ML11262A142
| ML11262A142 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/26/2011 |
| From: | Sean Hedger Operations Branch IV |
| To: | Byford R Entergy Operations |
| laura hurley | |
| References | |
| Download: ML11262A142 (151) | |
Text
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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: 08/26/11 Facility/Unit: ANO Unit One Region: I Ill j IV Reactor Type: W [1 CE LI 8W GE LI Start Time: Finish Time:
Instructions Use the answer sheets provided to document your answers, Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicants Signature Results Examination Value 75 Points Applicants Score Points Applicants Grade Percent
ANO Unit I - 2011 RO NRC Written Examination Question No. I QID: 0023 The following conditions exist immediately after a reactor trip:
- Group 2, Rod 4 failed to fully insert into the core
- RCS pressure is at 1750 psig and trending down
- Pressurizer level is at 50 inches and trending down
- A OTSG pressure is at 880 psig and trending down
- B OTSG pressure is at 885 psig and trending down
- GETs are 560°F and stable
- Turbine Trip Solenoid Power Available light is OFF Which of the following contains the required operator response as well as the reason for the response?
A. Manually actuate MSLI for affected SG(s) and EFW due to overcooling.
B. Commence emergency boration per RT-1 2 for the stuck rod.
C. Trip all Reactor Coolant Pumps due to loss of subcooling margin.
D. Initiate High Pressure Injection per RT-2 due to low pressurizer level and low RCS pressure.
ANO Unit I - 2011 RO NRC Written Examination Question No. 2 QID: 0506 Given:
- A Small Break LOCA has occurred.
- ATC has tripped the reactor.
- CBOT has tripped the turbine.
- Both OTSG Pressures are at 895 psig and stable
- SCM is 25°F.
- All RCPs are OFF.
The desired final OTSG levels will be maintained with EFW using _?_ Level instrument(s) and obtained with a fill rate of _?_.
A. EFIC Low Range, 2 to 8/min in Manual or 34Ogpm/SG in Auto B. EFIC High Range 2 to 8/min in Auto or 34Ogpm/SG in Manual C. EFIC Low Range 2 to 8/min in Auto or 34Ogpm/SG in Manual D. EFIC High Range 2 to 8/min in Manual or 34OgpmISG in Auto
ANO Unit I - 2011 RO NRC Written Examination Question No. 3 QID: 0029 Given the following plant conditions:
Reactor trip from full power
- Full ES actuation
- ICCMDS Display Subcooling Margin indicates 0 °F
- ICCMDS CET temperatures are alternating between superheated and saturated conditions.
All EOP actions have been performed for these conditions.
Which of the following describes the primary mode of RCS cooling for these conditions?
A. Reflux Boiling B. Forced Convection C. Natural Circulation D. Natural Conduction
ANO Unit I - 2011 RO NRC Written Examination Question No. 4 QID: 0825 Given:
-Plant is at 65% power
-P-32A, P-32C, and P-32D RCPs are running
-K08-C7 RCP BLEEDOFF TEMP HIGH alarms
-P-32A Seal Bleedoff temperature is 210°F Which of the following operator actions are required?
A. Reduce Reactor power to 50% and secure RCP P-32A.
B. Trip RCP P-32A and verify proper ICS response.
C. Close P-32A Seal Bleedoff Isolation CV-1 273 and Seal Bleedoff Isolation to Quench Tank SV-1 273.
D. Trip the Reactor and then trip RCP P-32A.
ANO Unit 1 -2011 RO NRC Written Examination Question No. 5 QID: 0549 Given the following:
- Plant is at 100% power.
- HPI pump discharge pressure is oscillating from 1500 to 2500 psig.
- Makeup flow rate is oscillating from 0 to 70 gpm.
- Seal Injection total flow is oscillating from 30 to 60 gpm.
- Pressurizer level is 215 inches and dropping.
- Letdown flow is 80 gpm and stable.
- Makeup tank level 50 inches and dropping.
Which of the following actions, and reasons for the actions, are procedurally required to be performed in response to these indications?
A. Trip HPI pump and isolate Letdown by closing Letdown Isolation, CV-1 221, due to indications of degraded suction.
B. Take manual control of RC Pumps Total Injection Flow, CV-1 207, and maintain 30-40 gpm to prevent RCP seal damage.
C. Take manual control of Pressurizer Level Control, CV-1 235, and stabilize Pressurizer level due to automatic valve control malfunction.
D. Trip HPI pump, trip reactor, and go to EOP 1202.001, Reactor Trip, due to loss of seal injection at power.
ANO Unit 1 -2011 RO NRC Written Examination Question No. 6 QID: 0164 An outage is in progress with the following conditions:
- The RCS is drained to 371.5 feet as indicated by RCS hot leg level.
- Decay heat removal flow becomes erratic.
- Indicated decay heat removal flow is 2500 gpm.
Which procedural action should be taken first to prevent a Loss of Decay Heat?
A. Reduce decay heat removal flow until flow stablizes.
B. Start the Standby Decay Heat pump.
C. Raise RCS level until flow stablilizes.
D. Raise decay heat removal flow by opening block valve.
ANO Unit 1 -2011 RO NRC Written Examination Question No. 7 QID: 0095 Given:
- RCS pressure has dropped to approximately 1500 psig.
- RB pressure has risen to 5 psig.
- CETs are approximately 500 degrees F.
Which of the following best describes the effects, and the reasoning behind the effects, on the ICW system or the components it cools?
- a. All RCPs must be secured due to loss of motor cooling.
- b. All RCPs must be secured due to loss of subcooling margin.
- c. ICW Booster pumps are protected by opening of bypass valve.
- d. ICW pumps must be secured due to isolation of SW to ICW coolers.
ANO Unit I - 2011 RO NRC Written Examination Question No. 8 QID: 0824 Given:
-Plant at 100% power.
-PZR Spray valve, CV-1008, fails to 30% open.
-RCS pressure 2120 psig and slowly dropping.
What pressure condition would cause the Technical Specification for RCS Pressure, Temperature, and Flow DNB Surveillance limits required to be entered?
A. 2135 psig B. 2120 psig C. 2105 psig D. 2080 psig
ANO Unit 1 -2011 RO NRC Written Examination Question No. 10 QID: 0826 Given:
-Reactor is tripped due to a steam line rupture.
-A SG pressure 430 psig
-B SG pressure 590 psig Which valves are positioned correctly per RT-6?
A. B MSIV CV-2692 closed and B EFW Isolation valve CV-2620 closed B, A MSIV CV-2691 closed and A EFW Isolation valve CV-2627 closed C. A MEW Isolation valve CV-2680 closed and A EEW Control valve CV-2645 open D. B MFW Isolation valve CV-2692 closed and B EFW Control valve CV-2647 closed
ANO Unit I - 2011 RO NRC Written Examination Question No. 11 QID: 0662 Given:
Recovery from an Overheating condition is in progress.
Auxiliary Feedwater Pump, P-75 is the only available source of water.
A SIG level is 18 inches and stable.
B SIG level is 21 inches and lowering.
Subcooling Margin is adequate.
Which of the following indicate the proper action to take and why?
A. Neither SIG can be fed due to unanalyzed stresses of feeding a dry SIG with Aux Feedwater.
B. A SIG can not be fed until primary to secondary heat transfer is established.
B SIG can be fed while monitoring tube to shell delta T due to unanalyzed stresses of feeding a dry SIG with Aux Feedwater.
C. Both SIG can be fed while monitoring tube to shell delta T until primary to secondary heat transfer is established.
D. Both SIG can be fed, tube to shell delta T is not a concern until primary to secondary heat transfer is established, then maintain tube to shell delta T within limits.
ANO Unit I - 2011 RO NRC Written Examination Question No. 12 QID: 0552 Which of the following would cause entry into 1202.008, Blackout?
A. All 6900V busses de-energized, 4l60V busses Al and A2 de-energized B. All 4160V busses de-energized C. All 6900V busses de-energized, all 4160V busses de-energized except A4 bus D. All 6900V busses de-energized
ANO Unit I - 2011 RO NRC Written Examination Question No. 13 QID: 0553 A Degraded Power event occurred.
Both EDGs are supplying associated ES buses.
You are directed to actuate MSLI for both SGs and verify proper EFW actuation and control per RT-6.
Which of the following would be a verification of primary to secondary heat transfer per RT-6?
A. Core exit temperature 600 °F and rising slowly.
B. T-hotlT-cold delta T 55°F and rising slowly.
C. T-cold 545°F dropping slowly and SG pressures 990 psig dropping slowly.
D. Core exit temperature 595 °F rising slowly with T-hot 580°F dropping slowly.
ANO Unit 1 -2011 RO NRC Written Examination Question No. 14 QID: 0850 Inverters are aligned with Inverter Y-25 supplying 120 Volt Vital AC Panel RS-4 and Inverter Y-22 supplying 120 Volt Vital AC Panel RS-2.
What would shifting the manual output transfer switch (S-2) on the Y-25 Inverter to the System Output To Y-22 position do?
A. Power RS-2 from Y-25 B. De-energize RS-4 C. Parallel RS-2 and RS-4 D. Cause Y-25 to shift to alternate source
ANO Unit I - 2011 RO NRC Written Examination Question No. 15 QID: 0625 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 component& temperatures should be closely monitored until P-4B can be re-aligned?
A. Circ Water Pumps P-3A & P-3B, HPI pump P-36B, Nuclear ICW components B. Condensate Pumps, Circ Water Pumps P-3C & P-3D, HPI pump P-36A, Nuclear ICW components C. Circ Water Pumps P-3A & P-3B, HPI pump P-36A, Nuclear ICW components D. Circ Water Pumps P-3C & P-3D, HPI pump P-36C, Non-Nuclear ICW components
ANO Unit 1 -2011 RO NRC Written Examination Question No. 16 QID: 0103 Given:
- Unit One Instrument Air pressure has been degrading for approximately 30 minutes.
- Unit Two Instrument Air pressure is steady.
- Inst. Air is being used to supply contractors using air line hoods.
Suddenly, Unit One Inst. Air pressure drops to 70 psig.
Which of the following actions are required at this pressure?
A. lnform RP and isolate Inst. Air from respirable air.
B. Isolate Unit 2 Inst. Air from Unit 1.
C. Place VSF-9 Outside Air damper in RESERVE position.
D. Place RCP Seal Injection Block, CV-1 206, in OVERRIDE.
ANO Unit I - 2011 RO NRC Written Examination Question No. 17 QID: 0614 An Overheating event is in progress.
Subcooling margin remains adequate.
The running RCP should be tripped when tube to shell delta T reaches:
A. 30°F (tubes hotter)
B. 60°F (tubes hotter)
C. 30°F (tubes colder)
D. 60°F (tubes colder)
ANO Unit 1 -2011 RO NRC Written Examination Question No. 18 QID: 0827 OPEN REFERENCE Due to a grid disturbance an over-excitation condition exists on the Main Generator.
Main Generator load is 800 Mwe Main Generator hydrogen pressure is 75 psig What is the main operational concern with continued operation in this condition?
A. Excessive field heating B. Excessive armature heating C. Excessive core end heating D. Slipping generator poles
ANO Unit I - 2011 RO NRC Written Examination Question No. 19 QID: 0494 Unit 1 is at 25% power and power escalation is in progress.
An asymmetric rod alarm comes in and control rod 7-3 API indicates 9% lower than the group average.
You are the CBOR and are required to monitor Quadrant Power Tilt (QPT) which has exceeded the allowed value by Technical Specifications and 1015.003A Unit 1 Operations Logs.
Select the equipment listed in the order from MOST accurate to LEAST accurate to obtain QPT.
A. Excore NI, Full Incore System (PMS), Minimum/Backup Incore Recorders B. Full Incore System (PMS), Excore NI, Minimum/Backup Incore Recorders C. Full Incore System (PMS), Minimum/Backup Incore Recorders, Excore NI D. Minimum/Backup Incore Recorders, Full Incore System (PMS), Excore NI
ANO Unit I - 2011 RO NRC Written Examination Question No. 20 QID: 0665 Given:
Plant operating at 100% power.
The following annunciators come into alarm simultaneously.
PZR LEVEL LO LO (K09-A3)
PZR LEVEL LO (K09-D3)
LRS-i 001 on C04 indicates 0 inches.
LIS-1 002 on C04 indicates 0 inches.
Pressurizer levels on SPDS also indicates 0 inches (L100i and Li 002).
Which action should be taken for the given condition?
A. Isolate letdown by closing CV-1 221, Letdown Coolers Inlet Isolation valve.
S. Adjust CV-1235, Pzr Level Control Valve, in hand to maintain previous slope of MUT level recorder.
C. Verify proportional Pressurizer Heater Controls hand/auto station in hand and full on to maintain RCS pressure.
D. Verify at least one Makeup Pump recirc valve CV-1300 or CV-i3Oi is open to ensure minimum recirc flow for the M/U Pump.
ANO Unit 1 - 2011 RO NRC Written Examination Question No. 21 QID: 0819 OPEN REFERENCE Given:
- A OTSG has a 20 gpm tube leak
- Reactor was tripped in accordance with 1203.023, Small Steam Generator Tube Leak
- Per 1202.001, CRS has transitioned to 1202.006, Tube Rupture
- RCS pressure 1700 psig
- RCS Tavg 540° F
- PZR level 65 RCS cooldown is in progress and the CRS has directed you to control RCS pressure in accordance with 1202.006.
Which of the following actions should you take?
A. Turn on PZR heaters to raise Subcooling Margin.
B. Open PZR Spray to lower RCS pressure.
C. Open Turbine Bypass Valves to raise cooldown rate.
D. Initiate HPI to raise PZR level.
ANO Unit I - 2011 RO NRC Written Examination Question No. 22 QID: 0162 Reactor power is 90% and generated megawatts is 800.
After a runback for loss of one main feedwater pump, the ICS should stabilize the plant at A. 360 Mwe B. 340 Mwe C. 45% Reactor Power D. 50% Reactor Power
ANO Unit I - 2011 RO NRC Written Examination Question No. 23 QID: 0828 Plant is at 100% power and the ATC notices a loss of NNI indication on 013.
Which of the following NNI power losses ALONE requires a manual reactor trip?
A. NNI-XAC B. NNI-XDC C. NNI-YAC D. NNlYDC
ANO Unit I - 2011 RO NRC Written Examination Question No. 24 QID: 0829 Diesel Generator #2 is running to supply A4 for maintenance on breaker A409, A2-A4 Feeder Breaker.
Low reactor coolant system pressure causes a reactor trip and ESAS actuation.
What will the ES Electrical response be?
A. A-3 and A-4 powered from SU #1, both diesel generators running unloaded.
B. A-3 and A-4 powered from SU #1, Diesel Generator # 2 tripped, Diesel Generator # 1 running unloaded.
C. A-4 powered from Diesel Generator #2, A-3 powered from SU #1, Diesel Generator # 1 running unloaded.
D. A-3 powered from Diesel Generator #1, and A-4 powered from Diesel Generator #2.
ANO Unit 1 -2011 RO NRC Written Examination Question No. 25 QID: 0290 During a large break LOCA, RCPs have been secured due to loss of Subcooling Margin.
Which one of the following indicates that the reactor core is covered?
A. SPDS automatically switches from the ATOG display to the ICC display.
B. The A Hot Leg temperature indicator indicates superheated conditions.
C. The RCS is saturated as indicated by Core Exit Thermocouples.
D. ICCMDS display indicates voids in the Reactor Vessel head and hot legs.
ANO Unit I - 2011 RO NRC Written Examination Question No. 26 QID: 0172 Which of the following conditions would procedurally require that a Natural Circulation Cooldown be performed?
A. A plant cooldown is required and normal offsite power is NOT available.
B. A steam generator steam leak exists following a reactor trip and P-7B EFW pump is NOT available.
C. EFW CST (T-41 B) level has dropped to less than 3 during a Blackout condition, D. A loss of offsite power has occurred and both DGs are tied to their respective busses with an adequate SCM and SU Xfmr #1 becomes available.
ANO Unit I - 2011 RO NRC Written Examination Question No. 27 QID: 0237 It is known that elevated containment temperatures and radiation levels can affect instrument readings.
How are allowances for these effects made when parameter values are required in EOP steps?
- a. Transmitters inside containment are environmentally qualified for these effects.
- b. The SE uses a set of instrument tables during accident conditions.
- c. SPDS displays alternate values when these conditions are reached.
- d. EOP parameter values for these conditions are inside brackets.
ANO Unit I - 2011 RO NRC Written Examination Question No. 28 QID: 0053 Without operator action, which of the following incidents would have the most detrimental effect on RCP operation?
A. Loss of nuclear ICW to RCP B. Main steam line rupture inside RB C. Loss of RCP seal injection D. RCP Bleedoff Normal Return, CV-1274, fails closed
ANO Unit I - 2011 RO NRC Written Examination Question No. 29 QID: 0834 The ATC notices that the pushbutton green light above HS-1 206 on C-04 for Seal Injection Flow Block valve is no longer illuminated.
What be the expected response of Seal Injection flow?
A. Seal injection flow will control at setpoint.
B. Seal injection flow will drop to zero.
C. Seal injection flow will rise due to flow lower than setpoint.
D. Seal injection flow will lower due to flow higher than setpoint.
ANO Unit I - 2011 RO NRC Written Examination Question No. 30 QID: 0657 A HPI pump is operating.
B HPI pump MOD is closed on A-4.
Which of the following best describes B HPI pump following ES actuation?
A. B HPI pump will start on A-3 if A HPI pump fails.
B. B HP1 pump will start on A-4 if A HPI pump fails.
C. B HPI pump will start on A-4 if C HPI pump fails.
D. B HPI pump will not auto start on either A or C HPI pump failure.
ANO Unit I - 2011 RO NRC Written Examination Question No. 31 QID: 0820 The plant is in Mode 5, Cold Shutdown.
Both DH loops are operable.
No RCPs are running.
Makeup Pump is running supplying seal injection.
The running DH pump is stopped in preparation for swapping to the other loop.
In accordance with Technical Specifications for the Reactor Coolant System, which of the following are NOT allowed at this time?
A. Allowing RCS temperature to drift up to 190°F.
B. Starting a Reactor Coolant Pump.
C. Raising MUT level using DI water.
D. Raising OTSG levels using EFW.
ANO Unit I - 2011 RO NRC Written Examination Question No. 32 QID: 0266 Given:
- All controls are in automatic
- RCS pressure 135 psig, slowly dropping
- Reactor Building pressure is 28 psia
- A and B OTSG levels at 415 inches Which pair of pumps should be pumping fluid as designed (not recirculating)?
A. HPI pumps and LPI pumps B. RB spray pumps and LPI pumps C. RB spray pumps and EFW pumps D. HPI pumps and EFW pumps
ANO Unit 1 -2011 RO NRC Written Examination Question No. 33 QID: 0303 Which of the following occurs when HPI is automatically actuated on low RCS pressure?
- a. RCP Seal INJ Block Valve CV-1 206 receives an open signal.
- b. Makeup Tank Outlet Valve CV-1 275 automatically closes.
- c. Decay Heat Cooler Outlet to HPI pump suction CV-1276 automatically opens.
- d. RCS Makeup Block Valve CV-1234 receives a close signal.
ANO Unit I - 2011 RO NRC Written Examination Question No. 34 QID: 0821 What would be the PRIMARY concern if the Quench Tank level was NOTmaintained >4000 gallons but <8300 gallons per 1103.005, Pressurizer Operations?
A. Inadequate NPSH for the Quench Tank Transfer Pump, P-44, causing damage to pump from cavitation.
B. Too much gas space in the Quench Tank would increase the potential for buildup of explosive hydrogen.
C. If the ERV opened during a transient, the rupture disk could rupture prematurely releasing steam to the Rx Bldg.
D. There would be an inadequate water trap for the Rx Bldg vent header during cold shutdown.
ANO Unit I - 2011 RO NRC Written Examination Question No. 35 QID: 0562 Which of the following identifies the correct power supplies to the Intermediate Cooling Water Pumps (P-33A, P-33B, P-33C)?
A. P33A and P33B are powered from B-12 while P33C is powered from B-22.
B. P33A is powered from B-12 while P33B and P33C are powered from B-22.
C. P33A, P33B and P33C are powered from B-12, B-22 and B32 respectively.
D. P33A, P33B and P33C are powered from B-il, B-i2 and B-13 respectively.
ANO Unit I - 2011 RO NRC Written Examination Question No. 36 QID: 0822 Given:
- 100% power
- P33B and P33C ICW pumps in service
- P33A (ICW Pump) out of service
- P33B (1GW Pump) trips What impact would this have on plant operations, and what actions are required per 1104,028, ICW System Operating Procedure?
A. Loss of Non-Nuc ICW, open 1GW cross connect valves CV-2238, CV-2239, CV-2240 and CV-2241 B. Loss of Non-Nuc ICW, close A to B cross connect valves CV-2238 and CV-2240 C. Loss of Nuc ICW, open lOW cross connect valves CV-2238, CV-2239, CV-2240 and CV-2241 D. Loss of Nuc lOW, close A to B cross connect valves CV-2238 and CV-2240
ANO Unit 1 -2011 RO NRC Written Examination Question No. 37 QID: 0628 Given:
- Plant is shutdown and cooldown is in progress.
- RCS pressure 215 psig.
- RCS temperature 200 °F.
- DH is in service.
Which of the following would result if the A RPS narrow range pressure transmitter (PT 1021) slowly failed high?
A. DH suction valve CV-i 050 would close.
B. SASS would select C RPS (PT-i 038).
C. ERV (PSV-1000) would open.
D. DH suction valve CV-1410 would close.
ANO Unit I - 2011 RO NRC Written Examination Question No. 38 QID: 0629 I&C is performing a surveillance on the A RPS channel.
NI input to lOS is selected to C RPS channel.
During this surveillance Power Range channel Nl-7 fails high.
Which of the following will occur?
A. Plant is stable since SASS will transfer to NNI-Y.
B. Control rods will start to insert, C. Control rods will start to withdraw.
D. Feedwater flows will go down.
ANO Unit 1 -2011 RO NRC Written Examination Question No. 39 QID: 0265 Given:
- Reactor tripped due to low RCS pressure.
- ESAS has actuated due to high Reactor Building pressure.
- RCS pressure is 1600 psig.
- Core Exit Thermocouple temperature is 475 °F.
Which of the following actions should be taken for these conditions?
- a. Restore RCP services.
- b. Leave one RCP running in each loop.
- c. Isolate RCP seal bleedoff.
- d. Trip all running RCPs.
ANO Unit 1 -2011 RO NRC Written Examination Question No. 40 QID: 0256 Why are Decay Heat Cooler Outlet Valves SW-22A and SW-22B throttled during normal operation?
A. To raise Service water flow to the Auxiliary Cooling Water System during normal operation.
B. To maintain adequate service water flow to the Reactor Building Coolers when ES actuates.
C. To reduce reactor coolant to service water differential temperature when ES actuates.
D. To maintain the Decay heat coolers full and reduce the chance of water hammer.
ANO Unit 1 - 2011 RO NRC Written Examination Question No. 41 QID: 0830 What are the power supplies for the Reactor Building Spray Pumps?
A. A3andA4 B. Al and A2 C. B5 and B6 D. B52 and B62
ANO Unit I - 2011 RO NRC Written Examination Question No. 42 QID: 0831 What is the initial speed (in RPM) of the steam driven EFW pump after auto start and PRIOR to ramp to operating speed?
A. 825 B. 875 C. 910 D. 960
ANO Unit I - 2011 RO NRC Written Examination Question No. 43 QID: 0063 Given:
- 100% power
- ICS in full automatic The CBOR places the ICS Delta T-Cold Hand Auto Station meter selection switch in POS (position). The meter reads 54%.
What does this mean in terms of ICS control of main feed water?
A. The average of feedwater loop A and feedwater loop B demand is 54%.
B. Feedwater loop B demand is greater than feedwater loop A demand.
C. The feedwater loop B demand is being boosted by a 4 °F Delta T-Cold error.
D. Feedwater loop A demand is greater than feedwater loop B demand.
ANO Unit I - 2011 RO NRC Written Examination Question No. 44 QID: 0435 Given:
- Reactor tripped due to loss of all offsite power.
- RCS T cold is 535°F and dropping.
- RCS pressure 1800 psig and dropping.
- OTSG pressures are -910 psig and dropping.
- A OTSG level is 210 and rising.
- B OTSG level is 195 and rising.
- A EFW flow is 370 gpm.
- B EFW flow is 350 gpm.
Which of the following is an appropriate response to the above conditions in accordance with RT-5, Verify Proper EFW Actuation and Control?
A. Maintain >570 gpm to each SG in HAND.
B. Throttle EFW to prevent overcooling.
C. Select Reflux Boiling setpoint.
D. Actuate MSLI on both OTSGs.
ANO Unit I - 2011 RO NRC Written Examination Question No. 45 QID: 0538 Plant conditions are:
- SCM is less than adequate.
- The RCS is in natural circulation mode.
- EFW pump P-7B failed to start.
- Both OTSG pressures are 900 psig.
The fill rate for the current condition is and the OTSG level set point of 378 is selected by A. 4.4 inch/mm depressing the Train A and Train B REFLUX BOILING pushbuttons on C09 B. 4.4 inch/mm EFIC automatically when RCPs are tripped C. 4.0 inch/mm depressing the Train A and Train B REFLUX BOILING pushbuttons on C09 D. 4.0 inch/mm EFIC automatically when RCPs are tripped
ANO Unit I - 2011 RO NRC Written Examination Question No. 46 QID: 0413 The plant is in Hot Shutdown with a normal electrical alignment.
Due to an electrical fault, K02-A6 HAl L.O. RELAY TRIP comes into alarm.
How will the electrical system respond?
- a. #1 EDG will auto-start and will supply bus A3.
- b. Bus Al will auto-transfer to transformer SU#1.
- c. Bus Al will auto-transfer to transformer SU#2.
- d. #1 EDG will auto-start, but will not supply bus A3.
ANO Unit 1 -2011 RO NRC Written Examination Question No. 47 QID: 0616 The CBOT notices on 010 that all of the 161 KV ring bus breakers have opened.
Which of the following will be de-energized as a result of the above indications?
A. Startup #1 Transformer B. Startup #2 Transformer C. Auto transformer D. Startup #3 Transformer
ANO Unit 1 -2011 RO NRC Written Examination Question No. 48 QID: 0087 During a Blackout condition, it may become necessary to perform an EDG start without DC control power.
In this condition, how is the generator output voltage adjusted (battery chargers are not loaded)?
- a. Adjusting engine speed via speed setting knob on governor.
- b. By adjusting the setpoint for the automatic voltage adjuster.
- c. Using the manual voltage adjuster on Exciter Control Panel.
- d. Using voltage adjuster handswitch on ClO.
ANO Unit I - 2011 RO NRC Written Examination Question No. 49 QID: 0088 The CRS directs you to perform Supplement 1 of 1104.036, #1 EDG Monthly Test.
You depress the start pushbutton on C10, nothing happens, then the EDG 1 OVERCRANK annunciator K01-B2 alarms.
The CRS directs the inside AC to check the EDG out and then depress the local RESET pushbutton.
Which of the following would occur after the AC depresses the RESET pushbutton?
- a. EDG would be ready for another manual start.
- b. EDG will not manually or automatically start.
- c. EDG output breaker will be locked out.
- d. EDG will immediately start cranking.
ANO Unit I - 2011 RO NRC Written Examination Question No. 50 QID: 0849 Given:
- #1 EDG is in the 8th hour of a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> full load run after maintenance
- #2 EDG is in standby
- An AO has just completed a fuel oil tanker truck off-load
- Sediment from the tanker entered the Fuel Oil Bulk tank T-25 and caused the outlet filter F 27 to clog What would be the result of this condition on the Unit 1 EDG Fuel Oil system?
A. Fuel Oil Day Tank T-30A level low alarm.
B. Fuel Oil Storage Tank T-57A implosion.
C. Fuel Oil Storage Tank T-57A level low alarm.
D. Fuel Transfer Pump P-16A D/P Hi alarm.
ANO Unit I - 2011 RO NRC Written Examination Question No. 51 QID: 0271 Which of the following must be performed to release TWMT T-1 6A contents with the Liquid Radwaste Process Monitor (Rl-4642) inoperable?
A. Chemistry personnel must have independent sample and anaylsis results as well as independently verified computer input data.
B. Chemistry must obtain grab samples every hour during a release via this pathway.
C. The release flow rate must be estimated at least once every four hours during the release.
D. Discharge Flume process monitor Rl-3618 must be checked for operability.
ANO Unit I - 2011 RO NRC Written Examination Question No. 52 QID: 0832 Given:
- Plant is at 100% power.
- Ambient outside temperature is 85°F and is the high for the day.
- SW bay level is 332 ft.
- ECP level is 5.8 ft.
- All 3 SW pumps are running.
Preparations are being made to swap SW suction from the Lake to the ECP.
Which of the following must be brought up during the pre-evolution brief for the suction swap?
A. Sluice Gates should not be operated for more than 10 minutes in an hour to prevent motor damage.
B. Check that individual SW pump flow is less than 8000 gpm to ensure adequate NPSH during the swap.
C. ECP level is already at the Tech Spec limit and this evolution will immediately cause entry into a TS LCO.
D. Continued operation with SW aligned to the ECP at this temperature could challenge ECP operability.
ANO Unit I - 2011 RO NRC Written Examination Question No. 53 QID: 0046 Given:
- Degraded Power
- Both EDGs operating
- ESAS has NOT actuated
- P4C failed to start
- P4B out of service Which of the following actions should be accomplished?
A. Close SW Loop II Isolation Valve (SW-bC).
B. Open SW Loop I & II Crossconnects (SW-5 and SW-6).
C. Close ACW Loop Isolation (CV-3643).
D. Cross-tie SW Loops at Makeup Pump (SW-14 thru SW-b 7).
ANO Unit 1 - 2011 RO NRC Written Examination Question No. 54 QID: 0227 Given:
Instrument Air pressure has dropped to 68 psig.
Field operators can not find an Inst. Air leak on Unit One.
Instrument Air pressure is now at 58 psig.
Which of the following is the appropriate procedural response for the given plant conditions to restore or conserve Instrument Air pressure?
A. Verify Service Air to Instrument Air cross-connect automatically opens.
B. Close Unit I to Unit 2 Instrument Air cross-connect.
C. Trip Reactor, actuate EFW and MSLI on both SGs.
D. If ICW available, isolate Seal Injection by closing CV-1206.
ANO Unit I - 2011 RO NRC Written Examination Question No. 55 QID: 0716 Given:
Plant power 100%
Rising Reactor Building temperature Slowly rising Reactor Building pressure Rising Reactor Building Dew Point Reactor Building Leak Detector rising activity Per 1203.039, Excess RCS Leakage, what action addresses these conditions?
A. Initiate Reactor Building Purge.
B. Start the Hydrogen Recombiners.
C. Maximize Reactor Building Cooling.
D. Place a second Main Chiller in service.
ANO Unit I - 2011 RO NRC Written Examination Question No. 56 QID: 0220 Given:
- Reactor power steady at 80%.
- PZR Level Control selected to LT-1 001 on C04
- A break in LT-1001s reference leg causes indicated level to rise.
How will Makeup Tank (T-4) level be affected by this failure?
A. Makeup flow drops, Makeup Tank level will rise.
B. No effect, SASS will auto select LT-1002.
C. Makeup flow rises, Makeup Tank level will drop.
D. Letdown flow drops, Makeup Tank level also drops.
ANO Unit 1 -2011 RO NRC Written Examination Question No. 57 QID: 0833 As indicated in the CRD system logic cabinets, each CRDM has absolute zone reference switches, NOT counting the out limit and an in limit switches.
A.5 B. 7 0.9 D. 11
ANO Unit 1 -2011 RO NRC Written Examination Question No. 58 QID: 0464 Given:
- Reactor startup is in progress.
- Count rate on NI-i & NI-2 is 1 E3 CPS.
During the next rod pull, the HI SUR rod hold alarms.
The most likely cause is due to SUR exceeding:
- a. 1 DPM on the source range monitors.
- b. 2 DPM on the source range monitors.
- c. 2 DPM on the intermediate range monitors.
- d. 1 DPM on the intermediate range monitors.
ANO Unit I - 2011 RO NRC Written Examination Question No. 59 QID: 0403 Initial Conditions:
- SASS Mismatch Annunciator
- Rx is Feedwater Limited Annunciator
- Feedwater is Rx Limited Annunciator
- Unit Tave TI-i 032 is 583 degrees F
- Loop A Tave TI-i 020 is 588 degrees F
- Loop B Tave TI-i 043 is 578 degrees F Which of the following procedurally required actions would clear the cross limits and return temperature indications to normal?
A. Select the NNI-Y signal for RCS loop A hot leg temperature.
B. Place the Controlling Tave Selector Switch in the Loop B position.
C. Place Loop A Feedwater Demand in hand and raise Loop A feedwater flow.
D. Select the NNI-Y signal for RCS loop B cold leg temperature.
ANO Unit I - 2011 RO NRC Written Examination Question No. 60 QID: 0723 What are the power supplies to the Hydrogen Recombiners, M-55A and M-55B?
A. M-55A B-53; M-55B B-61.
B. M-55A B-6; M-55B B-5.
C. M-55A B-61; M-55B B-53.
D. M-55A B-5; M-55B B-6.
ANO Unit I - 2011 RO NRC Written Examination Question No. 61 QID: 0200 A break has occurred on the discharge line downstream of the discharge valve of the in service Spent Fuel Cooling Pump (P-40A).
The pump is stopped and the discharge valve is closed.
What would you expect to happen with Spent Fuel Pool level?
A. The SFP will drain to 2 feet above the spent fuel assemblies.
B. Emergency makeup from service water will be needed to prevent the SFP level from exposing the spent fuel assemblies.
C. The SFP level will stay relatively constant due to siphon holes in the discharge piping.
D. The SFP level will drop 3 feet to the bottom of the suction pipe.
ANO Unit I = 2011 RO NRC Written Examination Question No. 62 QID: 0434 The plant is operating steady state at 100% power when Bus Al is deenergized.
Due to the above condition, which of the following will cause one of the main feedwater pumps to trip?
A. Low bearing oil pressure B. High discharge pressure C. Low suction pressure D. High vibrations
ANO Unit I - 2011 RO NRC Written Examination Question No. 63 QID: 0205 During 3 circulating water pump operation, the A circ water pump trips.
The standby circ pump was started and plant conditions have stabilized.
It is noticed that the condenser waterbox discharge temperature is 10 degrees higher and condenser vacuum has dropped.
Which of the following is the cause of this condition?
- a. The stopping and starting of a circ pump caused fouling to be removed from the tube sheet promoting better heat transfer capabilities.
- b. The discharge valve on the tripped pump did not go completely closed and circulating water is short cycling.
- c. The debris on the bar grates of the circulating water bays was stirred up during the circ pump swap causing reduced flow.
- d. These are normal conditions following rotation of circulating pumps and temperatures will return to normal within 30 minutes.
ANO Unit 1 -2011 RO NRC Written Examination Question No. 64 QID: 0273 The in-service Unit 1 Control Room Supply Vent Radiation Detector, 2RITS-8001A, detects a high radiation condition.
Which of the following will occur?
A. Control Room Air Supply Fan (VSF-8A or 8B) starts.
B. Control Room Chiller Unit (VCH-2A or 2B) trips.
C. Normal ventilation isolation dampers (CV-7905 & CV-7907) close.
D. CR Emerg. A/C Fan (2VSF-9) starts.
ANO Unit I - 2011 RO NRC Written Examination Question No. 65 QID: 0151 ONLY Fire Zones with cross-zoned detection have INHIBIT switches on their C463 modules.
When is the INHIBIT switch used?
A. To prevent automatic actuation if one of the detector strings has a fault.
B. To manually actuate the system from 0463 vs. locally.
C. To prevent nuisance alarms from one of the detector strings due to a fault.
D. To prevent manual actuation of the system on C463 from a faulty solenoid.
ANO Unit I - 2011 RO NRC Written Examination Question No. 66 QID: 0851 When communicating verbally to other personnel, which of the following should be a vital component of that face-to-face communication?
A. Including multiple instructions to prevent multiple communications.
B. Making a verbatim repeat back for precise communications.
C. Use standard terminology with a minimal use of acronyms for clarity.
D. Minimize repeat backs to clear the airways of unnecessary noise.
ANO Unit I - 2011 RO NRC Written Examination Question No. 67 QID: 0837 Which of the following IS a valid reason to override any automatically actuated safety system per EN-OP-i 15?
A. Required by procedures.
B. Subcooling margin is adequate.
C. Adequate core cooling is assured by a single indication.
D. Mis-operation in automatic mode is confirmed by a single indication.
ANO Unit I - 2011 RO NRC Written Examination Question No. 68 QID: 0838 For the purpose of maintaining an NRC operators license, which of the following should be reported to the NRC?
A. A change in marital status.
B. A traffic citation for speeding.
C. A new diagnosis for high blood pressure.
D. An audit by the IRS of previous years tax return.
ANO Unit I - 2011 RO NRC Written Examination Question No. 69 QID: 0458 Which one of the following conditions is required by Unit 1 Technical Specifications in order to consider the reactor in Mode 4?
A. The reactor must be subcritical by at least 1.5% Delta k/k.
B. RCS T average must be between 200 °F and 280 °F.
C. The neutron chain reaction is self sustaining and K eff 1.0.
D. RCS temperature is no more than 200 °F.
ANO Unit I - 2011 RO NRC Written Examination Question No. 70 QID: 0233 An NI calibration was performed yesterday.
Today due to a problem with a Condenser Vacuum pump, reactor power had to be lowered to 89% and has subsequently been returned to 100%.
When is the next NI calibration required to be performed?
A. Within the next 7 days.
B. Within the next 4 days.
C. Within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
D. Within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ANO Unit 1 -2011 RO NRC Written Examination Question No. 71 QID: 0231 Which of the following conditions is correct with regard to preparation and installation authorization of a common unit tagout?
A. Installation may be authorized by either the Unit 1 or the Unit 2 Operations Supervisor.
B. Preparers and reviewers from both units must be licensed operators.
C. Preparer and reviewer may be non-licensed if authorized by both Unit Operations Supervisors.
D. Preparer may be non-licensed as long as the opposite unit reviewer is licensed.
ANO Unit 1 -2011 RO NRC Written Examination Question No. 72 QID: 0043 A radioactive gas release of WGDT T-18B has been terminated by Gaseous Radwaste Monitor, RE-4830, in high alarm.
Examination of the recorder paper shows RE-4830 had been trending steadily at 2000 cpm when it jumped to 30,000 cpm and then dropped back to 2000 cpm.
What action should be taken?
A. Initiate a Work Request and check system alignment.
B. Reset RE-4830 and notify Nuclear Chemistry to perform offsite dose projections via RDACS.
C. Leave T-18B alignment as-is and re-submit sampling and release permit.
D. Reset RE-4830 and re-establish T-18B gaseous release.
ANO Unit I - 2011 RO NRC Written Examination Question No. 73 QID: 0853 What is the federal occupational exposure limit to the lens of the eye LDE (Lens Dose Equivalent) in accordance with 100FR2O?
A. 0.1 rems/calendar year B. 5.0 rems/calendar year C. 15.0 rems/calendar year D, 50.0 rems/calendar year
ANO Unit I - 2011 RO NRC Written Examination Question No. 74 QID: 0848 You are standing watch and it is now 1500 on 08/26/20 1 1.
Which of the following would be considered a fire system impairment in accordance with 1003.002, Insurance Impairment Reporting?
A. P-6A Electric Fire Pump inoperable due to corrective maintenance at 0800.
B. A smoke detector string in Corridor 98 defeated for PMs at 0900.
C. Leaking fire hose station in Aux Bldg 335 elevation isolated at 1030.
D. Control Room Halon System #3 failed surveillance at 0530.
ANO Unit I - 2011 RO NRC Written Examination Question No. 75 QID: 0835 Who performs the Transient Checklist during a transient per 1015.037, Post Transient Review?
A. Shift Manager B. Control Rooom Supervisor C. Shift Technical Advisor D. Control Board Operator Turbine
ANO Unit 1 -2011 RO NRC Written Exam KEY Question No. 1 QID: 0023 Point Value: I Answer:
A. Manually actuate MSLI for affected SG(s) and EFW due to overcooling.
Question No. 2 QID: 0506 Point Value: I Answer:
B. EFIC High Range 2 to 8Imin in Auto or 34Ogpm/SG in Manual Question No. 3 QID: 0029 Point Value: I Answer:
A. Reflux Boiling Question No. 4 QID: 0825 Point Value: I Answer:
D. Trip the Reactor and then trip RCP P-32A.
Question No. 5 QID: 0549 Point Value: I Answer:
A. Trip HPI pump and isolate Letdown by closing Letdown Isolation, CV-1221, due to indications of loss of suction.
Question No. 6 QID: 0164 Point Value: 1 Answer:
A. Reduce decay heat removal flow until flow has stablized.
Question No. 7 QID: 0095 Point Value: I Answer:
- a. All RCPs must be secured due to loss of motor cooling.
Question No. 8 QID: 0824 Point Value: I Answer:
D. 2080 psig
ANO Unit I - 2011 RO NRC Written Exam KEY Question No. 17 QID: 0614 Point Value: I Answer:
B. 60°F (tubes hotter)
Question No. 18 QID: 0827 Point Value: I Answer:
A. Excessive field heating Question No. 19 QID: 0494 Point Value: I Answer:
B. Full Incore System (PMS), Excore NI, Minimum/Backup Incore Recorders Question No. 20 QID: 0665 Point Value: I Answer:
B. Adjust CV-1235, Pzr Level Control Valve, in hand to maintain previous slope of MUT level recorder.
Question No. 21 QID: 0819 Point Value: I Answer:
B. Open PZR Spray to lower RCS pressure.
Question No. 22 QID: 0162 Point Value: I Answer:
A. 360 Mwe Question No. 23 QID: 0828 Point Value: I Answer:
A. NNI-XAC Question No. 24 QID: 0829 Point Value: I Answer:
C. A-4 powered from Diesel Generator #2, A-3 powered from SU #1, Diesel Generator # 1 running unloaded.
ANO Unit 1 -2011 RO NRC Written Exam KEY Question No. 25 QID: 0290 Point Value: I Answer:
C. The RCS is saturated as indicated by Core Exit Thermocouples.
Question No. 26 QID: 0172 Point Value: I Answer:
A. A plant cooldown is required and normal offsite power is NOT available.
Question No. 27 QID: 0237 Point Value: I Answer:
- d. EOP parameter values for these conditions are inside brackets.
Question No. 28 QID: 0053 Point Value: I Answer:
B. Main steam line rupture inside RB Question No, 29 QID: 0834 Point Value: I Answer:
B. Seal injection flow will drop to zero.
Question No. 30 QID: 0657 Point Value: I Answer:
C. B HPI pump will start on A-4 if C HPI pump fails.
Question No. 31 QID: 0820 Point Value: I Answer:
C. Raising MUT level using Dl water.
Question No. 32 QID: 0266 Point Value: I Answer:
ANO Unit 1 -2011 RO NRC Written Exam KEY Question No. 33 QID: 0303 Point Value: I Answer:
- d. RCS Makeup Block Valve CV-1234 receives a close signal.
Question No. 34 QID: 0821 Point Value: I Answer:
C. If the ERV opened during a transient, the rupture disk could rupture prematurely releasing steam to the Rx Bldg.
Question No. 35 QID: 0562 Point Value: I Answer:
B. P33A is powered from B12 while P33B and P330 are powered from B-22.
Question No. 36 QID: 0822 Point Value: I Answer:
A. Loss of Non-Nuc ICW, open ICW cross connect valves CV-2238, CV-2239, CV-2240 and CV-2241 Question No. 37 QID: 0628 Point Value: I Answer:
C. ERV (PSV-1 000) would open.
Question No. 38 QID: 0629 Point Value: I Answer:
B. Control rods will start to insert.
Question No. 39 QID: 0265 Point Value: I Answer:
- d. Trip all running RCPs.
Question No. 40 QID: 0256 Point Value: I Answer:
B. To maintain adequate service water flow to the Reactor Building Coolers when ES actuates.
ANO Unit I - 2011 RO NRC Written Exam KEY Question No. 41 QID: 0830 Point Value: I Answer:
A. A3andA4 Question No. 42 QID: 0831 Point Value: I Answer:
C. 910 Question No. 43 QID: 0063 Point Value: I Answer:
D. Feedwater loop A demand is greater than feedwater loop B demand.
Question No. 44 QID: 0435 Point Value: I Answer:
B. Throttle EFW to prevent overcooling.
Question No. 45 QID: 0538 Point Value: I Answer:
A. 4.4 inch/mm depressing the Train A and Train B REFLUX BOILING pushbuttons on 009 Question No. 46 QID: 0413 Point Value: I Answer:
- a. #1 EDG will auto-start and will supply bus A3.
Question No. 47 QID: 0616 Point Value: I Answer:
B. Startup #2 Transformer Question No. 48 QID: 0087 Point Value: I Answer:
- c. Using the manual voltage adjuster on Exciter Control Panel.
ANO Unit 1 -2011 RO NRC Written Exam KEY Question No. 49 QID: 0088 Point Value: I Answer:
- d. EDG will immediately start cranking.
Question No. 50 QID: 0849 Point Value: I Answer:
C. Fuel Oil Storage Tank T-57A level low alarm.
Question No. 51 QID: 0271 Point Value: I Answer:
A. Chemistry personnel must have independent sample and anaylsis results as well as independently verified computer input data.
Question No. 52 QID: 0832 Point Value: I Answer:
B. Check that individual SW pump flow is less than 8000 gpm to ensure adequate NPSH during the swap.
Question No. 53 QID: 0046 Point Value: I Answer:
C. Close ACW Loop isolation (CV-3643).
Question No. 54 QID: 0227 Point Value: I Answer:
B. Close Unit 1 to Unit 2 Instrument Air cross-connect.
Question No. 55 QID: 0716 Point Value: I Answer:
C. Maximize Reactor Building Cooling.
Question No. 56 QID: 0220 Point Value: I Answer:
A. Makeup flow drops, Makeup Tank level will rise.
ANO Unit I - 2011 RO NRC Written Exam KEY Question No. 57 QID: 0833 Point Value: I Answer:
A.5 Question No. 58 QID: 0464 Point Value: I Answer:
- b. 2 DPM on the source range monitors.
Question No. 59 QID: 0403 Point Value: I Answer:
A. Select the NNI-Y signal for RCS loop A hot leg temperature.
Question No. 60 QID: 0723 Point Value: I Answer:
A. M-55A B-53; M-55B B-61 Question No. 61 QID: 0200 Point Value: I Answer:
C. The SEP level will stay relatively constant due to siphon holes in the discharge piping.
Question No. 62 QID: 0434 Point Value: I Answer:
C. Low suction pressure Question No. 63 QID: 0205 Point Value: I Answer:
- b. The discharge valve on the tripped pump did not go completely closed and circulating water is short cycling.
Question No. 64 QID: 0273 Point Value: I Answer:
C. Normal ventilation isolation dampers (CV-7905 & CV-7907) close.
ANO Unit 1 -2011 RO NRC Written Exam KEY Question No. 65 QID: 0151 Point Value: I Answer:
A. To prevent automatic actuation if one of the detector strings has a fault.
Question No. 66 QID: 0851 Point Value: I Answer:
C. Use standard terminology with a minimal use of acronyms for clarity.
Question No. 67 QID: 0837 Point Value: I Answer:
A. Required by procedures.
Question No. 68 QID: 0838 Point Value: I Answer:
C. A new diagnosis for high blood pressure.
Question No. 69 QID: 0458 Point Value: I Answer:
B, RCS T average must be between 200 °F and 280 °F.
Question No. 70 QID: 0233 Point Value: I Answer:
D. Within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Question No. 71 QID: 0231 Point Value: I Answer:
B. Preparers and reviewers from both units must be licensed operators.
Question No. 72 QID: 0043 Point Value: I Answer:
D. Reset RE-4830 and re-establish T-18B gaseous release.
ANO Unit 1 -2011 RO NRC Written Exam KEY Question No. 73 QID: 0853 Point Value: I Answer:
C. 15.0 rems/calendar year Question No. 74 QID: 0848 Point Value: I Answer:
D. Control Room Halon System #3 failed surveillance at 0530.
Question No. 75 QID: 0835 Point Value: I Answer:
C. Shift Technical Advisor
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: 08/26/1 1 Facility/Unit: ANO Unit One Region: I [1 ii El iii El IV Reactor Type: W [1 CE El BW GE El Start Time: Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets, To pass the examination you must achieve a final grade of at least 80.00 percent 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 75 / 25 / 100 Points Applicants Scores / I Points Applicants Grade / I Percent
ANO Unit 1 -2011 SRO NRC Written Examination Question No. 76 QID: 0855 Following a reactor trip, the following conditions exist:
- Both SG pressures are LOWERING
- A SG pressure 971 psig
- B SG pressure 940 psig
- K07-C5 MSSV OPEN is in alarm
- SPDS indicates that the open MSSV is on the B SG.
Which of the following procedural actions would be used in response to the above conditions?
A. Actuate EFW and MSLI for B SG, verify proper actuation and control using RT-6, per 1202.001, Reactor Trip.
B. Control Turbine Bypass valves (TBVs) to quickly reduce SG pressures to reseat the MSSV per 1202.003, Overcooling.
C. Actuate EFW and MSLI for B SG, verify proper actuation and control using RT-6, per 1202.003, Overcooling.
D. Control Turbine Bypass valves (TBVs) to quickly reduce SG pressures to reseat the MSSV per 1202.001, Reactor Trip.
ANO Unit I - 2011 SRO NRC Written Examination Question No. 77 QID: 0839 Given:
- Reactor tripped due to a Pressurizer Vapor Space leak.
- K09-B1 RCS PRESSURE LO-LO alarm is in.
- CET temperatures 560° F and rising.
- A & B OTSG levels 13 and rising slowly.
- RCS pressure 1200 psig and stable.
- Both EDGs are in emergency standby.
For these conditions, which operating procedure should be used?
A. 1202.002, Loss of Subcooling Margin B. 1202.004, Overheating C. 1202.005, Inadequate Core Cooling D. 1203.015, Pressurizer Systems Failure
ANO Unit I - 2011 SRO NRC Written Examination Question No. 78 QID: 0639 Given:
- Plant is in Mode 5
- A Decay Heat Removal is in service
- P-34A Decay Heat Removal flow is steady at 1900 gpm.
- K10-B2 PROCESS MONITOR RADIATION HIGH in alarm
- RI-3809, Loop A DH Process Rad Monitor in alarm What procedure should be used to address the above conditions?
A. 1203.014, Control of Secondary System Contamination B. 1203.028, Loss of Decay Heat Removal C. 1203.030, Loss of Service Water D. 1203.039, Excess RCS Leakage
ANO Unit I - 2011 SRO NRC Written Examination Question No. 79 QID: 0731 Given:
A steam line rupture has caused excessive overcooling.
Which of the conditions below would have invoked PTS limits AND violate Technical Specification limits?
A. A cooldown resulting in a step change of 51 °F in 10 minutes with Tcold at 360 °F.
B. A cooldown rate of 90°F/hr with Tcold at 295 °F.
C. A cooldown resulting in a step change of 26°F in 10 minutes with Tcold at 279°F.
D. A cooldown rate of 110°F/hr with Tcold at 330°F
ANO Unit 1 -2011 SRO NRC Written Examination Question No. 80 QID: 0586 OPEN REFERENCE Given:
- Plant is at 100% power with no failed equipment.
- A loss of the 161 KV ring bus occurs (de-energized).
- Autotransformer is energized from the 500 KV ring bus.
Providing the 161 KV ring bus remains de-energized, when is the plant required to be in Mode 3?
A. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> B. Within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C. Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> D. Within 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />
ANO Unit 1 -2011 SRO NRC Written Examination Question No. 81 QID: 0840 Unit One has entered Technical Specifications 3.8.4 due to a loss of one of the required DC electrical power subsystems.
Which of the following components comprise a DC subsystem in according with the Tech Spec bases?
- 1. 125V DC panel
- 2. Battery
- 3. Inverter
- 4. Cables
- 5. 120v Vital AC panel
- 6. Static Switch
- 7. Battery Charger A. 1,2,4,7 B. 1,2,3,7 C. 2,4,6, 7 D. 2, 3, 5, 7
ANO Unit 1 -2011 SRO NRC Written Examination Question No. 82 QID: 0841 OPEN REFERENCE Given:
- Plant is at 40% power.
- A control rod (Grp 5 Rod 5) dropped at 1430.
- The control rod was declared inoperable.
- SDM was evaluated at 1500 and is NOTwithin limits of COLR.
Per Technical Specifications, which of the following actions are required?
A. Perform a SDM calculation by 0300.
B. Initiate shutdown to Mode 3 by 2300.
C. Initiate boration to restore SDM by 1530.
D. Restore control rod alignment by 1800.
ANO Unit 1 -2011 SRO NRC Written Examination Question No. 83 QID: 0590 Given:
- Plant startup in progress.
- Channel 1 Source Range, Nl-501 at 9 E4 cps Channel 2 Source Range, NI-502 at 1 E5 cps
- Reactor power Wide Range recorder, NR-502, is operable and at 5 E -2% power
- Intermediate Range Channel NI-3 at 2 E -11 amps
- Intermediate Range Channel NI-4 at 5 E -11 amps
- Power Range Channels NI-5 thru 8 at 0%
Which of the following actions are procedurally required and ensure compliance with Technical Specification 3.3.10, Intermediate Range Neutron Flux?
A. Trip the reactor immediately and refer to 1202.001, Reactor Trip.
B. Immediately suspend positive reactivity additions and initiate a shutdown so that all CRD breakers are open within one hour.
C. Lower power until Source Range is on scale and corrective maintenance is performed on appropriate IR channel(s).
D. Since NR-502 is operable, continue with plant operations until Power Range channels come on-scale.
ANO Unit I - 2011 SRO NRC Written Examination Question No. 84 QID: 0347 The main fuel bridge has a spent fuel assembly and is indexed over the core when an NI seal plate cover failure occurs.
Water level in the canal is falling at two inches per minute.
The main fuel bridge operator should:
A. Continue to the upender and place the assembly in the upender.
B. Leave the fuel assembly in the mast and evacuate the area.
C. Place the assembly in the fuel rack in the deep end of the canal.
D. Return the assembly to an available location in the reactor vessel.
ANO Unit I - 2011 SRO NRC Written Examination Question No. 85 QID: 0342 Given:
- Reactor at 80% power.
- Failed fuel ratio, as indicated by the WCO logs, has dropped by 45%.
According to Reactor power must be reduced to power.
A. 1203.045 Rapid Plant Shutdown 55%
B. 1203.019 High Activity In Reactor Coolant 55%
C. 1203.045 Rapid Plant Shutdown 40%
D. 1203.019 High Activity In Reactor Coolant 40%
ANO Unit 1 -2011 SRO NRC Written Examination Question No. 86 QID: 0607 Given:
- P-36A is the in-service Makeup Pump.
- Pressurizer level has dropped from 220 to 218 in 10 minutes.
- P-36A suction pressure is 40 psig and going down slowly.
- Makeup Tank level is 78 and trending down slowly.
- Seal Injection flow is oscillating from 38 to 43 gpm.
- MU-34D HPI temperature TE-1069A is reading 255°F.
- Aux. Building sump level is going up.
Considering the above conditions, which procedure will direct the Makeup Pump to be secured?
A. 1203.039, Excess RCS Leakage B. 1203.026, Loss of Reactor Coolant Makeup, Section 1 Loss of HPI Pump C. 1203.026, Loss of Reactor Coolant Makeup, Section 2 Large Makeup and Purification System Leak D. 1203.032, HPI Line Temperature High
ANO Unit 1 -2011 SRO NRC Written Examination Question No. 87 QID: 0842 Given:
- All Pressurizer heaters ON.
- RCS pressure is 2050 psig and going down.
- Quench Tank (T-42) level is rising.
- Pressurizer Level Control Valve, CV-1235, full closed.
For the above conditions, which of the following actions is procedurally required to be performed?
A. Take manual control of Pressurizer Level Control Valve (CV-1235) and open per OP-i 203.015, Pressurizer Systems Failure.
B. Close the ERV Isolation Valve (CV-i 000) per OP-i203.0i5, Pressurizer Systems Failure.
C. Take manual control of Pressurizer Level Control Valve (CV-i235) and open per OP-i 203.026, Loss of Reactor Coolant Makeup.
D. Close the ERV Isolation Valve (CV-1 000) per OP-1203.026, Loss of Reactor Coolant Makeup.
ANO Unit 1 -2011 SRO NRC Written Examination Question No. 88 QID: 0843 Given:
Plant is at 100% power and stable.
- A RPS is inoperable due to RCS pressure transmitter failure.
- l&C has finished performing a surveillance on C RPS and the SM declares the channel inoperable.
Which of the following actions are required to be performed FIRST per Technical Specification 3.3.1?
A. Place both A and C RPS channels in bypass.
B Place A RPS channel in trip, remove C channel from bypass, and prevent bypass of B, C, and D channels.
C. Reduce thermal power to <10% of Rated Thermal Power.
D. Place A in channel bypass and trip C RPS channel.
ANO Unit 1 -2011 SRO NRC Written Examination Question No. 89 QID: 0844 Given A LOCA has caused ES actuation Transfer to RB sump recirculation has been completed.
The following indications are observed:
- RB Flood level is steady
- Both LPI Pump Discharge pressures dropping to 100 psig and rising up to 160 psig
- Both RB Spray P-35A1B ES Failure annunciators are coming in and subsequently clearing
- HPI Flow Indications are erratic
- Dose assessment reports there is no offsite release in progress.
Which of the following actions should be taken for these conditions?
A. Verify BWST Outlet Valves CV-1407 and CV-1408 open per RT-10, Verify Proper ESAS Actuation.
B. Override and throttle both LPI Pumps close to but not below 2800 gpm per pump per 1202.010 Att. 1, Shift to RB Sump Suction.
C. Override and stop one RB Spray Pump per 1202.OlOAtt. 1, Shift to RB Sump Suction.
D. Override and throttle both RB Spray Pumps to 1050 - 1200 gpm each per RT-10, Verify Proper ESAS Actuation
ANO Unit I - 2011 SRO NRC Written Examination Question No. 90 QID: 0740 Given:
- Unit Tripped on loss of DOl
- EFW has actuated What is the status of EFW control valve CV-2646, P7B to A OTSG and EFW control valve CV-2648, P7A to B QTSG; and which procedure should FIRST be used to address the EFW system?
A. Valves closed; 1202.003, Overcooling B. Valves closed; 1203.036, Loss of 125 V DC C. Valves open; 1202.003, Overcooling D. Valves open; 1203.036, Loss of 125 V DC
ANO Unit 1 -2011 SRO NRC Written Examination Question No. 91 QID: 0570 The plant was at 80% power when ONLY one failure caused the following:
- Plant running back
- Tavg Control swaps to Loop A
- A Main Feedwater flow rapidly rising
- B Main Feedwater flow rapidly dropping
- Feedwater pumps discharge crosstie valve shut Which one of the following procedural actions would be used in response to the above conditions?
A. Place affected MFW pump in hand per 1203.022, Reactor Coolant Pump Trip B. Verify ICS in track and runback in progress per 1203.022, Reactor Coolant Pump Trip C. Place affected MEW pump in hand per 1203.001, ICS Abnormal Operation D. Verify ICS in track and runback in progress per 1203.001, ICS Abnormal Operation
ANO Unit 1 -2011 SRO NRC Written Examination Question No. 92 QID: 0450 Given:
- Refueling is in progress.
- A fuel assembly is being moved toward the upender in the Fuel Transfer Canal.
- Source Range channel Nl-502 power supply fails.
Which of the following actions is appropriate for these conditions?
A. All refueling operations may continue as long as one Source Range channel is operable.
B. The fuel assembly may be placed in any alternate core location during repairs.
C. The fuel assembly may be moved to the Spent Fuel Pool but core alterations are not allowed.
D. The fuel assembly must be placed back in its original position in the core.
ANO Unit I - 2011 SRO NRC Written Examination Question No. 93 QID: 0845 Given:
-Plant 100% power
-Dispatcher calls and requests Unit 1 to reduce power to 500 MWe in 10 minutes During power reduction the following alarms come in:
-MAIN STEAM PRESSURE HI/LO (K07 C6)
-UNIT MASTER IN TRACK (K07 Al)
Which of the following procedures would be in use to mitigate this event?
A. ICS Abnormal Operation 1203.001 and Rapid Plant Shutdown 1203.045 B. ICS Abnormal Operation 1203.001 and Power Reduction and Plant Shutdown 1102.016 C. Load Rejection 1203.020 and Rapid Plant Shutdown 1203.045 D. Load Rejection 1203.020 and Power Reduction and Plant Shutdown 1102.016
ANO Unit I - 2011 SRO NRC Written Examination Question No. 94 QID: 0846 Given:
Unit 1 refueling is in progress.
- Due to difficulties inserting a fuel assembly into the core, the Bridge Operator requests an alteration in the fuel load sequence.
Who must approve a change to fuel shuffle sequence?
A. SRO in Charge of Fuel Handling and Refueling Project Manager B. Operatons Manager and Refueling Project Manager C. SRO in Charge of Fuel Handling and Reactor Engineer D. Operatons Manager and Reactor Engineer
ANO Unit I - 2011 SRO NRC Written Examination Question No. 95 QID: 0407 The plant is at 100% power on New Years Eve night shift.
The on-duty CRS has a heart attack and must be transported to St. Marys at 0210.
What is the latest time at which a replacement CRS must be in the Control Room BEFORE Technical Specifications are violated?
A. 0400 B. 0500 C. 0600 D. 0700
ANO Unit 1 - 2011 SRO NRC Written Examination Question No. 96 QID: 0119 Given the following A Core Flood Tank (CFT) parameters with the plant is at 100% power.
- Level transmitter out of service
- CFT level is 12.5 feet
- Boric acid concentration is 2280 ppm
- CFT pressure is 580 psig Which of the above parameters makes the A CFT inoperable per Tech Specs?
A. Level transmitter B. CFT level C. Boric acid concentration D. CFT pressure
ANO Unit I - 2011 SRO NRC Written Examination Question No. 97 QID: 0852 OPEN REFERENCE Unit One is at 100% power.
The following items are on the schedule to be worked this shift:
- 1. 1305.001, Supplement 6, Area Radiation Monitor Monthly Alarm Check
- 2. 1305.036, Unit iPower Linear Amp Calibration At Power
- 3. WO#01 75862, Corrective Maintenance on TR-9001, Gen & Coolers Gas Outlet Temperature Recorder
- 4. Swapping SW Pumps P4C to P4B for strainer cleaning
- 5. 1304.021, Unit 1 N-16 Monitor Calibration In accordance with COPDO13, Operations Maintenance Interface Standards and Expectations, which of the above items are allowed to be worked this shift? (Shift Manager approval has NOT been given to exceed normal limits.)
A. 1,3,4 B. 2,3,4 C. 3,4, 5 D. 1,4,5
ANO Unit 1 -2011 SRO NRC Written Examination Question No. 98 QID: 0391 A worker arrives on site with 2.8 Rem accumulative dose for the calendar year.
The workers NRC form 4 is on file.
The workers expected exposure will be 1.6 Rem for his assigned job.
Whose authorization is required to extend the workers TEDE exposure limit?
- a. The workers Supervisor, Radiation Protection Manager, and Plant General Manager.
- b. The workers Supervisor and Radiation Protection Manager.
- c. Radiation Protection Manager, Plant General Manager and Site Vice President.
- d. This exposure limit can not be authorized per Entergy Admin Exposure Limits.
ANO Unit I - 2011 SRO NRC Written Examination Question No. 99 QID: 0411 A fire was reported at 0844 in the vicinity of the Old Radwaste Building.
It is now 0920 and the fire is still burning.
Based on the above conditions what is the time requirement for notification to the NRC?
A. Notification to the NRC is required within 15 minutes of the declaration of an emergency class.
B. Notification to the NRC is required immediately following notification of the ADH and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of the declaration of an emergency class.
C. Notification to the NRC is required immediately following declaration of an emergency class and notify the ADH within I hour.
D. Notification to the NRC is required within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of the declaration of an emergency class.
ANO Unit I - 2011 SRO NRC Written Examination Question No. 100 QID: 0357 During a declared Alert emergency, the TSC Director may NOT assume responsibility for Emergency Direction and Control until:
A. The next shifts Shift Manager arrives for shift relief and receives a turnover.
B. The Operations Manager arrives in the Control Room and passes on responsibility for EDC.
C. The TSC Director receives a turnover from the SM and assumes responsibility for EDC.
D. The emergency is downgraded to an NUE.
ANO Unit 1 -2011 SRO NRC Written Exam KEY Question No. 76 QID: 0855 Point Value: I Answer:
D. Control Turbine Bypass valves (TBVs) to quickly reduce SG pressures to reseat the MSSV per 1202.001 Reactor Trip.
Question No. 77 QID: 0839 Point Value: I Answer:
A. 1202.002, Loss of Subcooling Margin Question No. 78 QID: 0639 Point Value: I Answer:
B. 1203.028, Loss of Decay Heat Removal Question No. 79 QID: 0731 Point Value: I Answer:
D. A cooldown rate of 110°F/hr with Tcold at 330° F.
Question No. 80 QID: 0586 Point Value: I Answer:
D. Within 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> Question No. 81 QID: 0840 Point Value: I Answer:
A. 1,2,4,7 Question No. 82 QID: 0841 Point Value: I Answer:
C. Initiate boration to restore SDM by 1530.
Question No. 83 QID: 0590 Point Value: I Answer:
B. Immediately suspend positive reactivity additions and initiate a shutdown so that all CRD breakers are open within one hour.
ANO Unit 1 - 2011 SRO NRC Written Exam KEY Question No. 84 QID: 0347 Point Value: I Answer:
D. Return the assembly to an available location in the reactor vessel.
Question No. 85 QID: 0342 Point Value: I Answer:
D. 1203.019 High Activity In Reactor Coolant 40%
Question No. 86 QID: 0607 Point Value: I Answer:
C. 1203.026, Loss of Reactor Coolant Makeup, Section 2 - Large Makeup and Purification System Leak Question No. 87 QID: 0842 Point Value: I Answer:
B. Close the ERV Isolation Valve (CV-1 000) per OP-1203.015, Pressurizer Systems Failure Question No. 88 QID: 0843 Point Value: I Answer:
D. Place A in channel bypass and trip C RPS channel.
Question No. 89 QID: 0844 Point Value: I Answer:
B. Override and throttle both LPI Pumps close to but not below 2800 gpm per pump per 1202.010 Att. 1, Shift to RB Sump Suction.
Question No. 90 QID: 0740 Point Value: I Answer:
D. Valves open; 1203.036, Loss of 125 V DC Question No. 91 QID: 0570 Point Value: I Answer:
B. Verify ICS in track and runback in progress per 1203.022, Reactor Coolant Pump Trip
ANO Unit I - 2011 SRO NRC Written Exam KEY Question No. 92 QID: 0450 Point Value: I Answer:
C. The fuel assembly may be moved to the Spent Fuel Pool but core alterations are not allowed.
Question No. 93 QID: 0845 Point Value: I Answer:
A. ICS Abnormal Operation 1203.001 and Rapid Plant Shutdown 1203.045 Question No. 94 QID: 0846 Point Value: I Answer:
C. SRO in Charge of Fuel Handling and Reactor Engineer Question No. 95 QID: 0407 Point Value: I Answer:
A. 0400 Question No. 96 QID: 0119 Point Value: I Answer:
B. CFT level Question No. 97 QID: 0852 Point Value: I Answer:
C. 3,4, 5 Question No. 98 QID: 0391 Point Value: I Answer:
- c. Radiation Protection Manager, Plant General Manager and Site Vice President.
Question No. 99 QID: 0411 Point Value: I Answer:
B. Notification to the NRC is required immediately following notification of the ADH and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of the declaration of an emergency class.
ANO Unit 1 - 2011 SRO NRC Written Exam KEY Question No. 100 QID: 0357 Point Value: I Answer:
C. The TSC Director receives a turnover from the SM and assumes responsibility for EDC.