ML120090291
| ML120090291 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 01/09/2012 |
| From: | NRC/RGN-II |
| To: | Progress Energy Carolinas |
| References | |
| ES-401-8 | |
| Download: ML120090291 (105) | |
Text
ES-401 Site-Specific SRO Written Examination Form ES-4014 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant information Name:
Date:
Facility/Unit:
Region:
I II Q lii Q IV Q Reactor Type: W CE U BWD3E U 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-Only/Total Examination Values I
I Points Applicants Scores I
I Points Applicants Grade I
/
Percent
.1 ES-401, Page 31 of 33
ILC-11-2 NRC Exam
- 1. Given the following plant conditions:
- The unit has just experienced an automatic reactor trip from 100% RTP.
- The turbine failed to trip automatically.
- A manual turbine trip was initiated and the following indications are present:
- Left Turbine Stop Valve indicates CLOSED
- All Governor Valves indicate OPEN
- RCS pressure is 1860 psig Tavg is 542°F
- No SI equipment has actuated S!G Pressure Steam Flows A
895 psig 0.1 X 106 Ibm/hr B
915 psi 9
0.1 X 106 Ibm/hr C
835 psig 1.45 X 106 Ibm/hr Which ONE (1) of the following identifies the required operator response lAW PATH-i?
Runback the turbine until....
A. ALL Governor Valves indicate CLOSED AND verify TWO (2) charging pumps running B. at least the Right Upper and Right Lower Governor Valves indicate CLOSED (all Governor Valves not required to indicate closed) AND verify TWO (2) charging pumps running C. ALL Governor Valves indicate CLOSED AND manually initiate SI D. at least the Right Upper and Right Lower Governor Valves indicate CLOSED (all Governor Valves not required to indicate closed) AND manually initiate SI I
ILC-11-2 NRC Exam
- 2. Given the following plant conditions:
- The plant is at 100% RTP.
- PC-444J, PZR PRESS, has failed HIGH.
Assuming NO operator actions are taken, which ONE (1) of the following completes the following statement?
The FIRST reactor trip signal will be generated when the reactor protection (1) setpoint is exceeded.
PCV-455C, PZR PORV, will receive a closed signal once pressurizer pressure lowers below (2) psig.
A. (1) OTdeltaT (2) 2000 B. (1) Low Pressurizer Pressure (2) 2000 C. (1)OTdeltaT (2) 2185 D. (1) Low Pressurizer Pressure (2) 2185 2
ILC-11-2 NRC Exam
- 3. Given the following plant conditions:
- A LOCA has occurred.
J
- RCS pressure is 1100 psig and lowering.
- Containment pressure had peaked at 12 psig.
- The crew is performing actions of EPP-8, Post LOCA Cooldown and Depressurization.
Which ONE (I) of the following identifies the method that will be used to initiate cooldown of the RCS?
Initiate cooldown using the...
A. steam dumps at the maximum achievable rate.
B. steam dumps at no greater than 100°F per hour.
C. SIG PORVs at the maximum achievable rate.
- 0. SIG PORVs at no greater than 100°F per hour.
3
ILC-1l-2 NRC Exam
- 4. Given the following plant conditions:
- A Large Break LOCA has occurred from 100% RTP.
- Containment pressure is 23 psig and rising.
- PATH-i is being implemented.
- The CRS has directed the RO to trip the RCPs.
Which ONE (1) of the following is the basis for tripping the RCPs?
A. Allowing the RCPs to run would hinder Accumulator injection due to turbulent two-phase flow characteristics in loops.
B. Tripping the RCPs will protect them from overheating due to loss of cooling water.
C. Allowing the RCPs to run would force more water out of the break and cause core uncovery sooner.
D. Tripping the RCPs allows the loop seal to clear thus minimizing RCS inventory loss.
0 4
ILC-11-2 NRC Exam
- 5. Given the following plant conditions:
Attime 1852 j
- The plant experienced a reactor trip from 100% RTP
- 480V Bus E-2 de-energized and operators manually energized the bus from its associated EDG.
At time 1918
- PCV-17l6, Instrument Air Isolation to CV, failed closed and Air Operated Valves in Containment are repositioning to their fail position.
Which ONE (1) of the following completes the statement below?
At time 1933, RCP motor bearing temperatures will (1) and RCP seal leakoff temperatures will (2) the associated alarm setpoint.
A. (1) rise (2) rise above B. (1) rise (2) remain below C. (1) remain approximately constant (2) rise above D. (1) remain approximately constant (2) remain below 5
ILC-11-2 NRC Exam
- 6. Given the following plant conditions:
- The plant is operating at 100% RTP.
- RCS Makeup System is properly aligned and an Auto makeup is in progress.
- The air supply line to FCV-1 14A, Primary Water Flow Dilute Mode, severed ONE (1) minute ago.
Which ONE (1) of the following identifies the failed position of FCV-114A and expected alarm?
FCV-1 14A will fail (1) and APP-003-D5, BA FLOW DEV, (2) be received.
A. (I) OPEN (2) will B. (1) OPEN (2) will NOT C. (1) CLOSED (2) will D. (1) CLOSED (2) will NOT 6
ILC-1 1-2 NRC Exam
- 7. Which ONE (1) of the following identifies the basis for closing FCV-605, RHR HX Bypass Valve, and HCV-758, RHR HX Outlet Flow To Cold Legs, prior to starting the standby RHR Pump lAW AOP-020, Loss of RHR (Shutdown Cooling), Section E, Loss
)
of RHR Flow or Temperature Control?
A. Prevent cavitation of the pump.
B. Reduce the pump starting current and prevent pump runout.
C. Prevent water hammer damage to the RHR Heat Exchangers.
D. Control the introduction of cooler water from the stagnant water in the suction and discharge piping of the standby pump.
7
ILC-1 1-2 NRC Exam
- 8. Given the following plant conditions:
- EPP-1, Loss of All AC Power, is being implemented.
- The DS Bus has been energized lAW EPP-1, Attachment 6, Restoring AC Power At the DSDG Generator Control Panel.
- EPP-22, Energizing Plant Equipment Using DSDG, Attachment 1, Energizing Pressurizer Heaters from DS Bus, has been completed and specified heaters energized.
- PC-444J, PZR PRESS, has FAILED to 0% output.
Which ONE(1) of the following identifies the alternate method to control pressurizer heaters lAW EPP-22 based on the conditions given above?
A. Operate breakers on Pressurizer Htr Panel #3 Control Group B. Operate breaker 52/15B, 480V Bus 3 Main Bkr from the RTGB C. Operate breaker 52/1 2B, 480V Bus 2B-3 Tie Bkr from the RTGB D. Operate the PZR Heater Emergency Control Station in the Rod Control Room 8
ILC-1 1-2 NRC Exam
- 9. Given the following plant conditions:
An ATWS has occurred.
The crew is performing immediate actions of FRP-S.1, Response to Nuclear Power Generation/ATWS.
A manual reactor trip using both RTGB pushbuttons was unsuccessful.
Rods are being inserted in MANUAL.
lAO and OAO have been dispatched to locally trip the reactor.
The THINK and Manual Turbine Trip Buttons have been depressed.
Main Turbine Governor and Stop Valves indicate open.
Which ONE (1) of the following identifies the NEXT required action(s) that must be taken lAW FRP-S.1?
A. Close all MSIVs and MSIV Bypasses.
B. Depress and hold the GV Down and GV Fast pushbuttons.
C. Depress the turbine manual pushbutton and then depress and hold the the GV Down pushbutton ONLY.
D. Depress the turbine manual pushbutton and then depress and hold the GV Down and GV Fast pushbuttons.
9
ILC-11-2 NRC Exam
- 10. Given the following plant conditions:
- The plant was operating at 100% RTP.
- The plant has experienced a SIG tube rupture with a Loss of Coolant Accident.
- Current RCS level is at the hot leg centerline.
- No SI flow exists due to multiple malfunctions.
Which ONE (1) of the following identifies how the majority of the heat is removed from the core for the given conditions?
Boiling in the core produces steam which condenses in....
A. the reactor vessel annular space and re-floods the core.
B. the upper head and re-floods the core via the upper internals.
C. the S/G tubes and flows down the cold leg back to the core.
D. the S/G tubes and flows down the hot leg back to the core.
D 10
ILC-11-2 NRC Exam
- 11. Given the following plant conditions:
- Th
- Plant had been operating at 100% RTP for 285 days prior to a plant trip and safety injection ocurring.
- The crew is performing actions of FRP-H.1, Response to Loss of Secondary Heat Sink.
- Plant conditions require that an RCS Bleed and Feed be performed.
Which ONE(1) of the following completes the statement below?
To ensure adequate RCS Injection flow a MINIMUM of (1) safety injection pump(s) are/is required to be running AND (2)
PZR PORV(s) will be opened to provide an adequate RCS Bleed path.
A. (1)one (2) one B. (1)one (2) two C. (1)two (2) one D. (1)two (2) two 11
ILC-11-2 NRC Exam
- 12. Given the following plant conditions:
- Reactor power is at 100% RTP.
S.)
- A Generator Lockout occurs simultaneously with a loss of the Startup Transformer.
- Both EDGs fail to start.
Which ONE (1) of the following completes the statements below?
For the conditions given above, lAW EPP-1, Loss of All AC Power, steam is verified isolated to the Turbine by (1) and (2) are required to be CLOSED to isolate letdown flow.
A. (1) closing the MSIVs AND MSIV Bypasses (2) LCV-460A1B, Letdown Line Stop Valves B. (1) closing the MSIVs and MSIV Bypasses (2) CVC-204A/B, Letdown Line Isolation Valves C. (1) verifying BOTH Turbine Stop Valves CLOSED (2) LCV-460A1B, Letdown Line Stop Valves D. (1) verifying BOTH Turbine Stop Valves CLOSED (2) CVC-204A1B, Letdown Line Isolation Valves 12
ILC-11-2 NRC Exam
- 13. Given the following plant conditions:
- The reactor has tripped due to a loss of off-site power.
- Natural circulation flow is being established.
- The Subcooling Monitor indicates the following information:
- TIC at B07 558°F
- T/C at H04 555°F
- T/C at DOS 556°F
- T/CatRO8 554°F
- The RTGB indicates the following information:
- P1-445:
1800 psig
-P1-456:
1785 psig
- P1-457:
1795 psig Determine the current value of subcoolinq that will be utilized while in the EOP Network.
A. 60.8 - 62.5°F
- 8. 62.8
- 64.5°F C. 64.8
- 66.5°F D. 66.8
- 68.5°F J
13
ILC-11-2 NRC Exam
- 14. Given the following plant conditions:
- The plant is operating at 100% RTP.
- A loss of Instrument Bus 2 has occurred.
Which ONE (1) of the following completes the statement below?
Safeguards Train (1)
Sequencer is currently de-energized and (2)
A. (1) A (2) bistable Status Panel A will be de-energized B. (1) B (2) bistable Status Panel A will be de-energized C. (1) A (2) channel 2 bistables on Status Panel A will be illuminated with the exception of CV HI-HI Pressure D. (1) B (2) channel 2 bistables on Status Panel A will be illuminated with the exception of CV HI-HI Pressure 14
ILC-1 1-2 NRC Exam
- 15. Given the following plant conditions:
- Plant was operating at 100% RTP.
- A loss of A DC Bus occurs.
FIVE (5) minutes later, which ONE (1) of the following identifies the expected plant response due to the loss of A DC Bus?
Safety Injection Exciter Field Bkr Actuation Auto Trips A.
YES YES B.
YES NO C.
NO YES D.
NO NO 15
ILC-11-2 NRC Exam
- 16. Given the following plant conditions:
- Plant is at 35% RTP.
- APP-002-E7,INST AIR COMP D TRIP, illuminates.
- APP-002-F7, INST AIR HDR LO PRESS, illuminates.
- AOP-017, LOSS OF INSTRUMENT AIR, is entered.
- Station Air and Instrument Air have been cross-connected.
- Transition has been made to AOP-017, Section A, Modes I AND 2.
- Instrument Air pressure is 64 psig.
- B and C S/Gs Levels are at 42% and slowly lowering.
Which ONE (1) of the following completes the statement below?
The operating crew is required to while continuing in AOP-017.
A. cross-connect Station Air and Construction Air B. lower turbine load as necessary to maintain feed and steam flows matched C. trip the turbine and implement AOP-007, Turbine Trip below P-8, D. trip the reactor and Go to PATH-I D
16
ILC-11-2 NRC Exam
- 17. Given the following plant conditions:
A loss of BOTH Main Feedwater Pumps (MFP) has resulted in a manual reactor
)
trip.
All 3 AFW Pumps are disabled.
The crew is performing actions of FRP-H.1, Response to Loss of Secondary Heat Sink.
Wide Range S/G levels are at 25% and lowering.
Attempts to start either MFP have failed.
PZR Level was maintained greater than 16%.
Which ONE (1) of the following completes the statement below?
lAW FRP-H.1, RCS pressure will be reduced by opening (1) to allow the (2)
A. (1) one PZR PORV (2) Hi Steam Line DP and PZR Pressure SI signals to be blocked prior to performing actions to establish Condensate flow B. (1) CVC-31 1, Aux. Spray (2) Hi Steam Line DP and PZR Pressure SI signals to be blocked prior to performing actions to establish Condensate flow C. (1)0nePZRPORV (2) safety injection flow to inject into the RCS D. (1) CVC-31 1, Aux. Spray (2) safety injection flow to inject into the RCS 17
ILC-I1-2 NRC Exam
- 18. Given the following plant conditions:
A Reactor Trip and Safety Injection have occurred from 100% RTP.
Following the Immediate Action Verifications of PATH-I, Breaker 52/2BL, Feed to MCC-9, trips.
EPP-16, Uncontrolled Depressurization of All Steam Generators, is being performed.
All steam generator (SIG) pressures are lowering uncontrollably.
Which ONE (1) of the following completes the statement below regarding the preferred method for controlling feedwater flow in accordance with EPP-16?
The basis for lowering flow to 80 to 90 gpm to all S/Gs is to (1) and the preferred method of controlling AFW flow is to (2)
A. (1) minimize RCS repressurization rate (2) dispatch an operator to manually throttle the V2-16s B. (1) maintain S/G components in wet condition (2) dispatch an operator to manually throttle the V2-16s C. (I) minimize RCS repressurization rate
>1 (2) throttle the MDAFW Flow Controllers FIC-1424 and FIC-1425 D. (1) maintain S/G components in wet condition (2) throttle the MDAFW Flow Controllers FIC-1424 and FIC-1425 18
ILC-1 1-2 NRC Exam
- 19. Given the following plant conditions:
N
- The plant is operating at 50% RTP with OST-Ol 1, Rod Cluster Control Exercise &
Rod Position indication, being performed.
- When Control Bank D rods are returned to 164 steps it is noted that one rod is 17 steps below the rest of the bank.
- AOP-001, Malfunction of Reactor Control System, is implemented by the crew.
- The Shift Manager has directed that the rod be realigned lAW AOP-001.
Which ONE (1) of the following completes the basic method used to realign the rod in accordance with AOP-001 listed below?
Open the Control Bank Dt lift coil disconnect switch(es) for (1)
Realign the rod using (2) position of the rod bank selector switch.
Close all lift coil disconnect switches.
A. (1) all but the misaligned rod (2) CB D B. (1) all but the misaligned rod (2) M (MANUAL)
C. (1) the misaligned rod (2)CBD D. (1) the misaligned rod (2) M (MANUAL)
D 19
ILC-1 1-2 NRC Exam
- 20. Given the following plant conditions:
- Plant is at 100% RTP.
- C Charging Pump is in Auto and B Charging Pump is in Manual.
- Pressurizer level transmitter LT-459 is selected for control.
- The reference leg for LT-460 develops a leak.
Which ONE (1) of the following identifies the instrument and plant response?
LI-460 C Charging Pump PZR LVL Speed Controller Indication Output A.
Lowers Rises B.
Rises Lowers C.
Lowers Remains the same D.
Rises Rises 20
ILC-11-2 NRC Exam 21.
l&C has just completed a surveillance on the high voltage power supply to Source Range nuclear instrument N-31. The surveillance determined the as-found voltage was 1400 VDC, instead of the normal 1600 VDC.
Which ONE (1) of the following identifies the effect the lower voltage has on SR N-31 instrument response?
N-31 will indicate (1) than normal due to a reduction in voltage to the (2)
A. (1) higher (2) pulse height discriminator B. (I) higher (2) detector C. (1) lower (2) pulse height discriminator D. (1) lower (2) detector
)
21
ILC-11-2 NRC Exam
- 22. Given the following plant conditions:
- The plant is at 8% RTP with the Turbine at 1800 RPM, unloaded.
- The following is the current status of plant permissives:
REACTOR TRIP POWER POWER BLOCK ABOVE ABOVE P.7 P4 P.10 LO POWER AUTO ROD WIThDRWL STOP INTERM RANGE TRIP BLOCKED
- STEAM DUMP tAVG CoNTROL.
BLOCKED REACTOR TRIP BLOCK P4 LO TEMP SAFElY iNJECTION SOURCE LOPOWER RANGE RANGE TRIP TRIP BLOCKED BLOCKED LO PRESS LO PRESS SAFETY INJECTION PERMIT BLOCKED (lightly shaded blocks are illuminated, darker blocks are extinguished)
- An operator assisting l&C with N-35 maintenance removes the N-35 control power fuses.
Which ONE (1) of the following identifies the Reactor Protection System response for the N-35 IR Level Trip Bypass switch positions shown below?
NORMAL BYPASS A.
No Reactor Trip No Reactor Trip B.
Reactor Trip No Reactor Trip C.
No Reactor Trip Reactor Trip D.
Reactor Trip Reactor Trip 22
ILC-11-2 NRC Exam
- 23. Given the following plant conditions:
- Plant is in Mode 3.
J
- R-14C, Main Vent Stack (Low Range Noble Gas), is inoperable.
- A leak on C Waste Gas Decay Tank has resulted in an R-20, Fuel Handling Building Lower Level - Low Range, alarm.
- lAW AOP-009, Accidental Gas Release From a WGDT, the HP has been directed to obtain air samples of the affected area and local evacuation completed.
Which ONE(1) of the following completes the statements below?
lAW AOP-009, HVE-5A (1)
HVE-58 are required to be placed in service and (2) due to R-14C being inoperable.
A. (1)AND (2) R-1 IIR-12 are required to be selected to the VENT Position B. (1)OR (2) R-11IR-12 are required to be selected to the VENT Position C. (1)AND (2) veri that R-14D, Main Vent Stack Mid Range, is operable J
D. (1)OR (2) verify that R-14D, Main Vent Stack Mid Range, is operable Th 23
1LC-11-2 NRC Exam
- 24. Given the following plant conditions:
- The plant is operating at 100% RTP.
j
- The following fire alarms (color of text) have been received on the Fire Alarm Computer.
- A43 ZN-20 Fire Aim. TRN-A E1/E2 Room (RED)
- A51 ZN-20 Fire Aim. TRN-A E1/E2 Rm. Halon Actuated (RED)
- A55 ZN-NO Fire Aim. TRN-A FDAP Al Master Fire Aim. (RED)
- B04 ZN-20 Fire Aim. TRN-B E1/E2 Room (RED)
- B06 ZN-20 Fire Aim. TRN-B E1/E2 Rm. Hlon Actuated (RED)
- B09 ZN-NO Fire Aim. TRN-B FDAP BI Master Fire Aim. (RED)
Which ONE(l) of the following completes the statement below lAW AOP-041, Response to Fire Event?
The Control Room Operator is responsible for dispatching the fire brigade, starting the motor driven fire pump, placing the A. PCV-456 and PCV-455C Power isolation Switches to the ISOLATED position and securing Auxiliary Building Ventilation. (Control Room Ventilation to remain in Normai Mode.)
B. EDG and El/E2 Breakers Appendix R Isolation switches to NORMAL and securing Auxiliary Building Ventilation. (Control Room Ventilation to remain in Normai Mode.)
C. PCV-456 and PCV-455C Power isolation Switches to the ISOLATED position, securing Auxiliary Building Ventilation and placing Control Room Ventilation in Pressurization Mode.
D. EDO and El/E2 Breakers Appendix R isolation switches to NORMAL, securing Auxiliary Building Ventilation and placing Control Room Ventilation in Pressurization Mode.
24
ILC-1 1-2 NRC Exam
- 25. Given the following plant conditions:
- Plant is currently at 100% RTP preparing for a shutdown due to high RCS Activity levels.
- A RCS leak of 10 gpm has been identified inside Containment.
Which ONE(1) of the following identifies which process radiation monitors will indicate an elevated reading?
R-1 1:
Containment Air Particulate R-12:
Containment Air Gas R-14C: Plant Stack Gas (Low range)
R-11 R-12 R-14C A.
Yes Yes Yes B.
Yes Yes No C.
No Yes Yes D.
Yes No No 25
ILC-11-2 NRC Exam
- 26. Given the following plant conditions:
- Plant was operating at 100% RTP when a steam line break occurs in the CV.
- All RCS Cold leg temperatures are right of Pressure - Temperature Limit A.
- RCS pressure is 600 psig.
Which ONE(1) of the following completes the statement below?
The CSFST for CSF-4, RCS Integrity, states that entry requirements for FRP-P.1, Response to Imminent Pressurized Thermal Shock, RCS Cold Leg Temperature must have dropped greater than (1) in the last 60 minutes and RCS Cold Leg Temperature must be less than (2)
A. (1)100°F (2) 320°F B.
(1) 100°F (2) 290°F C. (1) 50°F (2) 320°F D. (1) 50°F (2) 290°F 26
ILC-11-2 NRC Exam
- 27. Given the following plant conditions:
The reactor has tripped due to a loss of off-site power.
A RCS cooldown to Mode 5 must be peormed.
A Natural Circulation cooldown is in progress in accordance with EPP-5, Natural Circulation Cooldown.
BOTH CRDM Cooling Fans, HVH-5A and 5B, are running.
TSC has determined that the RCS cooldown rate must exceed the EPP-5 limit.
Which ONE (I) of the following completes the statement below?
Following procedure transition, the RCS cooldown rate is limited to (1) in order to (2)
A. (1) 100°F/hr (2) remain within the Technical Specification limits B. (1)50°F/hr (2) remain within the Technical Specification limits C. (1) 100°F/hr (2) prevent formation of voids in the Reactor Vessel upper head region D. (1)50°F/hr (2) prevent formation of voids in the Reactor Vessel upper head region 27
JLC-11-2 NRC Exam
- 28. Given the following plant conditions:
- Plant cooldown is in progress lAW GP-007, Plant Shutdown from Hot Shutdown to J
Cold Shutdown.
- RCS temperature and pressure is 250°F and 375 psig.
- A and C RCP seal leakoff flows indicate 0.7 gpm.
- Seal injection flows are normal.
RCS pressure control malfunction occurs and pressure begins to lower.
- Maximum RCP Seal Leakoff Temperature is 145°F.
- Maximum RCP Pump Bearing Temperature is 132°F.
Which ONE (1) of the following completes the statement below?
At (1) the crew is required to (2)
A. (1) 325 psig RCS pressure (2) secure RCPs B. (1) 325 psig RCS pressure (2) open CVC-307, PRI SEAL BYP ISO C. (1) 210 psid across the RCP #1 Seal (2) secure RCPs
-J 28
ILC-I1-2 NRC Exam
- 29. Given the following plant conditions:
- The RCS is on RHR and solid.
- RCS pressure is 340 psig.
- PC-145, PRESSURE, in AUTO.
- HIC-142, PURIFICATION FLOW, controller setting is at 55% demand.
Subsequently,
- HIC-142 controller setting was adjusted to 50% demand.
Which ONE (I) of the following completes the statement below?
Steady-state to Steady-state, PC-I 45 controller output will (1) to restore letdown pressure to its original value and overall RCS pressure will (2)
A. (I) lower (2) rise B. (I) rise (2) rise C. (I) rise (2) lower D. (1) lower (2) lower 29
ILC-11-2 NRC Exam
- 30. Given the following plant conditions:
- The plant is operating at 100% RTP.
- C Charging Pump is currently running in AUTO and B Charging Pump is running in MANUAL at minimum speed.
- Maintenance has been completed on A Charging Pump and WCC has dispatched an operator to remove the clearance and align the pump for recirculation.
- During the valve alignments the operator incorrectly aligns the recirculation path by having BOTH CVC-277C, Charging Pump A Recirc Root, AND CVC-290, Charging Pump A To Charging Line, OPEN.
Which ONE(1) of the following completes the statement below, assuming no operator action?
The output on C Charging Pump speed controller will rise (1) and VCT level will (2)
A. (1) and maintain PZR program level (2) rise B. (1) to maximum (2) rise J
C. (1) and maintain PZR program level (2) remain the same D. (1) to maximum (2) remain the same J
30
ILC-11-2 NRC Exam
- 31. Given the following plant conditions:
Initial Conditions
- Plant is in Mode 5 with the RCS depressurized
- A RHR Pump is in-service.
- FC-605, RHR HX BYPASS FLOW, is in Manual with flow set at 3400 gpm.
Current Conditions
- APP-001-A7, RHR HX LO FLOW, is received.
- Observed that Sl-863A, RHR Loop Recirc, valve indicates dual position.
Which ONE (1) of the following completes the statement below?
Based on the conditions above, RCS Temperature will (1) and RCS Level will (2)
A. (1) rise (2) lower B. (1) rise (2) remain stable C. (1) lower (2) lower D. (1) lower (2) remain stable I
i.
31
ILC-1 1-2 NRC Exam
- 32. Which ONE (1) of the following identifies the reason for RCP restart lAW FRP-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK, if the SI termination criteria cannot be satisfied?
A. Restores PZR spray to allow RCS depressurization in subsequent steps.
B. Equalizes SIG pressures to allow simultaneous cooldown of all three loops in subsequent steps.
C. Mixes Safety Injection water and RCS water to ensure adequate shutdown margin.
D. Mixes Safety Injection water and RCS water to raise the fluid temperature entering the Reactor Vessel downcomer.
j)
J 32
ILC-11-2 NRC Exam
- 33. Which ONE(l) of the following completes the statements below?
The PRT high level alarm setpoint is (1)
The basis for this setpoint is to minimize the possibility of (2)
A. (1)91%
(2) challenging the rupture discs following a 100% Load Rejection without a reactor trip B. (1)83%
(2) challenging the rupture discs following a 100% Load Rejection without a reactor trip C. (1)91%
(2) thermally shocking the pressurizer safeties and PORVs which could cause them to leak D. (1)83%
(2) thermally shocking the pressurizer safeties and PORVs which could cause them J
to leak 33
ILC-11-2 NRC Exam
- 34. Given the following plant conditions:
- The plant had been operating at 100% RTP when a Reactor Trip and Safety Injection occurred due to a faulted steam line outside containment.
- While performing PATH-I actions the following indications were observed:
- APP-003-D3, PRT HI/LO LEVEL
- APP-003-C3, PRT HI PRESS, alarmed and cleared
- R-2, CV Low Range Monitor - Stable
- CV Sump Level - Rising Which ONE(1) of the following identifies the cause of the indications given?
A. Sl-857B, Loop B Cold Leg lnj Relief to PRT, failed open B. Reactor Vessel Head inner 0-ring fails C. PZR Safety Valve failed open D. A RCP #2 seal failure 34
ILC-11-2 NRC Exam
- 35. Given the following plant conditions:
- Unit has experienced a LBLOCA.
- EPP-1 0, Transfer to Long Term Recirculation, has been implemented.
- APP-002-E5, SI PMP COOL WTR LO FLOW, is received.
Which ONE(1) of the following completes the statements below lAW APP-002-E5?
The SI Pump Cooling Water Low Flow alarm setpoint is (IL GPM.
APP-002-E5 requires the operator to (2)
A. (1)100 (2) continue operation of the SI Pump B. (1)50 (2) continue operation of the SI Pump C. (1)100 (2) stop the SI Pump immediately D. (1)50 (2) stop the SI Pump immediately ZZ 35
ILC-ll-2 NRC Exam
- 36. Given the following plant conditions:
- The plant is in Mode I at 100% RTP
- The Pressurizer Pressure Controller, PC-444J, is in AUTOMATIC Which ONE (1) of the following identifies how RCS pressure and PC-444J Controller output will respond if the controller potentiometer setpoint is lowered from 6.7 to 6.4?
RCS Pressure Controller Output (Demand)
A.
Rise Rise B.
Rise Lower C.
Lower Rise D.
Lower Lower
)
36
ILC-11-2 NRC Exam
- 37. Which ONE(1) of the following completes the statement below?
A design feature of the Pressurizer maintains a small amount of flow in the spray lines inorderto A. reduce the potential for water hammer upon spray initiation.
B. maintain a small differential across the spray valves.
C. maintain a constant firing rate to the Control Group heaters.
D. reduce thermal stresses in the spray piping and auxiliary spray connection.
37
ILC-1 1-2 NRC Exam
- 38. Given the following plant conditions:
- Unit at 30% RTP
- Power Range channel N-43 has been removed from seMce lAW OWP-O1 Ito support drawer calibration.
Subsequently:
- Inverter A trips What impact will the failure have on the Reactor Protection System?
A. Reactor will trip from Power Range High Flux (HIGH) setpoint.
B. Reactor will trip from Power Range High Flux (LOW) setpoint.
C. Reactor will trip from Intermediate Range High Flux trip.
D. Reactor will NOT trip.
38
ILC-11-2 NRC Exam
- 39. Which ONE (1) of the following identifies the power supply to the ESFAS interposing relays?
)
Train A Train B A.
IB-7A IB-3 B.
18-6 IB-9 C.
IB-2 18-8 D.
lB-I lB-4 D
39
ILC-11-2 NRC Exam
- 40. A Large Break LOCA concurrent with a loss of the Startup Transformer has occurred.
- Train A Engineered Safeguards Sequencer did NOT automatically actuate.
- Both A and B CV Spray Pumps tripped.
Which ONE (1) of the following completes the statement below?
The MINIMUM action required to ensure containment pressure remains below its design limit is to verify (1) automatically started AND manually start (2) and ensure all associated cooling water outlet low flow alarms are clear.
A. (1) HVH-3 Q HVH-4 (2) HVH-1 ORHVH-2 B.
(1) HVH-3 AND HVH-4 (2) HVH-1 AND HVH-2 C. (1) HVH-1 ORHVH-2 (2) HVH-3 OR HVH-4 D. (1)HVH-1 AND HVH-2 (2) HVH-3 AND HVH-4 40
ILC-.11-2 NRC Exam
- 41. Given the following plant conditions:
- It is July 31 and the plant is at 100% RTP.
- Containment temperatures have been slowly approaching the ITS limit.
- ERFIS has just failed.
Which ONE(1) of the following identifies the correct order of preference for obtaining the official Containment Temperature lAW PLP-1 18, Hot Weather Operations?
- 1. RTGB Edge meter
- 2. Make a containment entry to obtain temperature readings.
- 3. Perform SPP-035, Containment Bulk Average Temperature Measurement A. 1,2,3 B. 1,3,2 C. 2,1,3
- 0. 3,1,2
)
41
ILC-1 1-2 NRC Exam
- 42. Given the following plant conditions:
- A Large Break LOCA and Loss of Offsite Power have occurred.
- EDG B tripped while starting.
- RWST is at 9% level.
- Alignment to the CV Sump has been completed.
- CV Pressure is currently 12 psig.
Which ONE (1) of the following completes the statement below?
Sl-844A and B, CV Spray Pump Suction Isolation Valves, will be (1) and RHR Pump A is capable of supplying suction to CV Spray Pump(s)
(2)
A.
(1) closed (2) A ONLY B. (1) closed (2) A and B C. (1) open (2) A ONLY D. (1) open (2) A and B J
42
ILC-1 1-2 NRC Exam
- 43. Given the following plant conditions:
- The plant had been operating at 100% RTP when a Large Break LOCA occurred.
I
- A malfunction in the CV Spray System results in Fl-949,Spray Additive Flow, indicating higher than actual flow.
- The crew has transitioned to Piggy-Back Mode lAW EPP-9, Transfer to Cold Leg Recirculation, with CV Pressure at 14 psig.
- Spray Additive Tank level is currently 60%.
Which ONE(1) of the following completes the statement below?
The resultant operational implication of Fl-949 failure is that during cold leg recirculation ECCS components will be more susceptible to (1) and lAW EPP-9 the required CV Sump pH is (2)
A. (1) chloride stress corrosion (2) 8.5-10.5 B. (1) chloride stress corrosion (2)greaterthan 10.5 C. (1) gas binding (2) greater than 10.5 D. (1) gas binding (2)8.5-10.5
_1 43
ILC-11-2 NRC Exam
- 44. Given the following plant conditions:
- The plant is operating at 100% RTP.
- Steam line break occurs on Steam Line A just outside the CV wall.
- MSIV A fails to close when demanded.
Which ONE (1) of the following identifies the design feature that will ensure that all of the S/Gs do NOT blowdown through the faulted steam line?
A. MSIV auto closure on High Steam Line Flow with Low Tave signal.
B. MSIV auto closure on High Steam Line Delta P signal.
C. Check valves downstream of each MSIV.
D. Check valves upstream of each MSIV.
iZ) 44
ILC-11-2 NRC Exam
- 45. Given the following plant conditions:
- Plant is operating in Mode I at 100% RTP.
- A Reactor Trip and Safe Injection has occurred.
- No AFW pumps are available.
- RCS Bleed-and-Feed is in progress lAW FRP-H.1, Response to Loss of Secondary Heat Sink.
- Both Condensate Pumps are running.
Which ONE (1) of the following completes the statement below?
To restore feed flow to the SIG(s) lAW FRP-H.1, the operator is required to place (1)
Feedwater Isolation Key Switch(es) in the OVRD/RESET position, verify the Feedwater Header Section Valves (2) and start 1 Main Feedwater Pump to feed (2)
SIG(s).
A. (1)ONE (2) OPEN (3) ONE B. (1)THREE (2) OPEN (3)ONE C. (1)ONE (2) CLOSED (3) ALL D. (1) THREE (2) CLOSED (3) ALL 45
ILC-1 1-2 NRC Exam
- 46. Which ONE (1) of the following completes the statement below?
At 15% RTP the programmed SIG level is approximately (1) and at 20% RTP the programmed S/G level is approximately (2)
A. (1)52%
(2) 52%
B. (1)49%
(2) 52%
C. (1)39%
(2) 39%
D. (1)29%
(2) 39%
46
ILC-1 1-2 NRC Exam
- 47. Given the following plant conditions:
B MFP is OOS for Maintenance and the following occurs:
- The Reactor was manually Tripped while operating at 20% RTP due to a trip of A MFP
- Tave is 546°F and lowering.
- PZR Level is 22% and slowly lowering.
- RCS Pressure is 2045 psig and lowering.
- Steam Generator Blowdown is Isolated.
- S/G levels are as follows:
- A S/G Narrow Range level is 42% and slowly rising.
- B S/G Narrow Range level is 41% and slowly rising.
- C S/G Narrow Range level is 45% and slowly rising.
Which ONE (1) of the following provides the action(s) that are required to be taken lAW EPP-4, Reactor Trip Response?
A. Initiate Safety Injection B. Borate to Cold Shutdown Boron C. Reduce Auxiliary Feedwater Flow D
Close the MSIVs & MSIV Bypasses 47
ILC-1 1-2 NRC Exam
- 48. Given the following plant conditions:
- The Plant is in Mode 3.
- B MDAFW pump is running.
- A small feedline break occurs between FCV-1425, MDAFW pump B FCV, and isolation valve V2-16C, SG C AFW Isolation Valve.
- FCV-1425 is closed and the break flow stops.
The CRS has directed isolation of the leak from all water sources.
Which ONE (1) of the following identifies the SGs available to be fed from A MDAFW pump?
A S/G A ONLY B. SIG B ONLY C. S/Gs A and B ONLY D. S/Gs A, B and C D
48
ILC-1 1-2 NRC Exam
- 49. Given the following plant conditions:
- Unit operating at 50% RTP.
- A Train of CR HVAC is in service
- Breaker 52/21A, Feed to MCC-5 (NORM POWER) & MCC-16, trips open.
- CRS has directed that MCC-5 be transferred to the DS Bus.
Which ONE (1) of the following completes the statements below?
MCC-16 Li) re-energize when MCC-5 is transferred to the DS Bus.
A Train of Control Room HVAC (2) be available.
A. (1) will (2) will B. (1)will (2) will NOT C. (1)will NOT (2) will NOT D. (1) will NOT (2) will 0
49
ILC-11..2 NRC Exam
- 50. Given the following plant conditions:
- A Loss of Offsite Power has occurred.
- BOTH EDGs have failed to auto stan.
- EPP-1, Loss of All AC Power, has been implemented.
Which ONE (1) of the following completes the statement below with respect to load shedding and station battery design?
lAW EPP-1, low priority loads (1) required to be shed from Instrument Buses 2 and 3 to minimize the discharge rate on both DC buses to assure that the station batteries achieve their (2) design time limitation.
A. (1)are (2) 30 minute B. (1)are (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. (1) are NOT (2) 30 minute D. (1) are NOT (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Th 50
ILC-11-2 NRC Exam
- 51. Given the following plant conditions:
.Th
- APP-01O-B2, EDG A START AIR LO PRESS, has been received.
- EDG A Air Receiver relief valve DA-1 1A has lifted and blown down the air receiver pressure to 80 psig prior to reseating.
Which ONE (1) of the following identifies the LOWEST pressure at which the A EDG Air Receiver will be pressurized to a value that supports 8 cold starts of the EDG?
A. 100
- 8. 210 C. 216 D. 220 ci 51
ILC-11-2 NRC Exam
- 52. Given the following plant conditions:
- OST-924-2, Process Radiation Monitoring System, Section 8.10, Fuel Handling Building Upper Level Monitor Test, is in progress.
- The CKT TEST pushbutton on R-21 has been depressed and held in the depressed position.
Given the above conditions, which ONE(1) of the following completes the statement?
While the CKT TEST pushbutton is depressed, the operator is required to check HVS-4 and (1)
OFF and when the CKT TEST pushbutton is released those fans are required to be checked (2)
HVS-4, Fuel Handling Building Supply Air Handling Unit HVE-15, Spent Fuel Building Exhaust Air Handling Unit HVE-1 5A, Spent Fuel Building Exhaust Air Handling Unit A. (1)HVE-15 (2) ON B. (1)HVE-15 (2) OFF C. (1)HVE-15A (2) ON D. (1)FIVE-15A (2) OFF 52
ILC-1 1-2 NRC Exam
- 53. Given the following plant conditions:
- A plant trip and safety injection has occurred due to multiple events.
- The crew is implementing PATH-I.
- C and D SW Pumps have tripped and cannot be restarted.
- North and South SW Header pressures are 35 psig.
Which ONE(1) of the following completes the statement below?
Based on the conditions given above, an action required by PATH-i to isolate the Service Water Supply to the Turbine Building is to close valve (1) and the basis for this action is to ensure (2)
A. (1) V6-16A, SW NORTH HEADER SUPPLY TO TURBINE BUILDING (2) adequate cooling flow to the EDGs B. (I) V6-16C, SW ISOLATION TO TURBINE BUILDING (2) adequate cooling flow to the EDGs C. (1) V6-16A, SW NORTH HEADER SUPPLY TO TURBINE BUILDING (2) SW Booster Pumps will NOT trip on low SW pressure Th D. (1) V6-16C, SW ISOLATION TO TURBINE BUILDING (2) SW Booster Pumps will NOT trip on low SW pressure 53
ILC-11-2 NRC Exam
- 54. Given the following plant conditions:
- The unit tripped due to a loss of off-site power.
- A EDG output breaker failed to close and cannot be manually closed.
- EPP-25, Energizing Supplemental Plant Equipment using the DSDG, has been completed.
Which ONE(1) of the following identifies the air compressor(s) available to be restarted under these conditions?
A. Instrument Air Compressor A ONLY B. Instrument Air Compressor B ONLY C. Instrument Air Compressors A AND B ONLY D. Instrument Air Compressors A AND B and the Primary Air Compressor.
54
ILC-1 1-2 NRC Exam
- 55. Given the following plant conditions:
Initial Conditions Plant is in Mode 3 at 547°F and 2235 psig.
A spurious Safety Injection signal has been received.
Current Conditions EPP-7, SI Termination, has been completed.
APP-002-B7, CV NAR RANGE HI/LO PRESS illuminates.
CV Pressure indicates - 0.4 psig and degrading.
Which ONE (1) of the following identifies the actions necessary to clear the alarm lAW OP-921, Containment Air Handling?
A. Reset Phase A and open Containment Pressure Relief Valves VI 2-10 and VI 2-11.
B. Reset Containment Ventilation Isolation and open Containment Pressure Relief Valves V12-10 and V12-11.
C. Reset Containment Ventilation Isolation and open Containment Vacuum Relief Valves V12-12 and V12-13.
D. Reset Phase A and open Containment Vacuum Relief Valves VI 2-12 and V12-13.
55
ILC-11-2 NRC Exam
- 56. Given the following plant conditions:
- The plant is operating at 25% RTP.
- Control Bank C step counters indicate 225 steps.
- Control Bank D step counters indicate 105 steps.
- Rod Control is in AUTOMATIC.
- A malfunction in the Automatic Rod Control Circuitry causes the rods to insert.
- The rods are stopped when the Rod Bank Selector Switch is taken to Manual(M).
- The Group Step Counters for Control Bank C and D did not function properly.
- A review of ERFIS identified that Control Bank D Rods inserted 10 inches.
Which ONE(1) of the following identifies what the Group Step Counters for Control Banks C and D would indicate if operating properly?
Bank C BankD A.
217 steps 89 steps B.
223 steps 95 steps C.
215 steps 95 steps D.
209 steps 89 steps
- Th 56
ILC-11-2 NRC Exam
- 57. Which ONE (1) of the following identifies (in the order presented) the normal power supplies for the Pressurizer Heaters?
Control Group Backup Group A Backup Group B 1.48OVBus 1 2.48OVBus2A 3.48OVBus2B
- 4. 480V Bus 3 A. 3,1,2 B. 3,2,4 C. 4,3, 1 D. 2,1,3 57
ILC-11-2 NRC Exam
- 58. Given the following plant conditions:
- Plant is at 100% RTP.
The following alarms are subsequently received:
- APP-005-A3, PR DROP ROD
- APP-005-C3, PR CHANNEL DEV
- APP-005-F3, PR UPPER CH HI FLUX DEV I AUTO DEFEAT
- It has been determined that N-44 Power Range Detector A failed LOW Which ONE (1) of the following completes the statement below?
The Nl-44C, Delta Flux Meter, will indicate pegged (1) and the Rod Control Selector Switch is (2) to be selected to the MANUAL (M) position.
A. (1) HIGH (2) NOT required B. (1) HIGH (2) required C. (1) LOW (2) NOT required D. (1)LOW (2) required 58
ILC-1 1-2 NRC Exam
- 59. Given the following plant conditions:
- The plant is in Mode 3 with GP-007, Plant Cooldown from Hot Shutdown to Cold Shutdown, in progress.
- RCSisat5lO°Fand 1150 psig.
- The PZR PRESS I HI STM LINE DP switch has failed to block the HI STM LINE DP signal.
Which ONE(1) of the following completes the statement below?
If the cooldown continues, the highest S/G pressure at which a HI STEAM LINE DP Safety Injection will be received is psig.
A. 685 B. 614 C. 585 D. 485 59
ILC-1 1-2 NRC Exam
- 60. Given the following plant conditions:
- A LOCA has just occurred and CV Pressure indicates 15 psig on ERFIS.
Which ONE(1) of the following completes the statement below?
In addition to ERFIS and AR-I 0CC, CV Conditions Recorder, CV Pressure is indicated in the control room by (1)
Wide Range Indicators on the RTGB and (2)
Extended Range indicator(s) on the PAM Panel.
A. (1)three (2) one B. (1)six (2) two C. (1)six (2) one D. (I)three (2) two 60
ILC-11-2 NRC Exam
- 61. Given the following plant conditions:
- The plant is operating at 100% RTP.
- A 20% Secondary Load Rejection has occurred.
- Steam dump valves did NOT actuate.
Which ONE (I) of the following identifies the sequence of actions required to be performed lAW AOP-01 5, Secondary Load Rejection, to operate the steam dump valves to reduce RCS Tavg?
A. Place PC-464B, Steam Header Press Controller, in Manual and adjust output as necessary.
B. Place the Steam Dump Mode Switch to STEAM PRESS and manually adjust output as necessary.
C. Place PC-464B, Steam Header Press Controller, in Manual and adjust output to MINIMUM. Place the Steam Dump Mode Selector Switch to STEAM PRESS and manually adjust output as necessary.
- 0. Place the Steam Dump Mode Switch to RESET, then place the switch to STEAM PRESS and manually adjust output as necessary.
61
ILC-1 1-2 NRC Exam
- 62. Given the following plant conditions:
- Plant is in Mode 3.
- A release is in progress from A Waste Gas Decay Tank.
- R-14C, PLANT STACK NOBLE GAS LOW RANGE, FAIL light illuminates.
Which ONE (1) of the following completes the statement below?
The condition would cause (1) to alarm and RCV-014, Waste Gas Release Isolation, would (2)
A. (1) APP-036-E7, RAD MONITOR TROUBLE, (2) remain OPEN B. (1) APP-036-E7, RAD MONITOR TROUBLE, (2) CLOSE C. (1) APP-036-D8, PROCESS MONITOR HI RAD, (2) remain OPEN D. (1) APP-036-D8, PROCESS MONITOR HI RAD, (2) CLOSE 62
ILC-11-2 NRC Exam
- 63. Given the following plant conditions:
- R-4, Charging Pump Room, is in alarm and has been validated.
- All non-essential personnel have been evacuated from the Charging Pump Room.
- The reason for the alarm is unknown.
Which ONE(1) of the following completes the statement below?
R-4, Charging Pump Room, Area Radiation Monitor measures (1) and the NEXT required action to be performed lAW AOP-005, Radiation Monitoring System, isto (2)
A. (1) both gamma and beta (2) align the Auxiliary Building Exhaust through the Charcoal Filter Unit B.
(1) gamma ONLY (2) align the Auxiliary Building Exhaust through the Charcoal Filter Unit C. (1) both gamma and beta (2) inspect the room for system leakage D. (1) gamma ONLY (2) inspect the room for system leakage 63
ILC-11-2 NRC Exam
- 64. Given the following plant conditions:
- The plant is operating at 100% RTP.
- A loss of Instrument Air has occurred with pressure currently at 75 psig.
- The crew is implementing AOP-01 7, Loss of Instrument Air.
Which ONE(1) of the following identifies the preferred flowpath when Station Air is required to be cross-connected with Instrument Air lAW AOP-01 7?
Flow is from the Station Air Compressor A. Station Air coalescing filter ---> Instrument Air Header B. bypass the Station Air coalescing filter --> Instrument Air Dryers NB --->
Instrument Air Header C. Station Air coalescing filter
> Instrument Air Dryers A/B -----> Instrument Air Header
- 0. bypass the Station Air coalescing filter -----> Instrument Air Header 64
ILC-1 1-2 NRC Exam
- 65. Given the following plant conditions:
- During clearance restoration on a drained section of Fire Water piping an isolation valve is opened too quickly and Fire Water pressure drops to 83 psig.
Based on the conditions given, which ONE (1) of the following identifies the impact on the Fire Water Pumps?
MDFP - Motor Driven Fire Pump EDFP - Engine Driven Fire Pump A. MDFP will start immediately AND the EDFP will start following a 2 sec. time delay B.
MDFP will start following a 2 sec. time delay and the EDFP will start immediately C. MDFP AND EDFP will both start following a 2 sec. time delay D. MDFP AND EDFP will both start immediately 65
ILC-1 1-2 NRC Exam
- 66. Which ONE (1) of the following statements identifies the administrative requirements of Standing Instructions lAW OPS-NGGC-1 000, Fleet Conduct of Operations?
A. A member of plant management is required to be listed as the Closure Contact.
B. Standing Instructions shall NOT be used to communicate emergency technical specification changes that have NOT been formally issued.
C. All active Standing Instructions issued since last standing watch must be reviewed.
D. Standing Instructions for Operational Issues are NOT required to have an expiration date.
66
ILC-11-2 NRC Exam
- 67. Given the following plant conditions:
N
- A plant event is in progress.
- The plant alarms are out-of-service.
- A Site Area Emergency has been declared.
Based on the conditions above, which ONE (1) of the following completes the statements below?
lAW OMM-OO1-4, Communications, the SM (1) required to communicate through the CRS to have an operator to place the VLC Switch to the emergency position.
lAW OMM-OO1-7,Notifications, the emergency announcements should be repeated (2) times.
A. (1) is NOT (2) TWO B. (1) is NOT (2) THREE C. (1) is (2) iWO D. (1)is (2) THREE 67
ILC-1 1-2 NRC Exam
- 68. Which ONE (I) of the following completes the statement below?
The Inadequate Core Cooling Monitor (ICCM) is designed to monitor for inadequate J
core cooling during a A. Large Break LOCA B. Small Break LOCA C. Loss of All AC Power D. Loss of Heat Sink Accident D
68
ILC-11-2 NRC Exam 69.
Which ONE (1) of the following statements applies to the temporary procedure change process lAW PRO-NGGC-0204, PROCEDURE REVIEW AND APPROVAL?
PNSC - Plant Nuclear Safety Committee A. The expiration date of the temporary change shall not exceed 21 days from the approval date.
B. Two SROs, one of which is a PNSC member, must approve a temporary change if the revision is a change of intent.
C. Two SROs, none of which are required to be a PNSC member, must approve a temporary change if the revision is a change of intent.
- 0. The expiration date of the temporary change shall not exceed four months from the interim approval date.
69
ILC-11-2 NRC Exam
- 70. Operations has been scheduled to perform a new Special Test that has been designated as an Infrequently Performed Test or Evolution lAW OPS-NGGC-1315, Conduct of Infrequently Performed Tests or Evolutions (IPTE).
Which ONE(1) of the following completes the statement below?
lAW OPS-NGGC-1315, the is required to designate the IPTE Manager.
A. Shift Manager B. Manager - Shift Operations C. Operations Manager D. Plant General Manager 70
ILC-1 1-2 NRC Exam
- 71. Given the following plant conditions:
- RCS cooldown is in progress lAW GP-007, Plant Cooldown from Hot Shutdown to J
Cold Shutdown.
- The RCS Filter radiation levels are 1100 mrem/hr at 30 cm from the filter housing.
- You have been assigned by the WCC SRO to hang a clearance on the filter for replacement.
Which ONE (1) of the following identifies The radiation area is required to be classified as a (1) and the Independent I Concurrent Verification (2>
be waived lAW OPS-NGGC-1 303, Independent Verification.
A.
(1) Locked High Radiation Area (2) can B. (1) High Radiation Area (2) can C. (1) Locked High Radiation Area (2) cannot I
D. (1) High Radiation Area (2) cannot 71
ILC-1 1-2 NRC Exam
- 72. Which ONE (1) of the following are the correct values for the IOCFR2O Federal Adult Occupational Dose Limits?
}
Skin Lens of Eye A.
50 rem/yr 5 rem/yr B.
50 rem/yr 15 rem/yr C.
15 rem/yr 5 rem/yr D.
15 rem/yr 15 rem/yr 72
ILC-11-2 NRC Exam
- 73. Which ONE (1) of the following identifies the procedure that provides the Incident Commander with detailed method of attack strategies for a fire in the MDAFW Pump Room?
A. AOP-041, Response to Fire Event B. OMM-OO2, Fire Protection Manual C. OMM-003, Fire Protection Pre-Plans D. APP-044, Fire Alarm Response Manual 73
ILC-11-2 NRC Exam
- 74. Given the following plant conditions:
- Plant was at 100% RTP.
- At time 1205 a Reactor Trip and several events occurred.
- At time 1215 an ALERT is declared by the CR-SEC.
- At time 1225 the Emergency Notification Form is completed and approved by the CR-SEC.
Which ONE(1) of the following identifies the LATEST time that the initial notification to the State and County officials is due?
A. 1220 B. 1230 C. 1235 D. 1240 74
ILC-11-2 NRC Exam
- 75. Given the following plant conditions:
- Plant cooldown is in progress. RCS Temperature is at 290°F.
- Excessive leakage has been identified in C RCP Bay.
- A RHR pump is providing decay heat removal.
- RCS letdown has been isolated.
- Two charging pumps are running at maximum speed.
- PZR level is 12% and lowering.
- RCS subcooling is 40°F.
Which ONE (1) of the following completes the statement below?
lAW AOP-033, Shutdown LOCA, the NEXT step required to be performed for mitigation strategy is to A. check SI Pump Suction Line to RWST - ANY REASON TO BELIEVE STEAM BOUND.
B. start the remaining Charging Pump and raise speed to maximum.
C. verify available SI Pump Breakers
- RACKED IN D. stop A RHR Pump.
75
ILC-1 1-2 NRC Exam
- 76. Given the following plant conditions:
- The plant is operating at 100% RTP.
- The crew is implementing AOP-035, SIG Tube Leak, due to an identified tube leak in B 8/G.
- Two charging pumps are running at maximum output and all letdown flowpaths have been isolated.
- RO reports that PZR Level is at 22% and continuing to lower in an uncontrolled manner.
Which ONE (I) of the following is the proper procedural progression for the given conditions?
EPP-7, SI Termination EPP-12, Post-SGTR Cooldown Using Backfill A. Trip the Reactor > Manual SI > PATH-I > PATH-2 --> EPP-12 B. Trip the Reactor > Manual SI > PATH-I > PATH-2 > EPP-7 > EPP-12 C. Continue in AOP-035 > Trip the Reactor and actuate SI when PZR level reaches 10% > PATH-I > PATH-2 > EPP-12 D. Continue in AOP-035, start the remaining charging pump and raise speed to maximum and monitor PZR level 76
ILC-11-2 NRC Exam
- 77. Given the following plant conditions:
Initial Conditions:
- The plant is at 100% RTP.
- OST-Ol 0, Power Range Calorimetric During Power Operation Daily, was performed at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />.
Current Conditions:
- FWUFM declared out of service at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />.
- A feedwater flow transient has occurred.
- HCV-1459, LP Heaters Bypass Valve, is observed to be OPEN with its control switch in AUTO.
- Main Feedwater Pump suction pressure is currently 375 psig.
Which ONE (1) of the following completes the statements below?
lAW OMM-001-2, Shift Routines and Operating Practices, Reactor Thermal Power is limited to a maximum of (1)
MWth briefly power excursions.
AOP-01 0, Main Feedwater/Condensate Malfunction, (2) contain steps to reduce power.
A. (1) 2346 MWth (2) does B. (1) 2339 MWth (2) does C. (1) 2339 MWth (2) does NOT D. (1) 2346 MWth (2) does NOT 77
ILC-11-2 NRC Exam
- 78. Given the following plant conditions:
- GP-007, Plant Cooldown From Hot Shutdown to Cold Shutdown is in progress.
- RCS temperature is 225°F with RHR Pump A in service
- At time 1500 the SUT has failed and both EDGs have tripped.
- At time 1520 efforts to restore power are still in progress.
Which ONE (1) of the following completes the statement below?
FCV-605 and HCV-758 will fail (1) and the Emergency Action Level required to be declared lAW the EAL Matrices is a(n)
(2)
FCV-605, RHR HX BYPASS FLOW HCV-758, RHR HX DISCH FLOW (Reference Provided)
A. (1) SHUT (2) Alert B. (1) OPEN (2) Alert C. (1) OPEN (2) Site Area Emergency D. (1) SHUT (2) Site Area Emergency 78
ILC-11-2 NRC Exam
- 79. The plant was operating at 100% RTP when the following occurs:
- B DC Bus has de-energized.
- EPP-27, Loss of DC Bus B, has been entered.
- The batteries and the in-service battery charger are determined to be damaged.
Which ONE (1) of the following completes the statements below?
OCBs 52/8 AND 52/9 (1)
Within four hours of the failure the standby battery charger is aligned to energize the bus to nominal voltage. lAW ITS 3.8, Electrical Power Systems, operability of the bus (2) restored.
A. (1) must be locally tripped (2) is NOT B. (1) must be locally tripped (2) is C. (1) will trip on Generator Lockout (2) is NOT j
D. (1) will trip on Generator Lockout (2) is 79
ILC-I1-2 NRC Exam
- 80. The Plant has experienced a LOCA Outside of Containment and the crew has implemented PATH-I and transitioned to EPP-20, LOCA Outside Containment.
Which ONE (1) of the following completes the statements below?
If ALL of the instruments were operable, (I) are the Reg. Guide 1.97 instruments that would be utilized by EPP-20 to diagnose and mitigate the accident.
Given the values listed for each instrument, the conditions of ITS LCO 3.3.3, Post Accident Monitoring (PAM) Instrumentation are (2)
P1-455, PZR Pressure P1-456, PZR Pressure P1-457, PZR Pressure P1-51 IAA, RCS Wide Range Pressure PI-51IBA, RCS Wide Range Pressure P1-402, RCS Wide Range Pressure P1-501, RCS Wide Range Pressure LT-459, PZR Level Transmitter LT-460, PZR Level Transmitter LT-461, PZR Level Transmitter (REFERENCE PROVIDED)
- 1750 psig and lowering
- 1725 psig and lowering
- Failed LOW
- 1750 psig and lowering
- 1750 psig and lowering
- 1725 psig and lowering
- Failed LOW
- 5% and lowering
- 5% and lowering
- 5% and lowering A. (1) P1-455, 456457,402,501, LT-459, 460,461 (NOT P1-SI IAA, 5IIBA)
(2) NOT met B. (1) P1-455, 456,457,402,501 (NOT LT-459, 460,461, PI-5IIAA, 5IIBA)
(2) NOT met C. (1) Pl-5IIAA, 5IIBA, 402, 501 (NOT LT-459, 460,461, P1-455, 456,457)
(2) met D. (I) PI-5IIAA, 5IIBA, LT-459, 460,461 (NOT P1-455, 456, 457,402,501)
(2) met 80
ILC-11-2 NRC Exam
- 81. Given the following plant conditions:
- Plant is operating at 100% RTP.
- A seismic event results in a rupture of the common AFW suction line to all AFW pumps coincident with a break in the RCS piping.
- Containment pressure reached 4.2 psig and is currently 3.5 psig and lowering.
- The crew has transitioned from PATH-I to FRP-H.1, Response to Loss of Secondary Heat Sink.
- RCS temperature is 360°F and pressure is 275 psig.
- SIG conditions:
S/G Level (WR)
Pressure A
42%
800 psig B
44%
810 psig C
44%
810 psig Which ONE (1) of the following completes the statement below?
For the conditions given above, a heat sink (1) required. The required procedural progression would be to (2)
A. (I)isNOT (2) transition to PATH-I, Entry Point A B. (I) is NOT (2) transition to PATH-I, Entry Point C C. (1)is (2) remain in FRP-H.1 D. (I)is (2) transition to Supplement I, Aligning RHR System for Core Cooling Mode 81
ILC-ll-2 NRC Exam
- 82. Given the following plant conditions:
- A seismic event has lead to a LOCA and wpture of SW piping to all HVH units in containment.
- PATH-I completed to the point of transition to another procedure.
- Only one train of CV Spray is operating properly.
- The following conditions exist in Containment:
- Containment Pressure is 24 psig and rising.
- Containment Sump Level is 385 inches and rising.
Which ONE (1) of the following completes the statement below?
Based on the current conditions, containment (I) is the highest priority and the basis for this is (2)
A. (I) pressure (2) one train of CV Spray cannot maintain pressure below the containment design pressure B. (I) pressure (2) due to containment pressure being greater than 10 psig with limited Containment Cooling C. (1) sump level (2) potential flooding of critical systems and components needed for future plant recovery may occur D. (1) sump level (2) dilution of sump water with SW may potentially cause a return to criticality 82
ILC-1 1-2 NRC Exam
- 83. Given the following plant conditions:
- The plant is at 100% RTP.
- A tube leak is identified in C SIC.
- Two charging pumps running at maximum speed are able to control and stabilize PZR level with one 45 gpm letdown orifice in service.
- Total RCP Seal Leakoff flow is 7.5 gpm.
Which ONE (1) of the following completes the statement below?
The required action to address this condition is to (1) and EAL Classification for this event is (2)
AOP-035, SIC Tube Leak GP-006-1, Normal Plant Shutdown from Power Operation to Hot Shutdown.
(REFERENCE PROVIDED)
A. (1) Shutdown the plant lAW GP-006-1 while concurrently performing AOP-035 (2) Unusual Event SU6.1, RCS leakage B. (1) Shutdown the plant lAW GP-006-1 while concurrently performing AOP-035 (2) Alert FAI.1, Any loss or any potential loss of either Fuel Clad or RCS C. (1) Perform AOP-035, Attachment 1, Local S/C Isolation, on C S/G and then commence a plant shutdown lAW GP-006-1 (2) Unusual Event SU6.1, RCS leakage D. (1) Perform AOP-035, Attachment 1, Local S/C Isolation, on C SIC and then commence a plant shutdown lAW GP-006-1 (2) Alert FAI.1, Any loss or any potential loss of either Fuel Clad or RCS 83
I 84.
ILC-1 1-2 NRC Exam TI-14O
[ti 144 11-1411 11-143 FI-150 PI-18 I
- Plant is stable at 100% RTP.
- R-9, Letdown Line Area, radiation monitor had a valid alarm and a reading of 15,000 mremlhr prior to R-9 failing.
- RCS samples indicate an RCS Activity of 550 pCi/gm 1-131 Dose Equivalent.
Which ONE(1) of the following completes the statement below?
lAW AOP-005, Radiation Monitoring System, letdown flow (1) and lAW the Emergency Action Level Matrices, an (2) must be declared.
(REFERENCE PROVIDED)
A. (1) may remain as-is (2) Unusual Event B. (1) may remain as-is (2) Alert C. (1) is required to be reduced (2) Unusual Event D. (1) is required to be reduced (2) Alert 84
ILC-1 1-2 NRC Exam
- 85. Given the following plant conditions:
Initial Conditions A loss of off-site power and reactor trip has occurred.
A rupture in the Instrument Air System has resulted in Instrument Air pressure lowering to 20 psig.
The crew performed actions of PATH-I and has transitioned to EPP-4, Reactor Trip Response.
Current Conditions after 15 minutes CETC temperature is 555°F and rising.
SIG pressure is 1075 psig and rising.
Which ONE (1) of the following completes the statements below?
RCS Natural Circulation (1) exist.
In the situation described above, detailed steps for restoration of RCS temperature control will be provided in (2)
A. (1)does (2) AOP-017, Loss of Instrument Air B. (1) does (2) EPP-4, Reactor Trip Response C. (I) does NOT (2) EPP-4, Reactor Trip Response D. (I) does NOT (2) AOP-01 7, Loss of Instrument Air 85
ILC-11-.2 NRC Exam
- 86. Given the following plant conditions:
Initial Conditions:
- Plant is operating at 100% RTP.
- A RCP Motor Upper Thrust Bearing temperature indicates 230°F.
- C RCP Motor Upper Guide Bearing temperature indicates 205°F.
Current Conditions:
- RTBs open.
- SIG Levels within normal band.
- Pressurizer pressure is normal.
Which ONE (1) of the following correctly describes whether RCPs A andlor C are required to be shutdown and whether the conditions of LCO 3.4.5, RCS Loops - Mode 3, are met?
A. Both A and C RCPs are required to be secured.
Conditions of LCO 3.4.5 met.
B. A RCP is required to be secured. C RCP is NOT required to be secured.
Conditions of LCO 3.4.5 met.
C. Both A and C RCPs are required to be secured.
Conditions of LCO 3.4.5 NOT met.
D. A RCP is required to be secured. C RCP is NOT required to be secured.
Conditions of LCO 3.4.5 NOT met.
86
ILC-1 1-2 NRC Exam
- 87. Given the following plant conditions:
- Plant is operating at 90% RTP following a refueling outage.
- PCV-455C, PZR PORV, has developed excessive seat leakage.
- APP-003-B3, PRT HI TEMP AND APP-003-C3, PRT HI PRESS, has alarmed.
- PRT Pressure is 6.1 psig and rising.
- RC-536, PZR PORV BLOCK, has been closed to isolate the leakage.
Which ONE (1) of the following completes the statements below?
lAW ITS LCO 3.4.11 Bases, PCV-455C (1) operable and power (2) required to be removed from RC-536.
A. (1) is NOT (2) is NOT B. (1)is (2)is C. (1)is (2) is NOT D. (1)IsNOT (2) is 87
ILC-11-2 NRC Exam
- 88. Given the following plant conditions:
- The plant is operating at 100% RTP.
- HVH-1 is under clearance due to bearing damage.
- B CV Spray Pump has been declared inoperable due to a crack discovered in the casing.
- APP-002-A7, HVH-112/3/4 HI VIB, is received and the HIGH VIBRATION white light is illuminated for HVH-3.
Which ONE (1) of the following completes the statements below?
To attempt to reset the High Vibration Alarm, APP-002-A7 directs (1)
Due to local observations the SM has directed that HVH-3 be declared inoperable.
The most time limiting ITS LCO required action is that (2)
(REFERENCE PROVIDED)
A. (1) stopping HVH-3 prior to depressing the vibration switch reset pushbutton (2) the containment spray train AND one containment cooling train be restored to OPERABLE status in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B. (1) resetting the high vibration alarm without stopping HVH-3 (2) ent into LCO 3.0.3 be peormed immediately C. (1) stopping HVH-3 prior to depressing the vibration switch reset pushbutton (2) entry into LCO 3.0.3 be performed immediately D. (1) resetting the high vibration alarm without stopping HVH-3 (2) the containment spray train AND one containment cooling train be restored to OPERABLE status in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 88
ILC-1 1-2 NRC Exam
- 89. Given the following plant conditions:
- The plant has experienced a Small Break LOCA inside Containment.
- PATH-I is currently being implemented.
- The BOP became distracted and allowed AFW to feed the S/Gs to the following Narrow Range levels.
- A S/G 2%
-BS/G 10%
- C S/G:
86%
Which ONE (1) of the following completes the statement below?
The major concern with C S/G is the increased dead weight (1) and isolation of feedwater to C S!G is required to be performed lAW (2)
A. (1) and water hammer effects on main steamlines (2) FRP-H.3, Response to Steam Generator High Level B. (1) and water hammer effects on main steamlines (2) Supplement G, Steam Generator Isolation C. (1) on the S/G vessel external supports in the CV (2) FRP-H.3, Response to Steam Generator High Level D. (1) on the SIG vessel external supports in the CV (2) Supplement G, Steam Generator Isolation 89
ILC-11-2 NRC Exam
- 90. Given the following plant conditions.
- The plant was at 100% RTP and expeenced a reactor trip coincident wfth a loss of theSUT
- A and B EDG are supplying power to 480V buses E-1 and E-2.
- APP-010-E5, EDG RM A COOL FAN HI TEMP!OVLD, alarm is received.
- Readings from a calibrated temperature instrument indicate that EDG A room is at 128°F.
Which ONE (1) of the following completes the statements below?
A EDG (1) required to be declared inoperable. The actions required due to the alarm and temperature reading is to (2)
A. (1) is NOT (2) notify the System Engineer to investigate the cause and initiate corrective action lAW APP-Cl 0-E5 B. (1) is NOT (2) shutdown lAW OP-604, Diesel Generators A and B C. (1)is (2) notify the System Engineer to investigate the cause and initiate corrective action lAW APP-01 0-E5 D. (1)is (2) shutdown lAW OP-604, Diesel Generators A and B 90
ILC-11-2 NRC Exam
- 91. Given the following plant conditions:
- Plant is in Mode 3.
- PZR level transmitter LT-459 fails LOW.
- No operator actions are taken.
- At 1700 PZR level is 85.1% and rising at a rate of 0.5%/mm.
- PZR pressure is being maintained constant.
Which ONE(1) of the following completes the statements below?
At the current rate of level rise (1) is the EARLIEST time at which the ITS 3.4.9, Pressurizer, will NOT be met.
The bases for the limit in this Mode is to ensure that the (2)
A. (1) 1712 (2) RCS does NOT go solid when criticality is achieved and preserves a steam space for pressure control B. (1) 1714 (2) RCS does NOT go solid when criticality is achieved and preserves a steam space for pressure control C. (1) 1712 (2) PZR level remains within the calibrated level range and provide protection against water relief through the PZR PORVs D. (1) 1714 (2) PZR level remains within the calibrated level range and provide protection against water relief through the PZR PORVs 91
ILC-11-2 NRC Exam
- 92. Given the following plant conditions:
- The plant was at 100% RTP.
- Power Distribution Control target values (100%).
N-41: -2.0%
N-43:
-2.0%
N-42: -2.0%
N-44:
-2.0%
- Target Band +1-5%
- APL=102%
- At 1600 the plant has just experienced two spurious OT Delta T turbine runbacks.
- At 1602 the plant stabilized at 88% RTP.
Time N-41AFD N-42 AFD N-43 AFD N-44 AFD 1603
-10.1
-10.2
-10.1
-10.3 1617
-8.9
-9.0
-8.9
-9.1 1642
-7.1
-7.2
-7.1
-7.3 1705
- 6.9
-7.0
-6.9
-7.1 1710
-6.5
-6.6
-6.5
-6.6 Which ONE (1) of the following completes the statement below?
lAW iTS 3.2.3, Axial Flux Difference, reactor thermal power (1) and the basis for this action is (2)
(REFERENCE PROVIDED)
A. (1) is limited to a maximum of 90% RTP (2) the xenon axial distribution at this power level is not a significant accident analysis parameter B. (1) is limited to a maximum of 90% RTP (2) the radial xenon peaking factors assumed in the accident analysis cannot be exceeded at this power level C. (1) must be reduced to below 50% RTP (2) the xenon axial distribution at this power level is not a significant accident analysis parameter D. (1) must be reduced to below 50% RTP (2) the radial xenon peaking factors assumed in the accident analysis cannot be exceeded at this power level 92
ILC-1 1-2 NRC Exam
- 93. Given the following plant conditions:
- The plant is at 100% RTP.
- Maintenance is preparing to enter the CV to repair a leak on a sensing line.
- CV Pressure Relief is in progress with CV pressure currently at 0.05 psig.
- CV Purge Gaseous Waste Release Permit has been issued to allow the CV Purge to commence.
- Both R-1 I AND R-12 are in service.
Which ONE (1) of the following completes the statements below?
The CV Purge and CV Pressure Relief (1) be performed concurrently in accordance with Tech Specs.
R-14C, Auxiliary Building Vent Stack Noble Gas Monitor, (2) required to be operable during the CV Purge in accordance with the ODCM.
A. (1)may (2) is NOT B. (1)may (2)is C. (1) may NOT (2) is NOT D. (1) may NOT (2) is 93
ILC-11-2 NRC Exam
- 94. Given the following plant conditions:
- The Motor Dven Fire Pump (MDFP) was staed remotely per OST-603, MDFP and EDFP Test (Weekly).
- The MDFP supply breaker tripped open during OST-603.
Which ONE(1) of the following completes the statement below?
MDFP indication (1) available on the Containment Fire Protection Panel.
The Fire Suppression Water Supply System is considered (2) lAW FP-012, Fire Protection Systems Minimum Equipment and Compensatory Actions.
A. (1) is NOT (2) Operable B. (1)is (2) Operable C. (1) is NOT (2) Inoperable D. (1)is (2) Inoperable 94
ILC-11-2 NRC Exam
- 95. The plant is in a refueling outage with core reload in progress.
Which ONE(1) of the following completes the statements below th respect to the required Approval Authority for refueling activities?
The (1) is the required Approval Authority for bypassing refueling interlocks.
The (2) is the required Approval Authority for unlatching a fuel assembly in the core.
A. (1) Refueling SRO (2) Refueling SRO B. (1) Shift Manager (2) Refueling SRO C. (1) Refueling SRO (2) Reactivity Monitor (Reactor Engineer)
D. (1) Shift Manager (2) Reactivity Monitor (Reactor Engineer) 95
ILC-11-2 NRC Exam
- 96. Given the following plant conditions:
- A plant heatup from a refueling outage is currently in progress.
- Highest available RCS temperature is 325°F and rising.
- The A MDAFW Pump has been declared OOS.
Which ONE (1) of the following completes the statement below?
The current technical specification operational MODE is (1) and lAW the Tech Specs, a change to the next higher MODE based on conditions given is (2)
A. (1)3 (2) allowed B. (1)4 (2) allowed C. (1)3 (2) NOT allowed D. (1)4 (2) NOT allowed 96
ILC-1 1-2 NRC Exam
- 97. Given the following plant conditions:
Initial Conditions at 1300 hour0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />s:
- The plant as at 100% RTP B CCW Pump is under clearance for maintenance.
Subsequently, B EDG is declared inoperable due to a broken fuel oil line.
Current Conditions at 1700 hour0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />s:
- Plant continues to operate at 100% RTP with the stated equipment inoperable.
Which ONE (1) of the following completes the statement below, based on the current plant conditions?
C CCW Pump is (1)
. The most limiting ITS LCO required action is I was (2L.
A. (1) inoperable (2) ITS LCO 3.0.3.
B. (1) inoperable (2) restore either B OR C CCW Pump to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
C. (1) operable (2) the one hour off-site power verification.
D. (1) operable (2) restore either B OR C CCW Pump to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
97
ILC-1 1-2 NRC Exam
- 98. Given the following plant conditions:
- A Site Area Emergency has been declared and all facilities are activated.
- The general radiation levels in Charging Pump Room is 130 Rem/hr.
- Entry into the area is required to perform a life saving activity.
Which ONE(1) of the following completes the statement below?
Based on EPOSC-04, Emergency Work Control, (1) is the maximum dose that the (2) can authorize the assigned worker.
A. (1)25Rem (2) Radiological Control Director B. (1)25Rem (2) Site Emergency Coordinator C. (1)lORem (2) Radiological Control Director D. (1)lORem (2) Site Emergency Coordinator 98
ILC-11-2 NRC Exam
- 99. Given the following plant conditions:
A plant event has occurred that has resulted in 10 CFR5O.54(x) being invoked for deviation from approved emergency procedures.
lAW AP-030, NRC Reporting Requirements, the NRC is required to be notified within hour(s).
A.1 B. 4 C.8 0.24 99
ILC-11-2 NRC Exam 100. Which ONE (1) of the following correctly completes the statements below regarding the process for which the NRC Headquarters Operations Officer (HOO) will contact the control room with a notification of a Nuclear Power Plant Attack Message?
An authentication code is contained in a book in the control room that (1) classified as safeguards information.
If the incorrect code is given, lAW OMM-001-4, Communications, the SM or his designee is required to (2)
A. (1) is NOT (2) receive the message and contact security to validate the threat B. (1)is (2) receive the message and contact security to validate the threat C. (1) is NOT (2) hang up and immediately call back the HOO D. (1)is (2) hang up and immediately call back the HOO 100
Reference Material Table of Contents
- 1. ITS Section 3.3.3, Post Accident Monitoring (PAM)
Instrumentation
- 2. ITS Section 3.6.6, Containment Spray and Cooling Systems
- 3. FMP-009, Attachment 10.2, Target and Operating Band Diagram
- 4. EAL Matrix ALL CONDITIONS
- 5. EAL Matrix HOT CONDITIONS
- 6. EAL Matrix COLD CONDITIONS
ID Points Type 0
007 E02 4 Iii 1 00 MCS A
008 AK2.03 1 1.00 MCS A
3 009 EK2.03 1 1.00 MCS D
4 011 BK 2.02 1 1.00 MCS B
5 015 AK2.08 1 1.00 MCS D
6 022 AA2.03 1 1.00 MCS C
7 025 AK3.01 1 1.00 MCS B
8 027 AA1.05 1 1.00 MCS C
9 029 EG2.4.49 1 1.00 MCS D
10 038 EKI.04 1 1.00 MCS D
11 054 AAI.04 1 1.00 MCS B
12 055 EG2.1.31 1 1.00 MCS A
13 056 AKI.03 I 1.00 MCS B
14 057 AA2.04 1 1.00 MCS C
15 058 AAI.03 1 1.00 MCS B
16 065 AA2.05 1 1.00 MCS D
17 W/EO5EK3.1 1 1.00 MCS B
18 W/E 12 EK3.3 1 1.00 MCS D
19 005 AK2.02 1 1.00 MCS A
20 028 AA2.04 1 1.00 MCS D
21 032 AA2.09 1 1.00 MCS D
22 033 AG2.2.44 1 1.00 MCS D
060 AK1.02 1 1.00 MCS B
3 067 AA1 06 1 1 00 MCS A
25 076 AK2.01 1 1.00 MCS B
26 W/E 08 EG2.4.2 1 1.00 MCS B
27 W/E 10 EK3.1 1
1.00 MCS A
28 003 A1.07 1 1.00 MCS C
29 004 K5.30 1 1.00 MCS B
30 004 K6.14 1 1.00 MCS B
31 005 K3.01 1 1.00 MCS A
32 006K5.101 1.00 MCS D
33 007 Al.01 1 1.00 MCS D
34 0071(3.01 1 1.00 MCS A
35 008 G2.4.50 1 1.00 MCS D
36 0101(1.031 1.00 MCS C
37 010 K4.01 1 1.00 MCS D
38 012 A3.05 1 1.00 MCS A
39 013 K2.01 1 1.00 MCS A
40 022 A3.01 1 1.00 MCS B
41 022 A4.05 1 1.00 MCS D
42 0261(1.011 1.00 MCS D
43 026 K3.02 1 1.00 MCS A
44 039 1(4.06 1 1.00 MCS C
_45 059 A2.04 1 1.00 MCS D
S 059A3021 100 MCS B
47 061 K5.01 1 1.00 MCS C
A ID Points Type 0
061 K6.02 1 1.00 MCS C
062 A2.10 1 1.00 MCS C
50 063 A1.01 1 1.00 MCS B
51 064 K6.07 1 1.00 MCS B
52 073 02.2.12 1 1.00 MCS A
53 076 G2.4.18 1 1.00 MCS B
54 078 K2.02 1 1.00 MCS C
55 103A4.091 1.00 MCS C
56 001 A3.05 1 1.00 MCS A
57 011 K2.021 1.00 MCS A
58 015 K6.01 1 1.00 MCS C
59 016K3.091 1.00 MCS D
60 028A4.021 1.00 MCS B
61 041 02.4.111 1.00 MCS C
62 071 K1.06 1 1.00 MCS B
63 072 K5.01 1 1.00 MCS D
64 079 K4.01 1 1.00 MCS A
65 086 A1.05 1 1.00 MCS A
66 G2.1.15 1 1.00 MCS C
67 02.1.17 1 1.00 MCS B
68 G2.1.27 1 1.00 MCS B
69 02.2.6 1 1.00 MCS A
02.2.7 1 1.00 MCS D
023131 100 MCS A
72 G2.3.4 1 1.00 MCS B
73 02.4.25 1 1.00 MCS C
74 02.4.39 1 1.00 MCS B
75 02.4.9 1 1.00 MCS B
76 038 EG2.4.1 1 SRO 1 1.00 MCS A
77 054 AG2.4. 11 SRO 1 1.00 MCS A
78 055 EA2.01 SRO 1 1.00 MCS 1) 79 058 AA2.03 SRO 1 1.00 MCS A
80 WJE 04 EG2.4.3 SRO 1 1.00 MCS C
81 WIE 05 EA2. I SRO 1 1.00 MCS B
82 W/E015 E02.1.32 SRO 1 1.00 MCS C
83 037 AG2.4.41 SRO 1 1.00 MCS B
84 076 AA2.05 SRO 1 1.00 MCS D
85 W/E 09 EA2. 1 SRO 1 1.00 MCS D
88 022 02.4.50 SRO 1 1.00 MCS B
90 064 02.4.46 SRO 1 1.00 MCS A
91 011 02.2.38 SRO 1 1.00 MCS B
92 045 A2. 11 SRO 1 1.00 MCS C
Answers G2.1.41 SRO I G2.2.35 SRO 1 97 G2.2.42 SRO 1 98 G2.3.4 SRO 1 99 G2.4.30 SRO 1 100 G2.4.43 SRO 1 1.00 MCS B
1.00 MCS D
1.00 MCS A
1.00 MCS B
1.00 MCS A
1.00 MCS C
ID Points Type 0
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