ML13023A058

Initial Exam 2012-302 Final RO Written Exam

ML13023A058
Person / Time
Site:	Sequoyah
Issue date:	01/22/2013
From:	NRC/RGN-II
To:	Tennessee Valley Authority
References
Download: ML13023A058 (81)

Text

___________

ES-401 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:

Date: Facility/Unit: Sequoyah Station Unit 1 & 2 Region: IEEI lIE llllVE ReactorType: WE CEEI BWE GE Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.

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

Applicants Signature Results Examination Value Points Applicants Score Points Applicants Grade Percent ES-401, Page 30 of 33

Name: Sequoyah Dec 2012 RO Exam Form: 0 Version: 0

1. Given the following plant conditions:

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

- The associated block valve stroked part way closed and the breaker tripped.

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

- RCS pressure is 1600 psig and slowly risinçj.

- IA Safety Injection pump trips.

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

Break flow will (1)

CCPIT flow will (2)

(1) (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 Saturday, November24, 2012 12:07:15 PM

Sequoyah Dec 2012 RO Exam

2. Which ONE of the following choices complete s the statement below?

During a large break LOCA, Reflux boiling is A. significant for heat removal during a Cold Leg break, ONLY.

B. insignificant for heat removal during a Cold Leg break, ONLY.

C. significant for heat removal during both a Hot or Cold Leg break.

D. insignificant for heat removal during either a Hot or Cold Leg break.

Saturday, November 24, 2012 12:07:15 PM 2

Sequoyah Dec 2012 RO Exam

3. Given the following plant conditions:

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

- All RCPs were secured by procedure.

- The core exit T/Cs all indicate >1200°F.

- SG #2 NR level is 30% and rising.

- The Loop 2 RCP is AVAILABLE and STOPPED.

Which ONE of the following completes the statements below?

FR-C.1, Inadequate Core Cooling, directs an RCP will be started (1) 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 (2) 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 Saturday, November 24, 2012 12:07:15 PM 3

Sequoyah Dec 2012 RO Exam

4. Given the following plant conditions,

- Unit 1 is operating at 100% power.

- The running charging pump, lA-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. l-HIC-62-81A only D. 1 -HIC-62-78A and I -HIC-62-81 A Saturday, November 24, 2012 12:07:15 PM 4

Sequoyah Dec 2012 RD Exam

5. Given the following:

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

- lA-A RHR pump in service.

- RHR flow was indicating 2400 gpm.

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

In accordance with AOP-R.03, RHR System Malfunction,u 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) make up to the RCS immediately by opening valve 1 -FCV-63-1, RHR suction from RWST.

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

C. (I) betweenl000gpmandl500gpm (2) stop the IA-A RHR pump, increase the level in the RCS and attempt to restore RHR cooling.

D. (1) between l500gpmand2000gpm (2) stop the IA-A RHR pump, increase the level in the RCS and attempt to restore RHR cooling.

Saturday, November 24, 2012 12:07:15 PM 5

Sequoyah Dec 2012 RO Exam

6. Given the following plant conditions,

- Unit I 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.

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

Saturday, November 24, 2012 12:07:15 PM 6

Sequoyah Dec 2012 RO Exam

7. 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.

Saturday, November 24, 2012 12:07:15 PM 7

Sequoyah Dec 2012 RO Exam

8. 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 / 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.

Saturday, November 24, 2012 12:07:15 PM 8

Sequoyah Dec 2012 RO Exam

9. 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-Sl-SXX-068-127.0, RCS Pressurizer and Temperature and Pressure Limit, requires the SRO and Nuclear Engineering to be first notified if the pressurizer surge line z\T exceeds (1) and if 1-PIC-68-340B is adjusted to 100% it will (2) the spray flow into the pressurizer when the auxiliary spray valve is opened.

ti-I A. 320°F lower B. 320°F raise C. 560°F lower D. 560°F raise Saturday, November24, 2012 12:07:15 PM 9

Sequoyah Dec 2012 RO Exam

10. Given the following plant conditions,

- Unit #1 was operating at 100% power when S/G #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 S/G #1 during performance of E-2?

A. To minimize CST depletion.

B. To minimize the potential of rupturing a S/G tube.

C. To minimize the RCS cooldown and mass and energy release.

D. To minimize the thermal stress on the tube sheet.

Saturday, November 24, 2012 12:07:15 PM 10

Sequoyah Dec2012 RO Exam

11. Given the following plant conditions,

- Unit I 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:

TIME 1-Ll-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 Saturday, November 24, 2012 12:07:15 PM 11

Sequoyah Dec 2012 RO Exam

12. Given the following plant conditions,

- Unit 2 is at 100% power.

- CSST B is aligned to the I 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 overcurrent 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 Saturday, November24, 2012 12:07:15 PM 12

Sequoyah Dec 2012 RO Exam

13. 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 PORVs D. NOT Established Raise steam flow through Steam Dumps Saturday, November 24, 2012 12:07:15 PM 13

Sequoyah Dec 2012 RO Exam

14. Given the following plant conditions:

- Unit I is at 100% power.

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

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

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

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 Saturday, November24, 2012 12:07:15 PM 14

Sequoyah Dec 2012 RO Exam

15. Given the following plant conditions:

- Unit I was operating at 100% power.

- A Loss Of Coolant Accident (LOCA) outside containment results 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 action taken and what would be the indication used to confirm the LOCA has been isolated?

A. Isolate RHR suction from RCS Pressurizer level rising B. Isolate RHR suction from RCS RCS pressure rising C. Isolate RHR Cold Leg Injection Pressurizer level rising D. Isolate RHR Cold Leg Injection RCS pressure rising Saturday, November 24, 2012 12:07:15 PM 15

Sequoyah Dec 2012 RO Exam

16. Given the following:

- A LOCA has occurred on Unit #1

- The crew is implementing 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?

Initiation of RCS cooldown to Cold Shutdown at less than 100°F/hr will be performed (1) RCS depressurization to decrease RCS subcooling and the reason for the RCS depressurization is (2)

(1) (21 A. before to refill the pressurizer B. before to reduce the break flow C. after to refill the pressurizer D. after to reduce the break flow Saturday, November 24, 2012 12:07:15 PM 16

Sequoyah Dec 2012 RO Exam

17. Given the following plant conditions:

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

- CST level is 25%.

Per FR-H.1, 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, MFW, Condensate, MDAFW from ERCW (2) Intact, Ruptured only C. (1) MDAFW, TDAFW, MEW, Condensate (2) Intact, Faulted only D. (1) MDAFW, MEW, Condensate, TDAFW from ERCW (2) Intact, Ruptured, Faulted Saturday, November 24, 2012 12:07:16 PM 17

Sequoyah Dec 2012 RO Exam

18. Given the following plant conditions:

- Unit 1 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 Saturday, November 24, 2012 12:07:16 PM 18

Sequoyah Dec 2012 RO Exam

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

A. Prevents a fuel assembly in the mast from being dropped.

B. Prevents bridge or trolley movement without assembly full up.

C. Prevents intentional shutdown of the manipulator crane.

D. Prevents movement of the fuel transfer cart from the SEP side to the Rx side.

Saturday, November 24, 2012 12:07:16 PM 19

Sequoyah Dec2012 RO Exam

20. 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 statements below?

An excessive depressurization rate of the leakincj steam generator can result in (1)

The preferred method of cooling a leakinc steam generator is by the use of (2)

A. (1) closure of intact SG MSIVs (2) MSIV bypass valve B. (1) inability to maintain required RCS subcooling (2) Steam Generator Blowdown C. (1) closure of intact SG MSIVs (2) Steam Generator B lowdown D. (1) inability to maintain required RCS subcooling (2) MSIV bypass valve Saturday, November 24, 2012 12:07:16 PM 20

Sequoyah Dec 2012 RO Exam

21. 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, S/G 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 Saturday, November 24, 2012 12:07:16 PM 21

Sequoyah Dec 2012 RO Exam

22. 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 Saturday, November 24, 2012 12:07:16 PM 22

Sequoyah Dec 2012 RO Exam

23. Given the following plant conditions,

- Unit I is operating at 100% power.

0800 The OATC places 1-HS-62-104A, CHARGING PUMP B, to STOP PULL TO LOCK after a fire is reported in the 1 B CCP room.

0810 Fire Operations extinguishes the fire and an investigation determines the room cooler motor and fan are destroyed but the 1 B CCP has no damage.

0810 The lB CCP room door has been blocked open to ventilate the room due to room temperature of 106°F.

0810 The OATC restores 1.-HS-62-104A, CHARGING PUMP B, to A AUTO.

0900 The room temperature is 102°F and slowly lowering.

1000 The room temperature is 84°F and the door is closed.

1100 The room cooler is repaired and room temperature is 82°F.

Which ONE of the following identifies (I) the earliest time the 1 B CCP is AVAILABLE and (2) the earliest time the 18 CCP is OPERABLE?

A. (1) 0810 (2) 1000 B. (1) 0810 (2) 1100 C. (1) 1000 (2) 1000 D. (1) 1000 (2) 1100 Saturday, November 24, 2012 12:07:16 PM 23

Sequoyah Dec 2012 RO Exam

24. 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 sicinificant 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 1 -RM-90-1 06 1 -RM-90-l 19 A. Stable Rising B. Stable Stable C. Rising Rising D. Rising Stable Saturday, November 24, 2012 12:07:16 PM 24

Sequoyah Dec 2012 RO Exam

25. 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/G as described in CAUTIONS in both procedures when its narrow range level first exceeds (2) during the event.

(1) (2)

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%

Saturday, November 24, 2012 12:07:16 PM 25

Sequoyah Dec 2012 RO Exam

26. 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 CR0 has been directed to VERIFY EGTS operation NORMAL.

Which ONE of the following identifies....

(1) 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. 9.5 to 10.5 water remove cesium and other particulates D. 9.5to 10.5 water remove iodine and other halogen gases Saturday, November 24, 2012 12:07:16 PM 26

Sequoyah Dec 2012 RO Exam

27. 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 (1)

The minimum RCS subcooling value required to allow the second SI pump to be stopped is (2j 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 EGGS injection flow and stabilize at a lower value when break flow equals EGGS injection flow.

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

(2) greater Saturday, November 24, 2012 12:07:16 PM 27

Sequoyah Dec 2012 RO Exam

28. 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, SG #3 steam flow and level A. rises; rises B. rises; lowers C. lowers; lowers D. lowers; rises Saturday, November 24, 2012 12:07:16 PM 28

Sequoyah Dec 2012 RO Exam

29. 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 Saturday, November 24, 2012 12:07:16 PM 29

Sequoyah Dec 2012 RD Exam

30. 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. lA-A SI Pump would cavitate.

B. NO ECCS pumps would cavitate.

C. lA-A Containment Spray pump would cavitate.

D. Both the lA-A and the lB-B CCPs would cavitate.

Saturday, November24, 2012 12:07:16 PM 30

Sequoyah Dec 2012 RO Exam

31. Given the following plant conditions:

- Unit I 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 I -FCV-74-1 6, RHR HTX A Outlet.

C. 120V AC Vital Instrument Power Board 1-Il.

D. 480V Shutdown Board IAI-A.

Saturday, November 24, 2012 12:07:16 PM 31

Sequoyah Dec 2012 RO Exam

32. Given the following plant conditions:

- A LOCA has occurred on Unit 1.

- 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 CCPs.

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.

Saturday, November 24, 2012 12:07:16 PM 32

Sequoyah Dec 2012 RO Exam

33. 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 anincreaseinPRT (1)

After the heaters are energized to establish a steam bubble, the bubble is confirmed (2) provided the RCS pressure is stable or slowly increasing.

w 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 Saturday, November 24, 2012 12:07:16 PM 33

Sequoyah Dec 2012 RO Exam

34. 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.

Saturday, November 24, 2012 12:07:16 PM 34

Sequoyah Dec 2012 RD Exam

35. Given the following plant conditions:

- Unit I 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-70-1 92 temperature input is failing high. Reactor power will rise slightly.

B. TCV-70-1 92 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.

Saturday, November 24, 2012 12:07:16 PM 35

Sequoyah Dec 2012 RO Exam

36. Given the following plant conditions:

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

- The setpoint on 1-PIC-68-340A, PZR Pressure Control, is changed 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 rise.

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

Saturday, November24, 2012 12:07:16 PM 36

Sequoyah Dec2012 RO Exam

37. 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 lnhibiV position.

- The Reactor Trip Breakers RTA, BYA and RTB 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.

Saturday, November 24, 2012 12:07:16 PM 37

Sequoyah Dec 2012 RD Exam

38. Given the following plant conditions:

- Unit us 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-Mi-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-0.1, 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-0.1 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 i25v DC Vital Battery Board while continuing in ES-0.1.

Saturday, November 24, 2012 12:07:16 PM 38

Sequoyah Dec 2012 RO Exam

39. Given the following plant conditions:

- Unit I 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 Saturday, November24, 2012 12:07:16 PM 39

Sequoyah Dec 2012 RD Exam

40. 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 LCD 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. Either an inlet or Inlet doors intermediate deck door D. Either an inlet or Intermediate doors intermediate deck door Saturday, November 24, 2012 12:07:16 PM 40

Sequoyah Dec 2012 RO Exam

41. 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 1 B-B trips when attempting to start.

- During performance of ES-I .3, Transfer To RHR Containment Sump 1-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 9.3 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.

C. 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.

Saturday, November24, 2012 12:07:16 PM 41

Sequoyah Dec 2012 RO Exam

42. Given the following plant conditions:

- Unit 1 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-i I 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, & III HI NEG RATE STMLINE PRESS lights on 1-XX-55-6B illuminate and then extinguish.

- I M-6B-B3, PS-A-2AR HIGH NEGATIVE RATES STEAMLINE PRESSURE LOOP 2, is in alarm.

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.

Saturday, November 24, 2012 12:07:16 PM 42

Sequoyah Dec 2012 RO Exam

43. 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.

Saturday, November 24, 2012 12:07:16 PM 43

Sequoyah Dec 2012 RO Exam

44. 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 SGs 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?

Note:

PT-1-33, Main Steam Header Pressure PT-3-1, Feedwater Header Pressure CAUSE OPERATOR ACTION A. Common sensing line to PT-i -33 Place feedwater reg valve controllers for has developed a leak; all 4 SGs in MANUAL and lower main feedwater flow.

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

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

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

Saturday, November 24, 2012 12:07:16 PM 44

Sequoyah Dec 2012 RO Exam

45. Which ONE of the following identifies the correct power supply to I -FCV-3-1 36B Auxiliary Feedwater ERCW Supply MOV?

A. 480v Unit Bd IA.

B. 480v C & A Vent Bd IA1-A.

C. 480v Rx MOV Bd 1A2-A.

D. l25vBatteryBdl Saturday, November 24, 2012 12:07:16 PM 45

Sequoyah Dec 2012 RO Exam

46. Which ONE of the following identifies the source and flow path of the cooling water for the TDAFW pump 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 Saturday, November 24, 2012 12:07:16 PM 46

Sequoyah Dec 2012 RO Exam

47. Given the following plant conditions:

- Unit I at 100% RTP.

- Operators are performing 0-SO-250-2,120 Volt AC Vital Instrument Power System, to remove 1-Il inverter from service and transfer the board to the spare inverter.

- As operators operate the 120V AC Vital Instrument Power Board 1-Il transfer switch to the ALTERNATE position, the following indications are noted:

• Annunciator 120V AC VITAL POWER BOARD 1-Il UV OR BKR TRIP is received. (1 M-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 Verify 120V AC Vital Instrument Power Board for the transfer. 1-Il voltage remains stable after the switch is fully positioned per 0-SO-250-2.

B. The indications are expected Verify 120V AC Vital Inverter 1-Il AC OUTPUT for the transfer. AMPS are zero per 0-SO-250-2.

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.

Saturday, November 24, 2012 12:07:16 PM 47

Sequoyah Dec 2012 RO Exam

48. Given the following plant conditions,

- Unit I 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 IA-A FAILURE OR BUS FEEDER UV/OVERVOLTAGE (1-M-1B) 6900 SD BD IA-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.

Saturday, November 24, 2012 12:07:16 PM 48

Sequoyah Dec 2012 RO Exam

49. Given the following plant conditions:

- Unit 1 is operating at 100% power.

- The 125 V DC Power System is normally aligned.

- The supply breaker from 480 V Shutdown Board IA1-A to Vital Battery Charger I trips open.

- Spare 125 V Battery Charger 1-S is in standby alignment.

- No operator action is taken.

Which ONE of the following statements describes the effect of this failure on the 125 V DC Vital Battery Board I?

A. The board is deenergized.

B. The board remains energized from the battery.

C. The board is automatically energized by its maintenance supply.

D. The board is automatically energized by the spare battery charger.

Saturday, November 24, 2012 12:07:16 PM 49

Sequoyah Dec 2012 RO Exam

50. The following conditions exist on Unit 1:

- Annunciator, P5-82-162 DIESEL GEN IA-A START AIR PRESS LOW ENG 1 OR 2 ( M26-A-C-1 ) 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 1A1 engine.

- The receiver air pressures currently are: IA1(A) at 100 psig and rising IA1(B) at 195 psig and stable.

Which ONE of the following identifies the status of IA-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 1AI(B) air receiver pressure is adequate to start the lA-A diesel.

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

Saturday, November 24, 2012 12:07:16 PM 50

Sequoyah Dec 2012 RO Exam

51. Which ONE of the following identifies the effect on Unit 2 EDGs if the Unit I Train A ERCW Supply header lost all flow?

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

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.

Saturday, November 24, 2012 12:07:16 PM 51

Sequoyah Dec 2012 RO Exam

52. Given the following plant conditions:

- Unit I is operating at 100% power.

- Annunciator1-RA-120A/121A STM GEN BLDN LIQ SAMP MON HI RAD is in alarm.

- The indicator for RM-90-I 20 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.

Saturday, November 24, 2012 12:07:16 PM 52

Sequoyah Dec 2012 RD Exam

53. Given the following plant conditions:

- The plant was at 100% power.

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

- Offsite power was lost to 6.9KV Start Bus I B.

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

- No other operator actions have been taken.

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

The J-A ERCW pump breaker closes seconds after the bus is energized.

If the J-A ERCW pump switch is taken to STOP and returned to A-AUTO the pump will A. (1) 15 (2) stop and restart B. (1) 20 (2) stop and stay off C. (1) 15 (2) stop and stay off D. (1) 20 (2) stop and restart Saturday, November 24, 2012 12:07:16 PM 53

Sequoyah Dec 2012 RO Exam

54. Given the following plant conditions:

- 6.9kV Shutdown Board IA-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.

Saturday, November24, 2012 12:07:16 PM 54

Sequoyah Dec 2012 RO Exam

55. 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

- UPRILWR 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. Enter TS 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. Enter TS 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 />.

Saturday, November 24, 2012 12:07:16 PM 55

Sequoyah Dec 2012 RO Exam

56. Given the following plant conditions:

- Unit I 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.

Saturday, November 24, 2012 12:07:16 PM 56

Sequoyah Dec 2012 RO Exam

57. 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 I -RE-90-1 06, Lower Containment Radiation Monitor.

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

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

1-LI-77-410A 98% -

1-LI-77-411A -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 LCO 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) LCO 3.4.6.1 Action is required.

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

(2) LCO 3.4.6.1 Action is required.

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

(2) LCO 3.4.6.1 Action is NOT required.

Saturday, November 24, 2012 12:07:16 PM 57

Sequoyah Dec 2012 RO Exam

58. 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.

Saturday, November 24, 2012 12:07:16 PM 58

Sequoyah Dec 2012 RO Exam

59. Given the following plant conditions:

- Unit I initially operating at 100% power

- AFD at -3.4%

- Annunciator window 1 -M-4B-C-7, ZB-442C BANK D AUTO ROD WITHDRAWAL BLOCKED, lit

- A feedwater malfunction induces a transient.

- The crew stabilizes Unit I at 80% power

- The OAC reports that Control Bank D rod M8 is indicating 28 steps withdrawn

- All 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 Saturday, November 24, 2012 12:07:16 PM 59

Sequoyah Dec 2012 RO Exam

60. 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 & A Vent Bd 1A2-A D. 480V Shutdown Bd 1A2-A Saturday, November 24, 2012 12:07:16 PM 60

Sequoyah Dec 2012 RO Exam

61. Given the following plant conditions:

- Both Units are at 100% power.

- Annunciator TIS-78-4 SPENT FUEL PITS TEMPERATURE HIGH (IM6D-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:

(1) whether the alarm is valid and (2) in accordance with AOP-M.06, Loss of Spent Fuel Pool Cooling, the appropriate method to stabilize temperature for the given conditions?

Alarm Method to stabilize temperature A. Valid Raise CCS flow through SEP Heat Exchanger A B. Valid Raise SFPC pump flow through SEP Heat Exchanger A C. Invalid Raise CCS flow through SEP Heat Exchanger A D. Invalid Raise SEPC pump flow through SEP Heat Exchanger A Saturday, November 24, 2012 12:07:16 PM 61

Sequoyah Dec 2012 RD Exam

62. Given the following plant conditions,

- Unit 2 is operating at 100% power.

- SG#2 NR levels indicate: 1-LI-3-55 1-Ll-3-52 1-LI-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.

Saturday, November 24, 2012 12:07:16 PM 62

Sequoyah Dec 2012 RO Exam

63. Given the following plant conditions;

- Unit I is operating at 100% power when CBP IA 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 (1) 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 (2) to reduce the risk of a unit trip if any additional secondary plant malfunctions occurs.

w L)

A. 250 85%

B. 250 75%

C. 320 85%

D. 320 75%

Saturday, November 24, 2012 12:07:16 PM 63

Sequoyah Dec 2012 RO Exam

64. 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%.

Saturday, November 24, 2012 12:07:16 PM 64

Sequoyah Dec 2012 RO Exam

65. Which ONE of the following is a direct input to 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 Saturday, November 24, 2012 12:07:16 PM 65

Sequoyah Dec2012 RO Exam

66. Given the following:

- Unit I at 100% power with Boric Acid Tank (BAT)A aligned.

- RWST Boric Acid concentration is 2550 ppm.

Which ONE of the following identifies BAT A Volume and Boric Acid Concentration that will meet Operability requirements?

REFERENCE PROVIDED A. 9600 gallons at 6500 ppm B. 9400 gallons at 6575 ppm C. 9250 gallons at 6775 ppm D. 9750 gallons at 6375 ppm Saturday, November 24, 2012 12:07:16 PM 66

Sequoyah Dec 2012 RO Exam

67. Given the following plant conditions:

- Unit 1 is in Mode 3 with RCS temperature at 547°F and pressure 2235 psig.

- Annunciator TS-68-31 6, 317 PRESSURIZER SPRAY LINES TEMP LOW alarms. (IM5A 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 STABLE or RISING B. Loop 3 is idle Pressurizer surge line temperature STABLE or RISING C. Pressurizer spray Pressurizer surge line bypass flow LOW temperature DROPPING D. Loop 3 is idle Pressurizer surge line temperature DROPPING Saturday, November 24, 2012 12:07:16 PM 67

Sequoyah Dec 2012 RO Exam

68. Given the following conditions:

- Unit I is operating at 9 X 10-1% power with startup in progress at EOL.

- Intermediate Range startup rate is 0 DPM.

- 1-PlC-I -33, STM DUMP PRESS CONTROL, is in AUTO at its normal setting.

Which ONE of the following would occur if I -PlC-I -33 controller set point was changed to 1115 psig?

Tavg would (1) and the reactor power would (2)

(j_)

A. decrease increase B. decrease decrease C. increase increase D. increase decrease Saturday, November 24, 2012 12:07:16 PM 68

Sequoyah Dec 2012 RO Exam

69. 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 />.

B. 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 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 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 />.

Saturday, November24, 2012 12:07:16 PM 69

Sequoyah Dec 2012 RO Exam

70. Given the following conditions:

• Unit I shutdown is on progress.

• Reactor power is 14% and lowering.

• Intermediate Range N 1-36 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 tripped at the Source Range Nls will have to be current conditions. MANUALLY reinstated.

B. Reactor tripped at the Source Range NIs will current conditions. 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.

Saturday, November 24, 2012 12:07:16 PM 70

Sequoyah Dec 2012 RO Exam

71. 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 19A CNDS VAC PMP LO RNG AIR EXH MON HIGH RAD is in alarm.

If the operators suspect SG-3 is ruptured, which ONE of the following radiation monitors could be used to confirm 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).

D. Observing 2-RM-423 (Main steamline high rad).

Saturday, November 24, 2012 12:07:16 PM 71

Sequoyah Dec 2012 RO Exam

72. 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 Taqçjed with a...

A. Storage position, only. Caution Order B. Storage position, only. Hold Order C. Storage position or inserted Caution Order to within 10 feet of the core.

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

Saturday, November 24, 2012 12:07:16 PM 72

Sequoyah Dec 2012 RD Exam

73. 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?

w A. Technical Support Center Alert B. Technical Support Center NOUE C. Operations Support Center Alert D. Operations Support Center NOUE Saturday, November24, 2012 12:07:16 PM 73

Sequoyah Dec 2012 RO Exam

74. 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 EPlP-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.

Saturday, November 24, 2012 12:07:17 PM 74

Sequoyah Dec 2012 RD Exam

75. Given the following plant conditions:

- An ATWS has occurred on Unit 1.

- When the operator places 1-HS-47-24, TURBINE TRIP, to the TRIP position the turbine trip buses fail to actuate.

Which ONE of the following identifies...

(1) the indicating light that will be LIT on 1-HS-47-24 and (2) the first action the operator is directed to take due to the turbine trip failure in accordance with FR-S.1, Nuclear Power Generation! ATWS?

Li)

A. RED Close MSIVs and Bypasses B. RED Manually runback turbine C. GREEN Close MSIVs and Bypasses D. GREEN Manually runback turbine You have completed the test!

Saturday, November 24, 2012 12:07:17 PM 75

References for 1211 NRC RO Exam

1. Steam Tables

2. Mollier Diagram

3. NDR-S1CI7 figure 2-4 Control and Shutdown Rod Locations (page 23)

4. TRM Figure 3.1.2.6 rev 26

A AR EVA Document No.: 61-9175754-000 NDR SIC19 PROPRIETARY Figure 2-3 Control and Shutdown Rod Locations R P N M L K J H G F E D C B A SP SA CB CC GB SP 2 SD SB SB SC 3 SP CD CD CD SA 4

SC SA SP SA SD 5 GB CC CA CC GB 6 SB SP SB SP 7 900 CC CD CA CD CA CD CC 8 SP SB SP SB 9 GB CC CA CC GB 10 SD SA SP SA SC 11 SA CD GD CD SP 12 SC SB SB SD 13 SP GB CC GB SA 14 SP I S

• Bank Identifier Number of Locations Bank Identifier Number of Locations

• SA 8 GA 4

• SB 8 GB 8 SC 4 CC 8

• SD 4 CD 9 SP (srare 12 Page 22

TRM FIGURE 3.1.2.6 (Units I & 2)

BORIC ACID TANK LIMS BASED ON RWST BORON CONCENTRATION 11000 EGION_OF ACCEPTABLE OPERATION j tc 1 0500 L LRT=250ppmB I

RWST = 2550 ppm B L 10000

/i RWST = 2600 ppmT 7j-cII I i I

\%%

Co z A RWST = 2650 ppm B:

0

-I

-J 9500 ]

Ui II 9000

- 6120_ppm (M rum urn)

I 8500 I

i 990_ppm (Maximum)

]

8000 I

I I 7500 I cIoo UNACCEPTABLE OPERATION 7000 fliecYVai u11 gal unusable volume and 800 ga for nstrunt error 6500 I 1 ;__1 6000 6100 6200 6300 6400 6500 6600 6700 6800 6900 7000 7100 BORIC ACID TANK CONCENTRATION - PPM BORON RWST Connfration

--2500 PPM --2550PPM 4--2600 PPM 2650PPM o2700 PPM SEQUOYAH UNITS I AND 2 314 1-10 September 26, 2003 TECHNICAL REQUIREMENTS Revtsion Nos. 13, 26, 27

ANSWER KEY REPORT for Sequoyah Dec 2012 RO Exam Test Form

0

1. ID Answers Points Type 0 1 008 AK1.02 1 1.00 MCS B 2 O11EK1.012 1.00 MCS D 3 015AA2.113 1.00 MCS B 4 022 AA1.01 4 1.00 MCS D 5 025 AA1.09 5 1.00 MCS C 6 026 AK3.03 6 1.00 MCS D 7 027 AK2.03 7 1.00 MCS C 8 029 G2.1.30 8 1.00 MCS D 9 038 G2.2.12 9 1.00 MCS A 10 040 AK3.04 10 1.00 MCS C ii 054AA2.0711 1.00 MCS A 12 055 EA2.03 12 1.00 MCS B 13 056AK1.0413 1.00 MCS C 14 058 EG2.2.38 14 1.00 MCS B 15 W/E04 EK2.0l 15 1.00 MCS D 16 W/E11 EK3.2 16 1.00 MCS B 17 W/EO5EAI.1 17 1.00 MCS A 18 077 AK2.03 18 1.00 MCS A 19 036 AK3.02 19 1.00 MCS B 20 037 AA1.0120 1.00 MCS C 21 059AK2.0121 1.00 MCS A 22 060 AK3.02 22 1.00 MCS B 23 067 AG2.2.37 23 1.00 MCS B 24 076 AK2.01 24 1.00 MCS C 25 W/E13 EA2.1 25 1.00 MCS C 26 W/E16 EK1.1 26 1.00 MCS B 27 W/E03 EAI.3 27 1.00 MCS D 28 003 K5.04 28 1.00 MCS C 29 004 K5.08 29 1.00 MCS C 30 005 K1.12 30 1.00 MCS B 31 005 K6.03 31 1.00 MCS A 32 006 G2.4.20 32 1.00 MCS A 33 007 K5.02 33 1.00 MCS B 34 008 A3.05 34 1.00 MCS D 35 008 A4.09 35 1.00 MCS D 36 O1OK1.0336 1.00 MCS B 37 012A3.0637 1.00 MCS B 38 013A2.0538 1.00 MCS D 39 022 K4.03 39 1.00 MCS D 40 025 K6.01 40 1.00 MCS A 41 026 A2.03 41 1.00 MCS B 42 039 Al .06 42 1.00 MCS C 43 059 K3.04 43 1.00 MCS A 44 059 A2.03 44 1.00 MCS C 45 061 K2.01 45 1.00 MCS C 46 061 K4.1346 1.00 MCS C Saturday, November 24, 2012 1:21:33 PM I

ANSWER KEY REPORT for Sequoyah Dec 2012 RO Exam Tes t Form: 0

1. ID A ncwnrc Points Type 0 47 062 Al.03 47 1.00 MCS D 48 062 G2.4 49 48 1 00 MCS C 49 063 A3.01 49 1.00 MCS B 50 064 K6.07 50 1.00 MCS C 51 064 G2.2.4 51 1.00 MCS D 52 073 K3.0l 52 1.00 MCS A 53 076 K4.02 53 1.00 MCS A 54 078 K2.02 54 1.00 MCS C 55 103 K3.01 55 1.00 MCS B 56 001 K3.02 56 1.00 MCS A 57 002 A3.01 57 1.00 MCS D 58 O1IAI.0358 1.00 MCS C 59 014K1.0259 1.00 MCS D 60 028 K2.01 60 1.00 MCS A 61 033 G 2.4.46 61 1.00 MCS A 62 035 K6.03 62 1.00 MCS C 63 056 A2.04 63 1.00 MCS C 64 071 K5.04 64 1.00 MCS D 65 075 K4.01 65 1.00 MCS B 66 G 2.1.25 66 1.00 MCS C 67 G 2.1.45 67 1.00 MCS C 68 G 2.2.1 68 1.00 MCS D 69 G 2.2.22 69 1.00 MCS B 70 G 2.2.44 70 1.00 MCS C 71 G 2.3.5 71 1.00 MCS D 72 G 2.3.12 72 1.00 MCS D 73 G 2.4.29 73 1.00 MCS C 74 G 2.4.43 74 1.00 MCS D 75 G 2.4.49 75 1.00 MCS B SECTION 1 ( 75 items) 75.00 Saturday, November 24, 2012 1:21 :33 PM 2