challenging the Pressurizer PORV's Page 9 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

10. Given the following conditions on Unit 2:

A loss of all AC Power occurred due to severe weather conditions and failure of emergency diesel generators to start and supply safeguard buses.

The operating crew is carrying out actions of 2-OHP-4023-ECA-0.0, Loss of All AC Power.

The operators are at a point where they are to commence cooldown and depressurization of the steam generators to 190 psig.

Based on these conditions, which ONE of the following statements describes the reason why a secondary depressurization is directed?

A. To prevent a challenge to the Core Cooling Safety Function Status Tree which is being monitored for implementation.

B. To remove stored energy in the steam generators to limit the potential of challenging RCS integrity.

C. To remove available energy in the steam generators and thus minimizing any challenges to the containment structure if a Faulted S/G were to occur.

D. To minimize RCS inventory loss through the RCP seals, which maximizes time to core uncovery.

Page 10 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

11. Given the following conditions on Unit 2:

Unit has just tripped due to a Loss of Offsite power.

Both EDGs started and energized the required loads.

All equipment responded as designed.

The following conditions exist:

Containment parameters are normal

Average core exit thermocouple (CET) temperature is stable.

Which ONE of the following combination of RCS pressure and average CET temperature verifies the MINIMUM required subcooling to AVOID Safety Injection per 2-OHP-4023-ES-0.2, Natural Circulation Cooldown?

Reference Provided: Steam Tables A. 600 psig, 590oF B. 500 psig, 460oF C. 450 psig, 430oF D. 375 psig, 400oF Page 11 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

12. Given the following conditions on Unit 1:

Unit is operating at 60% power

Pressurizer Level Control is in MANUAL

Pressurizer LEVEL CTRL SELECTOR switch is in the Channel 2-3 position

CRID 3 power supply fails Assuming no operator action, which ONE of the following statements describes the effect of this failure on the CVCS and PZR level control system?

A. QRV-251, CCP Disch Flow Control fails OPEN Letdown Isolates Actual Pressurizer Level Rises B. QRV-251, CCP Disch Flow Control fails CLOSED Letdown Isolates Actual Pressurizer Level Rises C. QRV-251, CCP Disch Flow Control fails CLOSED QRV-200, Charging Header Pressure Control Valve fails OPEN Actual Pressurizer Level Lowers D. QRV-251, CCP Disch Flow Control fails OPEN QRV-200, Charging Header Pressure Control Valve fails CLOSED Actual Pressurizer Level Lowers Page 12 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

13. Which ONE of the following describes the reason for disabling AMSAC, de-energizing DCS Inverters, and stopping all DC powered Turbine Oil Pumps in 2-OHP-4023-ECA-0.0, Loss of All AC Power ?

A. Allow turbine oil systems to be de-energized and drain to the main turbine lube oil tank.

B. Prevent inadvertent actuation of control systems and auto start of pumps.

C. Extend the DC battery life for N Train and BOP batteries.

D. Limit overheating of cabinets and pump motor overload.

Page 13 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

14. Given the following conditions:

An accidental spill of the Monitor Tank has occurred in the Aux Building.

Radiation levels in the area of the spill are 40 mRem per hour at 30 cm.

Contamination levels based on smear on the floor around the tank are 1.2 x104 dpm/100 cm2 beta-gamma.

Which ONE of the following describes how the area will be posted in accordance with PMI-6010, Radiation Protection Plan?

A. Radiation Area ONLY.

B. Contamination Area ONLY.

C. Radiation Area AND Contamination Area.

D. High Radiation Area AND Contamination Area.

Page 14 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

15. Given the following condition:

1-MRV-213, Unit 1 SG11 PORV, was locally isolated due to excessive leakby.

Which ONE of the following describes the status of the SG11 PORV Radiation Monitors and the required actions, if any?

Reference Provided: U1 TRM 8.3.8, Radiation Monitoring Instrumentation A. Channel MRA-1601 is Inoperable. Perform surveys of the SG PORV area every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Implement administrative controls to initiate an alternate method of monitoring.

B. Channel MRA-1601 is Inoperable. Restore to Operable Status within 7 days.

C. Channel MRA-1601 is still Operable provided it is indicating approximately the same as MRA-1602 (acceptable channel check).

D. Channel MRA-1601 is Inoperable. Implement administrative controls to initiate an alternate method of monitoring within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Page 15 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

16. Given the following conditions on Unit 2:

Unit was operating at 100% power when a malfunction of the Control Air system occurs.

The Control Air header rapidly depressurizes and cannot be restored.

Which ONE of the following describes the correct operator response?

Immediately trip the Reactor and implement:

A. 2-OHP-4023-E-0, Reactor Trip or Safety Injection.

2-OHP-4022-064-002, Loss Of Control Air Recovery, may be performed concurrently after transitioning to 2-OHP-4023-ES-0.1, Reactor Trip Response.

B. 2-OHP-4023-E-0, Reactor Trip or Safety Injection.

2-OHP-4022-064-002, Loss Of Control Air Recovery, is NOT needed since the EOP network may be performed without reliance on Control Air.

C. 2-OHP-4023-E-0, Reactor Trip or Safety Injection.

2-OHP-4022-064-002, Loss Of Control Air Recovery, may NOT be performed until completion of 2-OHP-4023-ES-0.1, Reactor Trip Response.

D. 2-OHP-4022-064-002, Loss Of Control Air Recovery, until restoration of Control Air from any source.

Perform 2-OHP-4023-E-0, Reactor Trip or Safety Injection steps as time allows.

Page 16 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

17. Given the following conditions:

A Main Transformer fire has occurred on Unit 1.

The Unit 1 Reactor and Main Turbine/Generator have been tripped.

The Turbine AEO has reported that the Main Transformer deluge system has actuated.

The Outside Tour AEO has reported that all three fire water pumps are running.

The reported status of the Fire Water System is ____________ for this event. The Main Transformer deluge system ___________ expected to automatically actuate once the Main Generator is tripped, ___________ fire water pumps are expected to be running.

A. abnormal; is; but only 2 B. abnormal; is not; but 3 C. normal; is; and 3 D. abnormal; is not; and only 2 Page 17 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

18. Given the following conditions on Unit 2:

Reactor Power is at 100% when a fire occurs in the Control Room Cable Vault.

A large amount of smoke accumulates in the Control Room,

The Shift Manager determines that the main control room must be evacuated in accordance with 2-OHP-4025-001-001, Emergency Remote Shutdown.

Which ONE of the following describe the operation of the Emergency Diesel Generators (EDGs)?

A. Start both EDGs prior to control room evacuation.

Locally control EDGs from LSI panels as required.

B. Trip both EDG HEAs prior to leaving control room.

Restore EDGs per 2-OHP-4025-R-15, if required C. Leave EDG control switches as is.

Locally Trip and Isolate EDGs in accordance with 2-OHP-4025-LTI-3, if required.

D. Leave EDG control switches as is.

Locally control EDGs from LSI panels as required.

Page 18 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

19. Given the following conditions on Unit 1:

Unit is in Mode 3.

The 4160 VAC distribution system is being supplied by the Reserve Auxiliary Transformers (RATs).

Due to a system disturbance, indicated voltage on the safeguards buses drops.

The following conditions now exist:

T11A Voltage Indication is 112 Volts

T11B Voltage Indication is 114 Volts

T11C Voltage Indication is 113 Volts

T11D Voltage Indication is 114 Volts Which ONE of the following describes the FINAL plant response if voltage remains at these values for an extended period?

A. All safeguards busses will be energized by their respective EDG.

B. T11A and T11C busses will be energized by their respective EDG.

C. T11A and T11B busses will be energized by its respective EDG.

D. Only T11A bus will be energized by its respective EDG.

Page 19 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

20. Given the following conditions on Unit 1:

Reactor power is 100%.

West CCP is in operation with the East CCP in standby.

West CCW pump is tagged out for maintenance.

Which ONE of the following describes the immediate operator actions required for a loss of Bus T11D:

A. Trip reactor because the RCP seals will overheat without Component Cooling flow.

B. Trip reactor because there is NO charging flow to replace letdown.

C. Initiate a controlled shutdown because the Charging pump will overheat without Component Cooling flow.

D. Initiate a controlled shutdown because the RCP seals will overheat without charging flow.

Page 20 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

21. Given the following conditions on Unit 2:

Reactor is at 100% power.

All control systems are in normal alignment.

Letdown flow is aligned with a flow of 120 gpm at QFI-301.

The following parameters are now noted on the CVCS system:

Seal Return Flows are 3 gpm per RCP

Charging flow is 137 gpm and rising.

2-QTA-160, Regen HX Outlet Temp - Letdown, has lowered 5°F from its steady state value.

VCT level is 33% and lowering.

PZR level is 55% and lowering slowly.

RCS temperature is 574°F and stable.

Which ONE of the following describes the effect on the unit and the action required to address the conditions?

A. RCS leakage is from the letdown line between the orifices and the letdown containment isolation valves. Isolate Letdown.

B. RCS leakage is from the charging line on the RCS side of the regenerative heat exchanger. Isolate Charging and Letdown.

C. RCS leakage is from the letdown line on the CVCS side of the regenerative heat exchanger. Initiate an investigation to determine if the leak is isolable.

D. RCS leakage is from the charging line on the CVCS side of the regenerative heat exchanger. Isolate Charging and Letdown.

Page 21 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

22. Given the following conditions:

QRV-200, RCP Seal Backpressure Valve, is operating at 30% open.

Assuming QRV-251, Charging Line Flow Control Valve is NOT adjusted, IF QRV-200 fails to 60% open, THEN:

Charging Pump RCP Seal Charging Flow to Discharge Press Injection Flow Regen Hx A. Lowers Rises Lowers B. Rises Lowers Rises C. Rises Rises Lowers D. Lowers Lowers Rises Page 22 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

23. Given the following conditions:

Unit 2 is in Mode 4 during cooldown per 2-OHP-4021-001-004, Plant Cooldown from Hot Standby to Cold Shutdown

West RHR Pump and Heat Exchanger are operating, aligned to the cooldown path through injection lines to Cold Legs Loops 2 & 3

RCS temperature is 300°F and stable

RCS pressure is 335 psig and stable The air supply line to IRV-320, West RHR Hx Outlet Valve, breaks, causing a complete loss of Instrument Air to the valve.

Which ONE of the following describes the effect on the plant and the action that could be taken to mitigate the transient?

A. RHR Flow through the West HX will be lost. Throttle open IRV-311 RHR HX Bypass to maintain greater than 3000 gpm RHR flow.

B. RHR Flow through the West HX will be lost. Stop the West RHR pump immediately to prevent overpressurizing letdown.

C. RHR Flow through the West HX will rise. Throttle ICM-111, RHR Discharge to Cold Leg 2 & 3 and IRV-311 RHR HX Bypass to prevent overcooling the RCS.

D. RHR Flow through the West HX will rise. Throttle ICM-321, West RHR Injection to Loops 2 & 3 and IRV-311 RHR HX Bypass to prevent overcooling the RCS.

Page 23 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

24. Given the following conditions:

Unit 2 has experienced a loss of both CCW pumps in MODE 3

NEITHER Unit 2 CCW pump can be restarted.

CVCS crosstie from Unit 1 is NOT available.

BOTH Unit 2 CCPs are running because a CCP swap was in progress.

2-OHP-4022-016-004, Loss of Component Cooling Water, is in progress.

Which ONE of the following describes the procedural requirements for CCP operation based on these conditions?

A. Immediately stop both CCPs.

B. Immediately stop one CCP; stop the second CCP within 1-1/2 minutes of the event.

C. Stop BOTH CCPs within 1-1/2 minutes of the event.

D. Immediately stop one CCP; run the second CCP as long as it continues to operate.

Page 24 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

25. Given the following conditions:

The Plant has just completed a Heatup to Normal Operating Temperature and Pressure.

Operators suspect a small leak through Pressurizer Safety Valve SV-45B.

What indication combinations are available to help the operator determine if this valve is faulted?

A. A significant PRT Temperature Rise (>200oF)

The Common Safety Valve Tailpipe Temperature indicator The Common Safety Valve line acoustic monitor B. A significant PRT Temperature Rise (>200oF)

The Safety Valve SV-45B Tailpipe Temperature indicator The Safety Valve SV-45B line acoustic monitor C. A slight PRT Temperature Rise (<50oF)

The Safety Valve SV-45B Tailpipe Temperature indicator The Common Safety Valve line acoustic monitor D. A slight PRT Temperature Rise (<50oF)

The Safety Valve SV-45B Tailpipe Temperature indicator The Safety Valve SV-45B line acoustic monitor Page 25 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

26. Given the following conditions:

Containment pressure instrument Channel #1, 2-PPP-303, declared inoperable.

Required actions per 2-OHP-4022-013-011, Containment Instrumentation Malfunction, have been completed.

Required Technical Specification Actions have been taken for Channel #1, 2-PPP-303.

Which ONE of the following describes the SI and CTS, and Containment Isolation Phase A (CIA) and B (CIB) response to a subsequent failure of CRID 4 power supply.

SI CTS CIA CIB ACTUATES ACTUATES ACTUATES ACTUATES A. YES NO YES NO B. YES YES YES YES C. NO YES NO YES D. NO NO NO NO Page 26 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

27. Given the following conditions:

Unit 1 and Unit 2 are operating at 100% Power.

North Spent Fuel Pit pump and cooler in service

Spent Fuel Pit at Normal Level

Spent Fuel Pit contains 2015 spent fuel assemblies

Refueling Water Purification aligned to purify Unit 1 RWST The 1-CRV-445, CCW from North SFP Hx, control air supply line ruptures causing valve to fail.

Which ONE of the following conditions describes the impact on the Spent Fuel Pool Cooling system and the actions needed to address this condition?

A. SFP Temperature will rise.

Place the South SFP Pump and Hx in service.

B. SFP Temperature will rise.

Manually control SFP temperature using 1-CRV-445 bypass valve.

C. SFP Temperature will lower.

Place the South SFP Pump and Hx in service.

D. SFP Temperature will lower.

Isolate 1-CRV-445 and manually control SFP temperature using 1-CRV-445 bypass valve.

Page 27 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

28. Given the following conditions on Unit 1:

A Small Break LOCA has occurred.

RCS Wide Range Pressure lowered to 1350 psig and is stable.

Containment pressure has remained less than 2.8 psig.

The actions of 1-OHP-4023-ES-1.2, Post LOCA Cooldown And Depressurization, are in progress.

Both CCPs are running with suction aligned to the RWST.

Both RHR Pumps are stopped in Neutral.

Both SI Pumps are running.

The crew is ready to depressurize the RCS to refill the Pressurizer.

Which ONE of the following is the FIRST method available to the operator to commence the RCS depressurization?

The operator will open:

A. One PZR PORV to depressurize the RCS.

B. All Pressurizer PORVs to depressurize the RCS.

C. The PZR Aux Spray Valve to spray down the PZR steam space.

D. PZR Normal Spray Control valve(s) to spray down the PZR steam space.

Page 28 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

29. The plant was in Mode 1. Reactor trip and safety injection have occurred. Due to high Aux Building radiation levels, the crew has entered 2-OHP-4023-ECA-1.2, LOCA Outside Containment. Actions have been taken in an attempt to isolate the break.

Given the following plant conditions:

PZR level is off-scale low

SI pump flow is 0 GPM

RCS pressure is 1700 psig and rising.

Aux Building Radiation Monitors are in alarm Which ONE of the following describes the status of the leak based on the requirements of 2-OHP-4023-ECA-1.2?

A. The leak is isolated based on SI flow of 0 GPM B. The leak is isolated based on RCS pressure rising.

C. The leak is NOT isolated based on PZR level indication not rising.

D. The leak is NOT isolated based on Aux Building radiation monitor indication.

Page 29 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

30. The control room operators are responding to a red path on the Heat Sink CSF. While attempting to restore feed flow to a SG in accordance with OHP-4023-FR-H.1, Response to Loss of Secondary Heat Sink, conditions degrade to the point that RCS bleed-and-feed must be established.

Under these conditions, RCS bleed-and-feed must be established expeditiously to:

A. prevent a loss of secondary heat sink.

B. minimize core uncovery and prevent inadequate core cooling.

C. prevent an overpressurization challenge to the reactor vessel.

D. prevent a rapid RCS overpressurization, followed by a rapid RCS depressurization due to RCP seal failure.

Page 30 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

31. Given the following conditions:

Unit 2 Reactor Tripped due to a loss of offsite power

The crew is implementing 2-OHP-4023-ES-0.2, Natural Circulation Cooldown Which ONE fo the following describes the reason for maintaining subcooling greater than 90°F if ALL CRD fans are running OR greater than 220°F if less than ALL CRD fans are running during the cooldown.

A. To collapse any voids formed in the CRD housings.

B. To prevent possible void formation in the upper head.

C. To prevent degradation of reactor coolant pump seals due to steam.

D. To ensure adequate subcooling due to possible degradation of core exit T/Cs accuracy.

Page 31 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

32. Given the following conditions:

1-OHP-4023-ECA-1.1, Loss of Emergency Coolant Recirculation, has just been entered

Refueling Water Storage Tank (RWST) level is 5.5%

Which ONE of the following procedure actions is performed FIRST?

A. Initiate makeup to the U-1 RWST from the Boric Acid Blender.

B. Start one reactor coolant pump.

C. Initiate makeup to the U-1 RWST from the U-2 RWST.

D. Secure all ECCS and CTS pumps taking a suction from the RWST.

Page 32 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

33. Operators are performing 2-OHP-4023-ECA-2.1, Uncontrolled Depressurization of All Steam Generators due to a steam leak inside containment along with failure of all SG stop valves to close.

Given the following plant conditions:

Containment pressure is 3 psig.

The crew has taken action to minimize the plant cooldown.

Steam Generator AFW flow indicates 25x103 pph each SG.

T-hots are slowly lowering.

The following alarms are received:

Ann. 213 Drop 5, STEAM GEN #1 WATER LEVEL LOW-LOW

Ann. 213 Drop 35, STEAM GEN #2 WATER LEVEL LOW-LOW

Ann. 214 Drop 5, STEAM GEN #3 WATER LEVEL LOW-LOW

Ann. 214 Drop 35, STEAM GEN #4 WATER LEVEL LOW-LOW Which ONE of the following actions is required in accordance with 2-OHP-4023-ECA-2.1?

A. Adjust AFW flow to 60x103 pph on each Steam Generator. The minimum NR level, per 2-OHP-4023-ECA-2.1, is 28%.

B. Adjust AFW flow to 60x103 pph on each Steam Generator. The minimum NR level ,

per 2-OHP-4023-ECA-2.1 , is 50%.

C. Maintain AFW flow at its current value. If T-hot starts to rise, raise AFW flow to stabilize RCS temperature.

D. Maintain AFW flow at its current value. If SG levels continue to lower, raise AFW flow to maintain SG levels >13% to prevent a transition to 2-OHP-4023-FR-H.1, Response to Loss of Secondary Heat Sink.

Page 33 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

34. Given the following conditions on Unit 2:

A LOCA occurred 60 minutes ago.

Containment Pressure has risen to 5 psig.

The crew has completed steps of 2-OHP-4023-ES-1.3, Transfer to Cold Leg Recirculation, to align RHR/CTS suctions to the recirculation sump and the CCP/SI suctions to RHR Discharge.

ONLY the Train A CCP, SI, RHR, and CTS pumps are operating.

The next step of 2-OHP-4023-ES-1.3 directs the crew to "Check if RHR Spray is Required".

Based on the indications above, which ONE of the following would best describe the required action AND the reason for the decision?

A. Place RHR spray in service NOW since ALL of the requirements are met.

B. Place RHR spray in service ONLY if the CTS pump trips.

C. Do NOT place RHR spray in service because the RHR pump suction is NOT aligned to the RWST.

D. Do NOT place RHR spray in service because ONLY one RHR pump is operating.

Page 34 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

35. Chemistry had confirmed two leaking fuel rods on Unit 1 when a Small Break LOCA occurred 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ago.

The following conditions exist on Unit 1:

All Red and Orange Paths have been addressed.

Containment pressure is 1.0 psig.

Containment air temperature is 215ºF.

Lower Containment high range area monitors, (VRA-1310/1410) are reading 10 R/HR

1-OHP-4023-FR-Z.3, Response to High Containment Radiation Level, is entered.

In accordance with 1-OHP-4023-FR-Z.3, which ONE of the following must be verified?

A. Both Containment Recirculation Fans (CEQ) are running.

B. Upper and Lower Containment Ventilation Fans (CUV/CLV) are running.

C. Containment Ventilation Isolation has occurred.

D. Control Room Ventilation System is in ISOLATE.

Page 35 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

36. Given the following conditions:

Unit 1 in Mode 4 cooling down to Mode 5

Pressurizer level is 80%

11PHC Pressurizer heater groups are in MANUAL and ON

Reactor coolant pumps (RCP) #13 and #14 are running

An electrical fault results in the loss of RCP Bus 1D and T11D Five minutes later it is reported the pressurizer outflow cannot be verified.

Which of the following actions will reinitiate and then maintain a continuous pressurizer outflow?

A. Verify pressurizer heaters from 11PHC output current and close NRV-164 Loop 4 PZR Spray Control valve B. Energize pressurizer heaters from 11PHA and close NRV-163 Loop 3 PZR Spray Control valve C. Raise the demand on NRV-164 Loop 4 PZR Spray Control valve D. Adjust charging and letdown to raise pressurizer level to 85%

Page 36 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

37. Unit 2 was operating at 100% power when an instrument failure caused Pressurizer Level to rise to 73%.

The Crew has restored the level control instrumentation and has stabilized charging and letdown The following conditions exist at 1300 hour0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months s:

2-QRV-160 and 2-QRV-161, Letdown Orifice Valves are Open

Letdown Hx Outlet Flow QFI -301 118 gpm

Charging Header Flow QFI -200 120 gpm

Total seal flow to RCPs QFI -210 to 240 32 gpm

Pressurizer Level NLP-151 to 153 73%

Assuming no operator actions, design RCP seal return flows, and pressurizer volume of 75 gallons/% at what time will the Pressurizer Level be returned to the 100%

program value?

A. 1348 hrs.

B. 1406 hrs.

C. 1522 hrs.

D. 1618 hrs.

Page 37 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

38. Given the following conditions:

Pressurizer Pressure Channel #1 has failed and has been placed in the tripped condition.

Reactor trip breaker testing was taking place at 75% power.

Pressurizer Pressure Channel #2 has spiked low causing an inadvertent Safety Injection Actuation and a reactor trip on Unit 1.

Pressurizer Pressure Channel #2 has returned to a normal reading.

The following conditions currently exist:

Reactor trip breaker A: OPEN

Reactor trip bypass breaker A: OPEN

Reactor trip breaker B: OPEN

Reactor trip bypass breaker B: CLOSED Which ONE of the following describes the impact (if any) this condition will have on restoring the plant to stable conditions?

A. The Train B Safety Injection signal will NOT be able to be reset. Train B equipment will have to be placed in Pull-to-Lockout to stop it.

B. The Train B Safety Injection signal will reset but Auto Safety Injection Actuation will NOT be blocked.

C. The Safety Injection signal will NOT be able to be reset on either train. Safeguards equipment will have to be placed in Pull-to-Lockout to stop it.

D. The Safety Injection signal will reset on both trains. Auto Safety Injection Actuation will be blocked.

Page 38 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

39. Given the following conditions on Unit 1:

A reactor startup is in progress.

The reactor is critical in the source range.

N41 Power Range channel has failed and been removed from service with all bistables placed in the trip condition.

A loss of power to the CRID 2 bus occurs.

Which ONE of the following actions will occur?

A. Reactor trips and N32 Source Range channel is de-energized.

N31 Source Range channel is still in operation.

B. The reactor is critical and BOTH source range channels are de-energized.

C. The reactor is critical and N32 Source Range channel is de-energized.

N31 Source Range channel is still in operation.

D. Reactor trips and BOTH source range channels are de-energized.

Page 39 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

40. Given the following conditions on Unit 2:

Reactor power is 3%

East Main Feedwater Pump is in service

Both MDAFW Pumps have been stopped with control switches in NEUTRAL Which ONE of the following signals will cause an automatic start of the MDAFW Pumps?

A. AMSAC East Main Feedwater Pump Trip B. Safety Injection East Main Feedwater Pump Trip C. Safety Injection Blackout Sequence D. Blackout Sequence Steam Generator Low Level of 26% on 1 of 4 SGs Page 40 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

41. During a power ascension, with reactor power at 48%, Control Bank C - Group 1 rod B-8 drops. Prior to the drop it was at 230 steps. While restoring the rod, a control rod urgent failure alarm occurs.

Which one of the following explains why the alarm actuated?

A. All other Bank C - Group 1 rod lift coil disconnect switches are open.

B. All Bank C - Group 2 rod lift coil disconnect switches are open.

C. The step counter of the pulse to analog (P/A) converter was not reset to 0.

D. Group C rod moving with group D rods withdrawn.

Page 41 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

42. Which set of the following describes the response of the reactor protection system to a controlling feedwater flow instrument failing low with no operator action from 100%

power conditions?

1) Turbine/Reactor trip on Low-Low level in associated steam generator

2) Turbine/Reactor trip on High-High level in associated steam generator

3) Feedwater Conservation

4) Feedwater Isolation A. 2 AND 3 B. 1 AND 3 C. 2 AND 4 D. 1 AND 4 Page 42 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

43. Given the following conditions:

Unit 2 is in Mode 3 at rated temperature and pressure awaiting a startup.

Lower Containment Cooling NESW supply is throttled to all ventilation units.

A power failure causes a loss of 4 of the 8 Lower Containment Vent units.

Average containment temperature rises from 100°F to 119°F.

Charging Flow Control is in MANUAL

Assume RCS Pressure and Temperature remain Constant.

Which ONE of the following describes the change in indicated Pressurizer level due to the rise in Containment temperature?

Density lowering in the _______ leg causes indicated pressurizer level to read

________ than actual level.

A. reference; higher B. reference; lower C. variable; higher D. variable; lower Page 43 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

44. Given the following conditions on Unit 1:

Unit is in Mode 1 at 100% power

A control air leak has resulted in isolation of glycol to containment.

WIN team states that it will take approximately 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to repair the control air leak.

Which ONE of the following describes the operating implications of the loss of glycol to containment.

A. Immediately declare the Ice Bed Inoperable. Monitor Ice Bed temperatures to ensure they remain < 27°F every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

B. Monitor Ice Bed temperatures to ensure they remain at an acceptable level. Enter appropriate Tech Spec actions if Ice Bed temperature rises to > 27°F C. Start all Unit 1 Air Handling Units (AHUs). Monitor Ice Bed Temperature locally once per hour until glycol system is restored.

D. Maximize Containment cooling. If glycol cannot be restored within ONE hour declare the Ice Bed Inoperable.

Page 44 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

45. Given the following conditions on Unit 1:

A Large Break LOCA has occurred 10 minutes ago

600 VAC buses 11C and 11D de-energized on the trip

All other systems function as desired.

Containment pressure is 5.0 psig and rising Which ONE of the following describes the current status of the CTS Pump discharge valves?

A. ALL CTS Pump Discharge valves are OPEN B. IMO-210, East CTS Pump Discharge is CLOSED IMO-211, East CTS Pump Discharge is CLOSED Both West CTS Pump Discharge valves are OPEN C. IMO-220, West CTS Pump Discharge is CLOSED IMO-221, West CTS Pump Discharge is CLOSED Both East CTS Pump Discharge valves are OPEN D. IMO-211, East CTS Pump Discharge is CLOSED IMO-210, East CTS Pump Discharge is OPEN IMO-221, West CTS Pump Discharge is CLOSED IMO-220, West CTS Pump Discharge is OPEN Page 45 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

46. Given the following conditions in Unit 1:

Unit is in Mode 5

Containment pressure is negative 0.3 psig.

RP has requested that Containment Purge be placed in service.

1-OHP-4021-028-005, Operation Of The Containment Purge System, provides a defined sequence of operation due to a concern with Containment Pressure.

Which ONE of the following describes this sequence and the reason for the concern while starting up the Containment Purge System?

A. Start one Purge Supply fan then open the supply fan valve since Technical Specifications require Containment pressure to be < 0 PSIG at all times.

B. Prior to starting the fans, open the Upper Containment Purge Supply valves to prevent Ice Condenser doors from opening when initiating containment purge.

C. Prior to starting the fans, open the Lower Containment exhaust fan valves to prevent Ice Condenser doors from buckling when initiating containment purge.

D. Start one Purge Exhaust fan then open the exhaust fan valve to prevent a positive pressure from adversely affecting the radiation monitor operations.

Page 46 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

47. Given the following condition on Unit 2:

Unit is operating at 100% power when an inadvertent Steam Line Isolation occurred.

Immediately following the isolation, and resultant plant response, the operators note that all the SG PORVs failed to open.

One minute following the Steam Line Isolation, which ONE of the following describes the maximum expected SG pressures?

A. 1025 psig B. 1040 psig C. 1065 psig D. 1085 psig Page 47 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

48. Given the following conditions:

Reactor power is 50% with a negative moderator temperature coefficient

Control Rods are in manual.

If steam flow is raised by 5 percent, which ONE of the following statements best describes how reactor power will respond to the change?

Reactor power will:

A. decrease to a new lower value.

B. increase temporarily, then return to its initial value.

C. increase to a new higher value.

D. decrease temporarily, then return to its initial value.

Page 48 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

49. Which ONE of the following power supply failures would allow the steam dump system to continue to operate?

A. CRID II B. CRID III C. 250 VDC Bus VDAB D. 250 VDC Bus VDCD Page 49 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

50. Unit 1 has just completed a Heatup and is preparing for a Reactor Startup.

You have been directed to open the FW pump Emergency Leak Offs (ELOs).

Which ONE of the following describes the indications/systems that you should check prior to opening these valves and why?

A. Ensure that the FW pump is reset to allow the ELOs to be opened.

B. Ensure that the FW pump oil system is operating and has been warmed to minimize the effects of cold seal water on FW pump bearings.

C. Ensure that the FW pump oil system is operating to prevent damage to the FW pumps due to condensate flow spinning the pumps.

D. Ensure that the FW pump has been removed from turning gear to prevent damage to the turning gear motor.

Page 50 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

51. The Unit 2 FW Pump Discharge Header Pressure Transmitter 2-FPC-250A slowly drifts LOW during normal plant operation.

This will cause the MFP Speed Control System to generate an indicated FW Delta-P signal ____(1)_____ than required, causing the main feed pump(s) to

______(2)_____.

Note: Assume FPC-250A is not identified as failed by DCS.

(1) (2)

A. larger speed up B. larger slow down C. smaller speed up D. smaller slow down Page 51 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

52. Which ONE of the following describes the functional relationship with respect to controlling steam generator (SG) levels between the Main Feedwater Pumps (MFPs) and the Main Feedwater Regulating Valves (MFRVs) when the unit is ramping from 50% to 100% power?

A. The MFPs maintain a variable differential pressure across the MFRVs, while the MFRVs throttle to maintain a constant SG water level.

B. The MFPs maintain a constant differential pressure across the MFRVs, while the MFRVs throttle to maintain a variable SG water level.

C. The MFPs maintain a variable differential pressure across the MFRVs, while the MFRVs throttle to maintain a variable SG water level.

D. The MFPs maintain a constant differential pressure across the MFRVs, while the MFRVs throttle to maintain a constant SG water level.

Page 52 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

53. Given the following conditions on Unit 2:

Unit is in Mode 1.

The TDAFW Pump is tagged out of service.

A Loss of Feedwater causes a reactor trip.

Coincident with the trip, T21D Differential trip actuates.

Which ONE of the following describes the Auxiliary Feedwater alignment and approximate flow rates?

A. 1 and 4 SGs being fed at 120 x 103 pph each B. 1 and 4 SGs being fed at 240 x 103 pph each C. 2 and 3 SGs being fed at 120 x 103 pph each D. ALL SGs being fed at 120 x 103 pph each Page 53 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

54. The operator incorrectly opens the breaker labeled "7.5 KVA Static Inverter Channel IV" on 250 VDC distribution panel "MCAB". The operator realizes the mistake and immediately recloses the breaker.

Which ONE of the following describes the effect of these actions, if any?

A. The alternate power source to the CRID Inverter will be lost when the breaker is reclosed. The CRID will transfer to the 120 VAC from the Regulating Transformer.

B. The alternate power source to the CRID Inverter will be lost. No automatic action will occur when the breaker is reclosed. The auto transfer lockout must be reset at the inverter.

C. The normal power source to the CRID Inverter will be lost so it will auto transfer to the alternate source. When the breaker is reclosed, it will auto transfer to the normal source.

D. The normal power source to the CRID Inverter will be lost so it will auto transfer to the alternate source. When the breaker is reclosed, the auto transfer lockout must be reset at the inverter.

Page 54 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

55. Which ONE of the following describes the effect on a closed Circulating Water pump breaker if DC control power is lost to the breaker?

A. The breaker immediately trips open and cannot be reclosed until control power is restored.

B. The breaker can be tripped from the Control Room but automatic trip functions are not operable.

C. Automatic trips are not operable and tripping the breaker from the Control Room is not possible.

D. Automatic breaker trips are operable but tripping the breaker from the Control Room is not possible.

Page 55 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

56. Given the following conditions on Unit 1:

Bus T11B normal supply breaker has opened.

DG1AB Diesel Generator has started and is tied to the bus.

Ann. 118, Drop 53, DG1AB TRIPS DISABLED is LIT Which ONE of the following conditions will automatically trip the diesel generator?

A. Engine Speed of 590 rpm B. CO2 actuating in the EDG Room C. Main Bearing Temperature 198° F D. Low Lube Oil Pressure 23 psig Page 56 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

57. Which ONE of the following describes a condition that would cause a load conservation signal to be generated for the DG1AB.

A. Train A SI and Train A Load Shed B. Train B SI and Train B CTS C. Train A SI and Train A CTS D. Train B SI with a Loss of Offsite Power Page 57 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

58. Which ONE of the following lists the two conditions that will independently cause termination of a liquid release by closing 12-RRV-285, Liquid Waste Disposal Effluent Discharge Header Shutoff Valve, and/or tripping the operating monitor tank pump?

A. Low circulating water flow High radiation sensed in the release header B. Low circulating water flow High radiation sensed in the circulating water flow C. Low release header radiation monitor sample flow High radiation sensed in the release header D. High release header radiation monitor sample flow High radiation sensed in the circulating water flow Page 58 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

59. Which ONE of the following lists the Unit 1 Control Room Ventilation system damper alignment for operation during a high alarm on ERS-7401, U1 Control Room Area Radiation Monitor?

1-HV-ACR-DA-1/1A 1-HV-ACR-DA-2 1-HV-ACR-DA-2A 1-HV-ACR-DA-3 Outside air to CR Outside air to CR PRZN Outside air to CR PRZN CR air to PRZN A. OPEN CLOSED PARTIAL OPEN OPEN B. CLOSED PARTIAL OPEN CLOSED OPEN C. OPEN PARTIAL OPEN CLOSED CLOSED D. CLOSED CLOSED PARTIAL OPEN CLOSED Page 59 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

60. Given the following conditions on Unit 2:

The East CCW HX is in service with the West CCW Pump running.

CCW Surge Tank level is stable.

CRS-4301, East CCW HX Radiation Monitor, generates an External Failure Alarm due to a faulty power supply Which ONE of the following describes the response of the CCW system for the given conditions and the subsequent operator actions required?

A. No automatic actions will occur since the West CCW pump is running.

Notify RP of the failed CRS-4301, East CCW HX Radiation Monitor.

B. No automatic actions will occur since the CRS-4401, West CCW HX Radiation Monitor is still functioning.

Split the CCW Trains with Misc Header on the West Train and isolate the East Train.

C. 2-CMO-420, West CCW HX Outlet, opens and 2-CMO-410, East CCW HX Outlet, closes.

Remove CRS-4301, East CCW HX Radiation Monitor, from service and re-align CCW flow through the West CCW Hx ONLY.

D. 2-CRV-412, CCW Surge Tank Vent Valve, will automatically close.

Notify RP to remove CRS-4301, East CCW HX Radiation Monitor, from service, then reopen 2-CRV-412.

Page 60 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

61. The operators are attempting to energize emergency bus T21A from DG2AB during a loss of all AC power.

Which ONE of the following states the equipment switch that would NOT be placed in PULL TO LOCKOUT and the reason why?

A. ESW pump to ensure diesel cooling.

B. CCW pump to ensure cooling to vital loads.

C. MDAFW pump to ensure an adequate heat sink is maintained.

D. CTS pump to ensure containment integrity is not challenged.

Page 61 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

62. A malfunction of the NESW system has resulted in a partial loss of NESW flow to the containment ventilation units.

Under this condition which ONE of the following sets of containment readings would result in Unit 2 containment still being within Technical Specification limits?

A. Pressure is 0.18 PSIG, upper containment temperature 97°F, lower containment temperature 115°F.

B. Pressure is 0.35 PSIG, upper containment temperature 105°F, lower containment temperature 97°F.

C. Pressure is 0.15 PSIG, upper containment temperature 105°F, lower containment temperature 105°F.

D. Pressure is -1.55 PSIG, upper containment temperature 97°F, lower containment temperature 115°F.

Page 62 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

63. Procedure 2-OHP-4022-064-001, Control Air Malfunction, has been entered based upon a 100 psi Control Air Pressure alarm.

Which ONE of the following is the correct sequence of events that will occur automatically as air pressures lower?

A. 95 psig at PPS-10 (20) Standby PAC starts 90 psig CAS wet receiver pressure CAC starts 85 psig at PPS-11 (21) Plant air header isolates B. 98 psig at PPS-10 (20) Standby PAC starts 97 psig CAS wet receiver pressure CAC starts 95 psig Control Air pressure Plant air header isolates C. 97 psig CAS wet receiver pressure CAC starts 95 psig at PPS-10 (20) Standby PAC starts 90 psig at PPS-11 (21) Plant air header isolates D. 95 psig CAS wet receiver pressure CAC starts 90 psig at PPS-11 (21) Plant air header isolates 85 psig at PPS-10 (20) Standby PAC starts Page 63 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

64. Given the following conditions on Unit 1:

Plant heatup is in progress with RCS temperature at 420°F.

Fire system engineer reports that the fire door at the entrance to the positive displacement charging pump and the centrifugal charging pump rooms is nonfunctional.

Additionally the engineer reports that no other fire system impairments exist.

Which ONE of the following is the minimum required action?

A. Establish an hourly fire watch patrol within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

B. Enter Tech Spec 3.0.3 due to no operable charging pumps.

C. Verify, by inspection, the operability of the manual fire fighting equipment within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

D. Close the door and establish a continuous fire watch on at least one side of the fire door within 15 minutes.

Page 64 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

65. Given the following conditions on Unit 1:

Reactor has tripped.

RO notes that two large sections of the containment isolation panel valves have just gone closed.

Which ONE of the following sets of conditions would indicate that this is due to a spurious Phase A signal?

CNTMT STEAM LINE SG PZR PRESSURE DELTA-P PRESSURE PRESSURE A. 2.9 psig 80 psid 1005 psig 2000 psig B. 0.2 psig 20 psid 450 psig 1810 psig C. 0.5 psig 15 psid 600 psig 1900 psig D. 1.7 psig 110 psid 800 psig 1850 psig Page 65 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

66. A licensed individual is planning to undergo some medical evaluations and a test utilizing radioisotopes. It has been determined that this test will not affect judgment or fitness for duty in any way.

Which ONE of the following describes the procedural requirements for these conditions?

The licensed individual:

A. Does not need to report this condition as a potentially disqualifying condition since it is not a fitness for duty issue.

B. Must report this situation to the fitness-for-duty liaison for independent verification that it is not a fitness for duty issue, prior to assuming license duties.

C. Must notify the Plant Manager who will evaluate the condition, prior to assuming license duties.

D. Must notify the Ops Training Manager of a potential disqualifying medical condition Page 66 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

67. Given the following conditions on Unit 2:

Reactor power is stable at 100%.

A Reactor Operator and the Unit Supervisor are in the Control Room.

A high vibration alarm is received on the Heater Drain pump requiring someone to go behind the panel to check the indications.

Which ONE of the following describes the procedurally accepted method of checking the indications?

A. The Unit Supervisor can go behind the panel to check the vibration.

B. The Reactor Operator can go behind the panel to check the vibration.

C. Both the Reactor Operator and the Unit Supervisor are allowed to go behind the panel to check the vibration as long as all controls are in automatic.

D. Neither the Reactor Operator or the Unit Supervisor can go behind the panels.

They must get another operator to check the vibration.

Page 67 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

68. Conservative Decision making states that :

"WHEN faced with unexpected or uncertain conditions, THEN personnel must promptly identify a transition point at which efforts to keep the unit on-line or on schedule are no longer conservative, nor reasonable."

Once this point is reached :

A. the reactor must be tripped immediately.

B. senior management must be notified to determine course of action.

C. actions must be taken to place the unit in a safe condition without hesitation.

D. the NRC must be notified and actions taken to address the problem within one hour.

Page 68 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

69. In accordance with administrative procedures, which ONE of the following conditions would permit troubleshooting to be performed on Technical Specification equipment?

A. Equipment is operating.

B. Equipment is declared inoperable.

C. Equipment is logged operable but degraded.

D. Equipment is operable but LCO time is not exceeded.

Page 69 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

70. A maintenance visual inspection requires momentarily placing a 'B' Train pump control switch in PULL-TO-LOCKOUT. The Unit condition is such that BOTH trains are required to auto start.

Which ONE of the following describes the status of the affected ESF system?

The 'B' Train pump is INOPERABLE until:

A. the control switch is independently verified in its normal position.

B. the pump's monthly surveillance has been performed.

C. the pump's auto start function is tested.

D. the pump is manually started.

Page 70 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

71. Given the following conditions on Unit 2:

A LOCA has occurred

The TSC has been fully staffed and activated

An individual is needed for lifesaving activities during which 30 Rem of TEDE exposure is expected to be received Which ONE of the following is correct concerning this lifesaving activity?

A. The individual is required to be a volunteer and the Site Emergency Coordinator is required to approve the exposure.

B. The individual is required to be a volunteer and the Operations Shift Manager is required to approve the exposure.

C. The individual is NOT required to be a volunteer and the Site Emergency Coordinator is required to approve the exposure.

D. The individual is NOT required to be a volunteer and the Operations Shift Manager is required to approve the exposure.

Page 71 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

72. Given the following conditions:

Units 1 and 2 are at 100% power.

Unit 2 has experienced several fuel pin failures.

A leak must be repaired on a pipe at the end of the Aux. Bldg. 601 ft. elev. pipe tunnel.

The general area dose rate in the location of the repair is 600 mrem/hr.

In order to reach the location of the repair the worker must transit through a 6 Rem/hr high radiation area for 2 minutes and return via the same path.

The worker currently has an accumulated annual dose of 400 mrem.

Which ONE of the following is the maximum allowable time that the worker can participate in the repairs and NOT exceed the TEDE Administrative Dose Limit?

A. 70 minutes B. 120 minutes C. 140 minutes D. 160 minutes Page 72 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

73. Given the following conditions on Unit 1:

Containment Purge System is operating in the VENTILATION MODE.

A HIGH alarm on VRS-1505, Auxiliary Building Ventilation Noble Gas Activity Monitor, occurs (unplanned).

Which ONE of the following describes the required operator response for the Containment Ventilation System to the failure alarm?

A. Stop the Containment Purge and consult with Radiation Protection prior to restarting the system.

B. Continue the Purge as long as VRS-1101, Containment Normal Range Area Radiation Monitor still indicating as expected.

C. Verify the following:

Containment ventilation isolation valves 1-VCR-101 through 1-VCR-107 close;

1-HV-CPS-1/2, Containment Purge Supply Fans 1 and 2, trip;

1-HV-CPX-1/2, Containment Purge Exhaust Fans 1 and 2, trip;

1-HV-CPR-1, Containment Pressure Relief Fan, trips;

1-HV-CIPS-1, Containment Instrument Room Purge Supply Fan, trips.

D. Verify the following:

Containment ventilation isolation valves 1-VCR-201 through 1-VCR-207 close;

1-HV-CPS-1/2, Containment Purge Supply Fans 1 and 2, trip;

1-HV-CPX-1/2, Containment Purge Exhaust Fans 1 and 2, trip;

1-HV-CPR-1, Containment Pressure Relief Fan, trips;

1-HV-CIPX-1, Containment Instrument Room Purge Exhaust Fan, trips.

Page 73 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

74. Given the following conditions on Unit 1:

A reactor trip occurred from 15% power.

Safety Injection was NOT actuated and was NOT required.

1-OHP-4023-E-0, Reactor Trip or Safety Injection, has been performed, and a transition to 1-OHP-4023-ES-0.1, Reactor Trip Response, has been made.

The following conditions exist:

Tavg is STABLE at 547°F

Pressurizer level is 11% and lowering slowly

RCS subcooling is 32°F and lowering slowly

All NR SG levels are 28 - 30%;

AFW flows indicate 0 klb/hr

Containment pressure is 0.7 psig and rising slowly Which ONE of the following describes the appropriate actions for these conditions?

A. Actuate SI and return to 1-OHP-4023-E-0 step 1.

B. Go to 1-OHP-4023-FR-H.1, Response to Loss of Secondary Heat Sink.

C. Go to 1-OHP-4023-FR-I.2, Response to Low Pressurizer Level.

D. Manually start ECCS pumps and continue with 1-OHP-4023-ES-0.1.

Page 74 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

75. Given the following conditions on Unit 2:

A Safety Injection (SI) has ocurred.

The Immediate Action steps of 2-OHP-4023-E-0, Reactor Trip Or Safety Injection, have just been completed.

The following steam generator conditions are noted:

SG 21 pressure is 740 psig and lowering slowly.

SG 22 pressure is 450 psig and lowering rapidly

SG 23 pressure is 735 psig and lowering slowly.

SG 24 pressure is 745 psig and lowering slowly.

Main Steam header pressure is 700 psig and lowering slowly.

Which ONE of the following actions should be promptly performed to mitigate the event?

A. Transition to 2-OHP-4023-E-1, Loss of Reactor or Secondary Coolant.

B. Transition to 2-OHP-4023-E-2, Faulted Steam Generator Isolation, C. Close all the SG stop valves and continue with 2-OHP-4023-E-0, Reactor Trip Or Safety Injection.

D. Close SG 22 Stop Valve and verify steam supply available to the Turbine Driven Axiliary Feedwater Pump (TDAFP)

Page 75 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

76. Given the following conditions on Unit 2:

Unit was at 90% power

Control Rods were in AUTO

CBD began to step out with no mismatch signal.

Rods were taken to MANUAL and rod motion ceased.

The following conditions now exist:

CBD Bank Demand position is now 222 Steps.

Group 2 Bank D RPIs ALL indicate 222 Steps.

Group 1 Bank D RPIs indicate as follows:

o Rod D4: 205 Steps.

o Rod D12: 222 Steps o Rod M12: 207 Steps o Rod M4: 222 Steps Reactor Engineering has determined that all CBD rods are free to move and has provided the following information:

R is 1.041

CFQ is 2.335

K(Z) is .95 (at 10 feet)

FQW ( Z ) is 2.174 (at 10 feet)

Which ONE of the following identifies the Technical Specification Action Condition(s) that must be entered?

Reference Provided: Unit 2 TS 3.1.4 Rod Group Alignment Limits A. 3.1.4.A Only B. 3.1.4.B Only C. 3.1.4.A and 3.1.4.B Only D. 3.1.4.B and 3.1.4.D Only Page 76 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

77. Given the following conditions on Unit 1:

A power escalation is in progress

At approximately 35% power the Main Turbine Trips The following conditions now exist:

All 4 Turbine Stop Valve Status Lights are lit

All RPIs have lost power

Train A Reactor Trip Breaker is Open

Train B Reactor Trip Breaker is Closed

WR Log Power = 7%

WR Startup Rate = 0.0 DPM and stable Which ONE of the following actions is required?

A. Implement 1-OHP-4023-E-0, Reactor Trip or Safety Injection.

Following completion of Immediate Actions, transition to 1-OHP-4023-ES-0.1, Reactor Trip Response.

B. Implement 1-OHP-4023-E-0, Reactor Trip or Safety Injection.

During verification of Reactor Trip, transition to Implement 1-OHP-4023-FR-S.1, Response to Nuclear Power Generation/ATWS, and manually insert control rods.

C. Implement 1-OHP-4022-001-002, Loss of Load (Load Rejection).

When directed go to 1-OHP-4023-FR-S.1, Response to Nuclear Power Generation/ATWS.

D. Implement 1-OHP-4022-001-002, Loss of Load (Load Rejection).

Upon Turbine Trip Verification, go to 1-OHP-4023-E.0, Reactor Trip or Safety Injection.

Page 77 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

78. Given the following conditions on Unit 2:

Reactor power was 100% power when an RCS leak developed.

The Unit Supervisor is implementing 2-OHP 4022-002-020, Excessive RCS Leakage.

The following conditions now exist:

Letdown flow is isolated.

East and West Charging pumps are operating.

Charging flow is 180 gpm.

Pressurizer level is 51% and constant.

VCT makeup is in Auto.

VCT level is 22% and lowering.

Containment pressure is 0.5 psig and constant.

Which ONE of the following describes the required operator action and why (assume all control systems function as designed)?

A. Verify that CCP suction automatically aligns to the RWST at 14.0% VCT level and perform a controlled rapid shutdown per 2-OHP-4022-001-006 Rapid Power Reduction Response, to maintain RCS Tavg-Tref.

B. Verify VCT auto makeup begins at 14.0 % and then restore 75 gpm letdown to ensure proper regen heat exchanger warming of the charging flow.

C. Verify that CCP suction automatically aligns to the RWST at 7.0% VCT level and perform a controlled rapid shutdown per 2-OHP-4022-001-006 Rapid Power Reduction Response since RCS leakage is greater than the Technical Specification Limit.

D. Trip the reactor and transition to 2-OHP-4023-E-0, Reactor Trip or Safety Injection since VCT level can NOT be maintained with VCT auto makeup.

Page 78 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

79. Given the following conditions on Unit 2:

Unit was operating at 100% power

2-OHP-4022-016-001, Malfunction of the CCW System is being implemented due to indications of a lowering CCW Surge tank level.

The Crew has started the West CCW pump, split the East and West Headers, and aligned the Miscellaneous Services Header to the East Header.

An AEO has reported that a CCW leak of approximately 150 gpm has been identified in the Aux Building 609' elevation, flowing toward the passenger elevator.

The following Surge Tank Level Recorder conditions exist:

Train 'A' Train 'B' CLR-410 CLR-411 Reading 48" 18" Trend Stable Lowering Which ONE of the following describes the leak location and the required actions?

The leak is located on the:

A. Miscellaneous Services Header. Trip the Reactor, Stop both CCW Pumps, and Implement 2-OHP-4022-016-004, Loss of CCW along with 2-OHP-4023-E-0, Reactor Trip or Safety Injection.

B. East Safeguards Header. Shutdown the East CCW pump and align the Miscellaneous Services Header to the West Safeguards Header.

C. West Safeguards Header. Shutdown the West CCW pump and the equipment cooled by the West Header.

D. Miscellaneous Services Header. Trip the Reactor, Trip the RCPs, and isolate the Miscellaneous Services Header while performing 2-OHP-4023-E-0, Reactor Trip or Safety Injection.

Page 79 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

80. Given the following conditions on Unit 2:

A reactor startup is in progress with the reactor just critical.

The operator has just stopped moving control rods.

Intermediate Range Power slowly rises above 2 x 10-10 amps.

ONE source range (SR) nuclear instrumentation channel (N-31) fails LOW.

Remaining power indications stabilize.

Which ONE of the following actions, if any, is required for compliance with Technical Specifications?

Reference Provided: Unit 2 TS 3.3.1, Reactor Trip System Instrumentation A. No action required, source range not required to be operable.

B. Trip the reactor and enter 2-OHP-4023-E-0, Reactor Trip or Safety Injection.

C. Conduct a reactor shutdown and restore both SR channels to operability prior to next startup.

D. Suspend all operations involving positive reactivity changes until both SR channels are restored to operability.

Page 80 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

81. Given the following conditions on Unit 2:

A SGTR has occurred coincident with a Loss of Offsite Power

2-OHP-4023-E-3, Steam Generator Tube Rupture, is being performed.

The Unit Supervisor is at Step 41, Select Appropriate Post-SGTR Cooldown Procedure.

The following conditions now exist:

RCS Wide Range Pressure is 800 psig and stable.

RCS Incore Thermocouples are 475oF and slowly lowering

RCS T-hots are 470 and slowly lowering

RCS T-colds are 445 and stable

SG Pressures are 387 psig and stable.

PZR level is 25% and slowly rising.

Which ONE of the following describes the status of natural circulation and the appropriate procedural transition for the Unit Supervisor?

A. Natural Circulation exists.

Transition to 2-OHP-4023-ES-3.1, Post-SGTR Cooldown Using Backfill.

B. Natural Circulation does NOT exist.

Transition to 2-OHP-4023-ES-3.2, Post-SGTR Cooldown Using Blowdown C. Natural Circulation does NOT exist.

Transition to 2-OHP-4023-ES-3.3, Post-SGTR Cooldown Using Steam Dump.

D. Natural Circulation exists.

Transition to 2-OHP-4023-ECA-3.1, SGTR With Loss Of Reactor Coolant -

Subcooled Recovery Desired.

Page 81 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

82. Given the following conditions on Unit 2:

Steam Gen 1/2/3/4 Steam Line Flow High Alarms - LIT

Steam Gen 1/2/3/4 SF>FWF Flow Mismatch Alarms - LIT

RCS Tavg is 561oF and lowering

Turbine load is lowering

Rods are stepping out

Steam flows are 3.6 x 106 lbm/hr and stable.

FW flows are 2.1 x 106 lbm/hr and rising.

Which ONE of the following correctly describes the cause and required action to be taken for the above conditions?

A. A steam line break exists. Direct the operators to perform a Reactor Trip and Main Steamline Isolation.

B. A feed line break exists. Direct the operators to perform a Reactor Trip and Main Feedwater Isolation.

C. Feedwater Pump Delta-P is too Low. Direct the operator to raise FW Pump Speed and FW pump flow.

D. MPC-253 has failed LOW. Direct the operators to perform actions for failed First Stage Turbine Impulse Pressure Transmitter.

Page 82 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

83. Given the following conditions:

A Gas Decay Tank release is in progress through the Unit 1 plant vent.

A High Alarm occurs on VRS-2505, Unit 2 Vent Low Range Noble Gas Radiation Monitor.

RP determines that VRS-2505 is INOPERABLE due to a failed high channel.

The effects of the VRS-2505 High Alarm are that 12-RRV-306, Vent Stack Release Valve, __________________.

Additionally, which ONE of the following is required by PMP-6010-OSD-001, Off-site Dose Calculation Manual?

Reference Provided: PMP-6010-OSD-001, Off-site Dose Calculation Manual, Attachment 3.4 (pages 57-59)

A. will automatically close Grab samples must be taken at least once per shift and analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

B. must be manually closed Grab samples must be taken at least once per shift and analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

C. will automatically close No actions are required as long as VRS-1505 remains OPERABLE.

D. must be manually closed No actions are required as long as VRS-1505 remains OPERABLE.

Page 83 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

84. Given the following conditions on Unit 2:

Unit is implementing 2-OHP-4023-ECA-0.0, Loss of all AC Power

Power has just been restored from the U2 AB EDG

Cooling flow to the U2 AB EDG is being checked per Step 32

ONLY the normal ESW supply to the U2 AB EDG is open and providing flow.

Which ONE of the following describes the actions the Unit Supervisor should direct and the reason for those actions?

A. Open the Alternate Supply to the AB EDG Maximizes flow through the EDG to compensate for maximum loading.

B. Leave the Alternate Supply to the AB EDG closed Prevents a loss of ESW cooling to both trains of equipment due to silt and mud build-up in the component's heat exchangers.

C. Open the Alternate Supply to the AB EDG Ensures adequate flow in the event of loss of the normal supply path.

D. Leave the Alternate Supply to the AB EDG closed Limits the amount of flow to the EDG to ensure that other components in the ESW train receive adequate flow to support safety functions.

Page 84 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

85. Given the following conditions on Unit 1:

Unit is preparing for a reactor start up following a refueling outage.

Tavg is 515°F with a heatup in progress.

During the outage testing was performed per the Containment Leak Rate Testing Program

At 0200, a Station Engineer reports that a mistake had been made in analyzing the required Containment Leak Rate Test results that were conducted prior to exceeding 200°F.

The initial calculated Type A leakage had been recorded as 0.5 La

Re-calculation indicates that the Type A leakage is actually 0.8 La

The re-calculated values have been verified and reviewed by the Shift Manager Which ONE of the following actions, if any, is required by Technical Specifications in response to this situation?

Reference Provided: Unit 1 TS 3.6.1, Containment and its Bases A. Continue with the heatup. Entry into Tech Spec 3.6.1 is not required.

B. Continue with the heatup. Do not enter Mode 2 until the leak test is re-performed C. Enter Tech Spec 3.0.3. Be in MODE 5 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

D. Enter Tech Spec 3.6.1. Be in MODE 5 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

Page 85 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

86. Given the following conditions on Unit 1:

A LOCA occurred 30 minutes ago

RCS pressure is 125 psig

RCS Core Exit TCs read 380°F

RCS Cold Leg temperatures are 250°F

1N SI Pump is running providing 650 gpm flow

1E RHR Pump is running providing 3000 gpm flow What is the appropriate action taken in response to the above conditions?

Entry into 1-OHP-4023-FR-P.1, Response to Pressurized Thermal Shock Condition, is:

A. made but NO actions are implemented before returning to procedure in effect.

B. made and cooldown will continue within a limit of 50°F in any 60 minute period.

C. made and a RCS temperature soak for a ONE hour period will be completed.

D. NOT required since RCS pressure is below 300 psig.

Page 86 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

87. Given the following conditions on Unit 1:

Unit is responding to a LOCA using 1-OHP-4023-E-1, Loss of Reactor or Secondary Coolant.

The Unit Supervisor is at Step 11, Initiate Evaluation Of Plant Status.

The following plant conditions now exist:

RWST Level is 42% and lowering

Containment pressure is 0.3 psig and stable

Containment Recirc Sump Minimum Recirc Level Lights - NOT LIT

East RHR Pump Compartment Sump Annunciator - LIT

East RHR Pump Discharge pressure is 600 psig

Aux Building area radiation monitors are in alarm Which ONE of the following procedures should the Unit Supervisor transition into from 1-OHP-4023-E-1?

A. 1-OHP-4023-ECA-1.2, LOCA Outside Containment B. 1-OHP-4023-ECA-1.3, Sump Blockage Control Room Procedure C. 1-OHP-4023-ECA-1.1, Loss of Emergency Coolant Recirculation D. 1-OHP-4023-ES-1.3, Transfer To Cold Leg Recirculation Page 87 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

88. Given the following conditions on Unit 1:

The Unit Supervisor entered 1-OHP-4022-016-001, Malfunction Of The CCW System, 5 minutes ago.

The following plant conditions now exist:

Reactor Power is 8%

All RCP Motor Bearing Lube Oil CCW flow low annunciators are lit.

All flows and temperatures are STABLE as follows:

RCP RCP RCP RCP

11 #12 #13 #14 o Upper Motor Bearing temps 189oF 190oF 205oF 191oF o Motor Bearing Lube Oil CCW flow 4 gpm 4 gpm 3 gpm 3 gpm Which ONE of the following describes the sequence of actions the Unit Supervisor will provide to the panel operators?

A. 1) Perform a rapid shutdown per 1-OHP-4021-001-006, Rapid Power Reduction

2) Trip #13 RCP immediately after the reactor is shutdown.

3) Close NRV-163, Loop 13 PZR Spray Control B. 1) Trip the reactor

2) Go to 1-OHP-4023-E-0, Reactor Trip or Safety Injection

3) Trip #13 RCP after Reactor Trip is verified

4) Close NRV-163, Loop 13 PZR Spray Control C. 1) Trip the reactor

2) Go to 1-OHP-4023-E-0, Reactor Trip or Safety Injection

3) Trip all RCPs after Reactor Trip is verified

4) Close NRV-163 and NRV-164, Loop 13 and 14 PZR Spray Control D. 1) Perform a rapid shutdown per 1-OHP-4021-001-006, Rapid Power Reduction

2) Trip all RCPs after the reactor is shutdown.

3) Close NRV-163 and NRV-164, Loop 13 and 14 PZR Spray Control Page 88 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

89. Given the following conditions:

The refueling crew has just set a new fuel assembly next to an irradiated fuel assembly in the Unit 1 core.

The manipulator crane operator observes the refueling cavity level lowering rapidly.

The SRO-CA and Control Room begin implementing 1-OHP-4022-002-006, Loss of Refueling Water Level during Refueling Operations.

The following conditions exist Twenty Minutes Later:

The Transfer Tube Gate Valve has been closed

The Weir Gate could NOT be closed

RCS level is 614' and lowering

RWST to RHR makeup is in progress Based on these conditions, which ONE of the following describes the correct actions for the Control Room SRO?

A. Go to 12-OHP-4022-018-001, Loss of SFP Cooling.

B. Go to 1-OHP-4022-017-001, Loss of RHR Cooling C. Direct the SRO-CA to verify integrity of the Refueling Cavity Seal D. Direct the SRO-CA to check for misalignment of the Refueling Cavity Drains Page 89 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

90. Given the following conditions on Unit 2:

Unit is in MODE 4 and preparing to startup following a refueling outage.

During the outage, all 5 Main Steam Safety Valves (MSSVs) associated with SG21 were removed and inspected.

The maintenance was satisfactory and the MSSVs will function if required.

The Inservice Testing of the MSSV setpoints has NOT been performed.

A risk assessment has NOT been performed.

Without reliance on SR 3.0.3, which ONE of the following describes if the reactor startup can proceed to MODE 3 with the MSSVs in this condition?

Reference Provided: Unit 2 TS Section 1.4, Frequency, Section SR 3.0, Surveillance Requirements, and TS 3.7.1, Main Steam Safety Valves A. No. The TS ACTIONS must be immediately entered and all portions of the post testing must be completed before entering MODE 3.

B. No. An alternate method of setpoint verification must be used and MSSV OPERABILITY must be demonstrated before entering MODE 3.

C. Yes. However, when the unit reaches MODE 2, the test must be at least started within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after entering MODE 2.

D. Yes. However, when test conditions can be established, the test must be completed prior to MODE 2.

Page 90 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

91. Given the following conditions on Unit 2:

A Main Generator fire has been confirmed by an AEO who reported that flames are coming out of the Unit 2 Main Generator Shaft.

After directing a Reactor/Turbine Trip and entering 2-OHP-4023-E-0, Reactor Trip Response, which ONE of the following would you direct the AEO to perform first?

Dispatch an AEO to:

A. Shut down the Main Generator Seal Oil System per 2-OHP-4021-080-002 Operation Of Shaft Seal Oil System B. Depressurize and Purge the Main Generator per 2-OHP-4022-053-002 Emergency Degassing Of The Electrical Generator C. Start All Fire Pumps per 12-OHP-4021-066-001, Fire Protection System (Water)

Operation.

D. Shut down the Generator Condition Monitor at 2-GCM-AARP-11, Generator Condition Monitor Auto Alarm Remote Panel Page 91 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

92. Given the following conditions on Unit 2:

A plant heatup is in progress following a forced shutdown

Reactor coolant average temperature at 450°F when the following Auxiliary Feedwater (AFW) trains become inoperable:

o 0100 on July 7, TDAFW train is declared inoperable due to 2-MCM-221 steam supply valve being inoperable.

o 1830 on July 8, 2E AFW train is declared inoperable.

o 1900 on July 8, 2-MCM-221 steam supply valve is restored to OPERABLE status.

Including any extensions permitted by TS, and without re-entering a Technical Specification condition requiring a plant shutdown, the 2E AFW train must be restored to OPERABLE status by __________________.

Reference Provided: Unit 2 TS 3.7.5 Auxiliary Feedwater System, TS Section 1.3 Completion Times A. 0100 on July 10.

B. 0100 on July 17.

C. 1830 on July 11.

D. 1830 on July 12.

Page 92 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

93. Given the following conditions on Unit 1:

The plant is operating at 6% power preparing for Turbine roll.

NLP-151, PZR Level Channel 1 failed 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago. The bistables have been tripped and all actions are complete as per 1-OHP-4022-013-010, Pressurizer Level Instrument Malfunction.

PZR level is currently 40% on the remaining PZR Level channels.

Which ONE of the following describes the effects on the plant if NLP-153, PZR Level Channel 3 fails low and the affect on Unit Supervisor's decision to trip bistables for the Channel 3 failure?

Note: Assume NO operator actions.

Reference Provided: Unit 1 TS Section 3.0 Limiting Condition for Operation Applicability and TS 3.3.1 Reactor Trip System Instrumentation A. Letdown will Isolate and heaters will de-energize.

Bistables may be tripped without causing a reactor trip. Power must remain less than 10%.

B. Letdown will remain in service and heaters will de-energize.

Bistables should NOT be tripped since a reactor trip will be generated. Power must remain less than 10%.

C. Letdown will remain in service and heaters will de-energize.

Bistables may be tripped without causing a reactor trip. Power must be reduced to less than 5%.

D. Letdown will Isolate and heaters will de-energize.

Bistables should NOT be tripped since a reactor trip will be generated. Power must be reduced to less than 5%.

Page 93 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

94. Given the following conditions on Unit 1:

Unit is in Mode 6

Refueling cavity is filled to 24.2 feet above flange

Core reload is in progress

RCS temperature is 82°F

1W RHR is OOS due to an Oil Leak

1E RHR train is in operation A leak has been reported on the 1E RHR pump mechanical seal heat exchanger. To repair the leak, the RHR pump must be stopped. Maintenance estimates it will take 40 minutes to complete repairs.

1. How does this affect the ability to continue core reload?

2. What is the basis for having one RHR loop in operation in this condition?

A. 1. Core reload must be stopped.

2. Provides for adequate RCS mixing and control of reactor coolant temperature.

B. 1. Core reload must be stopped.

2. Ensures that a core Keff of less than or equal to 0.95 is maintained during fuel handling operations.

C. 1. Core reload may continue provided no operations are permitted that would dilute the refueling cavity boron concentration.

2. Provide for adequate RCS mixing and control of reactor coolant temperature.

D. 1. Core reload may continue provided no operations are permitted that would dilute the refueling cavity boron concentration.

2. Ensures that a core Keff of less than or equal to 0.95 is maintained during fuel handling operations.

Page 94 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

95. Given the following conditions on Unit 2:

A normal plant startup and power escalation to 100% was initiated following a refueling outage.

The reactor achieved 100% rated power (3468 MWth) approximately 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago.

MTI has informed the Unit Supervisor the Blowdown flow instrument for SG21 is reading approximately 100 gpm higher than actual blowdown flow.

The Unit Supervisor should:

A. direct the control room operator to raise power slightly since actual thermal power is less than PPC calculated thermal power of 3468 MWth.

B. direct an immediate power reduction to ensure the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months average does not exceed 3468 MWth.

C. order that no reactor power adjustments be made for the next 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months so an accurate 1-hour power average is obtained.

D. order that no reactor power adjustments be made for the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and then make adjustments to power as required.

Page 95 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

96. Given the following conditions in Unit 2:

The unit was stable at 95% power with Rod Control in AUTO

Control Bank D is at 220 steps with AFD at -6.5%

A HIGH failure of Power Range channel N41 occurred

The reactor operator responded by placing Rod control in MANUAL 15 seconds after the event.

Which ONE of the following may require prompt crew actions to ensure continued compliance with Technical Specifications?

Reference Provided: U2 COLR (Cycle 18) and TDB 2-Figure 13.1, Target Band and ARM A. Axial Flux Difference (AFD)

B. Quadrant Power Tilt Ratio (QPTR)

C. Rod Insertion Limits (RIL)

D. Shutdown Margin (SDM)

Page 96 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

97. A LOCA that resulted in significant core damage occurred at 1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months . Containment Pressure and Radiation levels were recorded as follows:

Radiation Pressure Time (R/Hr) (psig) 1600 420,000 6.2 1630 420,000 6.2 1700 350,000 5.8 1730 280,000 5.3 1800 260,000 4.8 1830 120,000 4.6 1900 90,000 4.3 1930 90,000 4.0 2000 90,000 3.9 At 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months , while performing Emergency Operating Procedures, a step is encountered which states "Check PZR level - GREATER THAN 20% [24%

ADVERSE]".

Which ONE of the following describes the required Pressurizer level and why?

A. 20% because the Containment Radiation levels are no longer above the Adverse setpoint requirement.

B. 24% because adverse values must be used until evaluated for lasting effects because the integrated dose limit has been exceeded.

C. 24% because adverse containment exists due to the current containment radiation dose rate.

D. 20% because the Containment Pressure is no longer above the Adverse setpoint requirement Page 97 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

98. Which ONE of the following responses correctly reflects the bases for Reactor Coolant Specific Activity in Technical Specifications?

A. The short-lived radioactive isotope fission products will have decayed prior to any fuel movement.

B. Limitations on specific activity in the RCS reduces corrosion product activation and subsequent RCS integrity challenge.

C. During a LOCA the dose will NOT exceed the 10CFR20 limits at the site boundary.

D. During a steam generator tube rupture the release of activity through the atmospheric relief valves will NOT exceed 10CFR100 limits.

Page 98 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination

99. Given the following conditions on Unit 2:

A LOCA has occurred

The STA is monitoring the Critical Safety Functions and notes the following indications:

o WR log power 0%

o WR startup rate Negative o Containment Pressure 13 psig o CETCs 5 highest 760°F o RVLIS Narrow Range 76%

o Pressurizer Level 0%

o RCS Pressure 480 psig o AFW Flow 300 x103 pph SG21 SG22 SG23 SG24 o Narrow Range SG Levels 12% 15% 16% 12%

Given the conditions described above, to which ONE of the following procedures should the SRO transition?

A. 2-OHP-4023-FR-C.2, Response to Degraded Core Cooling B. 2-OHP-4023-FR-I.2, Response to Low Pressurizer Level C. 2-OHP-4023-FR-Z.1, Response to High Containment Pressure D. 2-OHP-4023-FR-H.1, Response to Loss of Secondary Heat Sink Page 99 of 100 Test Date: 7/2/2010

Cook 2010 NRC Examination 100. Given the following conditions on Unit 2:

The unit has tripped and experienced a safety injection.

While performing 2-OHP-4023-ES-1.2, Post LOCA Cooldown and Depressurization, an ORANGE path condition was noted for the Core Cooling Critical Safety Function.

2-OHP-4023-FR-C.2, Response to Degraded Core Cooling, was entered.

While performing steps of this procedure, the Shift Technical Advisor reports the following:

RED path condition exists for Core Cooling Critical Safety Function.

RED path condition exists for Containment Critical Safety Function.

NO other abnormal conditions were noted.

Based on these plant conditions, which ONE of the following is the appropriate action for the Unit Supervisor to take?

A. Complete actions of 2-OHP-4023-FR-C.2, Response to Degraded Core Cooling, and then transition to 2-OHP-4023-FR-Z.1, Response to Containment High Pressure.

B. Complete actions of 2-OHP-4023-FR-C.2, Response to Degraded Core Cooling, and then transition to 2-OHP-4023-FR-C.1.

C. Stop performing 2-OHP-4023-FR-C.2, Response to Degraded Core Cooling, and immediately transition to 2-OHP-4023-FR-Z.1, Response to Containment High Pressure.

D. Stop performing 02-OHP-4023-FR-C.2, Response to Degraded Core Cooling, and immediately transition to 2-OHP-4023-FR-C.1, Response to Inadequate Core Cooling.

Page 100 of 100 Test Date: 7/2/2010

ML102220150

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