ML120550249
| ML120550249 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/21/2012 |
| From: | NRC/RGN-II |
| To: | |
| Gerald Laska | |
| References | |
| ES-401-7 | |
| Download: ML120550249 (80) | |
Text
ES-401 Site-Specific RO Wr(tten Examination Form ES-401-7 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:
Date: 02/01/2012 Facility/Unit: SQN Units 1 & 2 Region: I II X Ill IV Reactor Type: W X CE El BW El GE El 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
SEQUOYAH JAN 2012 RD EXAM 2/1/2012
- 1. Given the following:
- Unit 2 is starting up and is at 2% power with the Steam Dump Control System operating as follows:
- Steam Dump Mode Selector Switch (HS-1-103D): STEAM PRESS
- Steam Dump Pressure Controller (PIC-1-33): AUTO
- A spurious Reactor Trip occurs, however Reactor Trip Breaker B fails to open.
Which ONE of the following identifies the steam generator (SG) pressure setpoint immediately after the reactor trip and the required actions to adjust SG pressure?
A. SG pressure corresponding to Tavg of 547F (- 1005 psig)
Use the lever at the bottom of the PlC-I -33 controller.
B. SG pressure corresponding to Tavg of 550°F (- 1026 psig)
Use the lever at the bottom of the PIC-1-33 controller.
C. SG pressure corresponding to Tavg of 547°F (- 1005 psig)
Use the setpoint up/down pushbuttons on the PlC-I -33 controller.
D. SG pressure corresponding to Tavg of 550°F (- 1026 psig)
Use the setpoint up/down pushbuttons on the PIC-1-33 controller.
Page 1
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 2. Given the following plant conditions:
- Unit I is operating at 100% power.
- A small leak has developed on the line connecting the pressurizer to the PORVs.
Which ONE of the following describes the initial response of the pressurizer pressure control and level control systems?
Pressurizer Pressure Controller Charging Flow Controller I -PIC-68-340A 1 -HIC-62-93A A. output will INCREASE output will INCREASE B. output will INCREASE output will DECREASE C. output will DECREASE output will INCREASE D. output will DECREASE output will DECREASE Page 2
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 3. Given the following plant conditions:
- A reactor trip and safety injection has occurred concurrent with a loss of off-site power.
- RCS pressure is 1500 psig and slowly lowering.
- The crew has transitioned to E-1, Loss of Reactor or Secondary Coolant.
- Containment pressure 2.9 psig and slowly rising.
Which ONE of the the following describes the level band that the Steam Generators are required to be maintained between and why?
A. 10-50%; to provide a static head of water to prevent primary to secondary leakage.
B. 25-50%; to provide a static head of water to prevent primary to secondary leakage.
C. 10-50%; to ensure an adequate SG inventory to maintain a heat sink.
D. 25-50%; to ensure an adequate SG inventory to maintain a heat sink.
Page 3
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 4. Given the following plant conditions:
- A large break LOCA has occurred on Unit 1.
- ES-I .3, Transfer to RHR Containment Sump, was completed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago.
- A loss of offsite power has just occurred.
Which ONE of the following describes a manual action required to be taken in response to this event?
A. STOP/PULL TO LOCK the Containment Spray pumps.
B. STOP/PULL TO LOCK Safety Injection Pumps.
C. STOP/PULL TO LOCK the RHR pumps.
D. STOP/PULL TO LOCK the CCPs.
Page 4
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 5. Given the following plant conditions:
- Unit 1 is operating at 100% power.
- The following alarms are received on M-27B-A:
- CCS REAC BLDG SUPPLY HEADER FLOW LOW
- RC PUMPS THRM BARRIER RETURN HEADER FLOW LOW
- RC PUMP 1 THRM BARRIER OUTLET FLOW LOW
- RC PUMP 2 THRM BARRIER OUTLET FLOW LOW
- RC PUMP 3 THRM BARRIER OUTLET FLOW LOW
- RC PUMP 4 THRM BARRIER OUTLET FLOW LOW
- RC PUMP I OIL COOLERS OUTLET FLOW LOW
- RC PUMP 2 OIL COOLERS OUTLET FLOW LOW
- RC PUMP 3 OIL COOLERS OUTLET FLOW LOW
- RC PUMP 4 OIL COOLERS OUTLET FLOW LOW
- Seal injection flow rate to each RCP is 8 gpm.
Which ONE of the following identifies how the operation of the RCPs will be affected if the operators do not respond to the alarms?
A. The RCPs are designed to operate without CCS indefinitely.
B. The RCPs will experience seal failure.
C. The RCP stator windings will overheat.
D. The RCP motor bearings will overheat.
Page5
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 6. Given the following plant conditions:
AT 10:00, Unit 1 plant conditions were as follows:
- 100% steady state power.
- The following parameters are observed:
- Letdown flow: 75 gpm as indicated on 1-Fl-62-82
- Total charging flow: 85 gpm as indicated on 1-Fl-62-93A
- Seal Injection flow: 10 gpm per RCP
- Seal return flow: 3 gpm per RCP At 12:00, Unit I plant conditions were as follows:
- 100% steady state power.
- 1-FCV-62-93, Charging Flow Control Valve, has failed closed.
- Normal letdown cannot be established.
- The following parameters are observed:
- Total charging flow: 40 gpm as indicated on 1-Fl-62-93A
- Seal injection flow: 10 gpm per RCP
- Seal return flow: 3 gpm per RCP Which ONE of the following identifies the trend in Pressurizer level at 10:00 and 12:00?
Pressurizer level at 10:00 was _(1) and pressurizer level at 12:00 was _(2)_.
(1) (2)
A. Increasing Increasing B. Increasing Decreasing C. Decreasing Increasing D. Decreasing Decreasing Page 6
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 7. Given the following plant conditions:
- Unit 2 RCS has been drained to 695lO during a refueling outage, per 0-GO-I 3, Reactor Coolant System Drain and Fill Operations.
- The reactor vessel head is in place but bolts are NOT tightened.
- Containment sump level starts increasing.
- Annunciator RCS MID LOOP LEVEL LOW (M6-C, A7) alarms.
- Running RHR pump amps are observed cycling between 20 and 40 amps.
Which ONE of the following identifies the procedure that is required to be entered to mitigate the event?
B. 0-SO-74-1, Residual Heat Removal System.
C. AOP-R.03, RHR System Malfunction.
D. AOP-R.05, RCS Leak and Leak Source Identification.
Page 7
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 8. Given the following plant conditions,
- The Unit 1 Main Control Room has been abandoned.
- The transfer switches per AOP-C.04, Shutdown from the Auxiliary Control Room, have been placed in the AUX position.
- Aux Control Room alarm PS-68-336AC RCS PRZR PRESS HI has just been received.
Which ONE of the following identifies the lowest RCS pressure when the alarm is received and where the PZR Backup heaters will be operated?
RCS Pressure Location A. 2310 psig 6.9 KvShutdown Boards 1A-A& lB-B B. 2310 psig 1-L-10, Auxiliary Control Room C. 2335 psig 6.9 Ky Shutdown Boards IA-A & 1 B-B D. 2335 psig 1-L-10, Auxiliary Control Room Page8
SEQUOYAH JAN 2012 RD EXAM 2/1/2012
- 9. Given the following plant conditions:
- Unit 1 is responding to an ATWS per FR-S.1, Nuclear Power Generation I ATWS.
- Power is lost to all of panel 1-M-2.
Which ONE of the following would the CRC utilize for indication of turbine stop valves being closed?
A. P-9 TURBINE TRIP/ REACTOR TRIP annunciator on Reactor First Out panel.
B. TV-I through TV-4 CLOSED lights on the EHC Control panel 1-XX-47-1 000.
C. Dispatch AUO to verify turbine stop valves closed on EHC local panel.
D. All 4 status lights Turb. Stop Valves Closed lit on 1 -XX-55-6A.
Page 9
SEQUOYAH JAN 2012 RD EXAM 2/1/2012
- 10. Given the following plant conditions:
- Unit I is operating at 100% power.
- ASGTRoccurs.
- The crew manually trips the reactor and initiates safety injection.
- Offsite power is lost on the trip.
- The crew is performing actions in E-3, Steam Generator Tube Rupture, to minimize break flow and refill the pressurizer.
In accordance with E-3, which ONE of the following identifies:
(1) the method that is attempted first to depressurize the RCS and (2) a potential consequence of performing this action?
A. (1)using a PZR PORV (2) PRT rupture disk ruptures.
B. (1) using Auxiliary Spray (2)thermal shock of PZR spray nozzle.
C. (1)using a PZR PORV (2) interruption of natural circulation flow.
D. (1) using Auxiliary Spray (2) PZR cooldown limit will be exceeded.
Page 10
SEQUOYAH JAN 2012 RO EXAM 2/1/2012 Ii. Given the following plant conditions:
- A Reactor Trip and SI has occurred on Unit 2 from 100% power.
- All SGs are depressurizing in an uncontrolled manor.
- The crew was unable to isolate any of the SGs.
- All SG levels are less than 10% NR.
- RCS cooldown rate is greater than 100°F/hr.
In accordance with ECA-2.1, Uncontrolled Depressurization of All Steam Generators, which ONE of the following identifies the correct action to take concerning AFW flow and the reason for the action?
A. Reduce AFW flow to 0 to each SG to stop RCS cooldown.
B. Reduce AFW flow to 50 gpm to each SG to prevent SG dryout.
C. Reduce AFW flow by 50 gpm to each SG to minimize RCS cooldown.
D. Reduce AFW flow to 440 gpm to prevent a required entry into FR-H.1, Loss of Secondary Heat Sink.
Page 11
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 12. Given the following plant conditions:
- Unit 2 is operating at 52% power.
- 2B MFP is in service.
- Due to excessive vibrations, the 2B MFP needs to be shutdown.
- Just as the 2A MFP has been reset and is ready to be placed in service the2BMFPtrips.
- Immediately following the Reactor Trip, the following SG NR levels are observed:
- #1 10%
- #2 15%
- #3 20%
- #4 18%
- RCS Tave is maintained at 552° F Which ONE of the following identifies the AFW pump(s) that will be automatically started and the reason why?
A. The 2A MDAFW pump, ONLY, starts due to low level in #1 SG.
B. Both MDAFW pumps, ONLY, start due to the level in #1 SG.
C. Both MDAFW pumps start due to trip of MEW pump.
D. Both MDAFW pumps and the TDAFW pump start due to Rx trip and Lo Tave.
Page 12
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 13. Given the following plant conditions:
- The crew is in ECA-O.O, Loss of All AC Power.
- Maximum cooldown rate allowed is commenced through the atmospheric reliefs.
- During the rapid depressurization of all intact SGs to 160 psig, an overshoot occurs.
- SG pressure is reduced to 50 psig before the depressurization is stabilized.
Which ONE of the following identifies the potential implication that could result from this overshoot in SG depressurization?
A. Natural circulation may be impeded.
B. Unacceptable upper head voiding may occur.
C. The integrity of the RCP seals may be challenged.
D. A Red Path on PTS may occur.
Page 13
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 14. Given the following plant conditions:
- The I B-B DG is tagged for maintenance
- A loss of off-site power has occurred.
- Unit I is responding per AOP-P.O1, Loss of Offsite Power.
- Unit 2 is responding per ECA-0.0, Loss of All AC Power.
- You are an extra UO and have been directed by U2 SRO to perform EA-250-1, Load Shed of Vital Loads After Station Blackout.
Which ONE of the following identifies both:
(1) the time load shedding actions of EA-250-1 are required to be completed and based upon that time (2) which loads will no longer be available after the required dc loads have been load shed?
A. (1) 45 minutes (2) MCR annunciators, permissive lights and SSPS status lights.
B. (1) 45 minutes (2) DC air side seal oil pump.
C. (1) 90 minutes (2) MCR annunciators, permissive lights and SSPS status lights.
D. (1) 90 minutes (2) DC air side seal oil pump.
Page 14
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 15. Given the following plant conditions:
- Unit I isatloo%RTP.
- MCR alarms received indicate that an electrical board has failed.
- All trip status lights on Panel 1-)O(-55-5 (1-M-5) are OFF with the exception of Protection Set 3 Trouble light which is LIT.
- The crew responds in accordance with the appropriate procedure.
Which ONE of the following identifies (1) the electrical board that failed and (2) the reason that manipulation of Auxiliary Feedwater (AFW) controls will be required?
A. 120 VAC Vital Instrument Board 1-I. To prevent overcooling caused by excessive AFW flow due to the LCVs failing open.
B. 120 VAC Vital Instrument Board 1-I. To allow the turbine driven AFW pump to be operated above minimum speed.
C. 120 VAC Vital Instrument Board 1-Ill. To prevent overcooling caused by excessive AFW flow due to the LCVs failing open.
D. 120 VAC Vital Instrument Board 1-Ill. To allow the turbine driven AFW pump to be operated above minimum speed.
Page 15
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 16. Given the following plant conditions:
- The crew entered AOP-M.O1, Loss of Essential Raw Cooling Water, due to high flow on ERCW Supply Header 2A.
- The leak was isolated by closing 2-FCV-67-223, Hdr 2A to Hdr I B Isol Valve.
- The crew completes the applicable section of AOP-M.01.
Which ONE of the following describes the ERCW Supply Header that will be aligned to the CCS heat exchangers after the remaining actions of AOP-M.01 are complete?
Reference Provided 2A112A2 Hx OBI!0B2 Hx IAIIIA2 Hx A. 2A ERCW Supply 2B ERCW Supply lB ERCW Supply Header Header Header B. 2A ERCW Supply ERCW Isolated 1 B ERCW Supply Header to Hx Header C. 2A ERCW Supply 2B ERCW Supply ERCW Isolated Header Header to Hx D. ERCW Isolated 2B ERCW Supply 1 B ERCW Supply to Hx Header Header Page 16
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 17. Given the following plant conditions:
- Both Units were operating at 100% power when a Station Blackout occurs.
- Both unit crews are reponding using ECA-0.0, Loss of All AC Power.
Which ONE of the following is the reason for the backup air supply for the TD AFW Pump LCVs and the action/condition required to align the backup supply?
A. Allows the LCVs to be CLOSED during a Station Blackout event and will require manual alignment locally when needed.
B. Allows the LCVs to be CLOSED during a Station Blackout event and is automatically supplied when air pressure drops below regulator setpoint.
C. Allows the LCVs to be OPENED during a Station Blackout event and will require manual alignment locally when needed.
D. Allows the LCVs to be OPENED during a Station Blackout event and is automatically supplied when air pressure drops below regulator setpoint.
Page 17
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 18. Given the following plant conditions:
- Unit 1 is responding to a Loss of Heat Sink per FR-H.1, Response to Loss of Secondary Heat Sink.
- All Steam Generator Wide Range levels are Off-Scale low.
- RCS temperature is approximately 588°F and rising slowly.
- Core Exit Thermocouples are 605° F and rising slowly.
Which ONE of the following describes the preferred method of initiating Auxiliary Feed flow for these conditions?
A. Feed at the maximum available feed flow to all S/Gs to reestablish SG inventory and secondary heat sink.
B. Feed at 50 to 100 gpm to one SG to prevent possible tube failures.
C. Feed at the maximum available feed flow to one S/G to reestablish SG inventory and secondary heat sink.
D. Feed at 50 to 100 gpm to all SGs to establish a controllable cooldown rate and prevent RCS pressure from reaching the PORV setpoint.
Page 18
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 19. Given the following plant conditions:
- Unit 2 is at 12% reactor power during a plant startup.
- The OATC reports that Rod H4 has dropped into the core.
- The crew enters AOP-C.O1, Rod Control System Malfunctions.
- While monitoring Tave the OATC reports RCS temperature at 540°F.
- PZR pressure is 2225 psig.
Which ONE of the following identifies the required actions and why?
A. Recover the control rod within 1 hr to prevent exceeding Enthalpy Rise Hot Channel Factor ( F AH).
B. Recover the control rod within 1 hr to ensure Moderator Temperature Coefficient remains within assumed values.
C. Immediately trip the reactor because the Enthalpy Rise Hot Channel Factor (EN AH ) value has been exceeded.
D. Immediately trip the reactor because the Moderator Temperature Coefficient may be outside the initial conditions assumed in accident analysis.
Page 19
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 20. Given the following plant conditions:
- Unit I tripped from 100% power.
- 1-FCV-62-135, RWST to CCP Suction is tagged closed for maintenance.
- The OATC is directed to perform EA-68-4, Emergency Boration.
- The OATC reports that neither Boric Acid Transfer pump will shift to fast speed.
Based on the above conditions, which ONE of the following identifies the flow path that meets the requirements of EA-68-4 for Emergency Boration?
A. Normal boration via FCV-62-140 & 144.
B. Emergency Boration via FCV-62-1 38.
C. Alternate Emergency Boration via VLV-62-929.
D. RWST via FCV-62-1 36.
Page 20
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 21. Given the following:
- Unit 1 is in Mode6.
- An irradiated assembly is in the manipulator crane and is being transferred from an incore location to the upender.
- The Refueling SRO determines a leak has developed in the Reactor Cavity Seal.
- No assemblies are in the RCCA change fixture.
In accordance with AOP-M.04, Refueling Malfunctions, which ONE of the following identifies the required action to be taken with the fuel assembly?
A. Place the fuel assembly in the upender and transport to the SFP.
B. Place the fuel assembly in the upender and lower the upender.
C. Place the fuel assembly in the RCCA change fixture.
D. Place the fuel assembly in any core location.
Page 21
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 22. Given the following plant conditions:
- Unit 1 is operating at 100% power.
- Unit 2 is in Mode 6 for a refueling outage.
- Chemistry reports that a sample of the Turbine Bldg sump exceeds the limit for ODCM sect 1.2.1.1 Radioactive Effluents; Liquid Effluents.
Which ONE of the following identifies (1) the reason for the declaring 0-RM-90-21 2 Station Sump Discharge rad monitor inoperable and (2) how the station sump pump discharge will be aligned?
A. (1) The radiation monitor failed to alarm.
(2) to the LVWT pond with the L valve closed B. (1) The radiation monitor failed to alarm (2) to the LVWT pond with the L valve open.
C. (1) The radiation monitor failed to alarm and isolate the release.
(2) to the LVWT pond with the L valve closed D. (1) The radiation monitor failed to alarm and isolate the release.
(2) to the LVWT pond with the L valve open.
Page 22
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 23. Given the following plant conditions:
- Unit I is at 100% power.
- Chemistry Lab is performing a sample of the reactor coolant system.
- PZR level starts dropping rapidly.
- A manual Reactor Trip and Safety Injection have been initiated.
- Containment pressure is 3.5 psig.
- While performing ES-O.5, Equipment Verifications, the CR0 observes that the RCS sample valves 1-FSV-43-22 and 1-FCV-43-23 status lights are red.
- All other status lights for CNMNT VENT; PHASE A; and PHASE B on panel 6K and 6L are green.
Which ONE of the following identifies the correct CRC response to the window indication?
A. The valves are in the correct position for an RCS sample; continue with the support system verification.
B. Contact Chemistry and direct them to secure Zinc Injection.
C. Initiate a manual Containment Phase B isolation signal on both A and B trains.
D. Immediately dispatch personnel to close both 1-FSV-43-22 and 1-FCV-43-23.
Page 23
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 24. Given the following plant conditions:
- Unit I was operating at 100% power.
- Reactor Trip and Safey Injection have occurred.
- The following plant conditions are observed:
- RCS pressure is 1100 psig and slowly rising.
- CETs 720°F and slowly rising.
- Containment pressure 3.1 psig and slowly lowering.
- RVLIS Lower Range 40% and slowly lowering.
- All required procedural actions have been taken.
Which ONE of the following identifies both:
(1) the procedure that is required to be entered and (2) the method used to depressurize the RCS, when directed by procedure?
A. (1) FR-C.1, Inadequate Core Cooling (2) Steam Dump Valves B. (1) FR-C.1, Inadequate Core Cooling (2) ATM Relief Valves C. (1) FR-C.2, Degraded Core Cooling (2) Steam Dump Valves D. (1) FR-C.2, Degraded Core Cooling (2) ATM Relief Valves Page 24
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 25. Given the following plant conditions,
- Unit I was operating at 100% power.
- The TD AFW pump is tagged out of service for maintenance.
- A Pressurizer PORV fails open.
- Reactor Trip and SI have actuated.
- 6.9 kV I B-B SD board trips on a differential fault and locks out.
- The associated PORV block valve was closed by the OATC.
- Total AFW flow to #1 & #2 SGs 460 gpm.
Which ONE of the following parameters would prevent SI from being terminated?
A. RCS pressure 1850 psig and stable.
B. All SG levels less than 10% and slowly lowering.
C. RCS subcooling 48°F and slowly lowering.
D. Pressurizer level is 8% and slowly increasing.
Page 25
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 26. Given the following plant conditions:
- The crew entered FR-H.2, Steam Generator Overpressure, due to an overpressure condition on SG #2.
- SG #2 pressure is 1170 psig.
- SG #2 narrow range level is 82%.
Which ONE of the following describes the appropriate actions, in sequence, to mitigate this event in accordance with FR-H.2?
A. First Isolate AFW flow and then initiate SG Blowdown.
B. First Verify Feedwater Isolation and then initiate SG Blowdown.
C. First Isolate AFW flow and then attempt to dump steam from the affected SG.
D. First Verify Feedwater Isolation and then attempt to dump steam from the affected SG.
Page 26
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 27. Given the following plant conditions:
- Unit I is responding to a LOCA.
- ES-i .3, Transfer To RHR Containment Sump, was completed and containment recirculation cooling is in progress.
- The STA has identified a yellow path on containment radiation.
Which ONE of the following identifies a high level action performed in FR-Z.3, High Containment Radiation, to minimize the effects of the high containment radiation condition?
A. VERIFY Phase A isolation.
B. VERIFY ABGTS operation.
C. VERIFY Containment Ventilation Isolation.
D. VERIFY Containment Spray remains in operation.
Page 27
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 28. Given the following plant conditions:
- Unit 1 is at 30% power.
- #2 RCP trips on overcurrent.
Which ONE of the following identifies how the indicated level in #2 SG initially responds and the effect of RCP trip on reactor status?
SG #2 Level Reactor Status A. Decrease RCP trip generates an automatic reactor trip.
B. Decrease Manual reactor trip is required due to RCP tripping.
C. Increase RCP trip generates an automatic reactor trip.
D. Increase Manual reactor trip is required due to RCP tripping.
Page 28
SEQUOYAH JAN 2012 RD EXAM 2/1/2012
- 29. Given the following plant conditions:
- Unit 1 is at 20% power.
- Excess Letdown had been placed in service while normal letdown was unavailable.
- Operators then return normal letdown to service.
Which ONE of the following identifies the expected response of #1 and #2 RCP seal leakoff flows when Excess Letdown is removed from service?
A. #1 seal leakoff rises.
- 2 seal leakoff rises.
B. #1 seal leakoff rises.
- 2 seal lea koff drops.
C. #1 seal leakoff drops
- 2 seal leakoff rises.
D. #1 seal leakoff drops.
- 2 seal leakoff drops.
Page 29
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 30. Given the following plant conditions:
- Unit I is operating at 100% power.
- 1-FCV-62-89, Charging Seal Water Flow Control Valve, is operating at 60% open.
- The RCP seal injection flows indicated in the Main Control Room are:
LOOP I = 8.4 gpm LOOP 2 = 8.3 gpm LOOP 3 = 9.8 gpm LOOP 4 = 9.4 gpm
- 1-FCV-62-89 suddenly drifts resulting in the following indications:
LOOP I = 5.4 gpm LOOP 2 = 5.3 gpm LOOP 3 = 6.8 gpm LOOP 4 = 6.4 gpm
- Assume NO adjustments have been made to 1-FCV-62-93, Charging Flow Control Valve.
Which ONE of following identifies both:
(1) the direction I -FCV-62-89 drifted and (2) the required operator action, if any?
A. (1) Further in the Closed direction; (2)Adjust 1-FCV-62-89 OPEN until all RCP seal injection flows are > 6.0 gpm.
B. (1) Further in the Closed direction; (2)Adjust 1-FCV-62-93 OPEN until all RCP seal injection flows are > 6.0 gpm.
C. (1) Further in the Open direction; (2)Adjust 1-FCV-62-89 CLOSED until all RCP seal injection flows are > 6.0 gpm.
D. (1) Further in the Open direction; (2) Adjust 1-FCV-62-93 CLOSED until all RCP seal injection flows are > 6.0 gpm.
Page 30
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 31. Given the following plant conditions:
- Unit 2 is in Mode 6 with core off-load ready to commence.
- A reactor cavity seal failure has just occurred.
- The crew has entered AOP-M04, Refueling Malfunctions.
- Cavity makeup from the RWST has been established in accordance with Appendix A, Filling Refueling Cavity From RWST.
Which ONE of the following identifies the alignment directed by AOP-M.04 for the RHR pumps and CCP5 if the RWST level drops below 5%?
RHR pumps CCPs A. Place in P-T-L Place in P-T-L B. Place in P-T-L Align suction to VCT C. Align suction to Place in P-T-L RCS Loop 4 hot leg D. Align suction to Align suction to VCT RCS Loop 4 hot leg Page 31
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 32. Given the following plant conditions:
- Unit 2 is at 100% power.
- A Reactor Trip and Safety Injection occurs.
Which ONE of the following identifies the effect this event has on RCP seal injection and RCP seal return?
A. Both RCP seal injection from CCPs and seal return to the VCT are isolated.
B. Neither RCP seal injection nor seal return to VCT are affected.
C. Only RCP seal injection from CCPs is isolated.
D. Only RCP seal return to the VCT is isolated.
Page 32
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 33. Given the following plant conditions:
- A small break LOCA has occurred.
- The crew is in ES-I .2, Post LOCA Cooldown and Depressurization.
- One RCP is operating.
- One CCP is operating.
- RCS Pressure is 1600 psig and stable.
- RCS subcooling is 72°F and stable.
- Two SI Pumps are in service.
Which ONE of the following describes how the plant and subcooling margin respond if one of the running SI pumps trips?
Subcoolinci Margin Plant Response A. Decreases RCS pressure will decrease.
B. Decreases RCS break flow will remain constant.
C. Remains the same Injection flow from the running SI pump increases.
D. Remains the same RCS pressure will remain constant.
Page 33
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 34. Given the following plant conditions:
- The OATC on Unit 2 has been directed to lower the level in PRT using 2-SO-68-5, Pressurizer Relief Tank.
- The RCDT pump hand switches are aligned for normal operation.
- The OATC opens 2-FCV-68-310, PRT Drain to RCDT.
Which ONE of the following identifies how the B RCDT pump is stopped?
A. Automatically when the OATC closes 2-FCV-68-31 0.
B. Automatically when the level in the PRT reaches 50%.
C. Manually by the AUO when the level in the PRT reaches 50%.
D. Manually by the AUO when directed by the OATC prior to closing 2-FCV-68-31 0.
Page 34
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 35. Given the following plant conditions:
- IA-A, 2B-B, and C-S CCS pumps are normally aligned and running.
- I B-B and 2A-A CCS pumps are aligned in Standby Auto.
- Unit 2 Start Buses 2A and 2B are inadvertantly de-energized.
- All 4 EDG5 started and operated as expected.
Which ONE of the following describes the response of the CCS system to these conditions?
A. All running CCS pumps will be load shed and will automatically start after the shutdown boards are energized.
B. 2B-B and C-S CCS pumps will be load shed, Only 2A-A and 2B-B CCS pumps will automatically start after the shutdown boards are energized.
C. 2B-B CCS pump will be load shed, Only 2A-A and 2B-B CCS pumps will automatically start after the shutdown boards are energized.
D. 2B-B and C-S CCS pumps will be load shed, 2A-A, 2B-B and C-S CCS pumps will automatically start after the shutdown boards are energized Page 35
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 36. Given the following conditions,
- Unit2isinMode5.
- The crew is preparing to draw a bubble in PZR per 0-GO-I, Unit Startup From Cold Shutdown to Hot Standby.
- Pressurizer is in water solid condition.
- The crew is performing actions to draw a bubble in the PZR.
With RCS Wide Range pressure at 150 psig, which ONE of the following identifies the temperature of the pressurizer liquid when a bubble starts to form?
A. 333-335° F B. 341-347°F C. 353-358°F D. 373-381°F Page 36
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 37. Given the following:
- Unit I isat 100% power.
- A loss of I 25V DC Vital Battery Board I occurs.
Which ONE of the following describes the effect on the Reactor Trip Breaker?
A. MCB indication is lost for RTA and BYA; breakers will NOT open on a Reactor Trip signal.
B. MCB indication is lost for RTB and BYB; breakers will NOT open on a Reactor Trip signal.
C. MCB indication is lost for RTA and BYA; breakers will open on a Reactor Trip signal.
D. MCB indication is lost for RTB and BYB; breakers will open on a Reactor Trip signal.
Page 37
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 38. Given the following plant conditions:
- Unit 1 is at 45%.
- Bypass breaker BYB is racked in and closed.
- PROTECTION SYSTEM TRAIN B TROUBLE (1-M6A-E-3) is in alarm.
- Electrical Maintenance is working on RTB.
Which ONE of the following identifies the effect that a loss of one of the I 5v or 48v power supplies inside the Train A SSPS logic cabinet will have on plant operation?
A. Failure of a single I 5v power supply will cause a reactor trip, but failure of a single 48v power supply will NOT.
B. Failure of a single 48v power supply will cause a reactor trip, but failure of a single 1 5v power supply will NOT.
C. A reactor trip will NOT occur due to a failure of a single I 5v or single 48v power supply.
D. A reactor trip will occur due to a failure of either a single 1 5v or a single 48v power supply.
Page 38
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 39. Given the following plant conditions:
- A loss of 120V AC Vital Instrument Power Board 1-I has occurred.
- Unit I reactor is tripped and the crew has implemented E-0, Reactor Trip or Safety Injection.
- The OATC has just reported that PZR pressure transmitter I -PT-68-334 (Channel II) failed LOW.
Which ONE of the following describes the plant response?
(Assume NO operator action)
A. SI master relays on both trains of SSPS would actuate AND both trains of ECCS equipment would start.
B. SI master relays on both trains of SSPS would actuate AND only B train ECCS equipment would start.
C. Only the B train SSPS SI master relays would actuate AND both trains of ECCS equipment would start.
D. Only the B train SSPS SI master relays would actuate AND only B train ECCS equipment would start.
Page 39
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 40. Given the following plant conditions:
- A Safety Injection occurred 30 minutes ago on Unit 1 due to a faulted SIC that is now depressurized.
- The crew has transitioned to ES-i .1. SI Termination.
- Reactor trip breaker A failed to open and remains closed.
- Both Safety Injection Reset pushbuttons have been depressed.
- Both Safety Injection Pump control switches have been placed to STOP and returned to A-AUTO.
Assuming 3 seconds has elapsed since the last switch manipulaton, which ONE of the following describes the status of Safety Injection Train A and Safety Injection Pump IA-A?
TrainA Pump lA-A A. RESET Running B. NOT RESET Running C. RESET Stopped D. NOT RESET Stopped Page 40
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 41. Given the following plant conditions:
- Unit 2 is at 100% power.
- 6.9 kv Shutdown Board 2B-B trips on a differential fault.
- All D/Gs functioned as designed.
Which ONE of the following is a result of this condition?
A. Train B RHR pump will be available when the blackout sequencer times out.
B. Feedwater flow is increased due to more demand by the S/G level program.
C. Available forced flow from the upper compartment coolers is reduced.
D. Unit runback will occur due to loss of HDT Pump.
Page 41
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 42. Which ONE of the following statements identifies both the Tech Spec 3.6.5.1, Ice Condenser, maximum containment ice bed temperature and a potential effect of operating above the maximum temperature?
Maximum Temp. Potential Effect A. 20°F Exceeding 12 psig inside Containment during a LOCA B. 20°F Exceeding 12 psig inside Containment during a Steam Line Break C. 27°F Exceeding 12 psig inside Containment during a LOCA D. 27°F Exceeding 12 psig inside Containment during a Steam Line Break Page 42
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 43. Given the following plant conditions:
- Unit 2 has experienced a Reactor Trip and SI due to a Steamline Break inside Containment.
- Phase B has actuated.
- The CR0 reports that neither 2A-A nor 2B-B CCS pump is running and they will NOT start.
Which ONE of the listed pumps, is expected to experience bearing failure within 10 minutes?
A. 2A-A Centrifugal Charging Pump.
B. 2A-A Safety Injection System Pump.
C. 2A-A Residual Heat Removal Pump.
D. 2A-A Containment Spray Pump.
Page 43
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 44. Given the following plant conditions:
- A plant cooldown is in progress.
- RCS pressure is 1850 psig.
- RCS temperature is 525°F.
- All required actions have been taken for the cooldown in accordance with 0-GO-7, Unit Shutdown from Hot Standby to Cold Shutdown.
An event occurs:
- RCS pressure is 1700 psig and lowering at 10 psi per second.
- SG pressures are 700 psig and lowering at 25 psi per second.
- Containment pressure is 1.2 psig and rising.
Assuming NO operator action, which ONE of the following describes the ESF actuation status?
A. Safety Injection AND Main Steam Line Isolation have occurred.
B. Safety Injection has occurred; Main Steam Line Isolation has NOT.
C. Main Steam Line Isolation has occurred; Safety Injection has NOT.
D. NEITHER Main Steam Isolation NOR Safety Injection have occurred.
Page 44
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 45. Given the following plant conditions:
- Unit 1 is at 72% power.
- PT-I -33, Steam Header Pressure to DCS, indicates 930 psig.
- PT-i -33A, Steam Header Pressure to DCS, indicates 900 psig.
- PT-i -338, Steam Header Pressure to DCS, indicates 895 psig.
- PT-i -338 fails Low.
Which ONE of the following describes the INITIAL effect this failure will have on the Unit 1 Main Feed Pump Turbine Master speed controller?
A. Output Increases.
B. Output Decreases.
C. Output remains the same.
D. Transfers to Manual and output remains the same.
Page 45
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 46. Given the following conditions:
- Unit 1 was operating at 100% power when a reactor trip occurs.
- Normal post trip conditions are observed except for the following:
- Neither MD AFW pump will start.
- The TD Trip/Throttle Valve Position is RED.
- Turbine AFP Speed on indicator 1-SI-46-56A, reads 0.
- With no operator action, 2 minutes after the Reactor Trip, 1-FCV-1-16, SG-4 Steam Supply to Turbine AFP is RED.
- AFW flow is observed to all SGs.
Which ONE of the following identifies (1) why 1 -FCV-1 -16 opened and (2) how the SG levels will be controlled?
A. (1) TD pump discharge pressure was <100 psig for >60 seconds.
(2) Manually by controlling TD AFP speed to maintain level 10 to 50%.
B. (1) TD pump discharge pressure was <100 psig for >60 seconds.
(2) Automatically by operation of TD LCVs maintaining level at 33%.
C. (1) TD pump discharge pressure was 100 psig less than SG pressure for 5 seconds.
(2) Manually by controlling TD AFP speed to maintain level 10 to 50%.
D. (1) TD pump discharge pressure was 100 psig less than SG pressure for 5 seconds.
(2) Automatically by operation of TD LCVs maintaining level at 33%.
Page 46
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 47. Given the following plant conditions:
- Unit 2 is in Mode 3 preparing for startup.
- Start Bus Selector switches are in Manual
- C CSST is inadvertently deenergized.
- 2B-B Diesel fails to start.
- RCS pressure is 2100 psig.
Which ONE of the following identifies the pressurizer heater groups that will automatically energize to control RCS pressure?
A. Backup heater groups 2A-A, 2B-B, and 2C only B. Backup heater groups 2A-A and control heater group 2D only C. Backup heater group 2A-A and 2C only D. Backup heaters groups 2A-A, 2B-B, and control heater group 2D only Page 47
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 48. Given the following plant conditions:
- Unit 2 is at 85% power.
- The following alarm is received:
- Annunciator 125V DC VITAL CHGR III FAIL/VITAL BAT Ill DISCHARGE.
- The CR0 reports that Battery Board Ill voltage indicates 0 volts.
Assuming NO operator action, which ONE of the following describes the impact on Unit 2?
A. All MSIVs will close.
B. Reactor Power will increase.
C. Reactor will Trip on high pressurizer level.
D. Control Air Compressors C and D will unload.
Page 48
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 49. Given the following plant conditions:
- Unit 1 at 100% power.
- Panel M-1 B Annunciator Window 6900V SD BD IA-A FAILURE OR BUS UNDERVOLTAGE/OVERVOLTAGE alarms.
- The crew enters AOP-P.05, Loss Of Unit I Shutdown Boards.
- A reactor trip occurs on high PZR pressure.
Which ONE of the following identifies the allowed usage of AOP-P.05 after the Emergency Operating Procedure network is entered following the reactor trip?
Continued performance of AOP-P.05 is A. allowed after the crew enters ES-0.1, Reactor Trip Response because ES-0.1 is NOT an accident mitigation EOP.
B. allowed after the crew enters ES-0.1, Reactor Trip Response because restoring power could have an impact on meeting the goals of the EOP.
C. NOT allowed until the crew exits ES-0.1, Reactor Trip Response because the procedure reader must remain dedicated to the EOP in effect until the EOPs are exited.
D. NOT allowed until the crew exits ES-0.1, Reactor Trip Response because actions taken in AOP-P.05 could degrade the performance of the EOP.
Page 49
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 50. Given the following plant conditions:
- Both Units are at 100% power
- All four Diesel Generators are in standby alignment.
Which ONE of the following completes the statement below?
As the ambient air temperature rises diesel generator operability is first required to be determined based on the number of operable (1) when the ambient temperature exceeds (2)
(1) (2)
A. Exhaust fans only 99.3°F B. Exhaust fans and Generator & Electrical Panel Vent fan 99.3°F C. Exhaust fans only 104°F D. Exhaust fans and Generator & Electrical Panel Vent fan 104°F Page 50
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 51. Given the following plant conditions:
- Unit I isatlO0%RTP.
- Alarm 1-RA-120B/121B STM GEN BLDN LIQ SAMP MON INSTR MALFUNC (M-1 2A-B6) annunciates.
Which ONE of the following describes the cause of the alarm and the mitigating actions that the crew would implement?
Cause Mitigating Action A. Loss of power to the Verify automatic termination of radiation monitor SIC blowdown release.
B. Loss of power to the Place the standby monitor in service radiation monitor C. High flow through the Verify automatic termination of radiation monitor S/G blowdown release.
D. High flow through the Place the standby monitor in service radiation monitor Page 51
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 52. Given the following plant conditions:
- Unit I was at 100% power when a manual SI is initiated.
Which ONE of the following describes the automatic response of the ERCW system?
1-FCV-67-146, CCS Hx IAI and 1A2 ERCW Return to Header B (1) and 0-FCV-67-152, CCS HXs OBI and 0B2 Discharge to B Discharge Header _(2)_.
A. (1) CLOSES (2) REPOSITIONS to 35% position B. (1) remains AS IS (2) remains CLOSED C. (1) remains AS IS (2) REPOSITIONS to 35% position D. (1) OPENS fully (2) remains CLOSED Page 52
SEQUOYAH JAN 2012 RD EXAM 2/1/2012
- 53. Given the following plant conditions:
- Unit I is in MODE 3 following a shutdown.
- A loss of Auxiliary Air occurred.
- Auxiliary Feedwater was aligned as directed by AOP-M.02, Loss Of Control Air to support current plant operations.
- EA-3-4, Local Alignment of TD AFW LCV Backup Air Supply has been implemented.
Which ONE of the following completes the statement below?
The operators will use (1) to restore Auxiliary Feedwater valve operation to normal and bottle pressure must be at least (2) to meet the OPERABILITY requirements following the restoration of the plant air systems.
A. (1) EA-3-4 (2) 800 psig B. (1) EA-3-4 (2) 1500 psig C. (1) 0-SO-32-1, Control Air System (2) 800 psig D. (1) 0-50-32-1, Control Air System (2) 1500 psig Page 53
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 54. Given the following plant conditions:
- Unit I is at 98% power.
- The Channel Ill Containment HIGH-HIGH PRESS, pressure switch is out of service for surveillance testing, and its bistable is in BYPASS.
- The associated Channel Ill HIGH PRESS, bistable has been TRIPPED.
- A voltage spike causes the Channel II Containment HIGH PRESS, pressure switch to fail HIGH.
Which ONE of the following describes both, (1) the Containment Isolation system response, and (2) the procedure the crew would use to mitigate this event?
Containment Isolation response Procedure A. Phase B AOP-l.05, Containment Instrument Malfunction B. Phase B E-0, Reactor Trip or Safety Injection C. Phase A AOP-l.05, Containment Instrument Malfunction D. Phase A E-0, Reactor Trip or Safety Injection Page 54
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 55. Given the following plant conditions:
- Unit 2 is operating at 100% power.
- Alarm LS-68-53A/B REAC COOL PMP 2 OIL RESERVOIR LEVEL HI-LOW (M5-B) has just been received.
- An emergency containment entry is being prepared to allow maintenance to add oil to the #2 RCP motor lower bearing from the remote fill line.
In accordance with 0-Pl-OPS-000-01 1.0, Containment Access Control, which ONE of the following identifies both:
(1) the chemical that is evaluated prior to making the containment entry and (2) the method used to control personnel exposure if the chemical is not within its limits?
A. (1) Formaldehyde (2) Containment Purge B. (1) Formaldehyde (2) Containment Air Return Fans C. (1) Oxygen (2) Containment Purge D. (1) Oxygen (2) Containment Air Return Fans Page 55
SEQUOYAH JAN 2012 RD EXAM 2/1/2012 56.
Given the following plant conditions:
- Unit I is shutdown.
- All RCS temperatures are approximately 300°F.
- RCS Pressure is 600 psig.
- Cold overpressure protection is armed.
- Both PORVs are closed.
- Loop 3 cold leg temperature instrument 1-Tl-68-60 fails LOW.
Which ONE of the following identifies the plant response to this instrument failure?
Reference Provided A. PORV-334 will open and remain open.
B. PORV-340 will open and remain open.
C. PORV-334 will open until pressure is below the lift setpoint.
D. PORV-340 will open until pressure is below the lift setpoint.
Page 56
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 57. Which ONE of the following identifies aN nuclear instruments that are powered from 120V AC Vital Instrument Power Board 1-I?
A. N-31 and N-41 pjjy B. N-35 and N-41 2fl1Y C. N-31andN-35Qfly D. N-31, N-35, and N-41 Page 57
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 58. Which ONE of the following identifies the primary function of the Isolation Amplifier associated with the Pressurizer Pressure Transmitters?
A. Protects the Pressurizer Pressure Control circuit.
B. Protects the Solid State Protection System circuit.
C. Amplifies the pressure output signal between containment and the instrument rack.
D. Amplifies the pressure output signal between the instrument rack and the main control room.
Page 58
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 59. Given the following plant conditions:
- Both Units are operating at 100% power.
- Alarm, LS-78-3 SPENT FUEL PIT LEVEL HIGH-LOW, (M6-D, D3) has just been received.
- The Aux Bldg AUO reports a leak on the discharge of the in-service Spent Fuel Pit Cooling Pump.
Assuming NO operator action, which ONE of the choices correctly completes the following statement?
Spent Fuel Pit level lowers until the running pump A. begins to cavitate at the NPSH limit.
B. trips on low spent fuel pit level interlock.
C. becomes air-bound when the suction line uncovers.
D. becomes air-bound when the anti-siphon holes uncover.
Page 59
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 60. Given the following plant conditions,
- Unit 1 is in Mode 6.
- Refueling activities are in progress.
- A fuel assembly has been damaged during removal from the core.
- AOP-M.04, Refueling Malfunctions, is in progress.
Which ONE of the following would provide the FIRST indications in the control room of a developing leak from the damaged fuel assembly?
A. Annunciator l-RA-90-106A CNTMT BLDG LWR COMPT AIR MON HI RAD (1-M12-A, A4) alarms and slowly rising counts on 1-RM-90-59A, Reactor Building Area Rad Monitor.
B. Annunciator0-RA-90-1O1AAUX BLDG VENT MONITOR HI RAD (0-M12-B, BI) and slowly rising counts on I -RM-90-1 30A and 131 A Containment Purge Exhaust Monitors.
C. Annunciators CONTAINMENT VENTILATION ISOLATION TRAIN A or TRAIN B (1-M6-C, C-5 & C-6 respectively) and rapidly rising counts on 1-RM-1 I2AIB/C Upper Containment Air Monitor D. Annunciator 1-RA-90-59A RX BLDG AREA RAD MON HIGH RAD, and slowly rising counts on 1-RM-90-106, Containment Lower Compartment Radmonitor.
Page 60
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 61. Given the following plant conditions:
- Unit 2 is at 50% RTP with rod control selector switch in Manual.
- Turbine Impulse PT-i -73 fails low.
Assuming NO operator action, which ONE of the following identifies the effect, if any, on the Distributed Controls System (DCS)?
A SG Level Control will NOT be affected B. SG Level Control will switch to Manual on all 4 SGs.
C. SG Level will decrease flow initially and level will stabilize at 33%.
D. SG Level will increase flow resulting in Feed Water Isolation at 81% level.
Page 61
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 62. Given the following plant conditions:
- Unit I is shutdown and at NOP and NOT
- Chemistry reports the Hydrogen concentration in A Waste Gas Decay tank at 5% by volume and Oxygen concentration at 3% by volume.
Which ONE of the following describes the gas concentration, if any, that exceeded the Unit I Tech Spec 3.11.2.5 limit for waste gas decay tanks?
A. Oxygen only.
B. Hydrogen only.
C. Neither Hydrogen or Oxygen.
Page 62
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 63. Given the following plant conditions:
- Both Units are at 100% power
- 0-RM-90-103A, Spent Fuel Pit Radiation Monitor, fails HIGH Which ONE of the following indentifies the expected plant response?
A. ONLY Train B ABGTS cleanup fan starts; ONLY Train B Aux. Building General Supply, Exhaust and Fuel Handling exhaust fans trip.
B. ONLY Train B ABGTS cleanup fan starts; ALL Aux. Building General Supply, Exhaust and Fuel Handling exhaust fans trip.
C. BOTH Train A and Train B ABGTS cleanup fans start; ONLY Train B Aux. Building General Supply, Exhaust and Fuel handling exhaust fans trip.
D. BOTH Train A and Train B ABGTS cleanup fans start; ALL Aux. Building General Supply, Exhaust, and Fuel handling exhaust fans trip.
Page 63
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 64. Given the following plant conditions:
- Both units are operating at 100% power.
- Control air system pressure begins to drop.
Which ONE of the following identifies...
(1) the pressure setpoint that the 0-PCV-33-4, Service Air isolation from Control Air, will close and (2) the expected position of 0-FCV-32-82, Train A Control Air Supply Valve, if the air pressure is stabilized at 73 psig?
0-PCV-33-4 0-FCV-32-82 A. 88 psig Open B. 88 psig Closed C. 77 psig Open D. 77 psig Closed Page 64
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 65. Given the following plant conditions,
- Both Units are operating at 100% power.
- Several fire alarms are received from the Unit I Auxiliary Building (charging pump area and cross zone detectors are in alarm).
- An AUO is sent to investigate.
- A Unit 2 CR0 reports that neither the electric fire pump nor the diesel fire pump is running.
- 0-Pl-26-299, Fire Protection Header Pressure reads 108 psig and lowering.
- Prior to a report from the Aux Bldg AUO, the IA-A charging pump trips and LCV-62-132, VCT Outlet To CCP, indicates CLOSED.
- The crew has implemented AOP-N.01, Plant Fires.
Which ONE of the following identifies the expected plant response to the above conditions and the required procedure actions?
A. (1) The fire pumps would not be required to start for these conditions.
(2) Go to AOP-M.09, Loss of Charging.
B. (1) The fire pumps would not be required to start for these conditions.
(2) Go to AOP-N.08, Appendix R Fire Safe Shutdown.
C. (1) Manually start the Electric Fire pump from 0-M-29.
(2) Go to AOP-M.09, Loss of Charging.
D. (1) Manually start the Electric Fire pump from 0-M-29.
(2) Go to AOP-N.08, Appendix R Fire Safe Shutdown.
Page 65
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 66. Given the following plant conditions:
- Unit 1 has automatically tripped from 100% and SI has actuated.
- The crew is performing actions in E-0, Reactor Trip or Safety Injection.
- You are the At the Controls operator.
- The following conditions exist:
- RCS temperature is 540°F and lowering
- RCS pressure is 1400 psig and stable
- Containment pressure is 3 psig and rising.
- The Unit Supervisor has reached step 8, CHECK RCP trip criteria,
- The Unit Supervisor states OATC, Check RCS pressure less than 1250 psig AND At least one CCP or SI pump RUNNING.
In accordance with OPDP-1, Conduct of Operations, which ONE of the following is the correct method to communicate the requested information to the Unit Supervisor?
A. RCS pressure is NOT less than 1250 psig and at least one CCP or SI pump is running.
B. Yes, RCS pressure is NOT less than 1250 psig and at least one CCP or SI pump is running.
C. No, (Name), RCS pressure is 1400 psig and stable and all CCPs and SI pumps are running.
D. Yes, (Name), RCS pressure is NOT less thanl25O psig, it is 1400 psig and all CCP and SI pumps are running.
Page 66
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 67. Given the following plant conditions:
- Unit 1 is in Mode 5 and has just achieved water solid condition.
- RHR Train A is operating in shutdown cooling mode.
- RCS is at 160°F.
- VCT temperature is 115°F.
- #2 RCP was the only RCP running and was inadvertently stopped 10 minutes ago after a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> run.
Which ONE of the following identifies the requirements that must be met prior to attempting a restart of the #2 RCP?
A. Must wait 30 minutes from the time the pump was stopped and can be restarted with current plant conditions.
B. Must wait 30 minutes from the time the pump was stopped but a steam bubble must be established in the Pressurizer.
C. No time restriction on restarting the pump and can be restarted with current plant conditions.
D. No time restriction on restarting the pump but a steam bubble must be established in the Pressurizer.
Page 67
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 68. Given the following plant conditions:
- Unit I core re-load is in progress with sixty assemblies loaded in the core.
Which ONE of the following would require core alterations to be suspended in accordance with Tech Specs?
A. Spent Fuel Pit level is at elevation 725 11.
B. Audible count rate is lost to containment.
C. Spent Fuel Pit boron concentration is 2055 ppm.
D. Source Range High Flux Level At Shutdown alarm is out of service.
Page 68
SEQUOYAH JAN 2012 RD EXAM 2/1/2012
- 69. Given the following plant conditions:
- Unit I is at 100% power.
- It is 0630 and you have just relieved the Unit I CR0.
In accordance with 1-SI-OPS-000-002.O, Shift Log, which ONE of the following completes the statement below?
The _(1)____ is responsible for ensuring that all Outside MCR appendices are complete and the applicable day shift appendices are required to be completed by
_(2)____
A. (1) Assistant Unit Operator (2) 1830 B. (1) Unit Operator/RO (2) 1830 C. (1) Assistant Unit Operator (2) 1000 D. (1) Unit Operator/RD (2) 1000 Page 69
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 70. Given the following,
- Unit I is operating at 100% power.
- Control Rod H-8 drops into the core.
- Unit I remains at power and no automatic protective or operator actions have occurred.
- The OATC reports that during the initial stages of the event Pressurizer pressure had dropped to 2195 psig before recovering to normal.
Which ONE of the following completes the statements below?
During this event, the Tech Spec DNB limit (1) exceeded.
Tech Spec 3.1.3.1 Moveable Control Assemblies, requires Reactor Power to be reduced to a maximum of _(2) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, unless the rod is realigned.
A. (1)was (2) 85%
B. (1)was (2) 75%
C. (1)was NOT (2) 85%
D. (1)was NOT (2) 75%
Page 70
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 71. Given the following:
- A source check is required to be performed on 0-RM-90-103, Spent Fuel Pit Radiation Monitor.
Which ONE of the following completes the following statement?
The CHECK SOURCE switch will be positioned LI) and the High Rad relay (2) be automatically blocked.
in A. in the main control room will NOT B. in the main control room will C. locally only will NOT D. locally only will Page 71
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 72. Given the following plant conditions:
- A release of the Monitor Tank is in progress through the Liquid Radwaste System using the normal effluent flow path.
- 0-RA-90-122A WDS LIQ EFF MON HIGH RAD (M12-B, C-I) annunciator alarms.
Which ONE of the following is required to continue the release if 0-RM-90-I22 is declared inoperable?
A. Release cannot be restarted until 0-RM-90-122 is repaired and restored to operable status.
B. Notify chemistry to perform grab samples during the release and analyze for principal gamma emitters. Additional samples are to be documented on the post release permit.
C. No further action is required since the tank has been sampled and a valid permit has been generated to comply with the ODCM requirements to document the liquid radioactivity release.
D. Release may resume only if two addtional samples are drawn and independently analyzed, release rate calculations are independently verified, and lineup independently verified.
Page 72
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 73. Given the following plant conditions:
- Unit 1 is cooling down for refueling.
- RCS pressure is 340 psig.
- Tavg is 175°F.
- lA-A D/G is tagged for maintenance.
- A loss of Off-Site power occurs.
- lB-B DIG fails to start.
Which ONE of the following identifies the plant procedure that the crew is required to enter to mitigate the event?
A. ECA-0.0, Loss of All AC B. AOP-P.01, Loss of Offsite Power C. E-0, Reactor Trip or Safety Injection D. AOP-P.05, Loss of Unit 1 Shutdown Boards Page 73
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 74. Given the following plant conditions:
- Unit I is operating at 45%.
- Due to scheduled maintenance in the 3KVA annunciator inverter cabinet, Channel B annunciators are inoperable.
- Annuciator ANNUNCIATOR DIAGNOSTIC ERROR (M6-D, E-4) is half lit.
- All channel B annunciator windows are dark.
- Two hours after shift change the OATC notices all lit channel A annunciator windows change to the dark condition.
Which ONE of the following identifies the required operating crew action to be performed for the given conditions?
A. Go to AOP-P.08, Loss of Control Room Annuciators, and reboot the ADDS terminal to restore indication.
B. Go to 0-SO-55-1, Annuciator System, and station personnel for increased monitoring.
C. Go to AOP-P.08, Loss of Control Room Annuciators, and station personnel for increased monitoring.
D. Go to 0-SO-55-1, Annuciator System, to reboot the ADDS terminal to restore indication.
Page 74
SEQUOYAH JAN 2012 RO EXAM 2/1/2012
- 75. Given the following plant conditions:
- A fire in the Control Building has forced an evacuation of the Main Control Room due to excessive smoke.
- AOP-C.04, Shutdown from Auxiliary Control Room, has just been entered.
In accordance with AOP-C.04, which ONE of the following identifies both the initial location the Unit I CR0 is directed to go to and what action the Unit 1 CR0 is directed to initially perform?
Location Action A. Aux Control Room Direct AUOs to manually stabilize plant until Controls are transferred to Aux Control Room B. Aux Control Room Ensure personnel are dispatched to perform applicable checklists and appendices using Appendix Z, Task Assigment Sheet.
C. AOP-C.04 Cabinet Ensure personnel dispatched to perform applicable checklists and appendices using Appendix Z, Task Assignment Sheet.
D. AOP-C.04 Cabinet Direct AUOs to manually stabilize plant until Controls are transferred to Aux Control Room Page 75
References for 1201 NRC RO Exam
- 1. Steam Tables
- 2. Mollier Diagram
- 3. Mechanical Flow Diagram Essential Raw Cooling Water System, 1, 2-47W845-2 rev 103
- 4. Pressure Temperature Limits Report Sequoyah Unit I LTOPS Selected Set points
1W 5EUOV4 2o(Z3O(
ANSWER KEY REPORT for SQN JAN 2012 POST ATLANTA RO EXAM Test Form: 0 iiuwers
- Th Points Type 0 1 007 EA1.10 1 1.00 MCS C 2 008 AK2.03 2 1.00 MCS C 3 009 EK2.03 3 1.00 MCS D 4 011 EK2.02 4 1.00 MCS D 5 015AK2.085 1.00 MCS D 6 022 AA1.03 6 1.00 MCS C 7 025 AA2.01 7 1.00 MCS C 8 027 AG2.1.30 8 1.00 MCS A 9 029 EG2.2.37 9 1.00 MCS D 10 038EA1.0710 1.00 MCS A 11 W/E12EK3.211 1.00 MCS B 12 054AA2.0312 1.00 MCS B 13 055EK1.0213 1.00 MCS A 14 056 AG2.4.34 14 1.00 MCS A 15 057 AK3.01 15 1.00 MCS D 16 062 AA2.03 16 1.00 MCS C 17 065 AK3.08 17 1.00 MCS A 18 W/E05 EK1.3 18 1.00 MCS C 19 003 AK3.07 19 1.00 MCS D 20 024 AA2.04 20 1.00 MCS D 21 036AK2.0121 1.00 MCS D 22 059 AK3.03 22 1.00 MCS A 23 069 AA1.01 23 1.00 MCS D 24 074 EA2.03 24 1.00 MCS B 25 W/E01 EG2.1.7 25 1.00 MCS D 26 W/E13 EK2.2 26 1.00 MCS D 27 W/E16 EK1.3 27 1.00 MCS C 28 003 A1.05 28 1.00 MCS B 29 003 A4.05 29 1.00 MCS B 30 004K6.3130 1.00 MCS C 31 005K1.1131 1.00 MCS D 32 006 K1.05 32 1.00 MCS D 33 006 K6.03 33 1.00 MCS D 34 007 G2.1.30 34 1.00 MCS D 35 008K4.0135 1.00 MCS D 36 010K5.0136 1.00 MCS C 37 012 K2.01 37 1.00 MCS C 38 012K6.0238 1.00 MCS D 39 013 K2.01 39 1.00 MCS B 40 013 K5.02 40 1.00 MCS B 41 0221(2.0241 1.00 MCS C 42 025 1(5.01 42 1.00 MCS C 43 026 A1.06 43 1.00 MCS D 44 039 A3.02 44 1.00 MCS C 45 059 A3.04 45 1.00 MCS A 46 061 A2.07 46 1.00 MCS A Wednesday, January 25, 2012 11:38:24 AM
ANSWER KEY REPORT for SQN JAN 2012 POST ATLANTA RO EXAM Test Form: 0 Answers
- ID Poit1 Te 0 47 062 K3.01 47 1.00 MCS A 48 063 K3.02 48 1.00 MCS A 49 064 G2.4.8 49 1.00 MCS B 50 064 A1.05 50 1.00 MCS B 51 073 A4.01 51 1.00 MCS B 52 076 1(4.03 52 1.00 MCS C 53 078 G2.4.11 53 1.00 MCS A 54 103 A2.03 54 1.00 MCS D 55 103 A2.05 55 1.00 MCS A 56 002 K6.06 56 1.00 MCS C 57 015K2.0157 1.00 MCS D 58 0161(5.0158 1.00 MCS B 59 033 A1.01 59 1.00 MCS C 60 034 A4.01 60 1.00 MCS C 61 035A3.0161 1.00 MCS A 62 071 G2.2.40 62 1.00 MCS 4- L £ 63 072 K4.02 63 1.00 MCS B 64 079 K1.01 64 1.00 MCS A 65 086A2.0465 1.00 MCS D 66 G2.1.1766 1.00 MCS C 67 G2.1.3267 1.00 MCS D 68 G 2.1.41 68 1.00 MCS B 69 G 2.2.12 69 1.00 MCS D 70 G 2.2.38 70 1.00 MCS B 71 G 2.3.5 71 1.00 MCS A 72 G 2.3.13 72 1.00 MCS D 73 G2.4.473 1.00 MCS B 74 G 2.4.32 74 1.00 MCS C 75 G 2.4.34 75 1.00 MCS C SECTION 1 (75 items) 75.00 Wednesday, January 25, 2012 11:38:24AM 2