ML14224A630

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301 Final RO Exam with Key
ML14224A630
Person / Time
Site: Surry  Dominion icon.png
Issue date: 08/12/2014
From:
NRC/RGN-II/DRS/OLB
To:
Virginia Electric & Power Co (VEPCO)
References
50-280/14-301, 50-281/14-301
Download: ML14224A630 (79)
v • d • e


Text

Question 1 A Plant startup is in progress in accordance with 1-GOP-1.5, UNIT STARTUP, 2% TO MAX ALLOWABLE with the following conditions:

  • Reactor power is at 11% and steady.
  • The Intermediate Range Trip and Power Range Low Trips have just been blocked.
  • Tave is 549 oF and steady.
  • Control Bank D is at 150 steps.

RCCA G-3 (Shutdown Bank A) drops partially into the core from 229 steps to 18 steps. The following conditions are noted:

  • Control Bank D starts moving out continuously.
  • Tave drops to 547 oF.
  • Power drops to 7%.

What actions shall be taken?

A. Place Rod Control to MAN position and go to AP-53.00, Loss of Vital Inst./Controls.

B. Place Rod Control to MAN position and perform a normal shutdown of the Unit per 1-GOP-2.3, Reactor Shutdown.

C. Manually trip the reactor and initiate normal boration per ES-0.1, Reactor Trip Response.

D. Manually trip the reactor and initiate emergency boration for stuck rod per ES-0.1, Reactor Trip Response.

Question 2 Unit 1 is operating at 100% when the following occurs:

  • 1-CH-FI-1130A, RCP A SEAL INJ FLOW reads 0.0 gpm.
  • RCP A Seal Wtr Out temperatures decreased from 125 oF to 103 oF.
  • RCP A Seal Leakoff flow is 2.5 gpm and steady.
  • RCP A Thermal Barrier CC Outlet flow is 40.0 gpm and steady.
  • RCP A CC Outlet Temp is 102 oF and steady.
  • ARP 1C-D3, RCP 1A SHAFT SEAL WTR LO INJ FLOW actions are in progress.

Based on the above indications, which one of the following describes:

1) The Abnormal Procedure that would be utilized for this condition:
a. AP-9.00, RCP Abnormal Conditions. OR
b. AP-9.02, Loss of RCP Seal Cooling.
2) Is an immediate Reactor Trip required (yes/no)?

A. 1) AP-9.00, RCP Abnormal Conditions.

2) No.

B. 1) AP-9.02, Loss of RCP Seal Cooling.

2) No.

C. 1) AP-9.02, Loss of RCP Seal Cooling.

2) Yes.

D. 1) AP-9.00, RCP Abnormal Conditions.

2) Yes.

Question 3 Given the following conditions:

  • Unit 1 is in Refueling with core off-load in progress.
  • Fuel Handlers are withdrawing an assembly from the core while performing a visual examination.
  • Refuel cavity level is 26 feet and stable.
  • After the assembly has been fully withdrawn into the manipulator mast, the following occur:

o Annunciator RM-K8, 1-RM-RI-162 HIGH alarm.

o Unit 2 BOP reports that 1-RM-RI-162, Manipulator Crane, has increased by a factor of 10.

Which one of the following describes:

1) The Abnormal Procedure that would be utilized for this condition:
a. 0-AP-22.00, Fuel Handling Abnormal Conditions. OR
b. 1-AP-22.01, Loss of Refueling Cavity Level.
2) The location where the fuel assembly shall be placed.

A. 1) 0-AP-22.00, Fuel Handling Abnormal Conditions.

2) Back in its original location in the core.

B. 1) 0-AP-22.00, Fuel Handling Abnormal Conditions.

2) In a vertical position in the upender.

C. 1) 1-AP-22.01, Loss of Refueling Cavity Level.

2) Back in its original location in the core.

D. 1) 1-AP-22.01, Loss of Refueling Cavity Level.

2) In a vertical position in the upender.

Question 4 Given the following plant conditions:

  • Unit 1 is at 95% Power, after extended Governor maintenance.
  • Core Burnup is at 9,000 MWD/MTU.
  • Power is ready to be raised back up to 100%.
  • PG Flow Cntrl, 1-CH-FC-1114A set to 100 gpm.
  • The STA determines that 100 pcm reactivity change is needed to increase power to 100%.
  • Target Rod height is Control Bank D at 219 steps.
  • Control Bank D is currently at 211 steps.
  • OP-RX-010 Reactivity Brief:

o 3.8 gallons of Boric Acid = 1 ppm change in RCS.

o 65.6 gallons of PG = 1 ppm change in RCS.

o Differential Boron Worth = -7.8 pcm/ppm.

Using the Integral Rod worth table determine the following:

1) Amount of dilution required in gallons.
2) Integrator setting of the CVCS blender to support the dilution of the RCS after the reactivity change is made (not accounting for Xenon change) per 1-OP-CH-007, CVCS Blender Operations.

(REFERENCE PROVIDED)

A. 1) Dilute 439 gallons. 2) Integrator set to 437 gallons.

B. 1) Dilute 439 gallons. 2) Integrator set to 435 gallons.

C. 1) Dilute 553 gallons. 2) Integrator set to 549 gallons.

D. 1) Dilute 553 gallons. 2) Integrator set to 551 gallons.

Question 5 Given the following:

  • Unit 1 is being cooled down to Cold Shutdown in preparation for Refueling.
  • RCS pressure is 390 psig.
  • RCS Temperature is 340 oF.
  • 1-OP-RH-001, RHR Operations is in progress to startup RHR for cooldown.

What are the FIRST actions taken per 1-OP-RH-001, to prevent the possibility of low boron concentration fluid in the RHR system diluting the RCS below minimum required Shutdown boron?

A. After starting RHR heatup, RHR boron concentration is verified by sampling to be above minimum required boron.

B. Before starting RHR heatup, a calculation is performed to ensure RHR volume combined with RCS volume will not dilute below minimum required boron.

C. RHR fluid is replaced by RCS fluid during RHR System warmup, which ensures boron remains equal to RCS boron.

D. RHR system is filled from the RWST, which ensures boron will be above minimum required boron.

Question 6 Unit 1 is operating at 100% power, when the following events occur:

o Vital Bus I / IA are lost.

o Unit 1 is manually tripped and safety injection is manually initiated due to a steam break inside containment.

Which ONE of the following describes:

1) The minimum time that must elapse before SI can be reset. AND
2) The SI Train that may be reset WITHOUT local action?

A. 1) 315 seconds after Hi CLS Signal 2) Train B B. 1) 315 seconds after Hi CLS Signal 2) Train A C. 1) 60 seconds after Manual SI initiation 2) Train B D. 1) 60 seconds after Manual SI initiation 2) Train A

Question 7 Given the following:

  • Unit 2 is operating at 100% power.
  • PRT Pressure is 10.3 psig and rising slowly.
  • PRT level is 82% and rising slowly.
  • PRT Temperature is 92 °F.

Which ONE of the following describes:

1) The action required to restore PRT parameters in accordance with ARP 2C-F7 and 2-OP-RC-011, PRT Operations.
2) The lowest pressure at which the rupture disc will rupture.

A. 1) Drain the PRT 2) 50 psig B. 1) Vent the PRT 2) 50 psig C. 1) Drain the PRT 2) 100 psig D. 1) Vent the PRT 2) 100 psig

Question 8 Given the following:

  • Unit 1 has tripped from 100% after operating at full power for 50 days following a Refueling outage.
  • RCS temperature is stable at 547 °F using AFW and Steam Dumps.
  • Current Boron concentration is 625 ppm.

Will Shutdown margin be met with Tave stable at 547 oF, with no operator action at the following times:

1) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after shutdown.
2) 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> after shutdown.

A. 1) No. 2) No.

B. 1) Yes. 2) Yes.

C. 1) Yes. 2) No.

D. 1) No. 2) Yes.

Question 9 Elevated Gaseous activity has been detected in Unit 1 containment.

  • The source identified as a primary side man-way leak on the B steam generator.
  • Annunciator Response Procedure 1-RM-Q8, CTMT GAS ALERT/FAILURE, has been initiated.
  • HP has been contacted and has requested one of the Iodine Filtration Fans; 1-VS-F-3A, or 1-VS-F-3B, be started.

Which ONE of the following describes:

1) The location where the fans are operated. AND
2) The power supply for the fans, 1-VS-F-3A and 1-VS-F-3B?

A. 1) Unit 1 Ventilation Panel.

2) MCC 1H1-2N; MCC 1J1-2W.

B. 1) Unit 1 Ventilation Panel.

2) MCC 1A1-1E; MCC 1B1-2E.

C. 1) Locally at breaker cubicle.

2) MCC 1H1-2N; MCC 1J1-2W.

D. 1) Locally at breaker cubicle.

2) MCC 1A1-1E; MCC 1B1-2E.

Question 10 Given the following:

A plant transient has led to a high pressure reactor trip of Unit 1. Following the trip, one of the pressurizer safety valves opened and did not reclose. RCS pressure lowered and SI actuation occurred.

Current plant conditions 5 minutes after the trip:

  • RCP trip criteria is met.
  • RCS pressure is at 980 psig and lowering.
  • Hot leg and CETC temperatures indicate 540oF.
  • Pressurizer level is 72% and rising.
  • Crew has reset SI, secured the A Charging pump and the A LHSI pump.
  • Crew has transitioned to 1-E-1, Loss of Reactor or Secondary Coolant.

After actions are taken per 1-E-1, which one of the following describes the status (running/secured) of:

1) 1-CH-P-1B, B Charging pump.
2) 1-SI-P-1B, B LHSI pump.

1-CH-P-1B 1-SI-P-1B A. 1) Secured. 2) Secured.

B. 1) Running. 2) Running.

C. 1) Running. 2) Secured.

D. 1) Secured. 2) Running.

Question 11 Unit 2 is in Cold Shutdown with the following conditions:

  • All three (3) RCPs are in service.
  • A spurious actuation of Train A Hi-Hi-CLS occurs.

Which ONE of the following, states the RCP(s), if any, that must be secured due to loss of supporting conditions?

A. None.

B. 2-RC-P-1A.

C. 2-RC-P-1B and 2-RC-P-1C.

D. All.

Question 12 Given the following:

  • Unit 1 is operating at 100%.
  • 1-CC-RI-105, CC HX A/B Out, is reading 5.94 E3 cpm and trending higher.
  • 1-CC-RI-106, CC HX C/D Out, is reading 4.11 E3 cpm and trending higher.

Which of the following sets of component failures is the most likely cause of these rad monitors to alarm? (both must be correct)

A. RCP Thermal Barrier and Seal Return Heat Exchanger.

B. Non Regenerative Heat Exchanger and Primary Sample coolers.

C. CRDM Shroud Coolers and Non Regenerative Heat Exchanger.

D. RCP Thermal Barrier and RCP Upper Oil cooler.

Question 13 Initial Conditions:

Unit 1 is heating up following a maintenance outage.

  • The RCS is in solid plant pressure control.
  • Current RCS Pressure is 100 psig.

Which ONE of the following describes the operator action necessary to raise RCS pressure to 300 psig in order to start the first RCP in accordance with 1-OP-RC-003, Reactor Coolant System Vent?

A. Throttle CLOSE 1-RH-HCV-1142, RHR Letdown Flow, to lower Letdown flow until RCS pressure stabilizes at 300 psig.

B. Close 1-CH-HCV-1200C, Letdown Orifice Isolation valve and throttle open 1-CH-FCV-1122, until RCS pressure stabilizes at 300 psig.

C. Adjust the setpoint of 1-CH-PCV-1145 to raise RCS pressure to 300 psig.

D. Throttle open 1-CH-FCV-1122 only, to raise makeup flow until RCS pressure stabilizes at 300 psig.

Question 14 Which ONE of the following describes the design used to limit thermal stresses on the Pressurizer Spray valve?

A. The installation of spray bypass valves.

B. The installation of thermal sleeves.

C. The size of the spray line.

D. The installation of an auxiliary spray line.

Question 15 Unit 2 was at 100% Rated Thermal power when a large break Loss of Coolant Accident (LOCA) occurred. The A LHSI pump failed to start and cannot be manually started.

Current conditions:

  • Containment pressure is 33 psia and slowly dropping.
  • Pressurizer level is 0%.
  • Refueling Water Storage Tank (RWST) level is 85% and decreasing.

What is the current mechanism by which core decay heat is being removed?

A. Reflux cooling and AFW Flow.

B. RCS break flow and Safety Injection Flow.

C. Forced two phase flow through the core and Safety Injection Flow.

D. RCS break flow and SI Cold leg recirculation.

Question 16 Given the following:

  • Unit 1 is at 100% rated Thermal Power.
  • Tave is 573 oF.
  • Pressurizer pressure is 2235 psig.
  • Pressurizer Pressure Protection, 1-RC-PI-1455 has failed HIGH.

For the given conditions, how are the A Loop OPT and OTT setpoints affected?

A. OPT and OTT setpoints both rise.

B. OPT setpoint remains the same and OTT setpoint rises.

C. OPT and OTT setpoints remain the same.

D. OPT setpoint rises and OTT setpoint remains the same.

Question 17 Which ONE of the following states a reason that a specific sequence is recommended by 1-AP-10.06, Loss of DC Power, when restoring power following a loss of a DC Bus?

A. To prevent actuation of safety injection.

B. To prevent overloading the associated DC Buses.

C. To allow early restoration of letdown.

D. To enable overcurrent protection of 480V loads as soon as possible.

Question 18 Unit 1 is operating at 100% power.

  • Lightning strike occurs on Unit 1 causing the following:

o Vital Bus IV/IVA is lost.

o Unit 1 Reactor Trip.

Which ONE of the following, if any, identifies the plant response assuming no operator action is taken?

A. High Steam Flow SI.

B. Header to Line Differential Pressure SI.

C. Lo Pressurizer Pressure SI.

D. No SI occurs.

Question 19 Twenty (20) minutes following a reactor trip from 100% power, the following indications exist:

  • N35 indicates 4.0 x 10 -10 Amps, N35 SUR indicates 0 DPM.
  • N36 indicates 2.1 x 10 -11 Amps, N36 SUR indicates -0.1 DPM.
  • Source Range detectors have not energized.

Which ONE of the following describes:

1) The reason Source Range channels have not energized.
2) The action required to manually energize the Source Range detectors?

A. 1) N35 is undercompensated.

2) Press the Source Range Trip BLOCK pushbuttons.

B. 1) N36 is overcompensated.

2) Press the Source Range Trip RESET pushbuttons.

C. 1) N35 is undercompensated.

2) Press the Source Range Trip RESET pushbuttons.

D. 1) N36 is overcompensated.

2) Press the Source Range Trip BLOCK Pushbuttons.

Question 20 Which of the following choices describes conditions for immediate potential damage to an operating Reactor Coolant Pump (RCP) if NO operator action is taken?

A. RCP Motor Upper Thrust bearing temperature is 195 oF and rising AND Annunciator RCP Frame Danger is lit.

B. RCP Thermal Barrier CC flow indicator is 0 gpm, and Thermal Barrier CC outlet temperature is 200 oF AND Annunciator RCP Thermal Barrier CC Hi flow is lit.

C. RCP Seal DPs are as follows: #1 is 2.0 psid, #2 is 1142 psid, and #3 is 1122 psid AND Seal leakoff is 3.05 gpm and Annunciator RCP Seal leakoff Hi flow is lit.

D. RCP seal leakoff flow is 1.5 gpm, and Stator temperature is 180 oF AND Annunciator RCP Seal leakoff low flow is lit.

Question 21 The following Unit 1 conditions exist:

  • RCS heatup from Cold Shutdown in progress.
  • RCS temperature is 170 °F.
  • RCS pressure is 250 psig.
  • OPMS is enabled.
  • RCS pressure channel 1-RC-PT-1458 fails high.

Which ONE of the following actions would close the PZR PORV that opened due to the failure of 1-RC-PT-1458?

A. Place the OPMS key switch for 1-RC-PCV-1455C in DISABLE.

B. Place the control switch for 1-RC-PCV-1455C in CLOSE.

C. Place the OPMS key switch for 1-RC-PCV-1456 in DISABLE.

D. Place the control switch for 1-RC-PCV-1456 in CLOSE.

Question 22 Given the following:

  • Unit 1 was operating at 100%.
  • Containment Pressure is 30 psia and increasing
  • Team is currently performing E-1, Loss of Reactor or Secondary Coolant.

Which ONE of the following describes:

1) The status of Containment Air Recirculation Fans. AND
2) Which Recirculation Spray Pumps are operated to maintain containment pressure less than 13 psia after containment pressure has been returned to less than atmospheric pressure?

A. 1) Containment Air Recirculation Fans A and C trip.

2) Outside Recirculation Spray pumps.

B. 1) Containment Air Recirculation Fans A and B trip.

2) Outside Recirculation Spray pumps.

C. 1) Containment Air Recirculation Fans A and C trip.

2) Inside Recirculation Spray pumps.

D. 1) Containment Air Recirculation Fans A and B trip.

2) Inside Recirculation Spray pumps.

Question 23 Given the following plant conditions:

  • The plant is operating at 100% power.
  • The PRZR Level - Channel Selector Switch is in CH3 (LT-461)/CH2 (LT-460).

The following is observed:

  • Actual Pressurizer level is 50 % and trending DOWN.
  • VCT level is 53% and trending UP.
  • RCS temperature and pressure are stable.

Which ONE of the following describes the event in progress?

A. FCV-1122, Charging Flow Control Valve, has failed SHUT.

B. Charging line leak outside CNMT downstream of FCV-1122, Charging Flow Control Valve.

C. Charging line leak inside CNMT downstream of Regenerative Heat Exchanger.

D. LT-460, Pressurizer Level Ch 2 has failed HIGH.

Question 24 Initial Conditions:

  • The RCS is solid.
  • RCS Temperature is 130 °F.
  • RCS Pressure is 300 psig and lowering slowly.
  • A RHR pump is running; A RHR heat exchanger in service.
  • Core off-load is scheduled to commence in two (2) days.
  • No RCPs are running.

Current Conditions:

  • RCS Pressure is 330 psig and rising.
  • A RHR heat exchanger outlet temperature is 152 °F and rising.
  • Narrow Range Containment sump level is 100%.

Which ONE of the following identifies the procedure the Team shall implement in response to these indications?

A. AP-16.01, Shutdown LOCA.

B. AP-27.00, Loss of Decay Heat Removal.

C. AP-31.00, Increasing or Decreasing RCS Pressure.

D. AP-16.00, Excessive RCS Leakage.

Question 25 Initial Conditions (Time 1000):

  • Unit 2 is responding to a LOCA inside containment.
  • Hi and Hi-Hi CLS have actuated.

Current Conditions (Time 1015):

  • The Service Building Operator reports large leak on the discharge of 2-CS-P-1A, Containment Spray Pump.
  • RO notes degraded flow and discharge pressure on 2-CS-P-1A.
  • Team has entered 2-E-1, Loss of Reactor or Secondary Coolant.

Which ONE of the following completes the statement:

In order to avoid damaging the pump, 2-CS-P-1A shall be secured as soon as Containment pressure decreases below ___(1)___, by resetting CLS using ___(2)___ reset pushbuttons and placing 2-CS-P-1A in pull-to-lock.

A. 1) 13 psia. 2) 1-of-2.

B. 1) 13 psia. 2) 2-of-2.

C. 1) 14 psia. 2) 1-of-2.

D. 1) 14 psia. 2) 2-of-2.

Question 26 Initial Conditions:

  • A normal plant cooldown is in progress on Unit 1. The Unit is not yet on RHR.
  • CC Surge tank level indication is 60% and stable.
  • SFP level is 23.5 and stable.

Current Conditions:

  • 1-SW-RI-107B, CC/SW HX B, indicates EEEEE.
  • SFP level has increased to 24.5 and rising.
  • CC Surge tank level indication is 31% and lowering.
  • Makeup to the CC surge tank is in progress.

Which ONE of the following identifies:

1) The source of the leak?
2) The source of water for maintaining CC System inventory?

A. 1) Spent Fuel Pit Heat Exchanger. 2) PG water.

B. 1) Spent Fuel Pit Heat Exchanger. 2) Condensate System.

C. 1) 1B CC Heat Exchanger 2) PG Water.

D. 1) 1B CC Heat Exchanger 2) Condensate System.

Question 27 A large break LOCA has occurred on Unit 2. The safety injection system has swapped to the cold leg recirculation mode. The BOP is verifying that 2-SI-MOV-2885A, B, C, and D (Low Head SI Pump Recirc Valves) are closed.

These valves close in order to _________.

A. prevent a radioactivity release.

B. ensure adequate low head flow is available to the charging pump suctions.

C. ensure adequate low head flow is available to the cold legs.

D. prevent low head SI pump runout.

Question 28 Given the following Unit 1 conditions:

  • RCS heatup is in progress in accordance with 1-GOP-1.1, Unit Startup, RCS Heatup from Ambient to 195 °F.
  • The RCS has been filled and vented.
  • The Pressurizer is solid.
  • PRT Level is 95%.
  • All Pressurizer Heaters are energized.

Which ONE of the following must be accomplished prior to drawing a bubble in the Pressurizer in accordance with 1-GOP-1.1?

A. Drain the PRT to 60 - 80%.

B. Check VCT oxygen concentration less than 3%.

C. Drain the Pressurizer to 22.2%.

D. Pressurize the RCS to 200 - 270 psig on 1-RC-PI-1403, NAR RNG.

Question 29 Given the following:

  • A large break LOCA occurred inside containment approximately 30 minutes ago.
  • CETCs are currently reading 190 oF.
  • Crew has just performed ES-1.3, Transfer to Cold Leg Recirculation; step 8, Equalize level in CAT and RWST.
1) With the current conditions, what is the most significant contributor of hydrogen concentration inside of containment? AND
2) What is the allowable hydrogen concentration to place the hydrogen recombiner in service?

A. 1) Radiolytic decomposition of water in the containment sump and reactor core.

2) Between 0.5% and 4.0%.

B. 1) Zircaloy - Water reaction between Zircaloy cladding, and water or steam.

2) Greater than 4.0%.

C. 1) Radiolytic decomposition of water in the containment sump and reactor core.

2) Greater than 4.0%.

D. 1) Zircaloy - Water reaction between Zircaloy cladding, and water or steam.

2) Between 0.5% and 4.0%.

Question 30 Given the following conditions:

  • Unit 1 is at 100% power.

An inadvertent actuation of A RPS Train occurs.

Which ONE of the following identifies the proper plant response for this situation?

A Reactor Trip Breaker B Reactor Trip Breaker A Reactor Trip Bypass Breaker A. OPEN CLOSED CLOSED B. OPEN CLOSED OPEN C. OPEN OPEN OPEN D. OPEN OPEN CLOSED

Question 31 Units 1 and 2 are operating at 100% power. The Fuel Cask is being loaded in the Spent Fuel Pit when the following alarms and indications are received:

  • VSP-C4, Spent Fuel Pit Lo LVL.
  • VCP-A4, Spent Fuel Pit Hi Temp.
  • 1-RM-RI-153, Fuel Pit Bridge WARN Light Lit.
  • 1-VG-RI-131A, Vent #2 Particulate Indicator is in Alert.
  • 1-VG-RI-131B, Vent #2 Norm Gas Indicator is in Alert.

The Auxiliary Building Watch reports a large leak on the A SFP Cooling Heat Exchanger with SFP level at 18.5 and lowering.

Which ONE of the following identifies the expected change in the Fuel Pit Bridge RM (1-RM-RI-153),

Vent #2 Particulate (1-VG-RI-131A), and Vent #2 Norm Gas RM (1-VG-RI-131B) indications after shifting the Fuel Building Ventilation to Filtered Exhaust?

1-RM-RI-153 1-VG-RI-131A 1-VG-RI-131B A. Lowering Lowering Lowering B. Lowering No Change No Change C. Rising Lowering Lowering D. Rising No Change No Change

Question 32 Unit 2 is in Refueling Shutdown with Fuel Movement in progress.

  • The ONLY running Containment Air Recirculation Fan trips on overcurrent.

Which ONE of the following identifies:

1) The effect on operability of the following Containment Radiation Monitors.
  • 2-RM-259, Containment Gaseous radiation monitor.
  • 2-RM-260, Containment Particulate radiation monitor.
  • 2-RM-262, Manipulator Crane radiation monitor.
2) The effect this event will have on Refueling Activities?

A. 1) 2-RM-259, and 2-RM-260 are inoperable, 2-RM-262 is operable.

2) Refueling activities may continue.

B. 1) 2-RM-259, and 2-RM-260 are inoperable, 2-RM-262 is operable.

2) Refueling activities must cease.

C. 1) 2-RM-260 is inoperable, 2-RM-259, and 2-RM-262 are operable.

2) Refueling activities may continue.

D. 1) 2-RM-260 is inoperable, 2-RM-259, and 2-RM-262 are operable.

2) Refueling activities must cease.

Question 33 Given the following:

  • Unit 1 is operating at 100% Rated Thermal Power.
  • Annunciator 0-RM-H4, 1-RM-RI-158, Chem Lab HIGH is lit.
  • 1-RM-RI-158, Chem Lab is reading 4.5 E+1 mR/hr.
  • VCT Pressure is 16 psig and lowering rapidly.

With the above conditions:

1) What is the MINIMUM VCT pressure required by 1-PT-36, Operator Rounds.
2) What actions are required per ARP 1D-E1, with regard to Charging Pump Suction?

A. 1) 15 psig.

2) Swap Charging pump suction to the U1 RWST.

B. 1) 15 psig.

2) Maintain Charging pump suction to the VCT.

C. 1) 10 psig.

2) Swap Charging pump suction to the U1 RWST.

D. 1) 10 psig.

2) Maintain Charging pump suction to the VCT.

Question 34 Unit 1 is operating at 100% when the following indications are observed over the next 30 minutes:

  • N-16 Stm Line A/Stm Line B/ Stm Line C increased from 0.1 to 35/35/155 gpd.
  • CNDSR AIR EJCTR 1-SV-RI-111 increased from 1.5 E2 to 1.32 E3 cpm.
  • Crew has initiated 0-OSP-RC-002, Steam Generator Primary to Secondary Leakage Monitoring and has confirmed leakage of 0.15 gpm to S/G C.
1) Which radiation monitor is used as the primary means of monitoring and assessing primary to secondary leakage in accordance with 0-OSP-RC-002?
2) Based on these indications what are the required actions to take?

Rad Monitor Required Actions A. 1) Air Ejector 2) Continue operating, increase sampling frequency.

B. 1) N-16 2) Continue operating, increase sampling frequency.

C. 1) Air Ejector 2) Commence ramp, and be in Hot Shutdown in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

D. 1) N-16 2) Commence ramp, and be in Hot Shutdown in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

Question 35 The plant is preparing to commence a rapid cooldown per E-3, Steam Generator Tube Rupture.

Which ONE of the following will result in a Main Steam Trip Valve closure while using the Steam Dumps during the (E-3) rapid cooldown?

A. Exceeding 1.5 x 106 lbm/hr on 1 of 3 SG steam lines.

B. Failing to block PRZR Low Pressure and Header to Line SI when Conditions permit.

C. Failing to block High Steam Flow SI when Conditions permit.

D. Exceeding 1.5 x 106 lbm/hr on 2 of 3 SG steam Lines.

Question 36 Given the following:

  • Unit 2 has tripped and safety injected due to a Steam Line Break at the Main Steam Header.
  • Unit 2 Turbine Building has been evacuated.
  • Unit 1 has lost both Charging Pump SW pumps.

Which ONE of the following will answer the following questions:

1) Which valve must be operated to cross-tie Charging Pump SW from Unit 2 to Unit 1?
2) What is the location of the valve?

A. 1) 2-SW-443, 1(2)-SW-P-10B pump discharge cross tie valve. 2) MER 4.

B. 1) 2-SW-443, 1(2)-SW-P-10B pump discharge cross tie valve. 2) MER 3.

C. 1) 1-SW-269, 1(2)-SW-P-10A pump discharge cross tie valve. 2) MER 4.

D. 1) 1-SW-269, 1(2)-SW-P-10A pump discharge cross tie valve. 2) MER 3.

Question 37 Given the following:

  • Unit 1 is operating at 100%.
  • Condenser Vacuum is 22.3 inches Hg and is lowering 0.4 inches Hg/minute.
  • Generator Megawatts are 825 Mwe and lowering rapidly.

Which of the following shall be done FIRST in accordance with 1-AP-14.00?

A. Commence a rapid downpower until vacuum recovers to > 25 inches Hg.

B. Commence a rapid downpower, until vacuum recovers to > 22.5 inches Hg.

C. Place the condenser hoggers in service.

D. Trip the reactor and check the Turbine Tripped.

Question 38 Initial Conditions:

  • Reactor power is 83%
  • 1-CN-P-1A, A Condensate pump is out of service for pump bearing replacement The following occurs:
  • 1F-C7/C8/C9, SG 1A/1B/1C CH3 FW<STM FLOW alarm and remain lit when acknowledged.
  • 1F-D7/D8/D9, SG 1A/1B/1C CH4 FW<STM FLOW alarm and remain lit when acknowledged.
  • 1H-G5/G6/G7, SG 1A/1B/1C LEVEL ERROR alarm and remain lit when acknowledged.
  • 1-FW-P-1A1, and 1-FW-P-1A2, Main FW Pump A; green and amber lights are lit.
  • 1-FW-P-1B1(1B2) Amps increase from 350 to 550 amps.
  • The crew enters 1-AP-21.00, Loss of Main Feedwater Flow.

Which ONE of the following describes:

1) The immediate operator action(s) required by 1-AP-21.00.
2) The reason for the action(s).

A. 1) Trip the Reactor and perform 1-E-0, Reactor Trip or SI.

2) Reduce steam flow to within capacity of the operating Main Feedwater pump.

B. 1) Trip the Reactor and perform 1-E-0, Reactor Trip or SI.

2) Prevent a challenge to the Reactor Protection System from loss of secondary heat sink.

C. 1) Reduce Turbine Load by use of Valve Position Limiter.

2) Reduce steam flow to within capacity of the operating Main Feedwater pump.

D. 1) Reduce Turbine Load by use of Valve Position Limiter.

2) Prevent a challenge to the Reactor Protection System from loss of secondary heat sink.

Question 39 Given the following:

  • Both Units were operating at 100% power when a Loss of Offsite Power (LOOP) to both units occurred.
  • One (1) minute after the LOOP, Unit 1 experiences a Hi CLS due to faulty instrumentation.
  • Two (2) minutes after the LOOP, all Unit 1 and Unit 2 AFW Pump breakers indicate CLOSED.

What is the status of Unit 1 and Unit 2 Aux FW Pumps?

1-FW-P-3A 1-FW-P-3B 2- FW-P-3A 2- FW-P-3B A. Running Off Running Running B. Running Running Running Off C. Running Off Running Off D. Running Running Running Running

Question 40 Unit 1 operating at 100% power.

An RCS leak has occurred in the Aux Building Sample Room. Which one of the following describes (1) The method of detection of this leak?

(2) For this leak, Neutron and Alpha radiation _________ (can, cannot) be detected by this radiation monitor.

A. (1) Aux Building Control Area (2) cannot B. (1) Sample Room (2) cannot C. (1) Aux Building Control Area (2) can D. (1) Sample Room (2) can

Question 41 Initial Conditions:

  • Unit 1 is operating at 100% power.

Current Conditions:

  • Unit was ramped to 85% power.

Which ONE of the following states:

1) Is further load reduction required to bypass the train?
2) Following the total load reduction from 100%, S/G pressure is __________ (higher/lower) than it was at 100%.

A. 1) No.

2) higher.

B. 1) Yes.

2) lower.

C. 1) No.

2) lower.

D. 1) Yes.

2) higher.

Question 42 Given the following:

  • Unit 1 is at 500 °F / 1700 PSIG cooling down to Cold Shutdown for a maintenance outage.
  • The TDAFW pump is tagged out.
  • A loss of off-site power (LOOP) to both units occurs.

Which ONE of the following describes the expected flowrate to the Unit 1 steam generators from the AFW System?

A. All three (3) steam generators will be fed with a total AFW of approximately 700 gpm.

B. All three (3) steam generators will be fed with a total AFW of approximately 350 gpm.

C. Two (2) steam generators will be fed with a total AFW of approximately 700 gpm.

D. Two (2) Steam Generators will be fed with a total AFW of approximately 350 gpm.

Question 43 The following conditions were noted during the performance of 1-OPT-EG-001, Number 1 Emergency Diesel Generator Monthly Start Exercise Test:

  • The EDG was loaded at a rate of 550 KW/MIN.
  • The maximum load was 2650 KW.
  • The maximum KVAR was 450 KVAR out.
  • The output voltage was stable at 4300 VAC.

Which ONE of the following was in violation of the EDG Precautions and Limitations per 1-OPT-EG-001?

A. Load Rate.

B. Maximum load.

C. Maximum KVAR out.

D. Output voltage.

Question 44 Given the following:

  • Both Units are operating at 100% with HI SW temperatures due to Hot Summer conditions
  • 1-SW-MOV-101B, BC HX SW SUPPLY, and 1-SW-MOV-102B, CC HX SW SUPPLY are open

o 1B-H2, BC HX Out Hi Temp.

o 1A-F1, Traveling Screens No Rotation.

o 1A-G1, Traveling Screens Hi Diff Lvl.

  • Unit 1 Main Condenser A waterbox CW outlet temperature has increased from 105 oF to 112 oF.
  • Unit 1 Main Condenser B, C, and D waterbox CW outlet temperatures are steady at 105 oF.
  • SW inlet temperature is 95 oF and slowly increasing 1 oF every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (due to hot weather)
  • Containment partial pressure is 10.4 psia.

Based on these indications determine the following:

1) The correct Service Water MOV alignment for Bearing Cooling?
2) Is the Containment Allowable Air Partial Pressure vs. Service Water Temperature, requirement met (yes/no).

(REFERENCE PROVIDED)

A. 1) Open 1-SW-MOV-101A, BC HX SW SUPPLY to supply BC from Water Box C.

2) yes.

B. 1) Open 1-SW-MOV-101A, BC HX SW SUPPLY to supply BC from Water Box C.

2) no.

C. 1) Open 1-SW-MOV-102A, CC HX SW SUPPLY to supply BC from Water Box B.

2) yes.

D. 1) Open 1-SW-MOV-102A, CC HX SW SUPPLY to supply BC from Water Box B.

2) no.

Question 45 Unit 1 is operating at 100% power.

  • During performance of PT-36 Logs, the RO notes that TURB SOL TRIP CKT, AST-2, indicating light on the Vertical Board 2 is NOT LIT.
  • The Service Building Watch reports the DC circuit breaker for this circuit is tripped.

Which ONE of the following states the Turbine Trip Signal that has been changed from a REDUNDANT output to a SINGLE output to initiate a Turbine Trip?

A. High 6th Point Heater level.

B. AMSAC.

C. Generator 86 device actuation.

D. Anti-motoring.

Question 46 Unit 1 and 2 are operating at 100% power when a Loss of Off-Site Power (LOOP) occurs.

  • #3 EDG is tagged out for a major maintenance package.
  • #2 EDG developed an oil leak and was tripped.
  • The AAC Diesel has been aligned to both Emergency Buses.

Which ONE of the following identifies the Station Battery bus, or busses, with a continuously lowering DC voltage?

A. Unit 1 A and Unit 2 B.

B. Unit 1 B and Unit 2 B.

C. Unit 2 A and Unit 2 B.

D. Unit 2 B only.

Question 47 Unit 1 is operating at 100% power with all systems operable. #1 EDG is being run for the monthly test.

The Emergency Diesel Generator mechanical overspeed trip mechanism actuates.

Which one of the following describes:

1) The specific automatic actions used to trip the EDG?
2) An additional function provided by this trip mechanism?

A. 1) Trips all fuel oil pumps.

2) Locks out the EDG starting circuits until the mechanism is manually reset.

B. 1) Trips all fuel oil pumps.

2) Initiates the cooldown cycle, then positions the fuel racks to the no fuel position.

C. 1) Pivots a rocker arm so fuel cannot get to the injectors.

2) Locks out the EDG starting circuits until the mechanism is manually reset.

D. 1) Pivots a rocker arm so fuel cannot get to the injectors.

2) Initiates the cooldown cycle, then positions the fuel racks to the no fuel position.

Question 48 Unit 1 is operating at 100% power with the team responding to a Loss of Instrument air pressure in accordance with ARP 1B-E6, IA LO HDR PRESS/IA COMPR 1 TRBL. Several minutes later the Reactor Operator makes the following report:

  • Instrument Air Pressure on PI-IA-100 is 65 psig and slowly lowering.
  • Letdown has isolated; 1-CH-LCV-1460A and 1-CH-LCV-1460B have closed.
  • SG NR Levels A/B/C are 40% and slowly decreasing.
  • Feed Reg Valve indicated demand is 90% and rising on all Feed Reg Valves.

Which ONE of the following describes:

1) Is immediate entry into 0-AP-40.00, Non Recoverable Loss of Instrument Air required?
2) Is an immediate Reactor Trip required?

A. 1) yes.

2) no.

B. 1) no.

2) yes.

C. 1) no.

2) no.

D. 1) yes.

2) yes.

Question 49 Given the following:

  • The crew is preparing to release Waste Gas Decay Tank (WGDT) 1B.
  • The desired WGDT Drum (header) pressure is 4.5 to 6.5 psig.

Which one of the following describes:

1. The method of adjusting WGDT header pressure if the indicated pressure falls outside the 4.5 to 6.5 psig band in accordance with OP-23.2.4?
2. The Release point of Waste Gas Decay Tank 1B?

A. 1) Adjust 1-GW-FCV-101, Process Vnt WGDT Effluent Flow Controller.

2) Vent Stack number 1.

B. 1) Adjust 1-GW-FCV-101, Process Vnt WGDT Effluent Flow Controller.

2) Process Vent Stack.

C. 1) Locally adjust 1-GW-PCV-103, Htr Prefilter Outlet Pressure Control Valve.

2) Vent Stack number 1.

D. 1) Locally adjust 1-GW-PCV-103, Htr Prefilter Outlet Pressure Control Valve.

2) Process Vent Stack.

Question 50 Unit 1 and 2 are operating at 100% power.

0-OPT-RM-001, Radiation Monitor Equipment Check is in progress.

1-RM-RI-151, Control Room Rad Monitor, is to be source checked.

When the CHECK SOURCE pushbutton is depressed a(n) ___(1)____ is applied to the detector, and the Radiation Monitor will return to normal indication after ____(2)____.

A. 1) radioactive source 2) 2 to 3 seconds B. 1) radioactive source 2) 3 minutes C. 1) electronic signal 2) 2 to 3 seconds D. 1) electronic signal 2) 3 minutes

Question 51 A LOCA has occurred in Unit 1 containment.

  • Off-Site power to the 1J 4160V Bus was lost at the time of the reactor trip.
  • #3 EDG tripped on overspeed on startup; mechanical damage to the EDG has been reported.
  • Seven (7) minutes following the start of the Recirc Spray pumps, the following alarms and indications are received:

o Annunciator 1-RM-C7, RS-SW HX C ALERT/FAILURE.

o 1-SW-RI-116, RS/SW HX C, RANGE and FAIL Lights are LIT.

o 1-SW-RI-116, RS/SW HX C, indicates 1.00 E0 cpm.

Which ONE of the following identifies the indication used to monitor for a release from the C RSHX?

A. Unit 1 Discharge Tunnel Rad Monitor, 1-SW-RI-120.

B. Unit 2 Discharge Tunnel Rad Monitor, 2-SW-RI-220.

C. Pen 3, RS/SW HX C, on recorder 1-RM-RR-150A.

D. Recirc Spray SW page on the Plant Computer System.

Question 52 Given the following conditions:

  • LOCA inside containment IN PROGRESS
  • RCS Pressure 360 psig and lowering
  • RVLIS Full Range 42% and lowering
  • Subcooling -30 °F and stable
  • SG NR level 5% and rising
  • Containment pressure 46 psia and rising
  • Containment Spray Pumps Not Running Which ONE of the following describes the COLOR and SAFETY FUNCTION to be addressed FIRST using the Critical Safety Function Status Trees?

A. RED condition on Heat Sink.

B. ORANGE Condition on Core Cooling.

C. RED condition on Core Cooling.

D. ORANGE condition on Containment.

Question 53 Unit 1 operating at 100% power, when the following occurred:

  • Breaker 15H8, Offsite power supply to 1H 4160V bus tripped open.
  • #1 EDG started, loaded on the 1H 4160V bus, and tripped on Differential Current.
  • The Team initiated 1-AP-10.07, Loss of Unit 1 Power.
  • Subsequently, a LBLOCA occurred inside Unit 1 Containment causing a reactor trip, safety injection, Hi CLS and Hi-Hi CLS actuations.

Which ONE of the following identifies which Recirc Spray Heat Exchangers (RSHXs) will have flow indicated on the Unit 1 Vertical Board?

A. A and C RSHXs.

B. B and D RSHXs.

C. A and D RSHXs.

D. B and C RSHXs.

Question 54 Unit 2 is operating at 100% power.

  • The System Operator contacts the Control Room to report that the 500 kV System High Voltage Limit has been triggered.
  • The system Operator requests that Unit 2 maximize VARS IN to assist in controlling System voltage.
  • The Team has initiated 0-AP-10.18, Response to Grid Instability.

Which ONE of the following states:

1) The limiting component(s) on the B and C Station Service Buses.
2) The limiting parameter of these component(s)?

A. 1) The running High Pressure Drain pump.

2) Stator Temperature.

B. 1) The running High Pressure Drain pump.

2) Rotor Temperature.

C. 1) The B Main Feedwater pump.

2) Stator Temperature.

D. 1) The B Main Feedwater pump.

2) Rotor Temperature.

Question 55 Unit 1 is starting up following a refueling outage, Unit 2 is at 100%.

Initial Conditions:

  • Unit 1 RCS Heatup in accordance with 1-GOP-1.7, Unit Startup, RCS Heatup from Ambient to HSD.
  • A S/G PORV is operating in AUTO to control RCS temperature at HSD (547 oF).
  • A sustained loss of the Semi-Vital Bus occurs.

Current Conditions:

  • Indications lost in the Control Room include the following:

o All RCP CC flow and temperature indications.

o PI-IA-100, Instrument Air Rcvr Disch Press.

o PI-IA-100, Containment Instrument Air Rcvr Disch Press.

o PI-SA-100, Service Air Rcvr Disch Press.

  • The crew has entered 1-AP-10.05, Loss of Semi-Vital Bus.

Which ONE of the following describes:

1) S/G PORV capability to control S/G pressure immediately following the Loss of the Semi-Vital Bus?
2) Alternate indication(s) available to monitor Service Air and Instrument Air parameters?

A. 1) S/G PORVs will not control in AUTO, operator will need to operate PORVs locally.

2) Plant Computer System (PCS).

B. 1) S/G PORVs will not control in AUTO, operator will need to operate PORVs locally.

2) Unit 2 and local indicators.

C. 1) S/G PORVs will continue to control in AUTO for approximately 30 minutes.

2) Plant Computer System (PCS).

D. 1) S/G PORVs will continue to control in AUTO for approximately 30 minutes.

2) Unit 2 and local indicators.

Question 56 Unit 1 is operating at 100%, when the following alarms and indications are received:

  • Service Air and Instrument Air pressure indications are 80 psig and lowering.

The Team initiates ARP 1B-E6, and closes 1-SA-SOV-175 and 2-SA-SOV-124, Service Air Receiver 1-SA-TK-1 and 2-SA-TK-1 Outlet SOVs.

Current Conditions:

  • MCR Service Air pressure indicates 75 psig and lowering.
  • Service Air Tank pressure indicates 75 psig and lowering.
  • MCR and local Instrument Air pressure indicates 85 psig and rising.

Which ONE of the following describes:

1) The location of the leak.
2) Is the Unit 2 Instrument Air Compressor running (yes/no)?

A. 1) Service Air Header leak.

2) yes.

B. 1) Service Air Header leak.

2) no.

C. 1) Service Air leak on Compressor discharge.

2) yes.

D. 1) Service Air leak on Compressor discharge.

2) no.

Question 57 Safety and Loss Prevention has requested that the 1-FP-P-1, Motor Driven Fire Pump be started to support Fire Brigade Hose training behind the Training Center.

Which ONE of the following describes:

1) The location where the Fire Pump is started. AND
2) The component (valve) that requires Administrative controls per 0-OP-FP-003 in order to fully close within 10 minutes of notification that 1-FP-P-1 is required for Fire protection?

A. 1) Locally in the Fire Pump House.

2) 1-FP-36, Recirculation for Fire Pump.

B. 1) Using the control switch on the Unit 2 benchboard.

2) 1-FP-36, Recirculation for Fire Pump.

C. 1) Locally in the Fire Pump House.

2) 1-FP-37, Recirculation for Fire Pump.

D. 1) Using the control switch on the Unit 2 benchboard.

2) 1-FP-37, Recirculation for Fire Pump.

Question 58 Given the following:

  • Unit 1 Core on-load is in progress.
  • A fuel assembly is currently being moved by the Manipulator to its core location.
  • Source Range NIs; N-31, and N-32 have a sustained increased from 30 cps to 150 cps.
  • RO confirms no instrument failure of either channels.

Which one of the following answers the questions below:

1) Which area(s) shall be evacuated?
2) For the area(s) to be evacuated, how is the Evacuation alarm made?

A. 1) Containment only.

2) Automatically from 1G-C1, NIS SOURCE RNG S/D HI FLUX alarm.

B. 1) Containment and Fuel Building.

2) Automatically from 1G-C1, NIS SOURCE RNG S/D HI FLUX alarm.

C. 1) Containment only.

2) Manually from Control Room BB 2-2 by actuating Plant Gen Emergency alarm.

D. 1) Containment and Fuel Building.

2) Manually from Control Room BB 2-2 by actuating Plant Gen Emergency alarm.

Question 59 Initially Unit 1 was operating at 100% power when the Team identified C steam generator faulted inside containment, tripped the reactor, and initiated safety injection.

Current Conditions:

  • RCS pressure is 1700 psig and lowering slowly.
  • Containment pressure is 18.5 psia and rising.
  • The BOP is performing E-0, Attachment 1, System Alignment Verification, and has identified the following valves in the OPEN position:

o 1-SI-TV-102A and 1-SI-TV-102B, RWST CROSS-TIE VALVES.

o 1-IA-TV-100, CTMT COMP DISCH TV.

o 1-CC-TV-110C, CARF C CLR CC RTN TV.

o 1-CC-TV-109B, RHR HX B CC RTN HDR TV.

Which ONE of the following indicates the required Team response to these indications in accordance with 1-E-0, Attachment 1?

A. 1-IA-TV-100 shall be CLOSED.

B. 1-CC-TV-110C shall be CLOSED.

C. 1-SI-TV-102A, and 1-SI-TV-102B shall be CLOSED.

D. 1-CC-TV-109B shall be CLOSED.

Question 60 A valve lineup is being performed on the Secondary Drains system following a maintenance outage.

  • The valve to be operated is a rising stem gate valve, fully open, and is required to be closed.
  • The valve is difficult to operate and the Project SRO has provided permission to use a leverage device to operate the valve.
  • The valve handwheel diameter is 24 inches.

Which ONE of the following is the maximum allowed length of the leverage device that can be used to operate the valve?

A. 12 inches.

B. 18 inches.

C. 24 inches.

D. 36 inches.

Question 61 The reactor is shutdown for a Refueling outage.

Which ONE of the following states:

1) The Administrative limit for entering Reduced inventory in accordance with 1-OP-RC-005, Draining the RCS from Flange Level to Mid-Nozzle (Reduced Inventory)
2) The Administrative limit for RCS boron concentration in accordance with 1-OSP-ZZ-004, Unit 1 Safety System Status for Cold Shutdown/Refueling.

A. 1) < 15.7 feet 2) 2350 ppm B. 1) < 16.25 feet 2) 2350 ppm C. 1) < 15.7 feet 2) 2250 ppm D. 1) < 16.25 feet 2) 2250 ppm

Question 62 With respect to LI-AA-700, Fatigue Management and Work Hour Limits for Covered Workers. Which of the statements below is correct:

No individual shall work more than A. 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> in any rolling 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, excluding shift turnover time.

B. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in any rolling 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, including shift turnover time.

C. 16 consecutive hours, excluding early arrival for a pre-shift brief for a special evolution.

D. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> in any rolling 7 day period, excluding shift turnover time.

Question 63 Which ONE of the following completes the statement below?

In accordance with OP-AA-200, Equipment Clearance, a temporary lift to allow testing of an electrical breaker shall not exceed _______ unless a longer period has been previously agreed upon.

A. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> B. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> C. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> D. 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />

Question 64 Given the following:

  • Unit 1 is at 100% power.
  • Letdown Pressure is 300 psig and is controlled in Auto
  • Letdown flow is 105 gpm.

The Reactor Operator adjusts 1-CH-PCV-1145, Letdown Line Pressure Control Valve, control setpoint adjustment knob (potentiometer) from 5.0 to 5.5.

After the RO makes this adjustment, Controller demand will ____(1)____ (raise, lower) and Letdown pressure will ____(2)____ (raise, lower).

Controller demand Letdown pressure A. 1) lower 2) raise B. 1) lower 2) lower C. 1) raise 2) raise D. 1) raise 2) lower

Question 65 Which ONE of the following describes the operation of the N-16 Radiation Monitors:

1) The minimum reactor power the N-16 radiation monitors are effectively turned on is

___(1)___. (10%, 18%)

2) The N-16 receives a switchable power input from ___(2)___ .(N-41 or N-42, N-43 or N-44)

A. 1) 10%

2) N-43 or N-44 B. 1) 18%
2) N-43 or N-44 C. 1) 10%
2) N-41 or N-42 D. 1) 18%
2) N-41 or N-42

Question 66 While taking LOGS in the auxiliary building, a mechanic, who is performing an overhaul on 1-CH-P-1A (A charging pump), approaches you and asks for your assistance in lifting the auxiliary oil pump. The mechanic states that your assistance will be required for 20-30 minutes.

Which ONE of the following states the proper response to this request?

A. Provide assistance and when logs are complete, ask health physics to assign the dose received while helping the mechanic to the mechanics RWP.

B. Render the requested assistance on the Operations RWP as long as the dose received will not cause you to reach either your DOSE RATE LIMIT or DOSE LIMIT.

C. Inform the mechanic that you are unable to render the requested assistance while on the current Operations RWP.

D. Call the health physics supervisor and request to be placed on the mechanics RWP. When complete, contact the health physics shift supervisor again, and get reassigned to the normal operations RWP.

Question 67 The reactor is operating at 100% power when the following is identified:

  • B Reactor Coolant Loop Flow, Channel I, II, III, indication is 30% and stable.

Which ONE of the following identifies:

1) The Emergency Procedure to be entered.
2) All of the method(s) provided in this procedure to secure steam flow to the Main Turbine from the Control Room?

A. 1) E-0, Reactor Trip or Safety Injection.

2) Manually trip the turbine, Close the Main Steam Trip Valves.

B. 1) E-0, Reactor Trip or Safety Injection.

2) Manually trip the turbine, Reduce turbine load by using the limiter, Close the Main Steam Trip Valves.

C. 1) FR-S.1, Response to Nuclear Generation/ATWS.

2) Manually trip the turbine, Close the Main Steam Trip Valves.

D. 1) FR-S.1, Response to Nuclear Generation/ATWS.

2) Manually trip the turbine, Reduce turbine load by using the limiter, Close the Main Steam Trip Valves.

Question 68 Unit 1 is operating at 100% power.

  • Reactor Operator notices that 1K-H1 Power indicating lights are out.
  • Reactor Operator verifies that the light bulbs are good.
  • Team enters 0-AP-10.13, Loss of Main Control Room Annunciators.

Which ONE of the following:

1) Identifies the power supplies that are lost?
2) Upon power restoration what is the minimal acceptable method to perform a functional check in order to confirm that alarming conditions in the field will actuate the appropriate alarm?

A. 1) MCC 1H1-1 and A DC bus.

2) Perform Annunciator Test by depressing the Annunciator TEST pushbutton.

B. 1) MCC 1H1-1 and A DC bus.

2) Place 1-AS-TCV-100, Steam to Batch Tank, in Auto and verify alarm 1D-B7, BATCHING TK LO TEMP. Actuates.

C. 1) MCC 1J1-1 and Vital Bus III.

2) Perform Annunciator Test by depressing the Annunciator TEST pushbutton.

D. 1) MCC 1J1-1 and Vital Bus III.

2) Place 1-AS-TCV-100, Steam to Batch Tank, in Auto and verify alarm 1D-B7, BATCHING TK LO TEMP. Actuates.

Question 69:

Unit 1 is initially at 88% power. A plant transient occurs causing the following changes:

Parameter Initial Current Reactor Power 88% 91%

Generator MWe 810.9 MWe 887.1 MWe Pressurizer Level 49.5% 48.3%

Pressurizer Pressure 2235 psig 2215 psig RCS Tave 569.7 oF 568.3 oF Valve Positioner Light Not-lit Lit Which one of the following procedures addresses all the conditions given?

A. 1-AP-31.00, Increasing or Decreasing RCS Pressure.

B. 1-AP-16.00, Excessive RCS Leakage.

C. 1-AP-38.00, Main Steam System Control Malfunction.

D. 1-AP-18.00, Loss of HP Heater Drain Pump.

Question 70 Given the following:

Initial Conditions:

  • Unit 1 has been tripped and safety injection actuated due to a SBLOCA inside containment.
  • The Team is currently performing 1-ES-1.2, Post LOCA Cooldown and Depressurization.
  • Low Pressurizer Pressure and Header to Line SI signals have been blocked.
  • SI has been reset.
  • A cooldown to CSD has just been started.
  • 1-MS-TCV-105 A & B are fully open
  • 1-MS-TCV-106 A & B are throttled open
  • Tave on C Loop is 545 °F and lowering.
  • Containment pressure is 14.7 PSIA and slowly rising.

Current Conditions:

o 1H-D4, LO T AVG INTLK LOOP 1A.

o 1H-E4, LO T AVG INTLK LOOP 1B.

Which ONE of the following describes the Plant response to this event?

A. 1-MS-TCV-105 A & B only shut.

B. 1-MS-TCV-106 A & B only shut.

C. 1-MS-TCV-105 A & B and 1-MS-TCV-106 A & B shut.

D. 1-MS-TCV-105 A & B and 1-MS-TCV-106 A & B remain open.

Question 71 A LOCA outside containment occurred on Unit 1. The crew has entered 1-ECA-1.2, LOCA OUTSIDE CONTAINMENT and has just closed 1-SI-MOV-1890C, LHSI TO COLD LEGS. The following plant conditions exist:

  • RCS pressure 993 psig and rising.
  • Pressurizer level offscale low.
  • Pressurizer pressure offscale low.
  • Subcooling 7 oF and rising.
  • CETC temp 540 oF and steady.
  • LHSI flow 2700 gpm and steady.

Which one of the below indications is a Tech Spec required Post Accident indication and would provide the earliest indication that the break is isolated to allow transition to 1-E-1.

A. LHSI flow steady.

B. CETC temp lowering.

C. RCS pressure rising.

D. Pressurizer pressure rising.

Question 72 Initial Conditions:

  • Unit 1 has tripped from 100% power due to a loss of all Main Feedwater.
  • AFW cannot be established from Unit 1 or Unit 2 via the cross-tie.
  • RCS Thot wide range temperatures are 556 °F and slowly lowering.
  • CETC temperatures are 565 °F and slowly lowering.

Local actions have been successful in restoring Unit 1 AFW flow.

Which ONE of the following describes:

1) The method for recovery of heat sink in accordance with 1-FR-H.1, Loss of Secondary Heat Sink.
2) The basis for the method selected.

A. 1) Feed all steam generators at 350 gpm total AFW flow.

2) Minimum flow to ensure an adequate heat sink.

B. 1) Feed each steam generator at a rate of 60 gpm.

2) Limit thermal stresses to steam generator components.

C. 1) Feed each steam generator at a rate of 60 gpm.

2) Minimum flow to ensure an adequate heat sink.

D. 1) Feed all steam generators at 350 gpm total AFW flow.

2) Limit thermal stresses to steam generator components.

Question 73:

Given the following:

  • Unit 2 was operating at 100% when a LBLOCA and Loss of offsite power occurred.
  • EDG 3 fails to start automatically, or manually.
  • Crew is performing 2-E-1, step 18; Initiate Evaluation of plant status.

Which one of the following conditions:

1) Require entry into 2-ECA-1.1, Loss of Emergency Coolant Recirculation?
2) Require securing the Outside Recirc Spray (OSRS) pump, 2-RS-P-2A in accordance with 2-ECA-1.1, Loss of Emergency Coolant Recirculation?

A. 1) Failure of 2-RS-P-2A, OSRS pump to start.

2) Operating 2-RS-P-2A without 2-CS-P-1A, Containment Spray pump operating.

B. 1) Failure of 2-RS-P-2A, OSRS pump to start.

2) Containment sump level < 4.0 feet.

C. 1) Failure of 2-CS-P-1A, Containment Spray pump to start.

2) Operating 2-RS-P-2A without 2-CS-P-1A operating.

D. 1) Failure of 2-CS-P-1A, Containment Spray pump to start.

2) Containment sump level < 4.0 feet.

Question 74 Unit 1 was initially operating at 100% power when a LBLOCA occurred.

  • SI, Hi CLS, and Hi-Hi CLS have actuated.
  • Containment pressure is 19 psia and lowering.
  • 1-RS-P-2B, B Outside Recirc Spray pump (ORSP) was manually started following the auto start of 1-RS-P-2A, A Outside Recirc Spray pump by the BOP.
  • Breaker 15J8, Normal supply to the 1J 4160v bus tripped and breaker 15J3, #3 EDG output breaker closed.

Which ONE of the following describes the effect of these events on the B Train of Recirc Spray pumps for the following:

1) When power is lost from 1J bus?
2) When power is restored to 1J bus?

A. 1) 1-RS-P-1B (IRSP), and 1-RS-P-2B (ORSP) trips.

2) 1-RS-P-1B (IRSP) restarts in 20 seconds, 1-RS-P-2B (ORSP) does not restart.

B. 1) 1-RS-P-1B (IRSP), and 1-RS-P-2B (ORSP) trips.

2) 1-RS-P-1B (IRSP) restarts in 10 seconds, 1-RS-P-2B (ORSP) restarts in 20 seconds.

C. 1) 1-RS-P-1B (IRSP) trips, 1-RS-P-2B (ORSP) breaker remained closed.

2) 1-RS-P-1B (IRSP) restarts in 20 seconds, 1-RS-P-2B (ORSP) restarts immediately.

D. 1) 1-RS-P-1B (IRSP) trips, 1-RS-P-2B (ORSP) breaker remained closed.

2) 1-RS-P-1B (IRSP) restarts in 10 seconds, 1-RS-P-2B (ORSP) restarts immediately.

Question 75 Given the following:

  • Large Break LOCA occurs on Unit 1.
  • All Equipment operates as designed.

Which ONE of the following completes the statements below:

1) The MINIMUM containment sump level to enter FR-Z.2, Response to Containment Flooding is

___(1)___ feet.

2) The MINIMUM containment pressure to enter FR-Z.1, Response to Containment High Pressure (Red Path) is ___(2)___ psia.

A. 1) 6.0

2) 23 B. 1) 7.2
2) 23 C. 1) 6.0
2) 60 D. 1) 7.2
2) 60

RO EXAM LIST OF ATTACHMENTS Attachment # Attachment Description 1 Integral Rod Worth Table 2 Containment Allowable Air Pressure vs. Service Water

ATTACHMENT 1 NRC VALIDATION ANSWER SHEET Question # Answer Question Answer RO 1 C 41 D 2 A 42 D 3 A 43 A 4 C 44 A 5 B 45 B 6 C 46 D 7 C 47 C 8 C 48 D 9 B 49 D 10 B 50 C 11 B 51 A 12 B 52 C 13 C 53 B 14 A 54 A 15 B 55 D 16 B 56 C 17 A 57 A 18 A 58 A 19 C 59 D 20 A 60 D 21 C 61 B 22 D 62 A 23 A 63 C 24 B 64 C 25 D 65 B 26 B 66 C 27 A 67 A 28 A 68 B 29 A 69 C 30 A 70 C 31 C 71 C 32 B 72 B 33 A 73 B 34 C 74 A 35 D 75 D 36 B 37 D 38 B 39 B 40 B NRC Validation Page 1

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