ML13073A504
| ML13073A504 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/01/2013 |
| From: | Vincent Gaddy Operations Branch IV |
| To: | Entergy Operations |
| laura hurley | |
| References | |
| 50-313/13-002 50-313/OL-13 | |
| Download: ML13073A504 (128) | |
Text
2013 Arkansas Nuclear One Initial NRC License Written Examination RO/SRO KEY
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- 1. C 2. D 3. D 4. B 5. D 6. D 7. A 8. A 9. B 10. B 11. B 12. C 13. A 14. A 15. B 16. B 17. A 18. A 19. C 20. A 21. D 22. D 23. A 24. C 25. B 26. B 27. D 28. B 29. D 30. B 31. D 32. A 33. B 34. B 35. B 36. C 37. C 38. A 39. A 40. D 41. C 42. D 43. D 44. D 45. D 46. C 47. B 48. C 49. A 50. C 51. D 52. C 53. C 54. D 55. D 56. D 57. A 58. C 59. D 60. B 61. C 62. C 63. B 64. B 65. C 66. C 67. A 68. D 69. A 70. B 71. D 72. A 73. C 74. C 75. C 76. B 77. A 78. D 79. A 80. C 81. D 82. D 83. D 84. C 85. A 86. D 87. D 88. A 89. C 90. B 91. A 92. D 93. C 94. B 95. B 96. C 97. C 98. A 99. A 100. C ES-401 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name: Date: 02/22/13 Facility/Unit: ANO Unit One Region: I II III IV Reactor Type: W CE BW GE Start Time:
Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.
Applicant Certification All work done on this examination is my own. I have neither given nor received ai
- d. ______________________________________
Applicant's Signature Results Examination Value
___75____ Points Applicant's Score
__________ Points Applicant's Grade
__________ Percent
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 1 The plant has been operating at full power for 60 days. On day 61, a disturbance on the electrical grid causes an automatic reactor trip to occur.
Reactor thermal power, due to decay heat, should be approximately ________ per cent of rated power 10 seconds after the reactor trip, and approximately ________ per cent of rated power 10 minutes after the reactor trip (choose the closest values).
A. 7.0; 0.2 B. 12.0; 0.2 C. 7.0; 2.0 D. 12.0; 2.0 2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
2 A leak exists on the upper tap of a Pressurizer level transmitter sensing line, causing a PZR steam space leak.
Indicated PZR level will ___________ and actual PZR level will _________.
A. Drop, Drop B. Drop, Rise C. Rise, Drop D. Rise, Rise
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 3 Which of the following ESAS Digital Channel Trip Conditions are designed to preclude a release path from containment to the environment, and to protect fuel cladding, during the worst case Small Break LOCA event?
A. ONLY High reactor building pressure at 4 psig B. ONLY High reactor building pressure at 30 psi g C. ONLY Low reactor coolant system pressure at 1590 psig
D. BOTH high reactor building pressure at 4 psig AND low reactor coolant system pressure at 1590 psig 2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
4 Given: Large break LOCA has occurred ESAS has actuated.
A3 bus is locked out and cannot be re
-energized.
LPI/HPI flow rates are as follows:
"B" LPI flow 3150 gpm "B" HPI pump total flow is 275 gpm Which of the following actions is required per the ESAS EOP for these conditions?
A. Restore full HPI flow on "B" HPI pump.
B. Secure the "B" HPI pump.
C. Energize bus B
-5 from bus B
-6.
D. Swap to RB sump recirculation.
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
5 The plant is steady state at 70% power per Dispatcher request.
Subsequently, you observe the following indications:
"A" MFW flow 2.3 e 6 lbm/hr "B" MFW flow 4.7 e 6 lbm/hr What event would cause this MFW flow discrepancy?
A. "B" MFW pump trip B. "A" T cold instrument failed high C. "A" RCP trip
D. "D" RCP trip
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question _
6_ Given the following conditions:
Loss of all AC power has occurred RCS system leakage of 30 gpm is occurring Atmospheric dump system is operating as expected Turbine driven Emergency Feedwater Pump, P
-7A, is running Makeup flow to the reactor coolant system is not occurring PZR level was 145 inches at the time AC power was lost Which of the following is the MAXIMUM amount of time that can elapse before the pressurizer empties?
A. 20 minutes B. 30 minutes C. 45 minutes D. 60 minutes
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 7 Which of the following Decay Heat Removal System valves relieve to the Reactor Building Sump? 1) PSV-1403, RCS DHR SUCTION LINE RELIEF VALVE
- 2) PSV-1404/-1405, BWST/RBS SUCTION LINE RELIEF VALVES
- 3) PSV-1406/-1407, DHR P UM P S P-34B/P-34A DISCHARGE RELIEF VALVES A. 1 only B. 1 and 2 only C. 2 and 3 only D. 3 only .
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 8 Given: The plant is at 330 MWe following a reactor plant startup.
A momentary loss of intermediate cooling water (ICW) occurred.
Group 6 rod 1 is noted to be 185 deg F five minutes after ICW had been lost.
Group 7 rod 2 stator temperature is noted to be 205 deg F on the plant computer.
All other control rod stator temperatures are between 155 deg F and 165 deg F and stable. According to Procedure 1203.003, "Control Rod Drive Malfunction," which of the following is required to be taken FIRST?
A. Manually trip the reactor and enter Procedure 1202.001, "Reactor Trip" B. Reduce power to less than 300 MWe and remain in Procedure 1203.003 C. Remove the six stator fuses associated with Group 7, rod 2 D. Transfer Group 6, rod1 to the auxiliary power supply 2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
9 The plant is operating at rated thermal power when the loop 'A' RCS narrow range pressure instrument, PT
-1021, INSTANTANEOUSLY fails high.
The effect of this failure is:
A. The Electro
-Magnetic Relief Valve will open.
B. Reactor Protection System channel 'A' will trip.
C. The pressurizer heaters will turn off.
D. The pressurizer spray valve will open.
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 10 Given: Leak rate of 15 gpm has been identified on A OTSG P36A is OP, P36C is ES PZR level is 195 " and slowly loweri ng Per 1202.006, Tube Rupture, which of the following identifies the FIRST operator action that should be taken to raise PZR level?
-3)
B. Open CV-1220, HPI Block valve C. Start P36C and open CV
-1285, HPI Block valve D. Place Pressurizer Level Control (CV
-1235) in HAND and open
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
11 While at 100 percent power, Unit 1 experienced a momentary grid disturbance and a loss of both Main Feedwater pumps.
EFW is not available.
The crew transitions to 1202.004, "Overheating", and the following conditions exist:
Vital and non
-vital buses remain energized and voltage is normal Both Main Feedwater pumps are NOT available All Reactor Coolant Pumps are off Subcooling margin is adequate Both EFIC OTSG levels are 20 inches and lowering Which of the following actions is procedurally required?
A. Perform RT
-16, Feeding Intact SG, to refill OTSGs to between 20 and 40 inches B. Perform RT
-16, Feeding Intact SG, to refill OTSGs to between 300 and 340 inches C. Perform RT
-16, Feeding Intact SG, to refill OTSGs to between 370 and 410 inches D. Initiate HPI Cooling per RT
-4
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
12 When recovering from a Station Blackout condition with no offsite power available and only one EDG operable, which of the following is true?
A. The EDG output breaker should automatically close once the EDG has started and ONE other feeder breaker to it s respective bus is closed B. The EDG output breaker hand switch must be momentarily held in the "close" position to energize its respective bus C. ONE A3-A4 crosstie breaker must be open prior to closing the EDG output breaker
D. The EDG should be used to back feed A2 to restore essential loads.
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 13_ Given the following conditions: Degraded power event has occurred EDGs are powering the 4160 volt buses Core exit temperature is 600 deg F RCS pressure is 1650 psia and decreasing At what RCS pressure will saturation occur?
A. 1543 psia B. 1574 psia C. 1588 psia D. 1606 psia
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Questio n 14 Given the following:
The unit is in Mode 1 Annunciator K01
-A6, "RS2 INVERTER TROUBLE," is in alarm.
RS-2 is aligned to its normal inverter, Y22.
A local operator reports that annunciator K1622
-05, "INVERTER FAILURE" is in alarm locally. Per Technical Specifications and plant procedures, the Inverter Y22 is ___________ and the action taken should be to ________________________ . A. Inoperable, transfer RS2 to Swing Inverter Y25.
B. Operable, manually transfer Y22 static switch to ALT SOURCE.
C. Inoperable, manually transfer Y22 static switch to ALT SOURCE.. D. Operable, transfer RS2 to Swing Inverter Y25.
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 15 Given the following indications at 100% power:
Annunciator D01 UNDERVOLTAGE (K01
-A7) in alarm Annunciator D01 TROUBLE (K01
-D7) in alarm Annunciator D01 CHARGER TROUBLE (K01
-E7) in alarm The reactor has tripped The turbine trip solenoid light is off Breaker position lights on the LEFT side of C10 are off Per Procedure 1203.036, "Loss of 125VDC," which of the following is the FIRST required action? A. Trip the main generator output breakers
B. Transfer D11 to emergency supply D02
C. Trip any running reactor coolant pumps
D. Transfer D12 to emergency supply D02
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
16 The plant is operating normally at rated thermal power with the following conditions:
Service water pumps P4A, P4B, and P4C are in service The service water cross
-tie valves are all open and in "AUTO" The P4B MOD breaker is aligned to provide power from the 'A4' bus Following an Engineered Saf eg uards Actuation System (ESAS) actuation; A. All the crosstie valves will close and P4B will trip in order to maintain train separation B. The crosstie valves between P4B and P4C will remain open to prevent deadheading the pump C. All four crosstie valves will close to establish divisional separation and P4B will continue to provide cooling water to the Aux Cooling heat exchanger D. All four crosstie valves will remain open as long as off
-site power is not lost in order to maximize system reliability
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Questio n 17 Which of the following describes why AOP 1203.024, "Loss of Instrument Air," directs closing the Breathing Air to Instrument Air cross
-connect when Breathing Air pressure drops to less than 80 psig?
A. Prevent the likelihood of personnel overexposure to airborne radiation B. Prevent automatic alignment of the Service Air system to the IA system.
C. Ensure operation of Critical Air Operated Components identified in Attachment A.
D. Ensure proper operation of the BA to IA cross connect line three solenoid operated valves (SV-5503A, SV-5503B and SV
-5503C) 2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
18 Unit 1 was at 100 percent power, normal lineup
. Given: CETs are 610°F, RCS pressure is 1400 psig.
A Loss of Offsite Power occurred and both EFW pumps could not be started.
The crew has just entered 1202.005, "Inadequate Core Cooling".
The following conditions exist:
A3 and A4 are energized by their respective Diesel Generators EFW pump P
-7B is now available HPI pumps P
-36A and P-36C have been started; and full flow has been verified (RT
-3)
In accordance with 1202.005, which of the following actions is required next?
A. Align P-36B to A4, start P
-36B AUX Lube Oil pump and start P
-36B B. Start P-36B AUX Lube Oil Pump and verify automatic start of P
-36B C. Verify RCP Seal Injection is aligned, start LPI pumps and open ERV (PSV
-1000)
D. Start LPI pumps, open ERV (PSV
-1000) and start P
-7B 2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
19 The plant has the following conditions:
The reactor has been tripped 3 Control Rods failed to fully insert The Control Room Supervisor (CRS) directs the At the Controls (ATC) operator to perform Emergency Boration per Repetitive Task 12 (RT 12)
Boric Acid Pump P39A and P3 9B have been started The RUN key has been depressed on the Batch Controller Batch Controller Flow Control Valve CV
-1249 is fully open The ATC operator observes that the Batch Controller output rate is 3 gpm. Per procedure 1202.012, "Repetitive Tasks," the ATC operator should FIRST:
A. Close CV-1250, Batch Controller Outlet B. Open CV-1251, Condensate to Batch Controller C. Secure P39A and P39B D. Adjust pressurizer level control set point to 220"
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 20 The plant is operating at full power. No planned releases are in progress when the following alarms occur:
PROC MONITOR RADIATION HI (K10
-B2) Liquid Radwaste Process Monitor (RI-4642), (C25, Bay 2)
Per Procedure 1203.007, "Liquid Waste Discharge Line High Radiation Alarm," which of the following actions is required to be taken FIRST?
A. Verify that no release is in progress by monitoring discharge flow to flume (FI
-4642) on C19 B. Verify that no release is in progress by verifying RADIATION MONITOR TROUBLE (K10-C1) has also annunciated C. Ensure Treated Waste Discharge to Circulating Water (CW) Flume (CZ
-58) Manual Valve is closed D. Ensure Filtered Waste Monitoring Tank Discharge to CW Flume (DZ
-25) Manual Valve is closed
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 21_ Given: The unit is in Mode 1 The following alarms are received:
o PROC MONITOR RADIATION HI (K10
-B2) o RADWASTE GAS PANEL TROUBLE (K09
-D5) o PROC MONITOR RE
-4830 (Gaseous Radwaste) High Alarm AOP 1203.006, "WASTE GAS DISCHARGE LINE RADIATION HIGH
", directs the crew to verify the automatic actuations for this condition have occurred as designed. Which of the following describes a purpose of this direction?
A. To ensure that Gas Collection Header discharge to Station Vent Plenum is secured B. To ensure that any running Waste Gas Compressors have tripped C. To ensure that Reactor Building Vent Header Isolation Valves CV
-4803 and CV
-4804 close D. To ensure that Auxiliary Building Vent Header gases are diverted to the Waste Gas Surge Tank T-17 2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 22 The following plant conditions exist:
The reactor is tripped Reactor Coolant Pumps are tripped Core Exit Thermocouples read 800 deg F and INCREASING RCS Pressure is 1500 psig and steady Pressurizer level is INCREASING Which of the following procedures should be used to mitigate the most urgent problem?
A. Procedure 1202.004, "Overheating" B. Procedure 1202.010, "ESAS" C. Procedure 1202.002, "Loss of Subcooling Margin" D. Procedure 1202.005, "Inadequate Core Cooling" 2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
23 Which of the following reactor coolant system related signals input to the Integrated Control System (ICS) as part of the plant runback logic?
A. Reactor Coolant Pump breaker positions B. Reactor Coolant Pump differential pressures C. Reactor Coolant System loop flows D. Reactor Coolant System total flow
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 24 A plant power escalation is in progress at 39% power.
The following conditions are observed:
Rapid rise in RCS temperature Rapid rise in RCS pressure Rapid rise in PZR level Megawatt output = 0 MSSV open alarm No other annunciators in alarm except for those expected for the above conditions.
What procedure contains the required mitigating operator actions?
A. 1202.001, Reactor Trip
B. 1203.001, ICS Abnormal Operation C. 1203.018, Turbine Trip Below 43% Power
D. 1203.027, Loss of Steam Generator Feed
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
25 Due to an event, Unit 1 has entered 1203.002, "Alternate Shutdown." All of the actions in the control room have been completed and you have been assigned RO #1 follow-up actions.
While opening CV
-1408, BWST Outlet Valve, you notice significant flow indicated by throttling noise and vibration.
Based on this, what is happening, and what action should you perform FIRST in accordance with 1203.002?
A. HPI is injecting into the reactor vessel. Close HPI Pump Recirculation Block (CV
-1300).
B. BWST is draining to the Reactor Building Sump. Close BWST Outlet Valve (CV
-1408). C. BWST is draining to the Reactor Building Sump. Immediately proceed to the Decay Heat vaults and close the RB Sump
- Line A and B Outlet valves (CV
-1405 and CV
-1406).
D. HPI is injecting into the reactor vessel. Open the other BWST Outlet (CV
-1407).
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
26 The plant has the following conditions:
A LOCA has occurred An RCS cooldown is in progress Calculations preparing for needed boration during the cooldown per procedure 1103.015 Attachments 4 and 5 show that the SDM at the beginning of the cooldown is
- The cooldown begins at 1400 with RCS temperature at 500 deg F and RCS pressure is 1300 psig At 1430, RCS temperature is 440 deg F, RCS Pressure is 1100 psig Based on the given conditions, what action is required to be taken FIRST and what is the MAXIMUM completion time for this action per Technical Specifications?
A. Initiate boration to restore SDM to within COLR limits within 30 minutes B. Adjust the RCS cooldown rate to meet rate restrictions within 30 minutes C. Initiate boration to restore SDM to within COLR limits within one hour D. Adjust the RCS cooldown rate to meet rate restrictions within one hour
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question _27_ Given the following:
SCM has been lost ESAS has actuated HPI has been stopped LPI is injecting 1202.010 ESAS has been entered RCS pressure has just dropped below 140 psig Boric Water Storage Tank has just reached six feet in level What is the NEXT required operator action and the MAXIMUM allowed time to perform this action? A. Isolate Core Flood Tank outlet valves; ten minutes B. Align LPI pump suction to RB sump; ten minutes C. Isolate Core Flood Tank outlet valves; three minutes D. Align LPI pump suction to RB sump; three minutes
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question
_28__ Given:
RCP 32A is running with the Normal and Emergency HP Lift Oil Pumps both stopped, NOT in pull
-to-lock. If RCP 32A handswitch is taken to STOP with no other manual actions, (1) How will the HP Lift Oil Pumps respond?
(2) Once RCP 32A shaft is stopped, what is the MINIMUM action required to maintain the Normal HP Lift Oil Pump stopped?
A. (1) The Normal and Emergency HP Lift Oil Pumps (P-63A & P-80A) should both start automatically.
(2) The Normal HP Lift Oil Pump P
-63A handswitch must be taken to STOP B. (1) The Normal and Emergency HP Lift Oil Pumps (P-63A & P-80A) should both start automatically.
(2) The Normal HP Lift Oil Pump handswitch P
-63A must be taken to STOP THEN PULL
-TO-LOCK C. (1) The Normal HP Lift Oil Pump P
-63A should start automatically. The Emergency HP Lift Oil Pump P
-80A should start automatically only if the Normal HP Lift Oil Pump P
-63A fails to start. (2) The Normal HP Lift Oil Pump P
-63A handswitch must be taken to STOP D. (1) The Normal HP Lift Oil Pump P
-63A should start automatically. The Emergency HP Lift Oil Pump P
-80A should start automatically only if the Normal HP Lift Oil Pump P
-63A fails to start. (2) The Normal HP Lift Oil Pump P-63A handswitch must be taken to STOP THEN PULL
-TO-LOCK 2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 29 Given: Unit One is operating at 100% power.
An ICS malfunction causes Tave to rise 2 deg F. What is the effect on the Pressurizer (PZR), including level and pressure, during this transient?
A. PZR level will rise to a higher steady state level. RCS pressure will drop to a lower value initially.
B. PZR level will rise to a higher steady state level. RCS pressure will rise to a higher value initially.
C. Makeup flow will rise to restore PZR level to setpoint. RCS pressure will drop to a lower value initially D. Makeup flow will drop to restore PZR level to setpoint. RCS pressure will rise to a higher value initially.
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
30 Given: The reactor is in MODE 5, the Decay Heat Removal System (DHRS) in service.
RCS pressure is at atmospheric pressure.
RCS temperature is 85 deg F and slowly rising.
An operator is in the process of increasing DHRS and service water flow rates, however, in order to minimize the potential for vibration induced piping damage, DHRS total flow should be limited to no more than __________ gpm.
A. 1600 B. 2000 C. 3550 D. 4000 2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 31 Given the following:
Plant is in Mode 6 Only P-34B Decay Heat Pump is running Which of the following would cause a loss of Decay Heat Removal?
A. A-1 voltage of 31 5 0 volts B. A-2 voltage of 31 5 0 volts C. B-5 voltage of 428 volts
D. B-6 voltage of 428 volts
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
32 THIS IS AN OPEN REFERENCE QUESTION.
The following is a diagram of analog channels for ESAS:
I&C Technicians have been authorized to perform maintenance on Analog Channel 1, and the following occur over the next two minutes (no operator action):
- 2. K11-E7 "ANALOG LOGIC BUFFER REMOVED" alarms 3. Power is lost to Analog Channel 1
- 4. PT-2406 fails high
What is the status of HPI and LPI?
A. Only LPI initiated B. Only HPI initiated C. Both HPI and LPI initiated D. Neither HPI nor LPI initiated
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
33 Quench Tank level is high
. The CRS directed transfer of water from the Quench Tank to the Clean Liquid Radwaste System per Section 13.0 of procedure 1103.005, "Pressurizer Operations," and during this evolution the following occurs:
K09-B4, "Quench Tank Level HI/LO" alarms Quench Tank level LIS-1051 reads 3800 gallons In reference to design limitations, which of the following operational problems should this present? A. Inadequate NPSH for the transfer pump B. Insufficient cooling water during relief operations C. Inadequate water level for level indication D. Loss of a loop seal on the relief lines
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question _34__ Given the following conditions:
Plant startup is in progress RCS pressure is 150 psig RCS temperature is 225 F Pressurizer level is 90 inches 1103.005, "Pressurizer Operation," is being utilized to draw a steam bubble in the pressurizer A three minute blow through the ERV resulting in a Quench Tank pressure rise of __________ psig in conjunction with saturation conditions in the __________ is indication that a steam bubble has now formed in the pressurizer.
A. at least three; RCS B. less than or equal to one; pressurizer.
C. At least three; pressurizer D. less than or equal to one; RCS
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question
_35__ The Intermediate Cooling Water system is aligned as follows:
P-33A is in service supplying the Non
-Nuclear loop; P-33B is in service supplying the Nuclear loop; P-33C is in standby.
Which of the following correctly describes the operation of the Intermediate Cooling Water System in this alignment
? A. P-33C should start immediately when P-33B discharge pressure drops below 35 psig.
P-3 3B to P-3 3C Suction / Discharge Cross
-Connect valves CV
-2241 and CV
-2239 should automatically shut.
B. P-33C should start when P
-33B discharge pressure drops below 35 psig for >10 seconds. P
-3 3B to P-3 3 C Suction / Discharge Cross
-Connect valves CV
-2241 and CV
-2239 should automatically shut.
C. P-33C should start immediately when P
-33B discharge pressure drops below 35 psig.
P-3 3B to P-3 3C Suction / Discharge Cross
-Connect valves CV
-2241 and CV
-2239 should remain open.
D. P-33C should start when P
-33B discharge pressure drops below 35 psig for >10 seconds. P
-3 3B to P-3 3C Suction / Discharge Cross
-Connect valves CV-2241 and CV
-2239 should remain open.
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 36 To prevent thermal stress across the pressurizer spray valve, Manual Bypass Valve RC
-4 provides a flow path for bypass flow to limit spray valve differential temperature.
RC-4 is operated to bypass flow across the __________.
A. Auxiliary Spray Line Tie
-in B. Motor Isolation Valve CV
-1009 C. Spray Flow Control Valve CV
-1008 D. Manual Isolation Valve RC
-3
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
37 The reactor is in the process of being started up with the following conditions:
All four RCPs are running.
The power range instruments indicate reactor power is approximately 12%
. The high startup rate rod hold for Intermediate Range Detector IR 3 has failed to trip. Given these conditions; A. A rod hold will occur if the Source Range Instruments sense a startup rate of 2 decades per minute. B. A rod hold will occur if the Intermediate Range Instruments sense a startup rate of 3 decades per minute.
C. The high start up rate rod hold has been bypassed.
D. The high start up rate rod hold will inhibit rod withdrawal until IR 3 is repaired or bypassed.
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 38 Reactor Building Pressure Transmitter (PT
-2407) has failed high causing an ES CH3 Trip (analog 3) and the ESAS Partial Trip annunciator (K11
-F6) to alarm.
With the above conditions, a power loss to which of the following would cause an ESAS actuation?
A. RS1 B. B71 C. RS3 D. B72 2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 39 Which of the following load centers supply power to the five (5) Reactor Building Ventilation Fans? A. B5, B6 and B7
B. B3, B4 and B2 C. B3, B4 and B7
D. B5, B6 and B2
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
40 Given: Reactor has tripped
. RCS pressure 1200 psig Reactor Building pressure 20 psia
What would be the consequences if the Reactor Building Cooler Chilled Water Bypass Dampers remained latched?
A. RB cooling fan motors would overheat B. Excessive heat load on the Chilled Water System C. Damage to RB ventilation plenum from excessive pressure D. Inadequate cooling of the RB atmosphere
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question _
41__ Which of the following are the correct cooling water source and bearing cooler for Reactor Building Spray Pump, P
-35B?
A. CCW, E-47B B. SW, VU C-1C and 1D C. SW, E-47B D. CCW, E-47A
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 42 Given that a Steam Generator Tube Rupture has occurred on "A" OTSG, answer the following:
(1) Per EOP 1202.006, "Tube Rupture," when is the crew required to start monitoring for the need to isolate the bad OTSG? (2) If "A" OTSG is isolated, which radiation monitor should be used to monitor the activity of the affected OTSG?
A. (1) When RCS pressure is < 700 psig (2) "A" OTSG N
-16 Detector (RI
-2691) B. (1) When RCS pressure is < 700 psig (2) Steam Line "A" High Range Rad Monitor (RI
-2682) C. (1) When RCS T-hot is < 490 deg F (2) "A" OTSG N
-16 Detector (RI
-2691) D. (1) When RCS T-hot is < 490 deg F (2) Steam Line "A" High Range Rad Monitor (RI
-2682) 2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 43 Per the Technical Specification Bases, the PRIMARY reason for maintaining Technical Specification Limiting Condition for Operation cooldown limits for the reactor coolant system (RCS) from hot shutdown conditions using the main steam system IS:
A. To ensure RCS pressure/temperature limits remain within the design basis accident analysis B. To ensure RCS pressure/temperature limits remain within ASME code requirements
C. To avoid pressurizer thermal shock and possible pressurizer failure D. To avoid conditions that might cause brittle fracture of the Reactor vessel
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question: 44 The reactor is at rated thermal power when one of the Reactor Coolant Pumps (RCPs) trips.
According to Procedure 1102.004, "Power Operations," with only three RCPs in operation, the MAXIMUM allowed feedwater flow to each steam generator is __________ lbm/hr due to feedwater flow induced vibration concerns at the resultant reactor power level
. A. 1.2 x E6 B. 4.0 x E6 C. 5.4 x E6 D. 5.7 x E6 2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question: 45 A Steam Line Break has occurred. The following conditions exist: The Reactor is tripped.
"A" OTSG pressure = 620 psig. "B" OTSG pressure = 550 psig.
All RCPs are running.
ESAS Channel 3 and 4 have not actuated.
If all safety systems function as designed, what are the expected statuses of the OTSGs?
A. Both "A" and "B" OTSGs are being fed by Main Feed B. Both "A" and "B" OTSGs are being fed by Emergency Feed C. "A" OTSG is being fed by Main Feed, "B" OTSG is being fed by Emergency Feed D. "A" OTSG is being fed by Main Feed, "B" OTSG is not being fed
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
46 Given: Both units have experienced a degraded power condition and the crew is performing 1202.007 (Degraded Power)
All feedwater is lost EDG #1 will not start EDG #2 is running P-7A tripped and will not reset Adequate subcooling margin exists Overheating condition exists In accordance with 1202.007, what action should operators perform next to restore maximum heat removal
? A. Run two HPI pumps for HPI cooling per RT
-4 B. Establish atmospheric dump pressure control on both SGs C. Cross-tie buses A3 and A4
D. Restore Instrument Air for ADV control
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
47 THIS IS AN OPEN REFERENCE QUESTION.
Isolation of bus B51 for maintenance would remove AC power to which load associated with EDG #1?
A. Soak Back Pump (P
-106A-1) B. Oil Circulating Pump (P
-106A-2) C. Starting Air Compressor (C
-4A1) D. C-4A1 Aftercooler Blower/Dryer/Motorized Drain Valve
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question _48__ Given: An electrical fault has made the normal supply to D11 inoperable D11 should be transferred to its emergency supply Which of the following is a concern per procedure 1107.004, "Battery and 125 VDC Distribution?"
A. The discharge rate of the battery cannot be monitored in this configuration.
B. The static guard circuit is disabled and could cause inadvertent grounds on the bus.
C. A single fault may disable both trains of safety equipment such as EDGs and ES pumps.
D. It will prevent EDG#2 from starting, should it be required in an emergency situation.
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 49 Given: A Station Blackout condition exists.
Battery Chargers are not loade
Answer the following questions:
(1) How is generator output voltage adjusted in this condition?
(2) What EDG protection is functional?
A. (1) Use the manual voltage adjuster on Exciter Control Panel.
(2) Mechanical Overspeed.
B. (1) Use the manual voltage adjuster on Exciter Control Panel.
(2) Local Emergency Stop Pushbutton.
C. (1) Adjust the setpoint for the automatic voltage adjuster.
(2) Mechanical Overspeed.
D. (1) Adjust the setpoint for the automatic voltage adjuster.
(2) Local Emergency Stop Pushbutton.
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 50 Per the Technical Specifications, which of the following is the MAXIMUM fuel oil storage tank inventory which would still REQUIRE the associated emergency diesel generator to be declared INOPERABLE IMMEDIATELY?
A. 18,000 gallons
B. 17,500 gallons C. 17,000 gallons
D. 16,500 gallons
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
51 One function of the Process Radiation Monitoring (PRM) System associated with monitoring the
_____________ is to automatically isolate the associated process flow in the event of a high radiation signal.
A. Intermediate Cooling Water System B. Steam Generators N
-16 activity C. Main Condenser Air Discharge System D. Waste Gas System
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 52 During plant operation at 100% power
- Annunciator alarm K07-A 5 (" A" OTSG N-16 TROUBLE) is received with RI-2691 reading 5.5 x 10³ cpm and stable Annunciator alarm K07-A6 ("B" OTSG N
-16 TROUBLE) is received with RI-2692 reading 4 x 10³ cpm and slowly rising After operators have taken both RI
-2691 and RI
-2692 from GROSS to ANALYZER per 1203.012F, ANNUNCIATOR K07 CORRECTIVE ACTION, the following readings are observed:
RI-2691 is reading 5.5 x 10³ cpm and stable RI-2692 is reading 3.5 x 10³ cpm and slowly rising Which of the following explains the observations above?
A. RI-2692 has a low voltage condition as confirmed by a drop in count rate following completion of 1203.012F.
B. RI-2691 is operating properly and a steam generator tube leak is confirmed as detected by a steady 5.5 x 10³ cpm reading.
C. RI-2691 has failed to 5.5 x 10³ cpm as confirmed by no change in count rate.
D. Both RI-2691 and RI
-2692 are operating properly with a confirmed steam generator tube leak present in both steam generators with different leak rates.
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
53 Given: ESAS actuation has occurred on channels 1 through 6 SW Pump P-4A does not start, P
-4B is aligned to the other SW loop HPI Pump P
-36B is aligned to the A4 bus
Which components' temperatures should be closely monitored until P-4B can be re
-aligned?
A. Circ Water Pumps P-3A & P-3B, HPI pump P
-36B B. Circ Water Pumps P
-3C & P-3D, HPI pump P
-36A C. Circ Water Pumps P
-3A & P-3B, HPI pump P
-36A D. Circ Water Pumps P
-3C & P-3D, HPI pump P
-36C
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
54 Which of the following Instrument Air (IA) indications in the control room require the initiation of a reactor trip?
A. PMS Point P5409 (Unit 1 IA pressure) reads 58 psig B. "INST AIR HEADER PRESS LO" alarm comes in C. PMS Point P3013 (Unit 2 IA pressure) reads 40 psig D. INSTRUMENT AIR HEADER PRESS (PI
-5409) reads 25 psig
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question
_55__ A LOCA is in progress with the following conditions; RCS Pressure is 1090 psig and slowly lowering ESAS has actuated RB pressure is 17.8 psia and steady 1202.005, INADEQUATE CORE COOLING, has been entered Which of the following correctly describes the ESAS channels that have actuated AND the appropriate repetitive task to be performed?
A. Channels 7, 8, 9, 10
- RT 9, MAXIMIZE RB COOLING B. Channels 1, 2, 3, 4
- RT 2, INITIATE HPI C. Channels 7, 8, 9, 10 - RT 2, INITIATE HPI D. Channels 1, 2, 3, 4
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 56 When a steam bubble exists in the Pressurizer, an increase in RCS temperature causes a Pressurizer ________ to occur.
The resultant pressure change is mitigated by ____
____. A. out-surge pressurizer spray flow quenching a portion of the steam bubble.
B. out-surge water in the pressurizer flashing to steam.
C. in-surge water in the pressurizer flashing to steam.
D. in-surge pressurizer spray flow quenching a portion of the steam bubble.
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 57 With the plant operating at 100% power, DC power is lost to non nuclear instrumentation channel X, and AC power is lost to non nuclear instrumentation channel Y.
Per Procedure 1203.047, "Loss of NNI Power," which of the following actions is required to be taken? A. Manually trip the reactor and maintain pressurizer level using a high pressure injection pump B. Place main feedwater, reactor demand, and diamond in HAND and operate the turbine bypass valves manually to control steam generator pressure C. Manually trip the reactor and close Reactor Coolant Pump Seal Injection Block Valve CV
-1206 D. Place main feedwater, reactor demand, and diamond in HAND and operate pressurizer heater banks as necessary to maintain reactor coolant system pressure
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
58 An Auxiliary Operator (AO) has been sent to check the breaker position for Hydrogen Recombiner 55A.
The AO calls the control room and asks where he would find the breaker.
The control room should direct the AO to:
A. A3 B. B33 C. B53 D. Y3
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
59 Given: The plant is operating at 80% power.
"A" OTSG NNIX Downcomer Temperature Instrument has failed LOW.
This malfunction would affect the output of "A" OTSG NNIX ____(1)___ level. This indicated level would read ____(2)____ than actual OTSG level.
(1) (2) A. Startup Higher B. Operate Higher C. Startup Lower D. Operate Lower 2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
60 The crew is performing a turbine startup in accordance with procedure 1106.009, TURBINE STARTUP (WARMUP & ROLL).
The CBOT performs the following step to latch the turbine:
7.11.3 Latch by one of the following methods:
( ) At panel C01, depress LATCH pushbutton and hold until PB backlight turns on and UNIT TRIP light turns off.
What valves should be open when this step is complete?
A. All Governor Valves and Intercept Valves only B. All Intercept Valves and Reheat Stop Valves only C. All Reheat Stop Valves and Throttle Valves only D. All Throttle Valves and Governor Valves only
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
61 During plant startup, the Condenser Vacuum System is being started up per procedure 1106.010, "Vacuum System Operations."
Preparations for both Condenser Vacuum Pumps C
-5A and C-5B, including setting the position of the pump inlet valves, are in progress.
C-5A is started, with C-5B in auto standby During the initial run of C
-5A, o The pump's amperage is 165 A o The pump's air flow is 33 scfm o Pump inlet valve V
-5A is currently 2 turns open Per procedure 1106.010, what action should be taken?
A. Open V-5A an additional turn B. Fully open V-5A C. Close V-5A a part turn D. Fully close V
-5A 2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question
_62__ THIS IS AN OPEN REFERENCE QUESTION.
The following conditions exist in the plant; Waste Gas System is aligned to compress WGDT T
-18A H2/O2 Analyzer C119A is inoperable Waste Gas Surge Tank, T
-17, H2 concentration has risen to 40%
O2 concentration is 7%
To what piece of equipment should H2/O2 Analyzer C119 be aligned to?
A. Gas Collection Header B. Aux Building Vent Header C. Inservice WGDT T
-18 D. Waste Gas Surge Tank T
-17 2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 63 Which of the following Area Radiation Monitors will cause a ventilation realignment when it alarms? A. RE-8060, Reactor Building High Range Radiation Monitor B. RE-8001, Control Room Area Radiation Monitor C. RE-8009 , Spent Fuel Pool Radiation Monitor D. R E-8017 , Fuel Handling Area Radiation Monitor
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 64 What is the design purpose of the backup air accumulators fo r the MSIVs?
A. To ensure air from the MSIV backup accumulators operate the Atmospheric Dump Valve for 30 minutes due to loss of Instrument air B. To ensure air from the MSIV backup accumulators will maintain Main Steam Isolation valve open for 30 minutes due to loss of Instrument air
C. To ensure air from the MSIV backup accumulators to operate the Atmospheric Dump Valve for 60 minutes due to loss of Instrument air D. To ensure air from the MSIV backup accumulators will maintain Main Steam Isolation valve open for 60 minutes due to loss of Instrument air
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
65 The plant is at 100% power when the following annunciator alarms: K16-C2, "TURB/MAIN GEN CO2 SYS TROUBLE" Simultaneously, the Inside AO reports leaking oil has ignited on the Main Turbine #3 bearing housing.
The Inside AO also reports that there are NO INDICATING LIGHTS lit on the C
-420 Turbine Cardox panel.
In ADDITION to tripping the main turbine and reactor, which of the following actions should be performed to limit damage from this fire?
A. Actuate the Cardox system via the applicable OPERATE switch on the C
-463 panels B. Depress the TRIP button for bearing #2/3 to the right of C
-420 C. Break glass and rotate the manual handle for bearing #2/3 to OPEN D. Depress the SPURT button for bearing #2/3 to the right of C
-420
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 66 You are assigned as an escort for visiting contractors.
In accordance with OP
-1000.019, "Station Security Requirements,"
Which of the following describes the MAXIMUM number of visitors that you may provide escort for at one time in a vital area, and the process required for entry into a Vital Area?
A. Three (3) visitors; visitors present badge to card reader first prior to entering a Vital Area.
B. Three (3) visitors; escort presents badge to card reader first prior to entering a Vital Area.
C. Five (5) visitors; visitors present badge to card reader first prior to entering a Vital Area.
D. Five (5) visitors; escort presents badge to card reader first prior to entering a Vital Area.
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
67 Given: The crew has entered 1203.019, "High Activity in Reactor Coolant" Due to dose rates you are directed to isolate Letdown and swap RCP seal bleed
-off from the Normal path to the Alternate path (Quench Tank.)
Which of the following combinations of indications are correct for the desired plant line
-up?
A. CV-1221, "L/D Cooler Outlet," green light SV-1270, "Seal Bleedoff Alternate Path," red light CV-1270, "Seal Bleedoff Normal Path," green light
B. CV-1221, "L/D Cooler Outlet," green light SV-1270, "Seal Bleedoff Alternate Path," green light CV-1270 ,"Seal Bleedoff Normal Path," red light C. CV-1221, "L/D Cooler Outlet," red light SV-1270, "Seal Bleedoff Alternate Path," red light CV-1270, "Seal Bleedoff Normal Path," green light D. CV-1221, "L/D Cooler Outlet," red light SV-1270, "Seal Bleedoff Alternate Path," green light CV-1270, "Seal Bleedoff Normal Path," red light.
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
68 Per procedure 1015.001, "Conduct of Operations," who is the operations staff required to contact when any annunciator is removed from service for malfunctioning alarms?
A. Operations Work Liaison B. Design Engineering
C. Engineering Progra ms D. System Engineering
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question _
69__ It is necessary to manipulate a valve within the boundary of an existing tag
-out. What is the requirement per the Configuration Control Program?
A. Manipulation of component must be less than one hour and must be returned to its normal position prior to next Operations shift turnover B. Manipulation of component must be less than one hour and must be returned to its normal position within twenty four hours of the manipulation C. Manipulation of component must be less than thirty minutes and must be returned to its normal position prior to next Operations shift turnover D. Manipulation of component must be less than thirty minutes and must be returned to its normal position within twenty four hours of the manipulation
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 70 A number of tools are available to track the status of equipment.
Some of these tools are:
- 1. LCO Tracking Record
- 2. eSOMS Configuration Control Record
- 3. Maintenance Configuration Tracking Log Sheet
- 4. Component Out of Position Log
- 5. Condition Report
- 6. Safety System Status Board The Surveillance Coordinator calls you, the Control Room Supervisor, and states that Hydrogen Recombiner, M
-55B, surveillance frequency was exceeded.
Which of the above items should you use to document entry of the LCO?
A. 2, 3, 5
B. 1, 5, 6 C. 1, 3, 5 D. 2, 4, 5
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 71 The following plant conditions exist:
The reactor is tripped Adequate subcooling margin does NOT exist Reactor Coolant Pumps are tripped Emergency Feedwater is supplying both Steam Generators Reactor Coolant System Pressure is 2450 psig Per Procedure 1202.002, "Loss of Subcooling Margin," which of the following actions should be performed FIRST?
A. Attempt to restore main feedwater flow to augment emergency feedwater flow to the steam generators
B. Bump a reactor coolant pump in the loop with the lowest steam generator level C. Lower steam generator pressure until secondary saturated temperature is 20 - 40 deg F less than core exit thermocouple temperature D. Open the electromatic relief valve and lower pressurizer pressure to less than or equal to 16 50 psig 2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
72 At ANO there are several highly sensitive radiation detectors, such as the Main Steam N
-16 Radiation Monitors, that us e photomultiplier tubes as part of their radiation detection process.
Radiation monitors that use photomultiplier tubes are ____________ type detectors
.
A. Scintillation B. Geiger-Mueller C. Ion Chamber D. Proportional
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question 73 In accordance with EN-RP-105, "Radiological Work Permits," a Radiation Work Permit would identify "An area, accessible to individuals, in which radiation levels external to the body could result in an individual receiving a deep dose equivalent greater than or equal to 1 Rem (10mSv) in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 cm (~12 inches) from the radiation source or from any surface that the radiation penetrates." as a __________.
A. Radiation Area B. High Radiation Area
D. Very High Radiation Area
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
74 Which of the following upsets in heat transfer has the HIGHEST priority per 1015.043, "ANO
-1 EOP/AOP User's Guide"?
A. Overcooling
B. Overheating C. Loss of Adequate SCM
D. Steam Generator Tube Rupture
2013 Arkansas Nuclear One Initial NRC License Written Examination RO Question:
75 Given: ANO Unit 1 is operating in Mode 1 The Unit 1 Shift Manager passes out, and medical assistance is requested A replacement Shift Manager has been contacted at home and will report onsite to take the watch within the hour
During the time period before the replacement takes the watch, per procedure 1903.010, "Emergency Action level Classification,"
who has the FIRST responsibility of Emergency Direction and Control if an event were to occur at Unit 1?
A. The Unit 1 Shift Technical Advisor B. The Unit 2 Shift Manager C. The Unit 1 Control Room Supervisor D. The Technical Support Center Director
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: 02/22/13 Facility/Unit: ANO Unit One Region: I II III IV Reactor Type: W CE BW GE Start Time:
Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent 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.
______________________________________
Applicant's Signature Results RO/SRO-Only/Total Examination Values 75 / 25 / 100 Points Applicant's Scores
/ / Points Applicant's Grade
/ / Percent 2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question _
76__ Given the following:
Reactor has tri pped Pressurizer level is 285 inches and rising slowly CET temperatures 590F and rising RCS pressure is 135 psig and lowering slowly HPI/LPI have initiated BWST suction has been shifted to RB sump suction Subsequently the RCS has returned to Region 1 of Figure 4.
Which procedure would initially be entered with the given plant conditions and what is the correct transition?
A. 1202.002 (Loss of Subcooling Margin) with a transition to 1203.041 (Small break LOCA cooldown) B. 1202.005 (Inadequate Core Cooling) with a transition to 1202.010 (ESAS)
C. 1202.002 (Loss of Subcooling Margin) with a transition to 1202.010 (ESAS)
D. 1202.005 (Inadequate Core Cooling) with a transition to 1203.041 (Small break LOCA cooldown)
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question 77 The plant is at 9 0% with current identified RCS leakage of 1.0 gpm. All other plant parameters are normal and as expected.
Subsequently the following occur:
RCP VIBRATION HI (K08
-B6) alarms. The plant computer shows a low oil reservoir for RCP P32B.
P32B indicates motor bearing temperature is 168 deg F. All other RCP motor bearing temperatures are normal.
As Control Room Supervisor you direct operators to "Reactor Coolant Pump and Motor Emergency," 1203.31, Section _____________ and the correct action for plant conditions is
____________.
A. 5, Motor/Bearing Trouble; initiate reactor building entry to add oil to the reservoir B. 2, Seal Failure; trip RCP 32B and verify proper ICS response
C. 5, Motor/Bearing Trouble; trip RCP 32B and verify proper ICS response
D. 2, Seal Failure; trip RCP 32B and perform immediate actions for reactor trip
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question 78 The plant is in Mode 4 following a normal reactor shutdown from full power with the following conditions:
Decay Heat Removal (DHR) Pump P
-34A is in service P-34 Suction Temperature on TI 1404 is 283 degrees F Annunciator K09
-C8 "DH PUMP A/B SUCT TEMP HI" is in alarm Service Water is in service and operating normally There is NO leakage from the Decay Heat System Per Procedure 1203.012H, "Annunciator K09 Corrective Action," which of the following actions is REQUIRED to be taken?
A. Place DHR Pump P
-34B in service and secure DHR Pump P
-34A B. Throttle open DHR Supply to Makeup Suction Valve CV
-1276 C. Throttle SW to Decay Heat Cooler SW
-22A to scribed "T" position.
D. Throttle closed E
-35A Cooler Bypass Valve CV
-1433 2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question:
79 Reactor power is 15% and Main Feedwater Pump (MFWP) P
-1A is out of service while the thrust bearing wear detector is being replaced. Then the following sequence of events takes place: The MFW P-1B Main Oil Pump trips and both standby oil pumps auto start Both MFW P
-1B standby oil pumps trip about a minute later The "B MFP TURBINE TRIP" (K07
-A8) alarm annunciates The control room operators report MFW P
-1B has failed to trip and they are unable to trip it from C02.
Indicated total feed flow is zero.
S/G levels are now 30" and lowering.
The Inside Auxiliary Operator (IAO) is directed to locally trip MFWP 1B.
Based on this sequence of events and assuming all the other plant equipment operated as designed, the CRS should:
A. Immediately trip the reactor and implement EOP 1202.001, Reactor Trip.
B. Trip the reactor when S/G level reaches 15" and enter EOP 1202.001, Reactor Trip.
C. Manually actuate EFW per 1203.027, Loss of S/G Feed, and stabilize S/G level.
D. Enter Procedure 1203.027, Loss of S/G Feed, when the IAO locally trips MFW P 1B
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question 80 THIS IS AN OPEN REFERENCE QUESTION.
Given: The unit is operating at 100% power.
At 0900 on February 18, 2013 , it was discovered that one connected cell's float voltage on D06 was determined to be 2.02 V.
At 1000 on February 18, 2013 , it was discovered that one connected cell's float voltage on D07 was determined to be 2.07 V.
Based on the above conditions, Technical Specifications require the unit to be in MODE 3 no later than what time?
A. 0500 on February 20, 2013 B. 0500 on February 19, 2013 C. 1700 on February 18, 2013
D. 1600 on February 18, 2013
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question:
81 Given: Reactor tripped and the crew is operating in Loss of Subcooling Margin (1202.002).
P-7A tripped.
P-7B is out for maintenance.
CET temperatures are 610°F and rising.
Offsite power is subsequently lost
. Both DGs are supplying their emergency buses.
RCS pressure is 1800 psig. Based on the above current conditions, the correct procedure transition is to ____
___.
A. Remain in Loss of Subcooling Margin (1202.002)
B. Overheating (1202.004)
C. Inadequate Core Cooling (1202.005)
D. Degraded Power (1202.007)
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question:
82 Given: On March 3, 2013, the plant is preparing for startup following refueling
. RCS temperature is 525 deg F. RCS pressure is 21 70 psig and slowly rising
. Preparations are being made to withdraw control rods.
At 1300, the following conditions occur:
"PZR LEVEL HI/HI" alarm is in LT-1001 (controlling channel) reads 280", increasing at 2"/minute With no operator action taken, what Technical Specification LCO action would be required using the MAXIMUM amount of time to restore the Pressurizer to operable status?
A. Restore pressurizer level within limits by 1400 B. Place the plant in Mode 3 by 1920 C. Place the plant in Mode 3 by 2000 D. Restore pressurizer level within limits by 1420
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question _
83__ Given the following:
Reactor is at 100% power Pressurizer level has reached 205 inches and is now dropping slowly OTSG N-16 monitor alarms on both S/Gs 1202.006, TUBE RUPTURE, has been entered
Which of the following indications CONCLUSIVELY shows on which S/G the tube rupture exists and what is the required next step with the given plant conditions?
A. Steam Line High Range RAD Monitors, Begin controlled shutdown at > 5%/minute B. Plant Monitoring System N16T screen, Trip the reactor C. Steam Line High Range RAD Monitors, Trip the reactor
D. Plant Monitoring System N16T screen, Begin controlled shutdown at > 5%/minute
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question 84 Given: A reactor trip and ESAS actuation occurred 60 seconds ago.
Containment temperature and pressure are at their alarm set points and rising.
The reactor operator announces Loss of Subcooling Margin.
As Control Room Supervisor, you direct the crew to __________ RCPs per 1202.002, Loss of Subcooling Margin, step 1. The reason for this is ____________________.
A. Trip RCPs; to prevent damage to the pump motors when the RCS flashes to steam
B. Leave RCPs running; to prevent uncovering the core C. Trip RCPs; to prevent the void fraction from exceeding design limits.
D. Leave RCPs running; to maintain forced flow through the core for decay heat removal
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question 85 The following plant conditions exist:
Reactor tripped due to a loss of both MFWPs approximately 15 minutes ago.
Annunciator K02
-B6 "A3 L.O. RELAY TRIP" is in alarm.
AFW pump, P
-75, is tagged out for maintenance.
Steam Driven EFW Pump, P
-7A, has tripped on overspeed.
RCS pressure is 1800 psig. CETs are 6 00°F. Both OTSG levels are 30".
Which of the following procedures should be in use for the above conditions?
A. 1202.002, Loss of Subcooling Margin B. 1202.004, Overheating C. 1202.011, HPI Cooldown D. 1203.037, Abnormal ES Bus Voltage
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question:
86 THIS QUESTION IS OPEN REFERENCE.
Following an outage, the reactor has been started up and is now operating at rated thermal power. A system engineer calls the control room and informs the crew three Emergency Core Cooling System (ECCS) valves in one ECCS train were not tested during the outage as required by Technical Specification (TS) Surveillance Requirement 3.5.2.3 (provided).
The three valves were last tested 20 months ago and one of the valves is inaccessible with the reactor at power.
A mid-cycle outage is scheduled to occur in 12 months. The control room crew ____________.
A. Is required to immediately enter TS 3.5.2.A.
B. Is required to enter TS 3.5.2.A when the 25% "grace period" expires.
C. Can delay entering TS 3.5.2.A for a maximum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the time of discovery if a risk assessment is performed and the risk is managed. Entry is then required.
D. Can delay entering TS 3.5.2.A until the mid
-cycle outage if a risk assessment is performed and the risk is managed.
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question 87 Given the following:
A high RCS pressure transient occurred 3 minutes ago Current plant conditions:
RCS pressure is 2050 psig and lowering All Pressurizer heaters are on Pressurizer level is 235 in and rising Quench Tank (T
-42) level is rising Annunciator alarm RELIEF VALVE OPEN (K09
-A1) There is a rise on acoustic Relief Valve Monitor (VYI
-1000A) Which of the following identifies the correct action and procedure required for these conditions?
A. Take manual control of Pressurizer Level Control Valve (CV
-1235) and open per OP
-1203.026, Loss of Reactor Makeup.
B. Close the Spray Line Isolation Valve (CV
-1009) per OP
-1203.015, Pressurizer Systems Failure, Section 6, Pressurizer Spray Valve (CV
-1008) Failure.
C. Trip the reactor and refer to EOP series (1202.XXX) per OP
-1203.015, Pressurizer Systems Failure, Section 2, Leaking Pressurizer Code Safety Valve.
D. Close the ERV Isolation Valve (CV
-1000) per OP
-1203.015, Pressurizer Systems Failure, Section 1, Electromatic Relief Valve (PSV
-1000) System Failure or Leak.
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question:
88 Given: Reactor tripped and the crew is operating in Overheating (1202.004)
Subcooling is inadequate CET temperatures are lowering Dry OTSGs are being refilled with EFW Adequate primary to secondary heat transfer cannot be established due to problems with EFW flow control RCP services cannot be restored Based on this, the crew should _______.
A. Go to HPI Cooldown (1202.011)
B. Remain in Overheating (1202.004) until heat transfer can be established
C. Go to Inadequate Core Cooling (1202.005)
D. Go to Reactor Trip (1202.00 1)
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question:
89 Which of the following conditions requires entry into Technical Specification 3.8.4, "DC Sources, Operating" and what is the bases for Technical Specification 3.8.4?
A. D04A, "Battery Charger" inoperable and D06, "Battery" operabl
- e. Bases is to insure reactor coolant pressure boundary limits are not exceeded as a result of abnormalities B. D04B, "Battery Charger" inoperable and D03B, "Battery Charger" inoperable.
Bases is to insure reactor coolant pressure boundary limits are not exceeded as a result of abnormalities C. D04A, "Battery Charger" inoperable and D04B, "Battery Charger" inoperable.
Bases is to insure adequate core cooling is provided, and reactor building operability and other functions are maintained in the event of a postulated DBA D. D03B, "Battery Charger" inoperable and D07, "Battery" operable.
Bases is to insure adequate core cooling is provided, and reactor building operability and other functions are maintained in the event of a postulated DBA
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question 90 The plant is in Mode 4.
During the performance of DG Surveillance 3.8.1.8, to demonstrate operability for a Loss of Offsite Power event, all DG loads are properly sequenced on in 14 seconds, except one non
-essential load that failed to trip off.
During the surveillance, the DG supplied connected loads for 5 minutes.
As Control Room Supervisor, you decide the EDG is ___________ because _____________.
A. Operable; the tripping of non
-essential loads does not affect operability.
B. Inoperable; the tripping of non
-essential loads affects operability.
C. Operable; the EDG is capable of meeting the 15 second time requirement.
D. Inoperable; the EDG did not supply connected loads for more than 5 minutes.
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question 91 Given: Plant power 100%
TE-1014 "A" Loop Narrow Range T
-hot SLOWLY starts to fail low.
What procedure should be used for this condition?
A. 1203.001, "ICS Abnormal Operation"
B. 1203.012F, "Annunciator K07 Corrective Action" (K07
-B4 SASS Mismatch)
C. 1202.001, "Reactor Trip" D. 1105.006, "Reactor Coolant System NNI"
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question 92 THIS QUESTION IS OPEN REFERENCE.
Given: The plant computer is unavailable.
Core EFPD is 200 Reactor power is 80%
NI-7 is out of service Calculated quadrant tilt is 5.90% in quadrant WX.
If these indications continue, which of the following actions is required to be taken in accordance with Technical Specifications?
A. Reduce applicable RPS trip setpoints 1.5%
B. Reduce applicable RPS trip setpoints 3%
C. Reduce applicable RPS trip setpoints 6%
D. Reduce applicable RPS trip setpoints 8%
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question:
93 While discharging liquid radwaste to the flume, the PROC MONITOR RADIATION HI (K10
-B2) alarms and there is also an alarm on the Liquid Radwaste Process Monitor (RI
-4642), (C25, Bay 2).
An operator reports one of the liquid radiation monitors has failed high.
The CRS should find the operability requirements for the failed liquid radwaste radiation monitor, in _____________.
A. Technical Specifications B. Technical Requirements Manual (TRM)
C. Off-Site Dose Calculation Manual (ODCM)
D. Updated Safety Analysis Report (USAR)
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question 94 Per OP-1015.043, ANO
-1 EOP/AOP User Guide, which of the following identifies one of the criteri a to bring steps forward from another EOP/AOP or steps within an EOP/AOP to be performed out of order:
A. The CRS and the Operations Manager's approval are required before performing the steps out of sequence.
B. The actions are necessary to mitigate the event and maintain the safety function.
C. The actions to be performed will affect the ability to assess the status of the safety functions.
D. The CRS and the Assistant Operations Manager's approval are required before performing the steps out of sequence.
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question:
95 While in Mode 5, a supporting SSC for a Technical Specification applicable system has been removed from service for maintenance activities. Prior to this, the applicable system was not out of service for any other reason.
Which of the following would be used to determine and track Maximum Out
-of-Service Time?
A. LCO 3.0.6 B. 1015.045, Safety Function Determination Program C. 1015.049, Configuration Control Program
D. 1015.048, Shutdown Operations Protection Plan
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question:
96 The plant has the following initial conditions: NI-3 and -4 read 2x10
-11 A RCS pressure is 415 psig RCS temperature is 270 deg F Reactor Coolant Pumps 32A and 32B are running Reactor Coolant Pumps 32C and 32D are off What is the current Mode of operation in accordance with the plant's Technical Specifications?
A. Mode 2 B. Mode 3 C. Mode 4 D. Mode 5 2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question 97 The plant is in Mode 6 and refueling is in progress. The Spent Fuel Pool (SFP) level is 23.5 feet over the top of the irradiated fuel assemblies in the storage racks.
Is the SFP inoperable or operable, and why?
A. The SFP is Operable; 23 feet is the minimum level allowed by Technical Specifications because this level will provide adequate shielding for a fuel element failure following a fuel handling accident if the storage racks are 95% full
. B. The SFP is Inoperable; the minimum level allowed by Technical Specifications is >23 feet because that level is required to provide adequate shielding against beta particles from the decay of Thorium
-232 (decay heat).
C. The SFP is Operable; 23 feet is the minimum level allowed by Technical Specifications because this level meets the assumptions of iodine decontamination factors following a fuel handling accident.
D. The SFP is Inoperable; the minimum level allowed by Technical Specifications is >23 feet because this level is required to provide adequate shielding against decay heat and gammas released through decay chains following a fuel handling accident.
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question 98 Large break LOCA has occurred EOF, TSC, and OSC have been activated and are operation al CV-1405, Train B RB Sump Outlet Valve, failed to open during transfer to RB sump recirculation P-34A, LPI pump operation is degrading No offsite release is in progress The OSC is dispatching a Repair Team to attempt repair of CV
-1405. What is the MAXIMUM dose each member of the team is allowed to receive, and whose authorization is required?
A. Planned dose shall not exceed 10 Rem TEDE with TSC Director's authorization B. Planned dose shall not exceed 10 Rem TEDE with OSC Director's authorization C. Planned dose shall not exceed 25 Rem TEDE with TSC Director's authorization D. Planned dose shall not exceed 25 Rem TEDE with OSC Director's authorization
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question 99 In the Emergency Operating Procedures, procedural steps marked with a bullet are considered ______________.
A. Non-sequential steps B. Floating steps C. Time Dependent steps D. Immediate Action steps
2013 Arkansas Nuclear One Initial NRC License Written Examination SRO Question:
100 Given: The reactor is operating at 80 percent power, There is a PROC MONITOR RADIATION HI (K10
-B2) alarm in, The control room crew has determined there is a 7 gpm Steam Generator Tube Leak.
The leak rate is increasing approximately 1 gpm every five minutes.
Based on this, the CRS should; A. Direct the reactor be tripped and then enter EOP 1202.001, Reactor Trip B. First enter AOP 1203.023, Small Steam Generator Tube Leak, and then transition to EOP 1202.001, Reactor Trip C. First enter AOP 1203.023, Small Steam Generator Tube Leak, and then transition to EOP 1202.006, Tube Rupture D. First enter AOP 1203.045, Rapid Plant Shutdown, then transition to EOP 1202.001, Reactor Trip