ML13274A446

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Initial Exam 2012-302 Draft RO Written Exam
ML13274A446
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 09/27/2013
From:
NRC/RGN-II
To:
Tennessee Valley Authority
References
Download: ML13274A446 (75)


Text

QUESTIONS REPORT forSQN Dec2012 RO Exam

1. Given the following plant conditions:

- Unit 1 is at 10% power following a refueling outage.

- The main turbine is being warmed up in preparation to sync to the grid.

- The OATC notes that CB A, rod H6 Red ROD at Bottom light is illuminated.

- The crew implements AOP-C.01, Rod Control System Malfunctions.

- RCS pressure is 2200 psig and slowly lowering.

- RCS Tave is 540° F In accordance with AOP-C.01, which ONE of the following statements identifies the required operator action(s)?

A Trip the reactor and enter E-0, Reactor Trip or Safety Injection.

B. Within 15 minutes increase RCS temperature above 541 °F.

C. Within 30 minutes ensure Quadrant Power Tilt Ratio (QPTR) is less than 1.09.

D. Within 60 minutes rod H6 must be realigned to within 12 steps of other CB A rods.

Tuesday, March 12, 2013 9:56:47AM

QUESTIONS REPORT for SQN Dec 2012 RD Exam

2. Given the following plant conditions:

- Unit I is operating at 100%.

- 1-RE-90-1 12, Upper Containment Radiation Monitor, is aligned to lower containment for scheduled maintenance on 1-RE-90-106, Lower Containment Radiation Monitor.

- LS-77-410A REACTOR BLDG AUX FL & EQ DRAIN SUMP HI alarms (1-XA-55-5A window C-5)

- The CR0 determines the Reactor Building auxiliary floor and equipment drain (pocket) sump level indication to be:

1-LI-77-410A - 98%

1-LI-77-41 1A - failed off scale low

- Neither pocket sump pump is running with both handswitches in NORM.

- The reactor building pocket sump rate of rise alarms on ICS (U0967 &

1U0968) are NOT in alarm.

Which ONE of the following identifies...

(1) the status of the pocket sump pumps and (2) the status of Tech Spec LCD 3.4.6.1 Reactor Coolant System Leakage Detection Instrumentation A. (1) The pocket sump pumps should have started automatically.

(2) LCO 3.4.6.1 Action is NOT required.

B. (1) The pocket sump pumps should NOT have started automatically.

(2) LCD 3.4.6.1 Action is required.

C. (1) The pocket sump pumps should have started automatically.

(2) LCD 3.4.6.1 Action is required.

D (1) The pocket sump pumps should NOT have started automatically.

(2) LCD 3.4.6.1 Action is NOT required.

Tuesday, March 12, 2013 9:56:47 AM 2

QUESTIONS REPORT for SQN Dec 2012 RO Exam

3. Given the following plant conditions;

- Unit I is currently holding power at 30%.

- RCP #3 trips.

Which ONE of the following describes how steam flow and water level in SG #3 initially responds?

Initially, SC #3 steam flow and level A. rises; rises B. rises; lowers C lowers; lowers D. lowers; rises Tuesday, March 12, 2013 9:56:47 AM 3

QUESTIONS REPORT for SQN Dec 2012 RO Exam

4. Given the following plant conditions:

- The operating crew is performing a dilution in preparation for rod withdrawal to criticality.

- The initial readings on SR monitors is 300 cps

- Keff is approximately 0.99 when the dilution is started.

- After the dilution is complete the SR monitors read 600 cps and stable.

Which ONE of the following is the final Keff?

A. .992 B. .993 C .995 D. .997 Tuesday, March 12, 2013 9:56:47 AM 4

QUESTIONS REPORT for SQN Dec 2012 RO Exam

5. Given the following plant conditions:

- A LOCA occurred forty minutes ago.

- ES-i .3, Transfer To RHR Containment Sump Recirculation, has been completed.

- RCS pressure is 150 psig and stable.

- Containment pressure peaked at 8 psig, and is currently 3 psig.

Which ONE of the following identifies what would happen if the lA-A RHR Pump were to trip?

A. IA-A SI Pump would cavitate.

B NO ECCS pumps would cavitate.

C. IA-A Containment Spray pump would cavitate.

D. Both the IA-A and the 1 B-B CCP5 would cavitate.

Tuesday, March 12, 2013 9:56:47 AM 5

QUESTIONS REPORT for SQN Dec 2012 RO Exam

6. Given the following plant conditions:

- Unit 1 is in Mode 4.

- RHR Train A is in service per 0-SO-74-1, Residual Heat Removal System.

- RCS temperature is stable at the current RHR flow rate.

Which ONE of the following malfunctions will result in a REDUCTION in flow through the RHR Heat Exchanger 1A?

A loss of A air to 1-FCV-74-32, RHR HTX Bypass.

B. air to 1-FCV-74-16, RHR HTX A Outlet.

C. I2OVAC Vital Instrument Power Board 1-Il.

D. 480V Shutdown Board IAI-A.

Tuesday, March 12, 2013 9:56:47 AM 6

QUESTIONS REPORT for SQN Dec 2012 RO Exam

7. Given the following plant conditions:

- A LOCA has occurred on Unit I.

- ES-I .3, Transfer to RHR Containment Sump, has been completed by the operating crew.

- A total loss of off-site power occurs.

Which ONE of the following identifies why both CCP handswitches are required to be placed in PULL TO LOCK?

A To prevent damage to the CCP5 B. To prevent thermal shock to the RCP seals C. To prevent overloading the diesel generators D. To prevent flashing in the regenerative heat exchanger Tuesday, March 12, 2013 9:56:48 AM 7

QUESTIONS REPORT for SQN Dec 2012 RO Exam

8. Given the following plant conditions:

- Unit I is in Mode 5 with the pressurizer (PZR) cold cal level at 40% with a nitrogen blanket present.

- The operating crew initiates action to establish solid water conditions in order to allow a steam bubble to be formed in the pressurizer.

Which ONE of the following choices completes the statement below?

The condition that will indicate that solid water operation has been established is an increase in PRT LU After the heaters are energized to establish a steam bubble, the bubble is confirmed f provided the RCS pressure is stable or slowly increasing.

LU A. level by changes in PRT parameters B. level when letdown flow exceeds charging flow C. temperature by changes in PRT parameters D. temperature when letdown flow exceeds charging flow Tuesday, March 12, 2013 9:56:48 AM 8

QUESTIONS REPORT for SQN Dec 2012 RO Exam

9. Given the following plant conditions:

- Unit 1 at 100% power.

- RCP #3 develops an 8 gpm leak in the thermal barrier.

Which ONE of the following identifies the automatic action(s), if any, that will take place within the CCS?

A. No automatic action occurs.

B. RCP #3 thermal barrier isolates.

C. Thermal barrier booster pumps trip and only RCP #3 thermal barrier isolates.

D Thermal barrier booster pumps trip and all four RCP thermal barriers isolate.

Tuesday, March 12, 2013 9:56:48 AM 9

QUESTIONS REPORT for SQN Dec 2012 RO Exam

10. Given the following plant conditions:

- Unit 1 is operating at 100% RTP

- 0-XA-55-27B-B, Window A-5, LETDOWN HX OUTLET FLOW/TEMP ABNORMAL alarms.

- The RO determines that Letdown HX Outlet temperature is 132°F and rising slowly.

Which ONE of the following identifies the event that has occurred, and the effect the event has on the unit prior to any action by the crew?

A. TCV-70-192 temperature input is failing high. Reactor power will rise slightly.

B. TCV-70-192 temperature input is failing high. Reactor power will drop slightly.

C. TCV-70-1 92 temperature input is failing low. Reactor power will rise slightly.

D TCV-70-1 92 temperature input is failing low. Reactor power will drop slightly.

Tuesday, March 12, 2013 9:56:48 AM 10

QUESTIONS REPORT forSQN Dec2012 RO Exam

11. Given the following plant conditions:

- Unit 1 was at 100% when a pressurizer PORV opened and stuck open.

- The associated block valve could not be closed.

- The crew is currently performing actions of ES-i .2, Post LOCA Cooldown and Depressurization.

- RCS pressure is 1600 psig and and slowly risincj.

- iA Safety Injection pumps trips.

Which ONE of the following completes the statements below as to how the SI pump trip affects break flow and CCPIT flow?

Break flow will 1JJ CCPITflowwill (ZI fl (2 A. begin dropping remain the same B continue to rise remain the same C. begin dropping start rising D. continue to rise start rising Tuesday, March 12, 2013 9:56:48 AM ii

QUESTIONS REPORT for SQN Dec 2012 RD Exam

12. Given the following plant conditions:

- Unit 1 is steady-state at 100% power.

- The setpoint onl-PIC-68-340A, PZR Pressure Control, is lowered to 60%.

Assuming NO additional operator actions are taken, which ONE of the following identifies the response of the plant?

A. Pressurizer backup heaters would energize and RCS pressure would rise.

B Pressurizer spray valves would modulate partially open and RCS pressure would lower.

C. Pressurizer control group heaters would remain energized and RCS pressure would remain stable.

D. Pressurizer spray valves would fully open and RCS pressure would lower below the low pressure trip setpoint.

Tuesday, March 12, 2013 9:56:48 AM 12

QUESTIONS REPORT for SQN Dec 2012 RO Exam

13. Given the following plant conditions:

- Unit 2 is at 100% power.

- 2-XS-68-339E, Level Control Channel Selector is in the LT-68-339 &

335 position.

- VCT level is at 38%

- PZR level transmitter 2-LT-68-339 loses the level in its reference leg.

- No ESF actuations occur as a result of the reference leg leak.

Assuming no operator action, which ONE of the following describes how the VCT level will respond throughout the event?

The VCT level will...

A. rise and be maintained between 63% and 93%.

B. lower, then be maintained between 20% and 41%.

C rise to between 63% and 93%, then lower and be maintained between 20%

and 41%.

D. lower to 7%, cause charging pump suction to transfer to the RWST, and remain low.

Tuesday, March 12, 2013 9:56:48 AM 13

QUESTIONS REPORT for SQN Dec 2012 RO Exam

14. During a LOCA, as RCS pressure and inventory are reduced, which ONE of the following correctly describes:

(1) the sequence that will occur for modes of core cooling and (2) the reason that reflux boiling occurs?

A. (1) Natural Circulation, then Reflux Boiling.

(2) Reflux boiling occurs when Natural Circulation has ceased and steam from the core migrates to the SIG tubes where it is condensed and returns to the core via the COLD leg.

B (1) Natural Circulation, then Reflux Boiling.

(2) Reflux boiling occurs when Natural Circulation has ceased and steam from the core migrates to the SIG tubes where it is condensed and returns to the core via the HOT leg.

C. (1) Reflux Boiling, then Natural Circulation.

(2) Reflux boiling occurs before Natural Circulation has had time to start. Steam from the core migrates to the S/C tubes where it is condensed and returns to the core via the COLD leg.

D. (1) Reflux boiling, then Natural Circulation.

(2) Reflux boiling occurs before Natural Circulation has had time to start. Steam from the core migrates to the S/C tubes where it is condensed and returns to the core via the HOT leg.

Tuesday, March 12, 2013 9:56:48 AM 14

QUESTIONS REPORT for SQN Dec 2012 RO Exam

15. Given the following plant conditions:

- Unit I is operating in Mode 3 in preparation for Reactor startup.

- Train-A SSPS Input-Error Inhibit Switch is in Inhibit position.

- The Reactor Trip Breakers are closed.

- BYB Bypass Breaker was inadvertently racked in during preparation for the Train-A SSPS test.

Which ONE of the following identifies the response of the plant if operations personnel close BYB Bypass Breaker?

A. No Trip or Alarm.

B Reactor will Trip.

C. Protection System Train-B Trouble alarm, No Trip.

D. Bypass Breaker BYB will trip open, No reactor Trip.

Tuesday, March 12, 2013 9:56:48 AM 15

QUESTIONS REPORT for SQN Dec 2012 RO Exam

16. Given the following plant conditions:

- Unit I at 100% power with the TD-AFW pump out of service for maintenance.

- Annunciator 125V DC VITAL CHARGER II FAILURE OR VITAL BAT II DISCHARGE on panel 1-M-IC (M1-C-B4) is in alarm and the crew is investigating the cause.

- Subsequently a reactor trip due to a spurious main turbine trip occurs.

- The crew is performing ES-Ui, Reactor Trip Response, when the OATC determines the Train B AFW pump is NOT running.

Which ONE of the following identifies:

(1) a reason the AFW pump B is not running AND (2) the allowed procedure use sequence provided by EPM-4, Users Guide, to allow placing the AFW pump B in service?

A. (1) Loss of control power to SSPS Train B slave relays.

(2) AOP-P.02, Loss of 125v DC Vital Battery Board, can be implemented ONLY after ES-Ui has been completed.

B. (1) Loss of control power to SSPS Train B slave relays.

(2) Implement AOP-P.02, Loss of 125v DC Vital Battery Board while continuing in ES-0.1.

C. (1) Loss of control power to the 6900v Shutdown Board.

(2) AOP-P.02, Loss of 125v DC Vital Battery Board, can be implemented ONLY after ES-0.1 has been completed.

D (1) Loss of control power to the 6900v Shutdown Board.

(2) Implement AOP-P.02, Loss of 125v DC Vital Battery Board while continuing in ES-0.1.

Tuesday, March 12, 2013 9:56:48 AM 16

QUESTIONS REPORT for SQN Dec 2012 RO Exam

17. Given the following plant conditions:

- Unit 1 initially operating at 100% power with AFD at -3.4% and annunciator window 1-M-4B-C-7, ZB-442C BANK D AUTO ROD WITHDRAWAL BLOCKED, lit when a feedwater malfunction induces a transient.

- When the Unit is stabilized at 80% power following the transient, the OAC reports that Control Bank D M8 rod is indicating 28 steps withdrawn while the other rods in the group are within the required alignment with the Step Counters at 190 steps.

Which ONE of the following identifies the status of the Rod Bottom light on the RPI display and the core condition resulting from the mispositioned control rod?

Reference Provided Rod Bottom Light Core Condition A. LIT AFD moving toward 0 B. NOT LIT AFD moving toward 0 C. LIT QPTR increasing D NOT LIT QPTR increasing Tuesday, March 12, 2013 9:56:48 AM 17

QUESTIONS REPORT for SQN Dec 2012 RO Exam

18. Given the following plant conditions:

- Unit I has tripped from 100% power due to a LOCA.

- All RCPs were secured by procedure.

Currently, FR-C.1, Inadequate Core Cooling, is being implemented by the crew.

- The crew is at the step to determine if an RCP is to be started.

- The core exit T/C and RCS loop conditions allow the pump to be started.

Which ONE of the following completes the statements below?

An RCP will be started Li) be established and if the pump is able to reduce the Core Exit temperature, the procedure directs the pump to continue to run until at least f dropped to a temperature less than 350°F.

A. (1) even if the pumps support conditions can NOT (2) one T-hot indication has B (1) even if the pumps support conditions can NOT (2) two T-hot indications have C. (1) only if the pumps support conditions can (2) one T-hot indication has D. (1) only if the pumps support conditions can (2) two T-hot indications have Tuesday, March 12, 2013 9:56:48 AM 18

QUESTIONS REPORT forSQN Dec2012 RO Exam

19. Given the following plant conditions,

- Unit I is operating at 100% power.

- The running charging pump, IA-A, trips.

In accordance with EA-62-5, Establishing Normal Charging and Letdown, when establishing letdown which ONE of the following identifies the controller(s) that is/are required to be placed in Manual?

Note:

1-HIC-62-78A = LETDOWN HX OUTLET TEMP 1-HIC-62-81A = LETDOWN PRESSURE PRESSURE CONTROL 1-HIC-62-93A = CHARGING FLOW CONTROL A. 1-HIC-62-93A only.

B. 1-HIC-62-93A and 1-HIC-62-78A.

C. 1-HIC-62-81A only D 1-HIC-62-78A and 1-HIC-62-81A Tuesday, March 12, 2013 9:56:48 AM 19

QUESTIONS REPORT for SQN Dec 2012 RO Exam

20. Given the following plant conditions:

- Unit 1 is at 100% power.

- An inadvertent manual Containment Isolation Phase-A signal is actuated.

Which ONE of the following Containment Cooling System fans will trip and isolate as a DIRECT result of this action?

A. Lower Compartment Coolers B. Upper Compartment Coolers C. Control Rod Drive Motor coolers D Incore Instrument Room coolers Tuesday, March 12, 2013 9:56:48 AM 20

QUESTIONS REPORT for SQN Dec 2012 RO Exam

21. Given the following:

- Unit 1 is in Mode 5 with RCS at Mid-Loop.

- IA-A RHR pump in service.

- RHR flow is indicating 2400 gpm.

- The IA-A RHR pump motor amps become very erratic.

In accordance with AOP-R.03, RHR System Malfunction, which ONE of the following indentifies:

(1) the RHR flow rate the operators are to maintain and (2) the action(s) that will be required if the lA-A RHR pump motor amps continue to be erratic?

A. (1) between 1500 gpm and 2000 gpm (2) stop the lA-A RHR pump and start the I B-B RHR pump.

B. (1) betweenl000gpmandl500gpm (2) make up to the RCS immediately by opening valve 1-FCV-63-1, RHR suction from RWST.

Cv (1) between 1000 gpm and 1500 gpm (2) stop the IA-A RHR pump, increase the level in the RCS and attempt to restore RHR cooling.

D. (1) between l500gpmand2000gpm (2) make up to the RCS immediately via valves 1-FCV-62-135 & 136, Suction of CCPs from the RWST.

Tuesday, March 12, 2013 9:56:48 AM 21

QUESTIONS REPORT forSQN Dec2012 RO Exam

22. Which ONE of the following identifies an ice condenser door that would require entering a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Technical Specification LCO if the door was found to be physically restrained from opening and which of the doors are equipped with flow proportioning springs to control opening?

Require 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> LCO entry if Doors equipped with physically restrained from opening flow proportioning springs A Only an inlet door Inlet doors B. Only an inlet door Intermediate doors C. Eitheraninletor lnletdoors intermediate deck door D. Either an inlet or Intermediate doors intermediate deck door Tuesday, March 12, 2013 9:56:48 AM 22

QUESTIONS REPORT forSQN Dec2012 RO Exam

23. Given the following plant conditions:

- Unit I was operating at 100% power with Containment Spray Pump IA-A out of service when a LOCA occurs.

- Containment Spray Pump I B-B trips when attempting to start.

- During performance of ES-i .3, Transfer To RHR Containment Sump i-FCV-63-73, CNTMT SUMP TO RHR PMP B SUCT, could NOT be opened.

- The operating crew is currently performing FR-Z.1, High Containment Pressure, and is addressing the step to determine if RHR spray should be placed in sevice.

- The following conditions exist:

- 90 minutes have elapsed since the accident.

- Containment pressure is 9.7 psig.

Which ONE of the following identifies the proper action associated with RHR spray and the reason why?

RHR spray would...

A. NOT be placed in service since ONLY one train of RHR is available.

B. NOT be placed in service because the containment pressure is below the setpoint requirement.

Cv be placed in service immediately because all required conditions are met.

D. be placed in service ONLY after the minimum time since the accident elapses.

Tuesday, March 12, 2013 9:56:48 AM 23

QUESTIONS REPORT for SQN Dec 2012 RD Exam

24. Given the following plant conditions,

- Unit 1 operators are performing actions of ECA-0.0, Loss of All AC Power.

- A step in ECA-0.0 directs the operators to locally isolate RCP seals using EA-68-1, RCP Seals and Thermal Barrier Isolation.

- Subsequently offsite power is restored and the operators have transitioned to ECA-0.1, Recovery From Loss of All AC Power Without SI Required.

Which ONE of the following describes the reason for isolating the CCS thermal barrier return prior to restarting the CCS pump?

A. To prevent thermal shock to the thermal barrier heat exchanger upon restart of the CCS system during recovery.

B. To prevent thermal shock to the RCP seal packages upon restart of the CCS system during recovery.

C. To ensure elevated heat loads as a result of the loss of all AC power are within the design cooling capacity of CCS prior to starting a CCS pump.

Dv To prevent steam from forming and circulating in the CCS system and ensures the CCS system is available to cool equipment necessary for recovery.

Tuesday, March 12, 2013 9:56:48 AM 24

QUESTIONS REPORT forSQN Dec2012 RD Exam

25. Given the following plant conditions:

- Unit 2 is at 80% power and raising power when a step load change in power occurs.

- Pressurizer pressure drops to 2205 psig.

- Automatic pressure control responds as designed.

- As pressure rises to 2214 psig, 2-PIC-68-340A, PZR Pressure Controller, output is observed to be 10% and not responding.

- The controller is placed in MANUAL with the controller output reading 10%.

Assuming no further operator action, which ONE of the following describes the system response?

A. All Heater banks remain ON and pressure will be controlled by Spray valve operation.

B. Heater banks C & D remain ON, Heater Banks A & B turn OFF and pressure will be controlled by Spray valve operation.

C All Heater banks remain ON and pressure will be controlled by PORV operation.

D. Heater banks C & D remain ON, Heater Banks A & B turn OFF and pressure will be controlled by PORV operation.

Tuesday, March 12, 2013 9:56:48 AM 25

QUESTIONS REPORT for SQN Dec 2012 RO Exam

26. Which ONE of the following identifies the direct source of 480v power to the Containment Hydrogen Recombiner lA-A?

A Reactor Vent Bd IA-A B. Reactor MOV Bd 1A1-A C. C&AVentBdlA2-A D. 480V Shutdown Bd 1A2-A Tuesday, March 12, 2013 9:56:48 AM 26

QUESTIONS REPORT for SQN Dec 2012 RO Exam

27. Given the following plant conditions,

- Unit 2 is operating at 100% power when an automatic Reactor trip signal is generated.

- The reactor fails to trip.

- The OATC attempts to trip the reactor but is unsuccessful.

In accordance with FR-S.1, Nuclear Power Generation I ATWS, which ONE of the following identifies both, (1) the immediate action required to be taken if the main turbine does NOT trip automatically and CANNOT be tripped from the main control board, and (2) an action, directed by procedure, when checking reactor and turbine trip status if the reactor has NOT been TRIPPED?

A. (1) Pull to Lock the EHC pumps.

(2) manually initiate Safety Injection.

B. (1) close the main turbine governor valves using VPL.

(2) manually initiate Safety Injection.

C. (1) Pull to Lock the EHC pumps.

(2) Open the breakers to MG sets locally.

D (1) close the main turbine governor valves using VPL.

(2) Open the breakers to MG sets locally.

Tuesday, March 12, 2013 9:56:48 AM 27

QUESTIONS REPORT for SQN Dec 2012 RO Exam

28. Given the following plant conditions:

- Both Units are at 100% power.

- Annunciator TIS-78-4 SPENT FUEL PITS TEMPERATURE HIGH (1 M6D-E3) alarms.

- AUO reports the Spent Fuel Pit Temperature is 128°F and has risen 4°F since the beginning of the shift.

- SFP Heat Exchanger A is in service with 2600 gpm SFPC pump flow and 2400 gpm CCS flow.

Which ONE of the following identifies both:

(1) whether the alarm is valid and (2) the appropriate method to stabilize temperature for the given conditions?

Alarm Method to stabilize temperature A Valid Raise CCS flow through SFP Heat Exchanger A B. Valid Raise SFPC pump flow through SFP Heat Exchanger A C. Invalid Raise CCS flow through SFP Heat Exchanger A D. Invalid Raise SFPC pump flow through SFP Heat Exchanger A Tuesday, March 12, 2013 9:56:48 AM 28

QUESTIONS REPORT for SQN Dec 2012 RO Exam

29. Given the following plant conditions,

- Unit 2 is operating at 100% power.

- SG#2 NR levels indicate: 1-LI-3-55 1-LI-3-52 1-Ll-3-51 45% 44% 43%

Which ONE of the following identifies the effect on SG level control if 1-LT-3-52 fails to 0% output?

A. 1-LT-3-51 will become the level input to the level control system.

B. 1-LT-3-55 will become the level input to the level control system.

C Level control input will be the average ofl-LT-3-51 and 1-LT-3-55.

D. Level control system will automatically transfer to manual control.

Tuesday, March 12, 2013 9:56:48 AM 29

QUESTIONS REPORT for SQN Dec 2012 RO Exam

30. Which ONE of the following identifies the reason I function for the Manipulator Crane interlock on LS-3, Gripper Full Up, mast limit switch?

A. Prevents gripper assembly from being disengaged to ensure a fuel assembly in the mast cannot be dropped.

Bb Prevents bridge or trolley movement to ensure possible suspended fuel assembly in the mast cannot be dropped.

C. Prevents intentional shutdown of the manipulator crane with a fuel assembly not fully up in the mast to prevent unnecessary exposure of fuel handling personnel.

D. Prevents movement of the fuel transfer cart from the SEP side to the Rx side to ensure a fuel assembly being lowered or removed from the upender isnt damaged.

Tuesday, March 12, 2013 9:56:48 AM 30

QUESTIONS REPORT for SQN Dec 2012 RO Exam

31. Given the following plant conditions,

- Due to a small tube leak, Unit I has been placed in Mode 3 and the operating crew is performing AOP-R.01, Steam Generator Tube Leak.

- During cooldown of the RCS to 350°F insufficient cooldown and depressurization of the leaking steam generator occurred resulting in additional actions being required for cooling and depressurizing the leaking steam generator.

Which ONE of the following completes the statement below?

An excessive depressurization rate of the leaking steam generator can result in .

The preferred method of cooling of the leaking steam generator is by the use of the (2L A. (1) closure of intact SG MSIVs (2) MSIV bypass valve operation B. (1) inability to maintain required RCS subcooling (2) Steam Generator Blowdown C (1) closure of intact SG MSIVs (2) Steam Generator Blowdown D. (1) inability to maintain required RCS subcooling (2) MSIV bypass valve operation Tuesday, March 12, 2013 9:56:48 AM 31

QUESTIONS REPORT for SQN Dec 2012 RO Exam

32. Given the following plant conditions:

- A SGTR occurs on Unit 1.

- Following the termination of Safety Injection in E-3, Steam Generator Tube Rupture, a loss of off-site power occurs.

- The crew is ready to depressurize the RCS to less than the ruptured steam generator pressure in accordance with step 20.

- Conditions require auxiliary spray to be used.

- 1-PIC-68-340B, LOOP 2 SPRAY CONTROL, is in MANUAL and at 50%.

Which ONE of the following completes the statement below?

0-SI-SXX-068-1 27.0, RCS Pressurizer and Temperature and Pressure Limit, requires the SRO and Nuclear Engineering is to be fjt notified if the pressurizer surge line AT exceeds L1 and if 1-PIC-68-340B is adjusted to 100% it will f2) the spray flow into the pressurizer when the auxiliary spray valve is opened.

in A 320°F lower B. 320°F raise C. 560°F lower D. 560°F raise Tuesday, March 12, 2013 9:56:48 AM 32

QUESTIONS REPORT for SQN Dec 2012 RO Exam

33. Given the following plant conditions:

- Unit I is in Mode 3.

- The crew is performing a plant cooldown in accordance with 0-GO-7, Unit Shutdown From Hot Standby to Cold Shutdown.

- Tave is 540°F and slowly lowering.

- PZR pressure is 1850 psig and slowly lowering.

- P-Il has energized and all blocking actions have been taken.

- SG pressures are all approximately 950 psig and slowly lowering.

- While attempting to increase the RCS cooldown rate, the UO inadvertently throttles the Condenser Steam Dumps too far OPEN.

- LP 2 Ch I, II, & Ill HI NEC RATE STMLINE PRESS lights on 1-XX-55-6B illuminate and then extinguish.

Which ONE of the following indentifies the automatic function(s), if any, that occur as a result of this condition?

A. No automatic actions occur.

B. Safety Injection actuates ONLY.

C Main Steam Line Isolation actuates ONLY.

D. Main Steam Line Isolation and Safety Injection Actuation occur.

Tuesday, March 12, 2013 9:56:48 AM 33

QUESTIONS REPORT for SQN Dec 2012 RO Exam

34. Given the following plant conditions,

- Unit #1 was operating at 100% power when SIG #1 faulted inside containment.

- The crew is currently performing E-2, Faulted Steam Generator Isolation.

Which ONE of the following identifies a reason the feed flow is isolated to SIC #1 during performance of E-2?

A. To minimize CST depletion.

B. To minimize the potential of rupturing a SIG tube.

C To maximize the cooldown capability of the non-faulted SIGs.

D. To maximize the time that the Turbine Driven AFW pump will be available.

Tuesday, March 12, 2013 9:56:48 AM 34

QUESTIONS REPORT for SQN Dec 2012 RO Exam

35. Given the following plant conditions,

- Unit 1 is operating at 55% power.

- Containment purge has been initiated per 0-SO-30-3, Containment Purge System Operation, for a planned containment entry.

- A feedwater line rupture occurs outside containment.

Loop #3 S/G narrow range level channels indicate as tabulated below at two minutes after the leak initiated:

TI ME 1 -LI-3-97 1 -LI-3-94 1 -Ll-3-93 2 minutes 15% 14% 13%

Which ONE of the following identifies the status of the following alarm windows at two minutes?

(1) LS-3-97B STM GEN LOOP 3 LEVEL LOW-LOW REACTOR TRIP, (M4-D; A-3) and (2) LS-3-93B STM GEN LOOP 3 LOW-LOW WATER LEVEL, (M6-B; C-4)

A (1) (M4-D; A-3) Lit (2) (M6-B; C-4) Lit B. (1) (M4-D; A-3) NOT Lit (2) (M6-B; C-4) Lit C. (1) (M4-D; A-3) Lit (2) (M6-B; C-4) NOT Lit D. (1) (M4-D; A-3) NOT Lit (2) (M6-B; C-4) NOT Lit Tuesday, March 12, 2013 9:56:48 AM 35

QUESTIONS REPORT for SQN Dec 2012 RO Exam

36. Given the following plant conditions,

- Unit 2 is at 100% power.

- CSST B is aligned to the 1 B Start Bus.

- Unit 2 loses off-site power.

- Both Unit 2 D/Gs failed to start.

- Both 2A and 2B Start Bus feeder breakers experienced an overcurrent lockout.

- Both the shutdown board normal feeder breakers experienced an overcurrent lockout.

- The faults in the switchyard and shutdown boards have been cleared.

- Both CSST A and C have been re-energized.

- The crew has decided to restore power to a Unit 2 shutdown board through its normal feeder breakers from offsite power using EA-202-1, Restoring Off-Site Power to 6900V Shutdown Boards.

Which TWO of the following lockout relays must be reset to recover the associated Unit 2 Shutdown Board from off-site power?

Off-site Power Shutdown Board A. Start Bus Feeder from CSST C 2B-B 6.9kV Shutdown Board overcurrent lockout overcurrent lockout B Start Bus Feeder from CSST C 2A-A 6.9kV Shutdown Board overcurrent lockout overcu rrent lockout C. Start Bus Feeder from CSST A 2A-A 6.9kV Shutdown Board overcurrent lockout overcurrent lockout D. Start Bus Feeder from CSST B 2B-B 6.9kV Shutdown Board overcurrent lockout overcurrent lockout Tuesday, March 12, 2013 9:56:48 AM 36

QUESTIONS REPORT for SQN Dec 2012 RO Exam

37. Given the following plant conditions;

- Unit 1 is operating at 100% power when CBP 1A trips.

- The operating crew enters AOP-S.04, Condensate or Heater Drains Malfunction.

- Investigation determines the pump to be damaged and will be out of service for several days.

Which ONE of the following completes the statements below in accordance with AOP-S.04?

An immediate load reduction may be required to maintain MFP suction pressures greater than a minimum of Li) psig.

With the pump being out of service for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the procedure directs an evaluation of a power reduction to at least less than f2) to reduce the risk of a unit trip if any additional secondary plant malfunctions occurs.

fl A. 250 85%

B. 250 75%

C 320 85%

D. 320 75%

Tuesday, March 12, 2013 9:56:48 AM 37

QUESTIONS REPORT for SQN Dec 2012 RO Exam

38. Given the following plant conditions,

- Unit #1 is operating at 100% power

- The Turbine Driven AFW pump is removed from service for maintenance.

- A loss of Offsite power occurs on Unit #1.

- The crew has entered ES-0.1, Reactor Trip Response.

While performing EA-68-6, Monitoring Natural Circulation Conditions, the following plant conditions are observed:

- Highest Core Exit Thermocouple = 595°F and stable

- RCS pressure = 1900 psig and stable

- All SIG pressures = 1040 psig and stable

- RCS hot leg temperatures (all loops) = 585°F and stable

- RCS cold leg temperatures = 540°F and stable Which ONE of the following indentifies the status of Natural Circulation and any action that would be required to be taken in accordance with ES-0.1?

Natural Circulation Action A. Established Raise steam flow through Steam Dumps B. Established Raise steam flow through SG PORV5 C NOT Established Raise steam flow through SG PORV5 D. NOT Established Raise steam flow through Steam Dumps Tuesday, March 12, 2013 9:56:48 AM 38

QUESTIONS REPORT for SQN Dec 2012 RO Exam

39. Given the following plant conditions:

- Unit 1 is at 100% power.

- Unit 2 is in Mode 6 with upper internals removal in progress.

- 125V DC Vital Battery III output breaker tripped and can NOT be reclosed.

- 125V DC Vital Battery Bank V has been connected to Vital Battery Bd III.

In accordance with Technical Specifications, which ONE of the following identifies a combination of chargers that if either is connected to Vital Battery Bd Ill will restore the Battey Bd Ill to OPERABLE?

A. Charger V or Spare 2-S B Spare Charger 2-S or 125 DC Battery Charger Ill C. Spare Charger 1-S or Charger V D. 125V DC Battery Charger Ill or Spare Charger 1-S Tuesday, March 12, 2013 9:56:48 AM 39

QUESTIONS REPORT for SQN Dec 2012 RO Exam

40. Given the following plant conditions:

- Unit I is operating at 100% power.

- A malfunction occurs and feedwater flow to each SG starts rising.

- Level in all SG5 are observed to be trending upwards.

Which ONE of the following identifies both the cause of the event and the required immediate operator action in accordance with AOP-S.01, Main Feedwater Malfunctions, to be performed to prevent SG overfill?

CAUSE OPERATOR ACTION A. Common sensing line to PT-1-33 Place feedwater reg valve controllers for has developed a leak; all 4 SGs in MANUAL and lower feedwater flow main feedwater flow.

B. Common sensing line to PT-I -33 Place PC-46-20, MFPTIA & I B Speed has developed a leak; Control to Manual to lower MFPT IA and 1 B discharge pressure.

C Common sensing line to PT-3-I Place PC-46-20, MFPT1A & I B Speed has developed a leak; Control to Manual to lower MFPT 1A and 1 B discharge pressure.

D. Common sensing line to PT-3-1 Place feedwater reg valve controllers for has developed a leak; all 4 SGs in MANUAL and lower feedwater flow main feedwater flow.

Tuesday, March 12, 2013 9:56:49 AM 40

QUESTIONS REPORT for SQN Dec 2012 RO Exam

41. Which ONE of the following radiation monitors is NOT designed to automatically terminate an accidental radiation release?

A 0-RM-90-212, Turbine Building Sump Rad Monitor B. 1-RM-90-120, SIG Blowdown Effluent Rad Monitor C. 0-RM-90-225, Condensate Demineralizer Rad Monitor D. 0-RM-90-122, Liquid Waste Disposal System Effluent Rad Monitor Tuesday, March 12, 2013 9:56:49 AM 41

QUESTIONS REPORT for SQN Dec 2012 RO Exam

42. Given the following plant conditions:

- Unit I is at 100% power.

- A significant feedwater heater level transient results in HI-HI levels in Feedwater Heater Al.

- Extraction steam to the feedwater heaters isolates.

Prior to any operator action, which ONE of the following will be the effect on indicated RCS Tcold, and reactor power?

A. RCS Tcold will lower, and reactor power will rise.

B. RCS Tcold will lower, and reactor power will lower.

C. RCS Tcold will rise, and reactor power will rise.

D. RCS Tcold will rise, and reactor power will lower.

Tuesday, March 12, 2013 9:56:49 AM 42

QUESTIONS REPORT for SQN Dec 2012 RO Exam

43. Given the following plant conditions:

- An accidental Gaseous Waste release results in an Auxiliary Building Isolation.

Which ONE of the following completes the statement below?

The Auxiliary Building (AB) is isolated during an Accidental Gaseous Waste release event in order to A. reduce gas entering the Auxiliary Building B ensure gas release is filtered C. maintain habitable conditions in the Auxiliary Building D. provide maximum decay time prior to release Tuesday, March 12, 2013 9:56:49 AM 43

QUESTIONS REPORT for SQN Dec 2012 RO Exam

44. Which ONE of the following identifies the correct power supply to 1-FCV-3-136B Auxiliary Feedwater ERCW Supply MOV?

A. 480v Unit Bd IA.

B. 480vC&AVentBd IAI-A.

C 480v Rx MOV Bd 1A2-A.

D. l25vBatteryBdl Tuesday, March 12, 2013 9:56:49 AM 44

QUESTIONS REPORT for SQN Dec 2012 RO Exam

45. Which ONE of the following identifies the source and flow path of the cooling water for the TDAFW bearings?

The cooling water to the TDAFW pump bearings is supplied from (1) and after flowing through the bearing jacket, the water is routed to (2)

A. (1) the ERCW system (2) the Floor Drain Collector Tank B. (1) the ERCW system (2) the ERCW return header C (1) a stage on the TDAFW pump (2) the TDAFW pump suction D. (1) a stage on the TDAFW pump (2) the Floor Drain Collector Tank Tuesday, March 12, 2013 9:56:49 AM 45

QUESTIONS REPORT for SQN Dec 2012 RO Exam

46. Given the following plant conditions:

- Unit I at 100% RTP.

- Operators are performing procedure to remove 1-Il inverter from service and transfer board to the spare inverter.

- As operators operate the 12OVAC Vital Instrument Power Board 1-Il transfer switch to the ALTERNATE position, the following indications are noted:

  • Annunciator 12OVAC VITAL POWER BOARD 1-Il UV OR BKR TRIP is received. (Mi-C, B7)

All Channel II SSPS status lights are lit.

Which ONE of the following describes what has happened and procedural actions required under these conditions?

EVENT ACTIONS A. The indications are expected Ensure the indications clear after the since the transfer switch is break switch is fully positioned.

before make.

B. The indications are expected Ensure the indications clear as soon as the since the transfer switch is break snare inverter assumes the load.

before make.

C. Vital Instrument Power Board 1-Il Implement the appropriate AOP ONLY to.

has been lost, restore the Vital Instrument Power Board.

D Vital Instrument Power Board 1-Il Trip the reactor, implement E-0, Reactor has been lost. Trip or Safety Injection, and the appropriate AOP to restore the Vital Instrument Power Board.

Tuesday, March 12, 2013 9:56:49 AM 46

QUESTIONS REPORT for SQN Dec 2012 RO Exam

47. Given the following plant conditions,

- Unit 1 is currently at 45% power.

- Main turbine controls are in MANUAL.

- The inter-tie transformer tap changer is in MANUAL for calibration.

The following annuciators alarm simultaneously:

6900V SD BD lA-A FAILURE OR BUS FEEDER UV/OVERVOLTAGE (1-M-1B) 6900 SD BD lA-A OVERVOLTAGE (1-M-26-A)

STA FREQ EXCESSIVE ERROR (ECB6-B)

- The crew enters AOP-P.07, Degraded Grid Conditions or Generation Voltage Regulator Malfunction.

- Attempts to contact the Transmission Operator are unsuccessful.

- The crew initiates a turbine load reduction to reduce frequency.

- 5 minutes after the event, the CR0 announces that frequency recorder 0-REC-241-2 indicates frequency has risen to 60.6 Hz.

Which ONE of the following indentifies the required action in accordance with AOP-P.07?

A. Continue turbine load reduction to reduce frequency to 60 Hz.

B. Trip the reactor, enter E-0, Reactor Trip or Safety Injection.

C Trip the turbine, enter AOP-S.06, Turbine Trip Below P-9.

D. Place the shutdown boards on D/Gs using Appendix F.

Tuesday, March 12, 2013 9:56:49 AM . 47

QUESTIONS REPORT for SQN Dec 2012 RO Exam

48. Given the following plant conditions:

- Unit I is operating at 100% power.

- 125V DC VITAL BAT BD I is on an equalizing charge.

- The following annunciator on 1-Mi-C is received:

- 125V DC VITAL BAT BD I ABNORMAL, (A5).

- I -EI-57-96, VITAL BATTERY BD VOLTS indicates I 33v when selected to Board I.

- 1-EI-57-92, 125V VITAL BATT BD I AMPS indicates less than 0 amps.

Which ONE of the following identifies a reason for the alarm?

A. Board voltage high B. Battery discharging C Ground on battery board D. Equalizing charge timer at 0 Tuesday, March 12, 2013 9:56:49 AM 48

QUESTIONS REPORT for SQN Dec 2012 RO Exam

49. Which ONE of the following identifies the effect, if any, on Unit 2 EDGs if the Unit 1 Train A ERCW Supply header lost all flow?

A. No effect.

B. Only the Backup supply to 2A-A EDG is lost.

C. Only the Backup supply to 2B-B EDG is lost.

D Only the Normal supply to 2A-A EDG is lost.

Tuesday, March 12, 2013 9:56:49 AM 49

QUESTIONS REPORT for SQN Dec 2012 RO Exam

50. The following conditions exist on Unit 1:

- Annunciator, PS-82-162 DIESEL GEN IA-A START AIR PRESS LOW ENG 1 OR 2 (M26-A-C-l ) has been received.

- The Outside AUO reports an air leak that has been isolated by closing valves on both sides of pressure regulator between the receivers on the IA1 engine.

- The receiver air pressures currently are: IAI(A) at 100 psig and rising 1A1(B) at 195 psig and stable.

Which ONE of the following identifies the status of lA-A diesel generator?

A. lA-A diesel is still operable since 1A2 engine starting air is normal.

B. lA-A diesel is inoperable since 1AI(A) air receiver pressure is abnormal.

C lA-A diesel is operable since IAI (B) air receiver pressure is adequate to start the IA-A diesel.

D. IA-A diesel is inoperable since IAI(B) air receiver pressure is inadequate to start the IA-A diesel.

Tuesday, March 12, 2013 9:56:49 AM 50

QUESTIONS REPORT for SQN Dec 2012 RO Exam

51. Given the following plant conditions,

- Unit I is operating at 100% power.

- The OATC places 1-HS-62-104A, CHARGING PUMP B, to STOP PULL TO LOCK after a fire is reported to be in the I B CCP room.

- The lB CCP room door has been blocked open to ventilate the room.

- Fire Operations extinquishes the fire and an investigation determines the room cooler motor and fan are destroyed but the lB CCP has no damage.

- The OATC restores 1-HS-62-104A, CHARGING PUMP B, t0AAUTO.

Which ONE of the following identifies ths status of 1 B CCP?

A. NOT available nor OPERABLE until the room cooler is repaired.

B. Available but cannot be made OPERABLE until the room door is closed.

C. Available and OPERABLE provided the room door remains blocked open.

D Available but cannot be made OPERABLE until the room cooler is repaired.

Tuesday, March 12, 2013 9:56:49 AM 51

QUESTIONS REPORT for SQN Dec 2012 RO Exam

52. Given the following:

- The Radwaste AUO reports that the following alarms on 0-L-2B:

WGA H2-02 HI WGA SYSTEM TROUBLE

- Waste Gas Analyzer reads 4.1% Oxygen and 4.5% Hydrogen for the currently aligned Gas Decay Tank.

Which ONE of the following is the identifies the required action(s) in response to this condition?

A. Within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, dilute the Gas Decay Tank until oxygen concentration 2%.

B. Within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, dilute the Gas Decay Tank until hydrogen concentration 4%.

C. Immediately suspend additions to the affected Gas Decay Tank and dilute the affected Gas Decay Tank to reduce hydrogen concentration 4%.

D Immediately suspend additions to the affected Gas Decay Tank and dilute the affected Gas Decay Tank to reduce oxygen concentration 2%.

Tuesday, March 12, 2013 9:56:49 AM 52

QUESTIONS REPORT for SQN Dec 2012 RO Exam

53. Given the following plant conditions:

- Unit 1 is operating at 100% power.

Annunciator 1-.RA-120A1121A STM GEN BLDN LIQ SAMP MON HI RAD is in alarm.

- The indicator for RM-90-120 is reading pegged high and the red light is on.

- No other radiation monitor reads abnormally.

- RM-90-121 responds properly to a source check.

Which ONE of the following reflects the correct action to take under these conditions?

A Ensure 1-FCV-15-44 closed to stop blowdown flow. Notify Chemistry. If monitor has failed, place pink tags.

B. Ensure 1-FCV-15-44 closed to stop blowdown flow. Entry into AOP-R.01, Steam Generator Tube Leak, is required.

C. Since RM-90-121 is reading normally blowdown should not have isolated. Notify Chemistry. If monitor has failed, place pink tags.

D. Since RM-90-121 is reading normally blowdown should not have isolated. Entry into AOP-R.01, Steam Generator Tube Leak, is required.

Tuesday, March 12, 2013 9:56:49 AM 53

QUESTIONS REPORT for SQN Dec 2012 RO Exam

54. Which ONE of the following identifies a CCW design feature required to be met to make the C-9 CONDENSER AVAILABLE permissive on 1-XA-55-4A, BYPASS AND PERMISSIVE panel on 1-M-4?

A. At least one CCW pit level above setpoint B At least one CCWP breaker must be closed C. At least one CCWP discharge valve must be fully open D. At least one waterbox must have both the inlet and outlet MOV5 open Tuesday, March 12, 2013 9:56:49 AM 54

QUESTIONS REPORT for SQN Dec 2012 RO Exam

55. Given the following plant conditions:

- The unit has been at 100% power.

- Total primary to secondary leakage is 29 gpd.

- Identified RCS leakage is 0.02 gpm.

- Unidentified RCS leakage is 0.02 gpm.

- Pzr level, VCT level, charging flow, and letdown flow are all stable.

If fuel failure resulted in a significant increase in RCS activity, which ONE of the following identifies how the listed process rad monitors would respond?

1-RM-90-106 - Lower Containment Radiation Monitor 1-RM-90-1 19 - Condenser Vacuum Pump Exhaust Rad Monitor I -RM-90-1 06 1 -RM-90-1 19 A. Stable Rising B. Stable Stable C Rising Rising D. Rising Stable Tuesday, March 12, 2013 9:56:49 AM 55

QUESTIONS REPORT for SQN Dec 2012 RO Exam

56. Given the following plant conditions:

- The plant is at 100% power.

- J-A ERCW pump is in service, in Auto, and selected for preferred start.

- Offsite power is lost to 6.9KV Start Bus 1 B.

- Offsite power is now available to Start Bus 1 B.

- Blackout relays are reset.

Which ONE of the following describes the operation of the J-A ERCW pump after the loss of power?

The pump breaker:

A. will trip and immediately reclose, the pump will start when D/G energizes the SD board. The pump can be normally shutdown at any time.

B. stays connected to the bus, the pump will start when the D/G energizes the board.

The pump can be normally shutdown ONLY after the SD board is paralleled to offsite power.

C will trip, the pump will start 15 seconds after the D/G energizes the SD board. The pump can be normally shutdown.

D. will trip, the pump will start 15 seconds after the D/G energizes the SD board. The pump can be shutdown ONLY after Q-A ERCW pump is selected for preferred start (Selector Switch 0-XS-67-285).

Tuesday, March 12, 2013 9:56:49 AM 56

QUESTIONS REPORT for SQN Dec 2012 RO Exam

57. Given the following plant conditions:

- Unit I is at 100% power with all equipment aligned and functioning normally.

- Generator reactive load indicates 70 MVAR OUT as indicated on 1-EI-57-8, MEGAVARS.

- A grid disturbance occurs which results in a gradually lowering grid frequency.

As a result of the above conditions, how will the identified generator parameter indication be affected?

Generator Amps 1-El-57-9, -10, -11 Exciter Amps 1-El-57-7 A Rising Rising B. Lowering Lowering C. Rising Lowering D. Lowering Rising Tuesday, March 12, 2013 9:56:49 AM 57

QUESTIONS REPORT for SQN Dec 2012 RO Exam

58. Given the following plant conditions:

- 6.9kV Shutdown Board lA-A tagged for maintenance.

- Subsequently, 6.9kV Shutdown Board 2B-B trips and locks out due to relay operation.

Which ONE of the following identifies the status of the Auxiliary Air Compressor power supplies?

A. Both Auxiliary Air Compressors have a power supply available.

B. Neither Auxiliary Air Compressor has a power supply available.

C Only the Auxiliary Air Compressor A-A has a power supply available.

D. Only the Auxiliary Air Compressor B-B has a power supply available.

Tuesday, March 12, 2013 9:56:49 AM 58

QUESTIONS REPORT for SQN Dec 2012 RO Exam

59. Given the following plant conditions:

Unit I reactor is shutdown.

- The RCS is being maintained at normal operating temperature and pressure.

- Containment entry is in progress for maintenance.

- The following annunciators on 1-M12-C are locked in.

- LWR PERS ACCESS OUTER DR LOCK

- LWR PERS ACCESS INNER DR LOCK

- UPR/LWR AIR LOCK BREACH

- Containment pressure has rapidly equalized with the Aux Building.

- Containment pressure currently indicates 0.18 PSID.

In addition to TS 3.0.3, which ONE of the following identifies both, a required TS entry AND its associated action statement?

A. EnterTS 3.6.1.4 INTERNAL PRESSURE and restore Containment to annulus DP within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

B EnterTS 3.6.1.1 CONTAINMENT INTEGRITY and restore Containment integrity within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

C. EnterTS 3.6.1.3 CONTAINMENT AIR LOCKS and restore both Containment Access doors to operable status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

D. EnterTS 3.6.1.2 SECONDARY CONTAINMENT BYPASS LEAKAGE and restore Secondary Containment Bypass Leakage within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Tuesday, March 12, 2013 9:56:49 AM 59

QUESTIONS REPORT for SQN Dec 2012 RO Exam

60. Given the following plant conditions:

- Unit 2 is operating at 1050 MWe.

- Generator reactive load is 200 MVARs outgoing.

- All systems are operating normally.

Which ONE of the following hydrogen pressures is the LOWEST that will provide acceptable generator cooling in accordance with the generator capability curve?

REFERENCE PROVIDED A 45 psig B. 55 psig C. 60 psig D. 75 psig Tuesday, March 12, 2013 9:56:49 AM 60

QUESTIONS REPORT for SQN Dec 2012 RO Exam

61. Given the following plant conditions:

- Unit 1 is operating at 100% reactor power.

- Annunciator TS-68-316, 317 PRESSURIZER SPRAY LINES TEMP LOW alarms. (M5A C-2)

Which ONE of the following identifies...

(1) the condition that would cause the alarm and (2) a diverse indication that would validate the condition did exist?

Condition Diverse Indication A. Pressurizer spray Pressurizer surge line bypass flow LOW temperature RISING B. Pressurizer spray Pressurizer surge line bypass flow HIGH temperature RISING Cv Pressurizer spray Pressurizer surge line bypass flow LOW temperature DROPPING D. Pressurizer spray Pressurizer surge line bypass flow HIGH temperature DROPPING Tuesday, March 12, 2013 9:56:49 AM 61

QUESTIONS REPORT for SQN Dec 2012 RO Exam

62. Given the following plant conditions:

- A refueling outage is in progress on Unit 1.

- Fuel load was completed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago.

- Both SR neutron monitoring channels have been reading a background count rate of 10 cps since refueling was completed and were determined to be OPERABLE.

- Control Rod Drive Shaft latching is in progress per FHI-10, Full Length Control Rod Drive Shaft Latching and Unlatching.

- You just heard an increase in the SR audio count rate and observed the following:

- SR Neutron Mon CH I is reading 15 cps

- SR Neutron Mon CH II is reading 32 cps Which ONE of the following identifies the action(s) you must take, and the reason(s) for taking the action(s), for the plant conditions given above?

A. Enter Tech Spec 3.9.2, Nuclear Instrumentation. Suspend Control Rod Drive Shaft latching because SR Neutron Mon Ch II is INOPERABLE.

B. Enter AOP-l.01, Nuclear Instrument Malfunction. Suspend Control Rod Drive Shaft latching because both source range instruments are inoperable.

C Announce over PA to evacuate containment. Suspend Control Rod Drive Shaft latching due to an unexpected increase in subcritical multiplication.

D. Enter Tech Spec 3.1.1.2, SHUTDOWN MARGIN (SDM) -Tavg <200°F. Initiate emergency boration per AOP-C.02, Uncontrolled RCS Boron Changes, due to an unexpected increase in subcritical multiplication.

Tuesday, March 12, 2013 9:56:49 AM 62

QUESTIONS REPORT for SQN Dec 2012 RO Exam

63. Given the following plant conditions,

- Unit 1 is operating at 45% power.

- The main turbine suddenly trips.

- During the resultant transient, the OATC observed PZR safety valve 68-566 open at 2280 psig, then reclose.

Which ONE of the following identifies the required Technical Specification actions to be taken in response to this event?

A. Restore the safety valve to operable status within 15 minutes or be in MODE 4 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Restore the safety valve to operable status within 15 minutes or be in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 4 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

C. Restore the safety valve to operable status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 4 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

D. Be in MODE 3 within 15 minutes, MODE 4 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 5 in the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Tuesday, March 12, 2013 9:56:49 AM 63

QUESTIONS REPORT for SQN Dec 2012 RO Exam

64. Given the following conditions:
  • Unit 1 shutdown is on progress.
  • Reactor power is 14% and lowering.
  • Intermediate Range Nl-36 fails HIGH.

Which ONE of the following identifies how the failure of the NI will effect the reactor trip system and the effect the failure will have on the Source Range NIs?

Reactor Trip System Effect on Source Range NIs A. Reactor trip will occur at the Source Range NIs will have to be time of failure. MANUALLY reinstated.

B. Reactor trip will occur at the Source Range NIs will time of failure. AUTOMATICALLY reinstate.

C. Reactor trip will occur if power Source Range NIs will have to be reduction is continued. MANUALLY reinstated.

D. Reactor trip will occur if power Source Range NIs will reduction is continued. AUTOMATICALLY reinstate.

Tuesday, March 12, 2013 9:56:49 AM 64

QUESTIONS REPORT for SQN Dec 2012 RO Exam

65. Prior to an entry into lower containment being made, which ONE of the following identifies the verifications that are required relative to the incore flux detector placement and tagging?

Detector Placement Taqced with a...

A. Storage position, only. Caution Order B. Storage position, only. Hold Order C. Storage position or inserted Caution Order to within lOfeet of the core.

D Storage position or inserted Hold Order to within 10 feet of the core.

Tuesday, March 12, 2013 9:56:49 AM 65

QUESTIONS REPORT for SQN Dec 2012 RO Exam

66. Given the following plant conditions:

- Unit 2 was operating at 100% power when a SG tube rupture develops.

- The reactor is tripped and SI is initiated.

Annunciator 2-RA-90-1 1 9ACNDS VAC PMP LO RNG AIR EXH MON HIGH RAD is in alarm.

Which ONE of the following radiation monitors could be used to determine the specific SG that developed the rupture?

A. Observing 2-RM-90-120 (SG blowdown liquid rad).

B. Observing 2-RM-90-124 (SG sample line monitor).

C. Observing 2-RM-90-255 (Cond vacuum pump exhaust hi rad).

Dv Observing 2-RM-421, 422, 423, 424 (Main steamline high rad).

Tuesday, March 12, 2013 9:56:49AM 66

QUESTIONS REPORT for SQN Dec 2012 RO Exam

67. Which ONE of the following identifies...

(1) the Emergency Response Organization responsible for dispatching Emergency Response Teams during a plant emergency and (2) the lowest level emergency that will result in the emergency center being required to be staffed?

A. Technical Support Center Alert B. Technical Support Center NOUE C. Operations Support Center Alert D. Operations Support Center NOUE Tuesday, March 12, 2013 9:56:49 AM 67

QUESTIONS REPORT for SQN Dec 2012 RO Exam

68. Given the following plant conditions:

- The Shift Manager has declared an ALERT on Unit 1.

- The Shift Manager has requested the Unit 2 CR0 to notify the NRC of the event.

- The ENS phone line in the control room is out of service.

In accordance with EPIP-3,Alert, which ONE of the following indentifies both:

(1) the communication system that you are to use and (2) the briefing guide to use when notifying the NRC?

A. (1) The ENS phone line must be used, contact would be made from another location using ENS.

(2) NRC Event Notification Worksheet from SPP-3.5, Regulatory Reporting Requirements.

B. (1) Any plant telephone line.

(2) NRC Event Notification Worksheet from SPP-3.5, Regulatory Reporting Requirements.

C. (1) The ENS phone line must be used, contact would be made from another location using ENS.

(2) EPIP-3, Appendix D, Notification of the NRC.

D (1) Any plant telephone line.

(2) EPIP-3, Appendix D, Notification of the NRC.

Tuesday, March 12, 2013 9:56:49 AM 68

QUESTIONS REPORT for SQN Dec 2012 RO Exam

69. Given the following plant conditions:

- A transient has occurred on Unit I resulting in the following alarms:

OTDT RUN BACK/ROD STOP ALERT

° ROD CONTROL URGENT FAILURE OPDTRUNBACK

- Reactor power indicates the following:

  • N41 105.2%
  • N42 106.2%
  • N43105.9%
  • N44106.1%
  • Tavgis57l°F Which ONE of the following indicates both:

(1) the accident that has occurred and (2) the action that is required?

A. (1) Uncontrolled Rod Withdrawal, (2) Trip the reactor.

B. (1) Uncontrolled Rod Withdrawal, (2) Place rod control in MANUAL.

C (1) SG Safety Valve opened coincident with a rod control failure, (2) Trip the reactor.

D. (1) SG Safety Valve opened coincident with a rod control failure, (2) Place rod control in MANUAL.

Tuesday, March 12, 2013 9:56:49 AM 69

QUESTIONS REPORT for SQN Dec 2012 RO Exam

70. Given the following plant conditions:

- A small break LOCA occurred on Unit 1.

- ES-I .2, Post LOCA Cooldown and Depressurization, is in progress.

- RCS pressure is 1420 psig and one charging pump has been stopped.

- The crew is ready to stop the first SI pump.

Which ONE of the following completes the statements below?

When the SI pump is stopped, RCS subcooling will drop fiL The minimum RCS subcooling value required to allow the second SI pump to be stopped is 21 than the value required for stopping the first pump.

A. (1) and stabilize at a lower value due to an increase in RCS temperature with lower ECCS injection flow (2) less B. (1) and stabilize at a lower value due to an increase in RCS temperature with lower ECCS injection flow (2) greater C. (I) due to reduced ECCS injection flow and stabilize at a lower value when break flow equals ECCS injection flow.

(2) less D (I) due to reduced ECCS injection flow and stabilize at a lower value when break flow equals ECCS injection flow.

(2) greater Tuesday, March 12, 2013 9:56:49AM 70

QUESTIONS REPORT for SQN Dec 2012 RO Exam

71. Given the following plant conditions:

- A Loss Of Coolant Accident (LOCA) outside containment has resulted in RCS Subcooling dropping to 0 °F.

- The operating crew is performing the actions of ECA-1 .2, LOCA Outside Containment.

- Actions are being taken to isolate the leak.

In accordance with ECA-1 .2 LOCA Outside Containment, which ONE of the following is the initial mitigating strategy and what would be the indication used to confirm the LOCA has been isolated?

A. Ensure RHR suction from RCS Isolated Pressurizer level rising B Ensure RHR suction from RCS Isolated RCS pressure rising C. Isolate RHR Cold Leg Injection Pressurizer level rising D. Isolate RHR Cold Leg Injection RCS pressure rising Tuesday, March 12, 2013 9:56:49 AM 71

QUESTIONS REPORT for SQN Dec 2012 RO Exam

72. Given the following plant conditions:

- The crew is implementing FR-H.1, Loss of Secondary Heat Sink.

- CST level is 25%.

Which ONE of the following describes the correct order of priority for:

(1) the source of feedwater to SGs and (2) the condition of the SGs that are to be fed?

A (1) MDAFW, TDAFW, MEW, Condensate (2) Intact, Ruptured, Faulted B. (1) TDAFW, MEW, Condensate, MDAFW from ERCW (2) Intact, Ruptured only C. (1) MDAEW, TDAFW, MEW, Condensate (2) Intact, Faulted only D. (1) MDAFW, MEW, Condensate, TDAFW from ERCW (2) Intact, Ruptured, Faulted Tuesday, March 12, 2013 9:56:49AM 72

QUESTIONS REPORT for SQN Dec 2012 RO Exam

73. Given the following plant conditions:

- Following a LOCA the crew is required to enter ECA-1 .1, Loss of RHR Sump Recirculation.

Which ONE of the following completes the statement below in accordance with EPM-3-ECA-1.1, Basis Document for ECA-1.1 Loss of RHR Sump Recirculation?

The Initiate RCS cooldown to Cold Shutdown at less than 100°F/hr step will be performed Lfl the step to RCS depressurization to decrease RCS subcooling and the reason for the RCS depressurization is to Lu A. before to refill the pressurizer B before to reduce the break flow C. after to refill the pressurizer D. after toreducethebreakflow Tuesday, March 12, 2013 9:56:49 AM 73

QUESTIONS REPORT for SQN Dec 2012 RO Exam

74. Given the following plant conditions,

- Unit 2 was operating at 100% power when a reactor trip occurs following inadvertent MSIV closure.

- During performance of ES-0.1, Reactor Trip Response, the STA reports 2-FR-0, Status Trees, indicate YELLOW path conditions exist for entry into both FR-H.2, Steam Generator Overpressure and FR-H.3,Steam Generator High Level.

- Steam Generator 3 pressure is currently 1125 psig and the narrow range level is 85%.

Which ONE of the following completes the statements below?

If the SRO implemented the YELLOW path to (1)

A S/G becomes an overfilled S/G11 as described in CAUTIONS in both procedures when its narrow range level first exceeds (2) during the event.

Lfl A. FR-H.2, a transition would be directed to FR-H.3 80%

B. FR-H.3, a transition would be directed to FR-H.2 80%

C FR-H.2, a transition would be directed to FR-H.3 84%

D. FR-H.3, a transition would be directed to FR-H.2 84%

Tuesday, March 12, 2013 9:56:49 AM 74

QUESTIONS REPORT for SQN Dec 2012 RD Exam

75. Given the following plant conditions,

- A LOCA is in progress on Unit 2 and fuel damage has occurred.

- The crew is performing FR-Z.3, High Containment Radiation.

- The CRC has been directed to VERIFY EGTS operation NORMAL.

Which ONE of the following identifies....

(I) an EGTS filter bank AP that is within the normal operating band and (2) the purpose of the charcoal filter on the fan suction?

EGTS Filter Bank AP Purpose of Charcoal filter A. 3.5 to 5.0 water remove cesium and other particulates B 3.5 to 5.0 water remove iodine and other halogen gases C. 9.5to 10.5 water remove cesium and other particulates D. 9.5 to 10.5 water remove iodine and other halogen gases Tuesday, March 12, 2013 9:56:49 AM 75