ML13023A060
| ML13023A060 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/22/2013 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| Download: ML13023A060 (104) | |
Text
ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:
Date: Facility/Unit: Sequoyah Station Unit I & 2 Region: I LI ii L] HID IV LI Reactor Type: W[l CE LI BW LI GED Start Time: Finish Time:
Instructions Use the answer sheets provided to document your answer
- s. 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 overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicants Signature Results RO/SRO-OnIy/Total Examination Values I I Points Applicants Scores
/ / Points Applicants Grade
/ I Percent ES-401, Page 31 of 33
Name: Sequoyah Dec 2012 SRO 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 1
- RCS pressure is 1600 psig and slowly rising.
- 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 flowwill (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 12:34:39 PM
Sequoyah Dec 2012 SRO Exam
- 2. Which ONE of the following choices completes 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 12:34:39 PM 2
Sequoyah Dec 2012 SRO Exam
- 3. Given the following plant conditions:
- Unit 1 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 LI) be established and if the pump is able to reduce the Core Exit temperature, the procedure directs the pump to continue to run until at least (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. (I) only if the pumps support conditions can (2) two T-hot indications have Saturday, November 24, 2012 12:34:39 PM 3
Sequoyah Dec 2012 SRO Exam
- 4. Given the following plant conditions,
- Unit 1 is operating at 100% power.
- The running charging pump, IA-A, trips.
In accordance with EA-62-5, Establishing Normal Charging and Letdown, when establishing letdown which ONE of the following identifies the controller(s) that is/are required to be placed in Manual?
Note:
1-HIC-62-78A = LETDOWN HX OUTLET TEMP 1-HIC-62-81A = LETDOWN PRESSURE PRESSURE CONTROL 1-HIC-62-93A = CHARGING FLOW CONTROL A. l-HIC-62-93A only.
B. 1-HIC-62-93A and 1-HIC-62-78A.
C. 1-HIC-62-81A only D. I -HIC-62-78A and I -HIC-62-81 A Saturday, November 24, 2012 12:34:39 PM 4
Sequoyah Dec 2012 SRO Exam
- 5. Given the following:
- Unit 1 is in Mode 5 with RCS at Mid-Loop.
- lA-A RHR pump in service.
- RHR flow was indicating 2400 gpm.
- The lA-A RHR pump motor amps and flow suddenly become very erratic.
In accordance with AOP-R.03, RHR System Malfunction, which ONE of the following indentifies:
(1) the RHR flow rate the operators are to maintain and (2) the action(s) that will be required if the IA-A RHR pump motor amps continue to be erratic?
A. (1) between l500gpmand2000gpm (2) make up to the RCS immediately by opening valve I -FCV-63-1, RHR suction from RWST.
B. (1) betweenl000gpmandl500gpm (2) make up to the RCS immediately by opening valve 1 -FCV-63-1, RHR suction from RWST.
C. (1) betweenl000gpmandlsoogpm (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 12:34:39 PM 5
Sequoyah Dec 2012 SRO 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 12:34:39 PM 6
Sequoyah Dec 2012 SRO 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 12:34:39 PM 7
Sequoyah Dec 2012 SRO 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 12:34:39 PM 8
Sequoyah Dec 2012 SRO 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?
O-Sl-SXX-068-1 27.0, RCS Pressurizer and Temperature and Pressure Limit, requires the SRO and Nuclear Engineering to be first notified if the pressurizer surge line AT 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.
Lu A. 320°F lower B. 320°F raise C. 560°F lower D. 560°F raise Saturday, November 24, 2012 12:34:39 PM 9
Sequoyah Dec 2012 SRO 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 12:34:39 PM 10
Sequoyah Dec 2012 SRO 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 I -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 12:34:39 PM 11
Sequoyah Dec 2012 SRO Exam
- 12. Given the following plant conditions,
- Unit 2 is at 100% power.
- CSST B is aligned to the lB 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, November 24, 2012 12:34:39 PM 9, 12
Sequoyah Dec 2012 SRO 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 PORVs C. NOT Established Raise steam flow through SG PORVs D. NOT Established Raise steam flow through Steam Dumps Saturday, November24, 2012 12:34:39 PM 13
Sequoyah Dec 2012 SRO 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 Ill 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 lii 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, November 24, 2012 12:34:39 PM 14
Sequoyah Dec 2012 SRO 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 12:34:39 PM 15
Sequoyah Dec 2012 SRO 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) (2L A. before to refill the pressurizer B. before to reduce the breakflow C. after to refill the pressurizer D. after to reduce the break flow Saturday, November 24, 2012 12:34:39 PM 16
Sequoyah Dec 2012 SRO 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 12:34:39 PM 17
Sequoyah Dec 2012 SRO Exam
- 18. Given the following plant conditions:
- Unit us 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 12:34:39 PM 18
Sequoyah Dec 2012 SRO 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 12:34:39 PM 19
Sequoyah Dec 2012 SRO 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 leaking steam generator can result in (1)
The preferred method of cooling a leaking 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 Blowdown D. (1) inability to maintain required RCS subcooling (2) MSIV bypass valve Saturday, November 24, 2012 12:34:39 PM 20
Sequoyah Dec 2012 SRO Exam
- 21. Which ONE of the following radiation monitors is NOT designed to automatically terminate an accidental radiation release?
A. O-RM-90-212, Turbine Building Sump Rad Monitor B. 1-RM-90-120, SIG Blowdown Effluent Rad Monitor C. 0-RM-90-225, Condensate Demineralizer Rad Monitor D. 0-RM-90-122, Liquid Waste Disposal System Effluent Rad Monitor Saturday, November 24, 2012 12:34:39 PM 21
Sequoyah Dec 2012 SRO 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 12:34:39 PM 22
Sequoyah Dec 2012 SRO Exam
- 23. Given the following plant conditions,
- Unit 1 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 I 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 I B 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 I B CCP is AVAILABLE and (2) the earliest time the 1 B 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 12:34:39 PM 23
Sequoyah Dec 2012 SRO 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 significant increase in RCS activity, which ONE of the following identifies how the listed process rad monitors would respond?
1-RM-90-106 - Lower Containment Radiation Monitor 1-RM-90-1 19 - Condenser Vacuum Pump Exhaust Rad Monitor I -RM-90-I 06 1 -RM-90-I 19 A. Stable Rising B. Stable Stable C. Rising Rising D. Rising Stable Saturday, November 24, 2012 12:34:39 PM 24
Sequoyah Dec 2012 SRO 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 SIG 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 12:34:39 PM 25
Sequoyah Dec 2012 SRO 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 Purrose 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. 9.5 to 10.5 water remove iodine and other halogen gases Saturday, November 24, 2012 12:34:40 PM 26
Sequoyah Dec 2012 SRO 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 (2) 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. (1) due to reduced ECCS injection flow and stabilize at a lower value when break flow equals ECCS injection flow.
(2) less D. (1) due to reduced ECCS injection flow and stabilize at a lower value when break flow equals ECCS injection flow.
(2) greater Saturday, November 24, 2012 12:34:40 PM 27
Sequoyah Dec 2012 SRO Exam
- 28. Given the following plant conditions;
- Unit 1 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 12:34:40 PM 28
Sequoyah Dec 2012 SRO 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 12:34:40 PM 29
Sequoyah Dec 2012 SRO 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 IA-A RHR Pump were to trip?
A. IA-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, November 24, 2012 12:34:40 PM 30
Sequoyah Dec 2012 SRO Exam
- 31. Given the following plant conditions:
- Unit 1 is in Mode4.
- RHR Train A is in service per 0-SO-74-1, Residual Heat Removal System.
- RCS temperature is stable at the current RHR flow rate.
Which ONE of the following malfunctions will result in a REDUCTION in flow through the RHR Heat Exchanger 1A?
A loss of A. air to 1-FCV-74-32, RHR HTX Bypass.
B. air to 1-FCV-74-16, RHR HTX A Outlet.
C. 120V AC Vital Instrument Power Board 1-Il.
D. 480V Shutdown Board 1AI-A.
Saturday, November 24, 2012 12:34:40 PM 31
Sequoyah Dec 2012 SRO 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 12:34:40 PM 32
Sequoyah Dec 2012 SRO 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 () provided the RCS pressure is stable or slowly increasing.
w L)
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 12:34:40 PM 33
Sequoyah Dec 2012 SRO Exam
- 34. Given the following plant conditions:
- Unit I 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 12:34:40 PM 34
Sequoyah Dec 2012 SRO Exam
- 35. Given the following plant conditions:
- Unit I is operating at 100% RTP
- O-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 12:34:40 PM 35
Sequoyah Dec 2012 SRO 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, November 24, 2012 12:34:40 PM 36
Sequoyah Dec2012 SRO 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 Inhibit 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 12:34:40 PM 37
Sequoyah Dec 2012 SRO Exam
- 38. Given the following plant conditions:
- Unit 1 is 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.l, 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.I has been completed.
B. (I) 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.l.
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.I has been completed.
D. (1) Loss of control power to the 6900v Shutdown Board.
(2) Implement AOP-P.02, Loss of 125v DC Vital Battery Board while continuing in ES-0.1.
Saturday, November 24, 2012 12:34:40 PM 38
Sequoyah Dec 2012 SRO 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, November 24, 2012 12:34:40 PM 39
Sequoyah Dec 2012 SRO 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 LCO if the door was found to be physically restrained from opening and which of the doors are equipped with flow proportioning springs to control opening?
Require 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> LCO entry if Doors equipped with physically restrained from opening flow proportioning springs A. Only an inlet door Inlet doors B. Only an inlet door Intermediate doors C. Either an inlet or Inlet doors intermediate deck door D. Either an inlet or Intermediate doors intermediate deck door Saturday, November 24, 2012 12:34:40 PM 40
Sequoyah Dec 2012 SRO Exam
- 41. Given the following plant conditions:
- Unit 1 was operating at 100% power with Containment Spray Pump 1 A-A out of service when a LOCA occurs.
- Containment Spray Pump I B-B trips when attempting to start.
- During performance of ES-I .3, Transfer To RHR Containment Sump 1-FCV-63-73, CNTMT SUMP TO RHR PMP B SUCT, could NOT be opened.
- The operating crew is currently performing FR-Z.I, 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, November 24, 2012 12:34:40 PM 41
Sequoyah Dec 2012 SRO Exam
- 42. Given the following plant conditi ons:
- Unit I is in Mode 3.
- The crew is performing a plant cooldo wn in accordance with 0-GO-7, Uni Shutdown From Hot Standby to Cold t Shutdown.
- Tave is 540°F and slowly lowering.
- PZR pressure is 1850 psig and slow ly lowering.
- P-il has energized and all blocking actions have been taken.
- SG pressures are all approximately 950 psig and slowly lowering.
- While attempting to increase the RC S cooldown rate, the UO inadvertently throttles the Condenser Steam Dum ps too far OPEN.
- LP 2 Ch I, II, & Ill HI NEG RATE STM LINE PRESS lights on i-XX-55-6B illuminate and then extinguish.
- 1 M-6B-B3, PS-A-2AR HIGH NEGA TIVE RATES STEAMLINE PRESSURE LOOP 2, is in alarm.
Which ONE of the following indenti fies the automatic function(s), if any, that result of this condition? occur as a A. No automatic actions occur.
B. Safety Injection actuates ONLY.
C. Main Steam Line Isolation actuates ONLY.
D. Main Steam Line Isolation and Saf ety Injection Actuation occur.
Saturday, November 24, 2012 12:34:40 PM 42
Sequoyah Dec 2012 SRO Exam
- 43. Given the following plant conditions:
- Unit I is at 100% power.
A significant feedwater heater level tran sient 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 Teold will rise, and reactor power will lower.
Saturday, November 24, 2012 12:34:40 PM 43
Sequoyah Dec 2012 SRO Exam
- 44. Given the following plant conditions:
- Unit 1 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 accordanc e with AOP-S.01, Main Feedwater Malfunctions, to be performed to preven t SG overfill?
Note:
PT-1-33, Main Steam Header Pressure PT-3-1, Feodwater 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 SG5 in MANUAL and lower main feedwater flow.
B. Common sensing line to PT-I -33 Place PC-46-20, MFPTIA & lB Speed has developed a leak; Control to Manual to lower MFPT IA and 1 B discharge pressure.
C. Common sensing line to PT-3-1 Place PC-46-20, MFPTIA & lB Speed has developed a leak; Control to Manual to lower MFPT 1A and lB 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, November24, 2012 12:34:40 PM 44
Sequoyah Dec 2012 SRO Exam
- 45. Which ONE of the following identifie s the correct power supply to 1 -FCV-3-1 36B Auxiliary Feedwater ERCW Supply MOV?
A. 480v Unit Bd IA.
B. 480v C & A Vent Bd 1A1-A.
D. 125v Battery Bd I Saturday, November 24, 2012 12:34:40 PM 45
Sequoyah Dec 2012 SRO Exam
- 46. Which ONE of the following iden tifies the source and flow path of the coo for the TDAFW pump bearings? ling water The cooling water to the TDAFW pum p bearings is supplied from (1) and after flowing through the bearing routed to jacket, the water is C2 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 12:34:40 PM 46
Sequoyah Dec 2012 SRO Exam
- 47. Given the following plant conditi ons:
- Unit I at 100% RTP.
- Operators are performing 0-SO-250-2,120 Volt AC Vital Instrument Pow System, to remove 1-Il inverter from er service and transfer the board to the spare inverter.
- As operators operate the 120V AC Vital Instrument Power Board 1-Il tra switch to the ALTERNATE positio nsfer n, the following indications are noted:
- Annunciator 120V AC VITAL PO WER BOARD 1-Il UV OR BKR TRIP received. (IM-C, B7) is
- All Channel II SSPS status lights are lit.
Which ONE of the following descri bes what has happened and procedura required under these conditions? l actions EVENT ACTIONS A. The indications are expected Verify 120V AC Vital Instrument Pow for the transfer. er Board 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 lnverter 1-Il AC for the transfer. OUTPUT AMPS are zero per 0-SO-250-2.
C. Vital Instrument Power Board 1-Il Implement the appropriate AOP ONLY has been lost, to.
restore the Vital Instrument Power Boa rd.
D. Vital Instrument Power Board 1-Il Trip the reactor, implement E-0, Re has been lost. actor Trip or Safety Injection, and the app ropriate AOP to restore the Vital Instrument Pow er Board.
Saturday, November 24, 2012 12:34:40 PM 47
Sequoyah Dec 2012 SRO Exam
- 48. Given the following plant conditions,
- Unit 1 is currently at 45% power.
- Main turbine controls are in MANUAL.
- The inter-tie transformer tap changer is in MANU AL for calibration.
The following annuciators alarm simultaneously:
6900V SD BD lA-A FAILURE OR BUS FEEDER UV/OVERVOLTAGE (1-M-IB) 6900 SD BD IA-A OVERVOLTAGE (1-M-26-A
)
STA FREQ EXCESSIVE ERROR (ECB6-B)
- The crew enters AOP-P.07, Degraded Grid Conditio ns or Generation Voltage Regulator Malfunction.
- Attempts to contact the Transmission Operator are unsuccessful.
- The crew initiates a turbine load reduction to redu ce 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 requ ired action in accordance with AOP-P.07?
A. Continue turbine load reduction to reduce frequ ency to 60 Hz.
B. Trip the reactor, enter E-0, Reactor Trip or Safe ty Injection.
C. Trip the turbine, enter AOP-S.06, Turbine Trip Belo w P-9.
D. Place the shutdown boards on D/Gs using Appendi x F.
Saturday, November 24, 2012 12:34:40 PM 48
Sequoyah Dec 2012 SRO 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 1 Al -A to Vital Battery Charger I trips open.
- Spare 125 V Battery Charger I-S is in stan dby alignment.
- No operator action is taken.
Which ONE of the following statements des cribes 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 12:34:40 PM 49
Sequoyah Dec 2012 SRO Exam
- 50. The following conditions exist on Unit 1:
- Annunciator, PS-82-162 DIESEL GEN IA-A START AIR PRESS LOW ENG I 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 IAI engine.
- The receiver air pressures currently are:
IAI(A) at 100 psig and rising 1AI(B) at 195 psig and stable.
Which ONE of the following identifies the status of 1 A-A diesel generator?
A. IA-A diesel is still operable since 1A2 engine starting air is normal.
B. IA-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 1AI(
B) air receiver pressure is inadequate to start the IA-A diesel.
Saturday, November 24, 2012 12:34:40 PM 50
Sequoyah Dec 2012 SRO Exam
- 51. Which ONE of the following identifies the effect on Unit 2 EDGs if the Unit 1 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 12:34:40 PM 51
Sequoyah Dec 2012 SRO Exam
- 52. Given the following plant conditi ons:
- Unit I is operating at 100% power.
- Annunciator 1-RA-120A1121A STM GE N BLDN LIQ SAMP MON HI RAD is in alarm.
- The indicator for RM-90-120 is reading peg ged high and the red light is on.
- No other radiation monitor reads abnorm ally.
RM-90-121 responds properly to a sou rce check.
Which ONE of the following reflects the correct action to take under these conditi ons?
A. Ensure 1 -FCV-1 5-44 closed to stop blowdown flow. Notify Chemistry. If monito failed, place pink tags. r has B. Ensure 1-FCV-1 5-44 closed to stop blowdown flow. Entry into AOP-R.01, St Generator Tube Leak, is required. eam 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 normal ly blowdown should not have isolated. Ent AOP-R.01, Steam Generator Tube Lea ry into k, is required.
Saturday, November 24, 2012 12:34:40 PM 52
Sequoyah Dec 2012 SRO 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 1 B.
- Offsite power is now available to Start Bus 1 B.
- No other operator actions have been taken.
Which ONE of the following describes the oper ation 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 12:34:40 PM 53
Sequoyah Dec 2012 SRO Exam
- 54. Given the following plant conditions:
- 6.9kV Shutdown Board lA-A tagged for maintenance.
- Subsequently, 6.9kV Shutdown Board 2B-B trips and locks out due to relay operation.
Which ONE of the following identifies the status of the Auxili ary Air Compressor power supplies?
A. Both Auxiliary Air Compressors have a power supply availab le.
B. Neither Auxiliary Air Compressor has a power supply availab le.
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, November 24, 2012 12:34:40 PM 54
Sequoyah Dec 2012 SRO Exam
- 55. Given the following plant conditions:
- Unit 1 reactor is shutdown.
- The RCS is being maintained at normal oper ating temperature and pressure.
- Containment entry is in progress for maintenan ce.
- The following annunciators on 1-M12-C are lock ed in.
- LWR PERS ACCESS OUTER DR LOCK
- LWR PERS ACCESS INNER DR LOCK
- UPR/LWR AIR LOCK BREACH
- Containment pressure has rapidly equalized with the Aux Building.
- Containment pressure currently indicates 0.18 PSID.
In addition to TS 3.0.3, which ONE of the follo wing 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 INTE GRITY 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 LOC KS 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. Enter TS 3.6.1.2 SECONDARY CONTAIN MENT BYPASS LEAKAGE and restore Secondary Containment Bypass Leakage with in 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 12:34:40 PM 55
Sequoyah Dec 2012 SRO Exam
- 56. Given the following plant conditions:
- Unit 1 is at 10% power following a refueling outa ge.
- The main turbine is being warmed up in preparati on to sync to the grid.
- The OATC notes that GB 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 12:34:40 PM 56
Sequoyah Dec 2012 SRO Exam
- 57. Given the following plant conditions
- Unit I is operating at 100%.
- 1-RE-90-1 12, Upper Containment Radiati on Monitor, is aligned to lower containment for scheduled maintenance on 1-RE-90-106, Lower Containment Radiation Monitor.
- LS-77-410A REACTOR BLDG AUX FL
& EQ DRAIN SUMP HI alarms (1-)(A-55-5A window C-5)
- The CR0 determines the Reactor Building auxiliary floor and equipment drain (pocket) sump level indication to be:
1-Ll-77-410A - 98%
1-Ll-77-41 IA - 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 &
1 U0968) are NOT in alarm.
Which ONE of the following identifies...
(1) the status of the pocket sump pum ps 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 hav e 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 12:34:40 PM 57
Sequoyah Dec 2012 SRO 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 follo wing 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 trans fer to the RWST, and remain low.
Saturday, November 24, 2012 12:34:40 PM 58
Sequoyah Dec 2012 SRO Exam
- 59. Given the following plant conditions:
- Unit 1 initially operating at 100% power
- AFD at -3.4%
- Annunciator window 1 -M-4B-C-7, ZB-442C BAN K D AUTO ROD WITHDRAWAL BLOCKED, lit
- A feedwater malfunction induces a transien t.
- The crew stabilizes Unit 1 at 80% power
- The QAC 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 12:34:40 PM 59
Sequoyah Dec 2012 SRO Exam
- 60. Which ONE of the follow ing identifies the direct source of Containment Hydrogen Recom 480v power to the biner 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:
34:40 PM 60
Sequoyah Dec 2012 SRO Exam
- 61. Given the following plant conditions:
- Both Units are at 100% power.
- Annunciator TIS-78-4 SPENT FUEL PITS TEM PERATURE HIGH (1 M6D-E3) alarms.
- AUO reports the Spent Fuel Pit Temperature is 128°F and has risen 4°F since the beginning of the shift.
- SFP Heat Exchanger A is in service with 2600 gpm SFPC pump flow and 2400 gpm CCS flow.
Which ONE of the following identifies:
(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 give n 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 SFPC pump flow through SEP Heat Exchanger A Saturday, November 24, 2012 12:34:40 PM 61
Sequoyah Dec 2012 SRO Exam
- 62. Given the following plant conditions,
- Unit 2 is operating at 100% power.
- SG#2 NR levels indicate: 1-Ll-3-55 1-Ll-3-52 1-Ll-3-51 45% 44% 43%
Which ONE of the following identifies the effect on SG level control if 1 -LT-3-52 fails to 0% output?
A. 1-LT-3-51 will become the level input to the level control system.
B. 1-LT-3-55 will become the level input to the level control system.
C. Level control input will be the average ofi -LT-3-51 and 1 -LT-3-55.
D. Level control system will automatically transfer to manual control.
Saturday, November 24, 2012 12:34:40 PM 62
Sequoyah Dec 2012 SRO 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 A. 250 85%
B. 250 75%
C. 320 85%
D. 320 75%
Saturday, November 24, 2012 12:34:40 PM 63
Sequoyah Dec 2012 SRO 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 12:34:40 PM 64
Sequoyah Dec 2012 SRO 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 MOVs open Saturday, November 24, 2012 12:34:40 PM 65
Sequoyah Dec 2012 SRO Exam
- 66. Given the following:
- Unit 1 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 12:34:40 PM 66
Sequoyah Dec 2012 SRO Exam
- 67. Given the following plant conditions:
- Unit I is in Mode 3 with RCS temperature at 547°F and pressure 2235 psig.
- Annunciator TS-68-316, 317 PRESSURIZER SPRAY LINES TEMP LOW alarms. (1M5A 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. Loop3is idle Pressurizer surge line temperature STABLE or RISING C. Pressurizer spray Pressurizer surge line bypass flow LOW temperature DROPPING D. Loop3is idle Pressurizer surge line temperature DROPPING Saturday, November 24, 2012 12:34:40 PM 67
Sequoyah Dec 2012 SRO 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 1 -PlC-I -33 controller set point was changed to 1115 psig?
Tavg would Cl) and the reactor power would (2) w L)
A. decrease increase B. decrease decrease C. increase increase D. increase decrease Saturday, November 24, 2012 12:34:40 PM 68
Sequoyah Dec 2012 SRO Exam
- 69. Given the following plant conditions,
- Unit I 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, November 24, 2012 12:34:40 PM 69
Sequoyah Dec 2012 SRO Exam
- 70. Given the following conditions:
- Unit 1 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 Nis 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 12:34:40 PM 70
Sequoyah Dec 2012 SRO 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 1 9A 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 12:34:40 PM 71
Sequoyah Dec 2012 SRO 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 Taqcjed 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 12:34:40 PM 72
Sequoyah Dec 2012 SRO Exam
- 73. Which ONE of the following identifies...
(I) 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 L)
A. Technical Support Center Alert B. Technical Support Center NOUE C. Operations Support Center Alert D. Operations Support Center NOUE Saturday, November 24, 2012 12:34:40 PM 73
Sequoyah Dec 2012 SRO 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 EPIP-3,Alert, which ONE of the following indentifies both:
(1) the communication system that you are to use and (2) the briefing guide to use when notifying the NRC?
A. (1) The ENS phone line must be used, contact would be made from another location using ENS.
(2) NRC Event Notification Worksheet from SPP-3.5, Regulatory Reporting Requirements.
B. (1) Any plant telephone line.
(2) NRC Event Notification Worksheet from SPP-3.5, Regulatory Reporting Requirements.
C. (1) The ENS phone line must be used, contact would be made from another location using ENS.
(2) EPIP-3, Appendix D, Notification of the NRC.
D. (1) Any plant telephone line.
(2) EPIP-3, Appendix D, Notification of the NRC.
Saturday, November24, 2012 12:34:40 PM 74
Sequoyah Dec 2012 SRO 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) L)
A. RED Close MSIVs and Bypasses B. RED Manually runback turbine C. GREEN Close MSIVs and Bypasses D. GREEN Manually runback turbine
- 76. Given the following plant conditions:
- The Unit I operating crew is performing ES-O.1, Reactor Trip Response.
- SG NR levels are as follows: #1 = 15%; #2 = 19%; #3 = 18%; #4 = 12%
- The crew has initiated performance of EA-2-2, Establishing Secondary Heat Sink Using Main Feedwater or Condensate System, due to AFW pump failures which prevented establishing the required AFW flow.
- Actions have been initiated to restore AFW.
- EA-2-2 contains an Appendix that requires an AUO to perform actions to prevent an Intermediate Heater String isolation.
Which ONE of the following completes the statements below?
Per EA-2-2, the AUO would be sent to the (1) to perform action required to prevent the Intermediate Heater String isolation.
When MFW is established, the SRO will (2)
W L)
A. 480V TB MOV Boards transition to O-GO-7, Unit Shutdown from Hot Standby to Cold Shutdown B. 480V TB MOV Boards remain in ES-O.1 until an AFW train is restored unless a cooldown becomes required C. Auxiliary Instrument Room transition to O-GO-7, Unit Shutdown from Hot Standby to Cold Shutdown D. Auxiliary Instrument Room remain in ES-O.1 until an AFW train is restored unless a cooldown becomes required Saturday, November 24,2012 11:57:55 AM 76
Sequoyah Dec 2012 SRO Exam
- 77. Given the following plant conditions:
- Unit I is operating at 100% power with the 1A Safety Injection pump tagged for maintenance.
1000 - A LOCA caused an automatic safety injection on Unit 1.
1005 - Shutdown Board lB trips and is damaged.
1015 - E-l, Loss of Reactor or Secondary Coolant, is implemented.
1030 - SI Termination criteria could NOT be met and the crew continued in E-1.
1040 - The crew is evaluating whether RCS cooldown and depressurization is required.
Current Conditions:
- RWST level is 78% and lowering.
- RCS pressure 290 psig and stable.
- 1-Fl-63-91A indicates Train A RHR flow to be 0 gpm
- Containment pressure peaked at 1.6 psig and is dropping.
Which ONE of the following completes the statements below?
The transition to ES-i .2, Post LOCA Cooldown and Depressurization, (1) be made.
ES-I .4,Transfer to Hot Leg Recirculation, will be implemented JZ) w A. will only if the TSC determines it is required B. will five hours after the initiation of the LOCA C. will NOT only if the TSC determines it is required D. will NOT five hours after the initiation of the LOCA Saturday, November 24, 2012 11:57:55 AM 77
Sequoyah Dec 2012 SRO Exam
- 78. Given the following plant conditions:
- While operating at 100% power, Unit 2 receives a reactor trip signal
- Coincident with the reactor trip a loss of off-site power occurs.
- During perlormance of the first step of E-0, Reactor Trip or Safety Injection, the following conditions exist:
- Reactor Trip Breaker A indicates RED.
- Reactor Trip Breaker B indicates GREEN.
- Reactor Power is 5% and lowering.
- Multiple control rods indicate NOT fully inserted.
Which ONE of the following identifies the correct procedure usage and the t 10CFR5O.72 report that is required to be completed?
Procedure Usage Report -
A. Go to FR-S.1, Nuclear Power Generation/ATWS a one-hour report B. Go to FR-S.1, Nuclear Power Generation/ATWS a four-hour report C. Remain in and continue the performance of E-0 a one-hour report D. Remain in and continue the performance of E-0 a four-hour report Saturday, November 24, 2012 11:57:55 AM 78
Sequoyah Dec 2012 SRO Exam
- 79. Given the following plant conditions:
- Unit I is shutdown with RCS at 450°F and 2235 psig when a loss of a 120v AC Vital Instrument Power Board occurs.
- The operating crew enters AOP-P.03, Loss Of Unit 1 Vital Instrument Power Board.
- The OATC reports the CCP suction has swapped to the RWST.
- The CRC reports level rising in SGs 3 and 4 and their AFW flows cannot be reduced using the LCV controllers.
Which ONE of the following completes the statements below?
The SRO will implement AOP-P.03, Section (1)
Tech Spec 3.8.2, Onsite Power Distribution Systems, (2) allow the Unit to remain in the current mode indefinitely with the 12OvAC Vital Instrument Power Board de-energized.
Li)
A. 2.1, Loss Of Unit I Vital Instrument Power Board 1-I will B. 2.1, Loss Of Unit I Vital Instrument Power Board 1-I will NOT C. 2.2, Loss Of Unit I Vital Instrument Power Board 1-Il will D. 2.2, Loss Of Unit 1 Vital Instrument Power Board 1-Il will NOT Saturday, November 24, 2012 11:57:55 AM 79
Sequoyah Dec 2012 SRO Exam
- 80. Given the following plant conditions:
- Unit 1 is operating at 100% RTP when a loss of all ERCW occurs.
- The operating crew implements AOP-M.01, Loss of Essential Raw Cooling Water in response to the event.
- Eight minutes after entering the AOP, the STA is monitoring Status Trees and reports all Status Trees GREEN except for SUBCRITICALITY due to the Intermediate Range Monitors indicating a positive Startup Rate.
Which ONE of the following identifies the correct use of procedures?
A. Immediate implementation of FR-S.1, Nuclear Power Generation I ATWS, is required.
B. Perform FR-S.1, Nuclear Power Generation / ATWS, in parallel with AOP-M.01.
C. Continue in AOP-M.01, do NOT implement FR-S.1, Nuclear Power Generation / ATWS.
D. Continue in AOP-M.01, Implementation of FR-S.1, Nuclear Power Generation I ATWS, is NOT required unless Power Range Monitors read 5%.
Saturday, November 24, 2012 11:57:55 AM 80
SRO Question for Review: Proposed changes to #81
- 81. Given the following plant conditions:
- Unit I is in MODE 4 following a Refuel Outage.
- ABGTS Train B is tagged for heater bank inspection.
- Annunciator PS-32-1 04 TRAIN A AUX CONTROL AIR PRESSURE LOW (1M15B-A4) alarms.
- AUO reports the Train A Aux air is isolated from station air, Train A Aux Air Compressor running and the Train A header is 67 psig and slowly dropping.
Which ONE of the following identifies (1) the current status of ABGTS and (2) the action, if any, required per Unit 1 Technical Specifications?
A. (1) ABGTS Train A remains OPERABLE until the Train A Containment Air Isolation valve automatically closes.
(2) LCO 3.0.3 entry would NOT be required.
B. (1) ABGTS Train A remains OPERABLE until the Train A Containment Air Isolation valve automatically closes.
(2) LCO 3.0.3 entry would be required.
C. (1) Both ABGTS Trains would be INOPERABLE with the current conditions.
(2) LCO 3.0.3 entry would NOT be required.
D. (1) Both ABGTS Trains would be INOPERABLE with the current conditions.
(2) LCO 3.0.3 entry would be required.
Sequoyah Dec 2012 SRO Exam
- 82. Given the following plant conditions:
- A Unit 1 reactor startup in accordance with GO-2, Reactor Startup, is in progress with the reactor critical at 2.0 Xl 0% power.
- The following window alarms on NIS/ROD CONTROL 1-XA-55-4B I I J
SOURCEflNTERMED RANGE CH A TROUbLE
- The operating crew determines Source Range CH I, 1-XX-92-5001, drawer has a blown Instrument Power fuse.
- The operating crew enters AOP-l.01, Nuclear Instrumentation Malfunction.
Which ONE of the following identifies how the drawer failure and operator actions affect plant operation?
Placing the drawer LEVEL TRIP switch to BYPASS in accordance with AOP-l.01, (1) prevent a reactor trip signal from being generated if power is reduced.
and Tech Specs (2) the startup to be continued to Mode 1.
A. (1) wIIINOT (2) will NOT allow B. (1) will (2) allows C. (1) wiIINOT (2) allows D. (1) will (2) will NOT allow Saturday, November 24, 2012 11:57:55 AM 82
Sequoyah Dec 2012 SRO Exam
- 83. Given the following plant conditions:
- Unit I turbine load is at 35%.
- Condenser vacuum is being lost due to air in-leakage.
- Operators have entered AOP-S.02, Loss of Condenser Vacuum.
- Condenser backpressure is 1.8 psia and rising at 0.1 psia/minute.
Which ONE of the following is the correct action in accordance with AOP-S.02 for the current conditions?
A. Trip the turbine and GO TO AOP-S.06, Turbine Trip.
B. Trip the reactor and GO TO E-0, Reactor Trip or Safety Injection.
C. Continue in AOP-S.02, if condenser pressure exceeds 2.7 psia and cannot be restored within 5 mm, trip the turbine and GO TO AOP-S.06, Turbine Trip.
D. Continue in AOP-S.02 if condenser pressure exceeds 2.7 psia and cannot be restored within 5 mm, trip the Reactor and GO TO E-0, Reactor Trip or Safety Injection.
Saturday, November 24, 2012 11:57:55 AM 83
Sequoyah Dec 2012 SRO Exam
- 84. Given the following plant conditions:
- A LOCA has occurred on Unit 2 and the crew is performing FR- C.1, Inadequate Core Cooling.
The current plant conditions exist:
- Containment pressure is at 2.2 psig and dropping after rising to 4.8 psig.
- RCPs #1 and #2 have been started.
- SGs are being depressurized to atmospheric pressure.
- Several core exit T/Cs in each quadrant including some near the center of the core indicate between 1200°F and 121 0°F and are slowly rising.
- SG levels are: SG1 SG2 SG3 SG4 29%NR 31%NR 22%NR 26%NR Which ONE of the following completes the statement below?
The Unit Supervisior will A. remain in FR-C.1 but another RCP can NOT be started B. remain in FR-C.1 and direct the OATC to start an additional RCP C. transition to SACRG-1, Severe Accident Control Room Guideline initial Response and direct the OATC to start an additional RCP D. transition to SACRG-1, Severe Accident Control Room Guideline Initial Response but conditions do NOT allow an additional RCP to be started Saturday, November 24, 2012 11:57:55 AM 84
Sequoyah Dec 2012 SRO Exam
- 85. Given the following plant conditions:
- Unit I is operating at 100% power when the operating crew initiates a Reactor trip and enters E-0, Reactor Trip or Safety Injection due to a feedwater transient.
- During performance of E-0 Immediate Operator Actions an automatic Safety Injection occurs.
- The operating crew performs E-0 to the last step without identifying a transition.
Which ONE of the following completes the statements below?
To properly identify the required procedure, the Unit Supervisor will (1) to identify the proper transition.
Status Tree implementation (2) currently required to be in progress.
A. implement ES-0.0, Rediagnosis is B. implement ES-0.0, Rediagnosis is NOT C. loop back in E-0 to re-perform steps is D. loop back in E-0 to re-perform steps is NOT Saturday, November 24, 2012 11:57:55 AM 85
Sequoyah Dec 2012 SRO Exam
- 86. Given the following plant conditions:
- Unit 1 RCS heatup is in progress with the RCS temperature at 523°F and pressurizer pressure at 2115 psig.
- All Shutdown Bank Rods are withdrawn to the full out position.
Which ONE of the following identifies the minimum required status of the Reactor Coolant Pumps in accordance with Tech Spec 3/4.4.1, Reactor Coolant Loops and Coolant Circulation and the bases for the requirement?
Two RCPs operable with (1) to ensure _(2)_.
A. (1) both in operation (2) adequate decay heat removal capacity and to prevent boron stratification.
B. (1) at least one in operation (2) adequate decay heat removal capacity and to prevent boron stratification.
C. (1) both in operation (2) adequate decay heat removal capacity in the event of a bank withdrawal accident.
D. (1) at least one in operation (2) adequate decay heat removal capacity in the event of a bank withdrawal accident.
Saturday, November 24, 2012 11:57:55AM 86
Sequoyah Dec 2012 SRO Exam
- 87. Given the following plant conditions:
- Unit 1 is being cooled down following a shutdown for a refueling outage.
- With the RCS at 340°F a LOCA occurred resulting in a Safety Injection due to the containment pressure increase.
- While performing AOP-R.02, Shutdown LOCA, the operating crew is unable to get either of the RHR containment sump valves, 1-FCV-63-72 or 1- FCV-63-73, to OPEN from the MCR.
- Subsequently, the following annunciator window alarms on I -M-6E:
LS-63-50B RWST LVL LO-LO Which ONE of the following completes the statements below?
In accordance with AOP-R.02, the failure of the sump valves to open requires the crewtogoto (1)
In accordance with the ARP, (2) taking suction from the RWST are required to be stopped and locked out.
£1)
A. ECA-1 .1, Loss of RI-IR Sump Recirculation all pumps B. ECA-1 .1, Loss of RHR Sump Recirculation only the RHR pumps C. AOP-R.03, RHR System Malfunction all pumps D. AOP-R.03, RHR System Malfunction only the RHR pumps Saturday, November 24, 2012 11:57:55 AM 87
Sequoyah Dec 2012 SRO Exam
- 88. Given the following:
- Unit I is operating at 100% power.
- Annunciator Panel 1-XA-55-5A, Window E-2 alarms.
PS-68-331 PRESSURIZER POWER RELIEF LINE TEMP HIGH
- OATC determines pressurizer PORV 340 has failed open and takes action to close PORV 340 BLOCK VALVE.
- An AUO removes power from the Block valve after it is closed.
- After the unit conditions are stabilized, the PRT conditions are:
Pressure Temperature Level 6.5psig 133°F 81%
Which ONE of the following completes the statements below?
Tech Spec LCO 3.4.3.2 (1) the unit to continue to operate for a unlimited period of time with the PORV failed opened and isolated.
To restore the PRT to normal conditions requires the performance of I -SO-68-5, Pressurizer Relief Tank Section (2)
Li) L)
A. allows 8.4, Reducing the Temperature of the PRT B. allows 8.6, Reducing the Pressure of the PRT C. does NOT allow 8.4, Reducing the Temperature of the PRT D. does NOT allow 8.6, Reducing the Pressure of the PRT Saturday, November 24, 2012 11:57:55 AM 88
Sequoyah Dec 2012 SRO Exam
- 89. Given the following plant conditions:
- A leak has developed in the Component Cooling Water system on Unit 1.
- The crew is performing actions of AOP M.03, Loss of Component Cooling Water.
- A Train Surge Tank level indicates 0%.
- B Train Surge Tank level indicates 57% and stable.
Which ONE of the following describes the effect of this condition, and the action required?
A. Component Cooling Water System operability meets safety analysis assumptions.
Trip the reactor, Trip RCPs, and enter E-0, Reactor Trip or Safety Injection.
B. Component Cooling Water System operability meets safety analysis assumptions.
Monitor RCP temperatures and continue attempts to identify and isolate the leak in accordance with M.03. Mode 1 operations may continue until technical specifications requires a unit shutdown.
C. Component Cooling Water System operability no longer meets safety analysis assumptions. Trip the reactor, Trip RCPs, and enter E-0, Reactor Trip or Safety Injection.
D. Component Cooling Water System operability no longer meets safety analysis assumptions. Monitor RCP temperatures and continue attempts to identify and isolate the leak in accordance with M.03. Mode I operations may continue until technical specifications requires a unit shutdown.
Saturday, November 24, 2012 11:57:55AM 89
Sequoyah Dec 2012 SRO Exam
- 90. Given the following plant conditions:
0700 - Unit 1 is operating at 100% power with 1-Sl-OPS-000-002.0, Shift Log Appendix G, Increase Monitoring of UHS temperature, in progress.
1000 - ERCW header temperatures are confimed to have exceeded the maximum allowed Ultimate Heat Sink temperature and a Unit shutdown is initiated.
1230 - Efforts by River Scheduling result in restoring ERCW temperature to below the the Ultimate Heat Sink maximum limit.
1235 - The shutdown is terminated with Reactor power at 40% and efforts initiated to begin raising reactor power.
Which ONE of the following identifies...
(1) the maximum required average ERCW temperature that allows the Ultimate Heat Sink temperature to be restored to an OPERABLE condition and (2) latest time allowed to make the initial required §50.72 report in accordance with NPG-SPP-03.5, Regulatory Reporting Requirements?
Li)
A. 87°F 1400 B. 87°F 1800 C. 85°F 1400 D. 85°F 1800 Saturday, November 24, 2012 11:57:55 AM 90
Sequoyah Dec 2012 SRO Exam
- 91. Given the following plant conditions:
- Unit I is operating at slightly over 50% rated thermal power awaiting repairs to secondary equipment.
- Power Range indications: Nl-41 Nl-42 Nl-43 Nl-44 50.1% 50.1% 50.2% 49.8%
1200 - The applicable Surveillance Instruction is performed to verify QPTR and AFD are within limits.
1400 - Power Range Monitor N-43 begins an erratic oscillation cycling between 48% and 51%. The SRO declares N-43 to be INOPERABLE and performs the actions required by AOP-l.01, Nuclear Power Malfunction.
1700 - The NIS drawer power range upper and lower flux deviation alarms are discovered to be failed and are declared INOPERABLE.
Which ONE of the following completes the statements below?
Prior to action taken in the AOP, the BYPASS AND PERMISSIVE 1-XA-55-4A panel window E-4, P-9 LOW POWER TURB TRIP-REAC TRIP BLOCK, will (1) during the N 1-43 oscillations.
The conditions require (2) to be performed before 0500 the next day.
L1 L)
A. cycle 0-Sl-NUC-000-044.0, Axial Flux Difference B. cycle 0-Sl-NUC-000-1 33.0,Quadrant Power Tilt Ratio C. remain LIT 0-Sl-NUC-000-044.0, Axial Flux Difference D. remain LIT 0-Sl-NUC-000-1 33.0,Quadrant Power Tilt Ratio Saturday, November 24, 2012 11:57:55 AM 91
Sequoyah Dec 2012 SRO Exam
- 92. Given the following plant conditions:
- Unit I is operating at 100% power.
- On 12-12-2012 an SRO made the following discovery:
- 1-Sl-ICC-090-271 .0, Channel Calibration of Upper Inside Containment Post Accident Hi Range Area Monitor 1 -R-90-271 exceeded its NRC late date (maximum extension date) as of 12-09-2012 and is out of its 18 month required frequency.
Which ONE of the following identifies the status of the radiation monitor?
A. The monitor is required to be declared INOPERABLE and a 30-day clock to restore the monitor to OPERABLE started on 12-12-2012.
B. The requirement to declare the monitor INOPERABLE can be delayed up to a maximum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from 12-12-2012 to allow the surveillance to be performed.
C. The monitor is required to be declared INOPERABLE and a 30-day clock to restore the monitor to OPERABLE started on 12-09-2012.
D. The requirement to declare the monitor INOPERABLE can be delayed for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, starting on 12-12-2012, provided a risk evaluation is performed and the risk managed to allow the surveillance to be performed.
Saturday, November 24, 2012 11:57:55 AM 92
Sequoyah Dec 2012 SRO Exam
- 93. Given the following plant conditions:
- Unit I is operating at 100% power.
- Unit 2 is in Mode 3 awaiting forced outage maintenance completion.
2143 - A fire is reported on Auxiliary building El. 690 General Spaces just outside the Unit I Penetration Room Door and U-I initiates AOP-N.0l, Plant fires.
2144 - Shift Manager initiates AOP-N.01 Appendix B, Shift Manager Actions.
2146 - The Unit 1 OATC is monitoring conditions listed on AOP-N.01 Appendix E.l, Unit I Fire Safe Shutdown Entry Criteria.
The Unit 2 OATC is monitoring conditions listed on AOP-N.0l Appendix E.2, Unit 2 Fire Safe Shutdown Entry Criteria.
2149 - The Unit I OATC reports pressurizer PORV 340A has spuriously opened and both PORVs and both PORV Block Valves handswitches have been placed to the CLOSE position.
The Unit I SRO implements AOP-N.08, Appendix R Fire Safe Shutdown.
2155 - Incident commander and Fire Brigade Leader report the fire has been extinguished.
Which ONE of the following completes the statements below?
The US/SRO on Unit 2 Li)
EPIP-I, Emergency Plan Classification Matrix, (2) declaration of the REP.
REFERENCE PROVIDED A. (1) is required to implement AOP-N.08 at 2149 (2) requires B. (1) is required to implement AOP-N.08 at 2149 (2) does NOT require C. (I) will be required to implement AOP-N.08 only if Appendix E conditions develop on Unit 2 (2) requires D. (1) will be required to implement AOP-N.08 only if Appendix E conditions develop on Unit 2 (2) does NOT require Saturday, November 24, 2012 11:57:55 AM 93
Sequoyah Dec 2012 SRO Exam
- 94. Given the following plant conditions:
- Both units are operating at 100% power and are staffed with the minimum allowed number of licensed operators on-site in accordance with OPDP-1, Conduct of Operations.
- Shortly after shift change the crew realizes that both the OATC and the Unit Supervisor on Unit 1 have a no-solo restriction on their license.
- None of the other license holders on shift have a no-solo restriction on their license.
Which ONE of the following completes the statements below?
The current staffing on Unit 1 (1)
In accordance with OPDP-1, if any of the currently on-shift licensed persons become incapacitated, the Shift Manager shall arrange for replacement personnel to restore the shift complement within a maximum of (2) hours.
L1 A. is allowed 2 B. is allowed 4 C. is NOT allowed 2 D. is NOT allowed 4 Saturday, November 24,2012 11:57:55 AM 94
Sequoyah Dec 2012 SRO Exam
- 95. Given the following plant conditions:
- Unit I is in Mode 6 with core off-load in progress.
- Chemistry reports the RCS boron concentration to be 1990 ppm.
In addition to stopping fuel movement, which ONE of the following identifies (1) the highest priority required Operator action and (2) the basis for the Tech Spec LCO that must be entered A. (1) Immediately implement performance of 0-Sl-OPS-062-21 4.0, Uncontrolled Boron Dilution.
(2) Ensures the spent fuel pool is not diluted below 2200 ppm.
B. (1) Immediately implement performance of AOP-C.02, Uncontrolled Boron Concentration Changes.
(2) Ensures the reactor will remain subcritical during core alterations.
C. (1) Immediately implement performance of 0-Sl-OPS-062-21 4.0, Uncontrolled Boron Dilution.
(2) Ensures the reactor will remain subcritical during core alterations.
D. (I) Immediately implement performance of AOP-C.02, Uncontrolled Boron Concentration Changes.
(2) Ensures the spent fuel pool is not diluted below 2200 ppm.
Saturday, November 24, 2012 11:57:55 AM 95
Sequoyah Dec 2012 SRO Exam
- 96. Given the following plant conditions:
- Unit I is at 100% RTP when annunciator LS-68-34A/B REAC COOL PMP 2 OIL RESERVOIR LEVEL HI-LOW alarmed.
- The cause was determined to be a faulty low level switch for the lower bearing oil reservoir. The lower bearing reservoir is determined to be normal and compensatory measures have been established.
- The following decisions have been made:
- Repair the level switch during the upcoming refueling outage scheduled to begin in 70 days.
- Disable the alarm prior to lifting the leads to the faulty switch.
- Lift the leads to the faulty level switch.
- Re-enable the alarm to restore alarm capability for the remaining oil reservoir level switches.
Which ONE of the following completes the statements below?
A Technical Evaluation is first required prior to (1)
A 50.59 Review is first required to be completed (2) w A. disabling the alarm before the alarm is initially disabled B. disabling the alarm only if the alarm is not restored to normal within 90 days C. lifting the level switch leads before the alarm is initially disabled D. lifting the level switch leads only if the alarm is not restored to normal within 90 days Saturday, November 24, 2012 11:57:55 AM 96
Sequoyah Dec 2012 SRO Exam
- 97. Given the following plant conditions:
- Unit 1 operating in MODE 1.
Which ONE of the following identifies a condition where an entry into the Unit 1 narrative log is required for equipment made inoperable but the completion of an entry into the LCO Tracking Log would NOT be required in accordance with OPDP-8, Operability Determination Process and Limiting Condit ions for Operations Tracking?
A. A Safety Function Determination identifies that no loss of Safety Function exists.
B. The equipment made inoperable will be restored to oper able status before the end of the current shift.
C. The equipment made inoperable is not required unless the unit enters MODE 3.
D. The equipment made inoperable is being tracked in acco rdance with the clearance procedure.
Saturday, November 24, 2012 11:57:55 AM 97
Sequoyah Dec 2012 SRO Exam
- 98. Which ONE of the following completes the statement below?
With Unit I in Mode 1, compliance with Technical Specification 3.48, Reactor Coolant System Specific Activity ensures that the 2-hour dose at the site boundary will not exceed a small fraction of (1) limits following a (Z) w A. 10CFR2O Loss of Coolant Accident B. IOCFR2O Steam Generator Tube Rupture C. I OCFRI 00 Loss of Coolant Accident D. I OCFR1 00 Steam Generator Tube Rupture Saturday, November 24, 2012 11:57:55AM 98
Sequoyah Dec 2012 SRO Exam
- 99. Given the following plant conditions:
1000 - Unit I entered Mode 4 during shutdown for a refueling outage.
0130 - AOP-N.03, Flooding, was implemented due to extremely heavy rainfall in the upstream watershed and River System Operations (RSO) confirms the flood level at the plant is predicted to crest at a maximum of El. 706 within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Which ONE of the following identifies both..
(I) the AOP-N.03 section(s) that are required to be completed, and (2) how the cooling of the core will be maintained in accordance with AOP-N
.03 after the section(s) are complete?
A. (1)2.3, Stage I Mode 1,2,3, or4fly (2) Core cooling will be maintained by the steam generators being supplied by AFW with RHR out of service.
B. (1)2.3, Stage I Mode 1,2,3, or4pjjjy (2) Core cooling will be maintained by both the RHR system and the steam generators being supplied by AFW.
C. (1) 2.3, Stage I Mode 1, 2, 3, or 4 and 2.7, Stage II Preparation Mode 4 (2) Core cooling will be maintained by the steam generators being supplied by High Pressure Fire Protection system.
D. (1) 2.3, Stage I Mode 1, 2, 3, or 4 and 2.7, Stage II Preparation Mode 4 (2) Core cooling will be maintained by the Spent Fuel Pool cooling system crosstied with RHR.
Saturday, November 24, 2012 11:57:55AM 99
Sequoyah Dec 2012 SRO Exam 100. Given the following plant conditions:
- A General Emergency has been declared due to a plant event that resulted in a radiation release.
- The duration of the release is estimated to be 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- Wind Direction is from 152 degrees © 10 mph.
- Dose projections and surveys have not yet been performed Which ONE of the following identifies the Protective Action Recommenda tions required in accordance with EPIP-5, General Emergency?
REFERENCE PROVIDED A. Shelter the entire 10 mile EPZ, consider issuance of KI in accordance with the State Plan.
B. Evacuate Al -Bi -Cl -Dl, A2, and A3. Shelter the remainder of the 10 mile EPZ.
C. Evacuate Al-BI-CI-DI, A2, -3, -4, -5, -6 and B2. Shelter the remainder of the 10 mile EPZ.
D. Evacuate Al -BI -Cl -Dl, A2, A3, and B2. Shelter the remainder of the 10 mile EPZ.
You have completed the test!
Saturday, November 24, 2012 11:57:55 AM 100
ANSWER KEY REPORT for Sequoyah Dec 2012 RO Exam Test Form: 0 Answers
- ID 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 AAI.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 11 054 AA2.07 11 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 EK2.01 15 1.00 MCS D 16 W/E11 EK3.2 16 1.00 MCS B 17 W/E05 EA1.1 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 AA1.01 20 1.00 MCS C 21 059 AK2.01 21 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 EA1.3 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 OIOK1.0336 1.00 MCS B 37 012 A3.06 37 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 026A2.0341 1.00 MCS B 42 039 A1.06 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 0611(4.1346 1.00 MCS C Saturday, November 24, 2012 1:21:33 PM
ANSWER KEY REPORT for Sequoyah Dec 2012 RO Exam Test Form: 0 Answers
- ID Points Type 0 47 062 A1.03 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 K3.01 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 58 011 A1.03 58 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
ANSWER KEY REPORT for Sequoyah Dec 2012 SRO Exam Test Form: 0
- II) Points Type 0 1 007 EG2.1.30 76 1.00 MCS B 2 009 EG2.1.23 77 1.00 MCS A 3 056 AA2.42 78 1.00 MCS C 4 057 AA2.19 79 1.00 MCS D 5 062 AG2.4.8 80 1.00 MCS C 6 065 AA2.08 81 1.00 MCS D 7 032 AG2.1.23 82 1.00 MCS B 8 051 AA2.02 83 1.00 MCS D 9 074 AG2.2.44 84 1.00 MCS B 10 W/E01 EA2.1 85 1.00 MCS C 11 003 G2.2.25 86 1.00 MCS C 12 005 G2.4.50 87 1.00 MCS A 13 007 A2.01 88 1.00 MCS C 14 008 A2.02 89 1.00 MCS A 15 076 G2.4.30 90 1.00 MCS A 16 015A2.0191 1.00 MCS D 17 072 G2.2.37 92 1.00 MCS D 18 086 G2.4.11 93 1.00 MCS A 19 G2.1.494 1.00 MCS A 20 G 2.1.36 95 1.00 MCS B 21 G 2.2.5 96 1.00 MCS A 22 G 2.2.23 97 1.00 MCS B 23 G 2.3.14 98 1.00 MCS D 24 G2.4.11 99 1.00 MCS C 25 G2.4.38 100 1.00 MCS D SECTION 1 (25 items) 25.00 Saturday, November 24, 2012 1:21 :49 PM