ML051890112
| ML051890112 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/24/2005 |
| From: | Mccall K AmerGen Energy Co |
| To: | D'Antonio J Operations Branch I |
| Conte R | |
| References | |
| 50-289/05-301 50-289/05-301 | |
| Download: ML051890112 (102) | |
Text
U. S. Nuclear Regulatory Commission Site-Specific Written Examination Applicant Information Name:
Region I Date:
FaciIity/Unit: Three Mile Island License Level: SRO Reactor Type: B&W I Start Time:
I Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. The passing grade requires a final grade of at least 80.00 percent. Examination papers will be collected six hours after the examination starts.
I Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Examination Value 100 Points Applicant's Score Points I Applicant's Grade Points
Q 001 NRC SRO 03-1 Licensing Examination Q 001 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor operating at 50% power, with ICs in automatic.
- RPS Channel 1C is de-energized due to loss of Vital Bus 1C (Inverter I C failure).
- All four Reactor Coolant Pumps operating.
- Core power imbalance is negative 3%.
Event:
- Reactor Coolant Pump RC-P-1 D trips due to breaker fault.
Based on these conditions, identify the ONE selection below that describes:
(1) Response of the Reactor Protection System to this event.
(2) Reason for the RPS response.
A. (1) Channel D (only) trips.
(2) Nuclear overpower based on RCP operating status.
B. (1) Channel D (only) trips.
(2) Nuclear overpower based on RCS Flow and Imbalance.
C. (1) Channels A, B and D trip.
(2) Nuclear overpower based on RCP operating status.
D. (1) Channels A, B and D trip.
(2) Nuclear overpower based on RCS Flow and Imbalance.
Q 002 NRC SRO 03-1 Licensing Examination Q 002 Three Mile Island Nuclear Station May 2005 In accordance with OP-TM-226-000, Reactor Coolant Pumps, identify the ONE condition below that requires the operator to trip all 4 RCPs.
A. Operating Makeup Pump trips.
- 6. Major steam leak environment in the RB.
C. NS-V-15, RB NS Cooling Isolation Valve (MOV), closes due to a circuit failure.
D. Operating Intermediate Closed Cooling Pump trips, and the standby pump fails to start.
Q 003 NRC SRO 03-1 Licensing Examination Q 003 Three Mile Island Nuclear Station May 2005 Initial plant conditions:
- Reactor operating at 100% power with ICs in full automatic.
- Makeup Pump Recirc Valve MU-V-36 is tagged (valve open, breaker open) out of service for maintenance.
Event:
- Reactor trip due to low RCS pressure.
- Loss of off-site power (LOOP)
- Emergency Diesel Generator EG-Y-1 B FAILED to start.
- Channel A and B ES Actuation.
- Makeup System Flow Data:
- MU-V-16A HPI flow is 200 gpm.
- MU-V-16B HPI flow is 200 gpm.
- RCP seal injection flow is 35 gpm.
- Makeup Pump MU-P-1A recirculation flow (last measured) is 100 gpm.
Identify the ONE selection below that completes the following statement describing the effect of this malfunction on operation of the HPI system:
For purposes of throttling HPI, in accordance with OP-TM-EOP-010, current HPI flow equals A. 535gpm.
B. 500gpm.
C. 435gpm.
D. 400gpm.
Q 004 NRC SRO 03-1 Licensing Examination Q 004 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor operating at 100% power with ICs in full automatic.
- 1C 480V ES Valves Motor Control Center is powered from its normal power supply.
Event:
- Reactor trip due to high RCS pressure.
- Failed open Pressurizer safety valve resulted in ES actuation.
- 1P 480V Bus trip due to electrical fault at the time of the ES actuation.
Based on these conditions identify the ONE selection below that completes the following statement:
HPI pump suction from the BWST will be supplied through A. BWST suction valve MU-V-14A (only).
B. BWST suction valve MU-V-14B (only).
C. Both BWST suction valves MU-V-14A and MU-V-14B.
D. Both Decay Heat Pump Piggy-back Valves DH-V-7A and DH-V-7B.
Q 005 NRC SRO 03-1 Licensing Examination Q 005 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor is in Cold Shutdown condition.
- Decay Heat Removal Train A is operating.
- Decay Heat Closed Cooling flow through the Decay Heat Removal cooler is
- Total loss of Instrument Air (0 psig) occurred.
throttled to maintain the RCS at I30 degrees F.
Identify the ONE statement below that describes the response of the cooling system and subsequent effect on RCS temperature for this situation.
A. Closure of DC-V-65A (Cooler bypass) AND DC-V-2A (Cooler inlet) results in B. Opening of DC-V-65A (Cooler bypass) AND DC-V-2A (Cooler inlet) results in RCS heatup.
RCS cooldown.
C. Closure of (ONLY) DC-V-2A (Cooler inlet) results in RCS heatup.
D. Opening of (ONLY) DC-V-2A (Cooler inlet) results in RCS cooldown.
Q 006 NRC SRO 03-1 Licensing Examination Q 006 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor operating at 100% power, with ICs in full automatic.
- CF-T-1A level has been raised using OP-TM-213-469, Makeup to CF-T-1A for Batches of Less Than 100 Gallons.
- Fill isolation valve CF-V-19A has not yet been closed.
- Chemistry is initiating sampling of CF-T-1A using N1807, Primary Chemistry Sampling.
- Sample isolation valve CF-V-20A is open to support their sample for final boron concentration verification.
Event:
- Automatic reactor trip due to low RCS pressure.
- RCS leak (LOCA) inside the RB.
- NO ES actuations have occurred yet.
Based on these conditions identify the ONE selection below that describes when to expect automatic closure (assuming no failures) of CF-V-19A and CF-V-20A.
A. CF-V-19A will close when Reactor Trip Isolation occurs; CF-V-20A will close when Reactor Trip Isolation occurs.
B. CF-V-19A will close when Reactor Trip Isolation occurs; CF-V-20A will close when 4 psig ES actuation occurs.
C. CF-V-19A will close when 4 psig ES actuation occurs; CF-V-20A will close when Reactor Trip Isolation occurs.
D. CF-V-19A will close when 4 psig ES actuation occurs; CF-V-20A will close when 4 psig ES actuation occurs.
Q 007 NRC SRO 03-1 Licensing Examination Q 007 Three Mile Island Nuclear Station May 2005 Initial plant condition:
- 100°/~ power.
Event:
- Reactor tripped.
- PORV lifted for 15 seconds.
Based on these conditions, identify the ONE selection below that describes the sequence of events, following the PORV lift and the effect on containment.
A. (I)
WDG-V-1 relief valve opens to the vent header, the vent header and waste gas compressors maintain pressure.
(2) No affect on containment.
B. (1) RCDT sparger and the volume of water in the RCDT keep the pressure from reaching either the relief or rupture disk setpoints.
(2) No affect on containment.
C. (1) WDG-V-1 relief valve opens to isolated header, rupture disk blows.
(2) Activity is detected on RM-A-2.
D. (I) WDG-V-1 relief valve opens to containment rupture disk blows, (2) RB ES pressure setpoint is exceeded.
Q 008 NRC SRO 03-1 Licensing Examination Q 008 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor operating at 100% power, with ICs in full automatic.
- RPS Channel D in MANUAL BYPASS due to an RCS pressure amplifier failure (OFF-SCALE LOW).
Event:
- Monthly surveillance is required to be performed for RPS Channel C Based on these conditions identify the ONE selection below that describes the final automatic RPS trip coincidence logic after RPS Channel D is returned to NORMAL with the channel tripped, and Channel C is placed in MANUAL BYPASS.
A. 2 out of 4.
B. 2 out of 3.
- c. 1 outof3.
D. 1 out of 2.
Q 009 NRC SRO 03-1 Licensing Examination Q 009 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor tripped due to loss of offsite power (LOOP).
- MAP C-3-2, IC Surge Tank Level Hi/Lo, actuates.
- IC-T-1 surge tank level is 6 inches, lowering at 1 inch per minute.
- RM-L-9 activity indication is normal and steady.
Based on these conditions, identify the ONE selection below that describes:
(1) Operational impact of this malfunction.
(2) Required actions.
A. (1) Air induction at IC-P-1NB pump suction can result in slug flow or total loss of (2) Start Demineralized Water Booster Pump DW-P-1 to establish makeup from IC System flow.
Demineralized Water Storage Tank DW-T-1.
B. (1) Air induction into the RM-L-9 counting chamber will result in erroneous (2) Start Demineralized Water Booster Pump DW-P-1 to establish makeup flow activity readings.
from Demineralized Water Storage Tank DW-T-1.
loss of IC System flow.
Tank DW-T-I.
C. (I) Air induction at IC-P-1NB pump suction can result in slug flow or total (2) Open IC-V-5 to establish makeup flow from Demineralized Water Storage D. (1) Air induction into the RM-L-9 counting chamber will result in erroneous activity readings.
Tank CA-T-7.
(2) Open IC-V-5 to establish makeup flow from the Reclaimed Water Pressure
Q 010 NRC SRO 03-1 Licensing Examination Q 010 Three Mile Island Nuclear Station May 2005 Initial plant conditions:
- Reactor tripped.
- RCS pressure 1985 psig.
- Pressurizer Relief Valve RC-RV-1A leakage to the RC Drain Tank.
- RC Drain Tank pressure rising.
Event:
- RC Drain Tank relief valve WDG -V-I fails to open.
- RCDT pressure continues to rise.
- Rupture disc bursts at 55 psig, reducing RCDT pressure to 5 psig.
Based on these conditions identify the ONE selection below that describes the change in fluid conditions downstream of the Pressurizer relief valve when the RC Drain Tank rupture disc bursts:
(1) Initial tailpipe conditions.
(2) Final tailpipe conditions.
A. (I) 636 degrees F.
(2) 636 degrees F.
B. (1) 355 degrees F.
(2) 245 degrees F.
C. (I) 303 degrees F.
(2) 228 degrees F.
D. (1) 287 degrees F.
(2) 162 degrees F.
Q 011 NRC SRO 03-1 Licensing Examination Q 011 Three Mile Island Nuclear Station May 2005 From the list below identify the ONE statement that describes the design feature installed so the SAFETY GRADE Reactor Protection System can supply reactor power, flow and pressure signals to NON-SAFETY GRADE ICS/NNI control systems.
A. Electrical separation of the RPS channels ensures a power supply failure in the control system will not disable more than one RPS channel.
back into the RPSmpreventing the RPS channel from tripping.
ensures control system testing inside the RPS cabinet will not prevent the RPS channel from tripping.
B. Buffer amplifier signal isolation prevents control system failures from feeding C. Use of independent ICs Calibration Test Modules inside the RPS cabinets D. Physical separation of the RPS cabinets prevents physical damage (for instance, a control system amplifier fire inside the RPS cabinet) from disabling more than one RPS channel,
Q 012 NRC SRO 03-1 Licensing Examination Q 012 Three Mile Island Nuclear Station May 2005 Initial plant conditions:
- Turbine trip from 20% power.
- Automatic EFW actuation due to OTSG 1 B low level.
- MFW isolation actuation due to OTSG 1B low pressure.
Current plant conditions:
- OTSG 1 N I B pressures 895 psig.
- OTSG 1 B level is being controlled by EFW at the REMOTE AUTOMATIC setpoint.
- Reactor power is 3%.
Based on these conditions, identify the ONE selection below that describes MINIMUM actions required to clear OTSG 1 B Low Pressure Feedwater Isolation signal to enable the operator to open FW-V-92B.
A. Press (BOTH) Train A and Train B DEFEAT pushbutton.
B. Press Train B (ONLY) DEFEAT pushbutton.
C. Press (BOTH) Train A and Train B ENABLE pushbuttons.
D. Press 16 Train B (ONLY) ENABLE pushbutton.
Q 013 NRC SRO 03-1 Licensing Examination Q 013 Three Mile Island Nuclear Station May 2005 Initial conditions:
- Reactor tripped due to extended loss of off-site power (LOOP).
- Emergency Feedwater suction supplied by the Reactor River Water System
- RCS at Hot Shutdown conditions.
Event 1:
- Train A and B ES actuations:
- Reactor Building Spray actuation - BOTH BS-P-1A and BS-P-1 B start.
- 1600 psig, 500 psig and 4 psig RB pressure.
Event 2:
- RB Emergency Cooling Pump RR-P-1A trips - will not restart.
C u rrent cond it ions:
- RB pressure 32 psig rising slowly.
- All 3 RB Emergency Cooling Units (AH-E-IA, 1 B and 1 C) operating.
Based on these conditions identify the ONE selection below that describes:
(1) Concern(s) to be addressed by operator action(s).
(2) Action(s) that comply with RR system limits and precautions.
A. (1) Excessive emergency cooling coil differential temperature, due to reduced cooling water flow.
(2) Stop RB Cooling Fan AH-E-1A; Close emergency cooling outlet valve RR-V-4A.
B. (1 ) Emergency Diesel Generator overload.
(2) Stop RB Cooling Fan AH-E-I B; Close emergency cooling inlet AND outlet valves RR-V-3B and RR-V-4B.
C. (1) Higher (peak) containment temperatures and pressures, and EFW suction supply.
(2) Continue to operate all 3 RB Cooling Fans; Maintain Emergency Feedwater supply valves EF-V-4 and EF-V-5 OPEN.
D. (1) RR-P-1B pump runout, and prioritization of containment cooling over EFW during LOCA conditions.
Ciose Emergency Feeawaier suppiy vaive EF-v-4 or EF-V-5.
(2) Continue to operate all 3 RB Cooling Fans;
Q 014 NRC SRO 03-1 Licensing Examination Q 014 Three Mile Island Nuclear Station May 2005 Plant Conditions:
- Plant is stabilizing after a LOCA.
- RCS pressure 600 psig.
- RB pressure 25 psig.
- The following ESAS signals have been cleared to throttle HPI.
- A Train HPI signal bypassed
- A Train LPI signal bypassed
- A Train RB Cooling and Isolation defeated Event:
- Large Break LOCA.
- RCS pressure 40 psig.
- RB pressure 40 psig.
For the conditions and events above, identify the ONE statement below that states MINIMUM actions required to be taken.
A. Start BS-P-1A manually.
B. Start BS-P-1A manually and close A train containment isolation valves.
C. Start both BS-P-1A and BS-P-1B and press both 3Opsig manual actuation pushbuttons.
D. Manually initiate A train HPI/LPI and RB Cooling and Isolation and Containment Isolation.
Q 015 NRC SRO 03-1 Licensing Examination Q 015 Three Mile Island Nuclear Station May 2005 Initial conditions:
- Reactor trip from full power due to LOCA.
- RB pressure reached 5 psig.
- Manual ESAS actuation signals were NOT initiated.
- Automatic ES Actuation status:
Train A Train B 1600#
Bypassed Bypassed 4#
Defeated Actuated (NOT defeated)
BASED ON THESE INITIAL CONDITIONS, identify the ONE statement below that describes automatic component response if a steam break causes RB pressure to rise rapidly (spike) to 40 psig.
A. Only BS-P-1 B starts.
- 8. Both BS-P-1A and BS-P-1B start.
C. Neither BS-P-1A or BS-P-1 B start; Train 'A' RB Spray (6s) valves open D. Both BS-P-1A and BS-P-1 B start; Both Train ' A and Train '6' RB Spray (BS) valves open.
Q 016 NRC SRO 03-1 Licensing Examination Q 016 Three Mile Island Nuclear Station May 2005 Sequence of events:
Time RCS Pressure Event 0950 1900 psig 1000 1200 psig 1030 800 psig RB Pressure peaked at 6 psig.
1130 700 psig LPI/HPI Pumps in "Piggyback" Mode.
1200 550 psig Core Flood Tanks dumping.
1230 150 psig LPI systems injecting BWST water into RCS.
Reactor trip from full power due to LOCA.
HPI systems injecting BWST water into the RCS.
- RB Spray Pumps are NOT operating.
- RB Sump recirculation is NOT initiated.
Based on this event, identify the EARLIEST TIME below when sodium hydroxide (NaOH) will actually be injected into the reactor core.
A. Time = 1000.
B. Time = 11 30.
C. Time = 1200.
D. Time = 1230.
Q 017 NRC SRO 03-1 Licensing Examination Q 017 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Small break LOCA occurred coincident with a loss of off-site power (LOOP).
- ES Train A and Train B actuated.
- Both EDGs are supplying their respective bus.
- Average of the five highest core exit thermocouples is 556 degrees F.
- RCS Tavg is 546 degrees F.
- RCS cooldown rate is 20 degrees per hour.
- Primary-to secondary heat transfer does NOT exist.
- RCS Pressure stable at 1230 psig.
Event:
- In accordance with EOP-006, LOCA Cooldown, you are directed to Reduce OTSG pressure so that secondary Tsat is 60 degrees F lower than incore thermocouple temperature.
Based on these conditions identify the ONE correct action below to establish an acceptable RCS cooldown rate.
A. Open the Turbine Bypass Valves to reduce OTSG pressure to 640 psig.
B. Open the Turbine Bypass Valves to reduce OTSG pressure to 753 psig.
C. Open the Atmospheric Dump Valves to reduce OTSG pressure to 640 psig.
D. Open the Atmospheric Dump Valves to reduce OTSG pressure to 753 psig.
Q 018 NRC SRO 03-1 Licensing Examination Q 018 Three Mile Island Nuclear Station May 2005 Plant conditions :
- Plant heatup in progress using 1102-1, Plant Heatup To 525 degrees F.
- FW-P-1A is being placed in service using OP-TM-401-103, Shifting FW-P-1A From
- FW-P-1A trip function has been tested.
Standby Mode To Operating Mode.
In accordance with OP-TM-401-103, identify the ONE selection below that describes operation of FW-P-1A speed controls, starting with the feedpump on the turning gear.
A. Use ICs FP A Turbine Speed Demand control station in HAND. After FW B. With the ICs FP A Turbine Speed Demand control station in AUTO, adjust valve dP is 60-90 psid, transfer this control station to AUTO.
the ICs FP A Bias Control until FW valve dP is 60-90 psid.
C. Turn FP A Turbine Full Range Manual Speed Control Switch to ON. When the High Speed Stop (HSS) lamp is lit transfer the control switch to OFF.
D. Use 1A FPT Governor control switch until speed stops increasing - then position and hold the control in FAST RAISE until the HSS lamp is lit. When additional speed is required, use ICs FP A Turbine Speed Demand control station in HAND.
Q 019 NRC SRO 03-1 Licensing Examination Q oqg Three Mile Island Nuclear Station May 2005 Initial plant conditions:
- Reactor operating at 60% power.
- FW-P-1A is the only available Main FW Pump.
Event:
- Reactor trip due to FW-P-1A trip.
Current plant conditions:
- All 3 Emergency Feedwater Pumps are operating.
- EFW control valves EF-V-30A-D are controlling OTSG levels at setpoint.
- RCS subcooling margin is 41 degrees F and steady.
- FW-P-1A has been restarted, and is in HAND maintaining 0.1 mlbm/hr to each OTSG.
Based on these conditions identify the ONE selection below that describes required disposition of EFW equipment.
A. Return EFW systems to normal standby conditions.
B. Stop all EFW pumps, and manually close EF-V-30A-D.
C. Continue operating EFW as the preferred source of FW.
D. Continue operating EFW as a back up to the only operating MFW pump.
Q 020 NRC SRO 03-1 Licensing Examination Q 020 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor tripped due to loss of off-site power (LOOP).
- EF-P-1 has tripped
- All other Emergency Feedwater System Components have
- OTSG levels are at 40% on the Operating Range and increasing
- Emergency Feedwater control valves EF-V-30A, B, C, D in AUTO.
- RCS is subcooled.
responded as designed.
Event:
- HSPS switches for Loss of All Reactor Coolant Pumps are taken to DEFEAT in preparation for resetting EF-P-1.
Based on these conditions identify the ONE selection below that describes OTSG level control setpoint after the HSPS switch operation described above.
A. 0% on the Operating Range.
- 6. 25" on the Startup Range.
C. Current value of 40% on the Operating Range.
D. 50% on the Operating Range.
Q 021 NRC SRO 03-1 Licensing Examination Q 021 Three Mile Island Nuclear Station May 2005 The plant is experiencing low system grid voltage.
Identify the ONE condition below that will cause the normal feeder breaker to the 1 D 4160V Bus to trip and the emergency diesel to start and load the bus.
A. 3800V for 20 seconds.
B. 3200V for 13 seconds.
C. 2900V for 2.5 seconds.
D. 2000V for 0.5 second.
Q 022 NRC SRO 03-1 Licensing Examination Q 022 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor startup in progress.
- Operating crew is raising power from 20%.
- FW-P-1A is operating.
- All major equipment is available.
Based on these conditions identify the ONE selection below that describes an occurrence that would indicate the existence of a problem in the A 125/250V DC Distribution System.
A. MAP K-3-4, MN TURB DC OIL PMP STRTTTRBL, actuates.
- 6. Loss of control power indication for all Reactor Coolant Pumps.
C. FW-V-7A and FW-V-7B, Feedwater Pump Recirculation Valves, both open fully.
D. RCP Seal Return Valve MU-V-26 fails open while ESAS Status Panel indicates MU-V-26 closed.
Q 023 NRC SRO 03-1 Licensing Examination Q 023 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor is tripped.
- Loss of off-site power (LOOP).
- EG-Y-1A and EG-Y-1 B failed to start.
- Station Battery 1A load shedding has just been completed in accordance with OP-TM-AOP-020, Loss of Station Power.
- Load was reduced from 300 Amps down to 150 Amps.
If battery load was maintained at 300 Amps, the battery would be discharged in 3.5 HOURS from now.
Based on these conditions identify the ONE selection below that describes how long Battery 1A will be able to supply the REMAINING loads from now.
A. 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
B. More than 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, but less than 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
C. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
D. More than 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
Q 024 NRC SRO 03-1 Licensing Examination Q 024 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor operating at 100% power with ICs in full automatic.
- NO Emergency Diesel Generators operating.
Event 1:
- Alarm A-1-2, DIESEL GEN 1A TROUBLE, actuation Field report:
- STARTING AIR PRESSURE LOW alarm is actuated on EG-Y-1A local panel.
- Air compressor has been isolated from BOTH starting air receivers
- Starting air pressure is now steady at 120 psig.
in order to terminate the leak.
Event 2:
- Loss of offsite power (LOOP) concurrent with ES actuation.
Based on these conditions identify the ONE selection below that completes the following statement:
Emergency Diesel Generator EG-Y-1A will A. start and meet all design basis requirements.
- 6. start but may NOT reach full speed to pick up electrical load within IO-second C. attempt to start but trip when the Start Failure Relay (SFR) actuates.
requirement.
D. NOT attempt to start because it is locked out by the Shutdown Relay (SDR)
Q 025 NRC SRO 03-1 Licensing Examination Q 025 Three Mile Island Nuclear Station May 2005 Plant conditions:
- WDG-T-1 B Waste Gas Tank radioactive gas release in progress.
Event:
- Fuse failure de-energizes RM-A-7, Waste Gas Release Monitor Based on these conditions identify the ONE selection below that describes:
(1) Effect of this malfunction on the radioactive effluent release.
(2) Design feature that produces/enables the effect.
A. (1) Gas release will continue.
(2) RM-A-7 interlocks are "energize to actuate."
- 6. (1) Gas release will continue.
(2) RM-A-7 interlock circuit is still energized from RMS interlock power supply.
C. (1) Gas release will NOT continue (2) RM-A-7 monitor is de-energized with its interlock defeat switch in NORMAL position.
D. (1) Gas release will NOT continue.
(2) RM-A-7 and WDG-V-47 solenoid have common power supply
Q 026 NRC SRO 03-1 Licensing Examination Q 026 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor operating at 100% power with ICs in full automatic.
- Drought and heat wave has resulted in slowly reduced river water level and
- Operating crews have been in OP-TM-AOP-005, River Water Systems Failures, rising river water temperature.
for several days.
Event:
- Auxiliary Operator report:
- ISPH Pump Bay Water Level is 281 feet elevation.
- River Water temperature is 95 degrees F.
Based on these conditions identify the ONE selection that describes required action(s), and the problem.
A. Initiate plant shutdown to be at CSD within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Margin of safety for ECCS heat removal capability is being challenged.
B. Trip the reactor, then stop ail four Reactor Coolant Pumps.
C. Trip the reactor, reduce to one Reactor Coolant Pump.
RCP failure may occur due to inadequate cooling of components.
Nuclear River Water System, heat removal capacity is being challenged.
D. Initiate Operability Determination of Safety related river water pumps.
NPSH requirements may not be met with all river water pumps running.
Q 027 NRC SRO 03-1 Licensing Examination Q 027 Three Mile Island Nuclear Station May 2005 Identify the ONE condition below that describes when the backup cooling water supply (Fire Service Water) is used to cool Instrument Air compressors IA-P-1A and IA-P-1 B.
A. Low SCCW System pressure.
B. High SCCW System temperature.
C. Tripping of all 3 SCCW pump breakers D. High Instrument Air compressor temperature.
Q 028 NRC SRO 03-1 Licensing Examination Q 028 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor tripped.
- RCS LOCA inside the RE3 caused RB pressure to rise to 35 psig.
- All ES actuations and systems operated as designed.
- Current RB pressure is 15 p i g.
- Current RCS pressure is 40 psig.
Based on these conditions, identify the ONE selection below that describes MINIMUM required actions to enable re-opening NS-V-15, NS cooling to the Reactor Building.
A. Bypass 1600 psig and 500 psig ES actuations.
- 6. Bypass 1600 psig and 500 psig ES actuations.
Defeat 4 psig RB Isolations.
C. Defeat 4 psig ES Actuations.
Reset 30 PSlG RB Isolation.
D. Reset 30 PSlG RB Isolation
Q 029 NRC SRO 03-1 Licensing Examination Q 029 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor operating at 100% power with ICs in full automatic.
- RPS surveillance in progress on C RPS channel.
- Breakers/electronic trips associated with C RPS channel were tripped.
- NLO has manually re-closed the DC breakers associated with C RPS cabinet.
- Fault Reset pushbutton has NOT been depressed on the Diamond Rod Control Panel.
Based on these conditions identify the ONE selection below that describes the IMMEDIATE effect if 120V AC Vital Bus 1 D is tripped (de-energized).
A. CRD Groups 1 and 3 (ONLY) would drop.
B. CRD Groups 1, 2, 3, and 4 (ONLY) would drop.
C. CRD Groups 5,6, and 7 (ONLY) would drop.
D. CRD Groups I through 7 would drop
Q 030 NRC SRO 03-1 Licensing Examination Q 030 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor startup in progress.
- Reactor is supercritical, power level entering the Intermediate Range.
- Operator is manually withdrawing control rods to achieve +I.4 DPM startup rate.
NI-11 NI-12 N 1-3 N 1-4 1 E5 CPS 1 E5 CPS 1 E-1 0 Amps 1 E-10 Amps
- All four Source and Intermediate Range NI channels indicate transient +I
.O DPM,
- Group 7 rods are 30% withdrawn.
- Group 8 APSRs are 30% withdrawn.
slowly rising.
Event:
- NI-3 Rate of Change Amplifier fails HIGH.
Identify the ONE statement below that descibes the automatic response to these conditions addressing ability to withdraw AND insert rods.
A. (1) Operator can continue to withdraw control rods.
(2) Operator can insert control rods.
B. (1) Operator CANNOT withdraw control rods.
(2) Operator can insert control rods.
C. (1) Operator CANNOT withdraw control rods.
(2) Operator CANNOT insert control rods, but this does not prevent dropping the rods on a reactor trip.
D. (1) Operator CANNOT withdraw GROUP 8 APSRs.
(2) Operator CANNOT insert GROUP 8 APSRs.
Q 031 NRC SRO 03-1 Licensing Examination Q 031 Three Mile Island Nuclear Station May 2005 Initial plant conditions:
- Reactor is operating at 100% power with ICs in full automatic.
Event:
- ICs signal input for RCS Loop A flow is slowly failing low.
- ICs signal input for total RCS Flow is normal.
- MAP H-3-2, SASS Mismatch, actuates, but there is NO SASS actuation.
- MAP H-2-4, Rx Inlet Delta-TC Hi, actuates.
- MAP H-1-2, OTSG A BTU Limit, actuates.
Based on these conditions, identify the ONE set of ICs Hand/Auto Stations that is required to be transferred to HAND to mitigate the consequences of this event.
A. Loop A Feedwater Master, and Loop B Feedwater Master.
B. Loop A and Loop B Startup Feedwater valves FW-V-16A and FW-V-I6B, and Loop A and Loop B Main Feedwater valves FW-V-17A and FW-V-17B.
C. Feedwater Pump FW-P-1A (ONLY), and Loop A Feedwater Valves FW-V-16A and FW-VI 7A ONLY.
D. Both Feedwater Pumps FW-P-1A and FW-P-1 B, and Loop A Feedwater Valves FW-V-16A and FW-V-17A.
Q 032 NRC SRO 03-1 Licensing Examination Q 032 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor operating at 100% power with ICs in full automatic.
- Pressurizer level control is selected to RCI-LT1.
Event:
- The following alarms actuate:
- MAP G-1-5, Pzr Level Lo-Lo.
- MAP G-3-5, Pzr Level Hi/Lo.
- MAP D-3-1, MU Flow Hi.
- RC1-LT-3 and RC-LI-777 both indicate 235 inches, and rising.
- Makeup Tank level is 75 inches, lowering at a rate corresponding to the rise in Pressurizer level.
Based on these conditions identify the ONE selection below that describes why 1202-29 (first) immediate action guides the operator to transfer Pressurizer level control to HAND and then to adjust Makeup flow.
A. Stabilize pressurizer level by controlling Makeup Tank level steady.
B. Minimize decrease in RCP seal injection flow by reducing Makeup flow.
C. Prevent cavitation of the operating Makeup Pump by reducing Makeup flow.
D. Reduce RCS pressure rise to prevent automatic Pressurizer spray valve RC-V-1 operation.
Q 033 NRC SRO 03-1 Licensing Examination Q 033 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor is in refueling shutdown condition.
- Core re-load in progress.
- RM-G-7, Reactor Building Main Fuel Handling Bridge Radiation Monitor, scale selector switch is in the ALL position.
Event:
- CRO turns RM-G-7 scale selector switch to the 1E2 position, and then RELEASES the switch.
Identify the ONE selection below that describes current RM-G-7 Control Room indication.
A. 1E-1 to 1E7 mR/hr.
B. 1E-1 to 1E2 mR/hr.
C. 1El to 1E3 mR/hr.
D. 1 E2 to 1 E5 mR/hr.
Q 034 NRC SRO 03-1 Licensing Examination Q 034 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor operating at 100% power, with ICs in full automatic.
- HSPS Train B High RB Pressure enableldefeat switch is in DEFEAT for testing.
Event:
- OTSG 1A feedwater piping rupture inside the RB.
Current plant conditions:
- RB pressure 4.1 psig.
- OTSG 1A pressure is 590 psig and lowering slowly.
- OTSG 1 B pressure is 101 0 psig and steady.
Based on these conditions, with no operator action, identify the ONE selection below that describes:
(1) OTSG level control setpoints.
(2) Controlling valves.
A. 1) OTSG 1A = 25 inches.
OTSG 1B = 25 inches.
- 2) OTSG 1A - EF-V-30A and EF-V-30D.
OTSG 1B - EF-V-30B and EF-V-30C.
B. I ) OTSG 1A = 0 inches.
OTSG 1B = 25 inches.
- 2) OTSG 1A = EF-V-30A and FW-V-16A.
OTSG 1B = EF-V-30C and FW-V-16B.
C. 1) OTSG 1A = 25 inches.
OTSG 16 = 25 inches.
OTSG 1B - EF-V-30C and FW-V-16B.
- 2) OTSG 1A - EF-V-30A.
D. 1) OTSG 1A = 0 inches.
OTSG 1B = 25 inches.
- 2) OTSG 1A - EF-V-30D and FW-V-16A.
OTSG 1B - EF-V-30B and FW-V-16B.
Q 035 NRC SRO 03-1 Licensing Examination Q 035 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Plant startup in progress.
- Reactor power 22%.
- Unit Load Demand 20%.
- Turbine Generator on line.
- Turbine Bypass Valves are closed in automatic.
Based on these conditions identify the ONE controlling setpoint for the Turbine Bypass valves.
A. 895 psig.
B. 960 psig.
C. I010 psig.
D. 1040 psig.
Q 036 NRC SRO 03-1 Licensing Examination Q 036 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor is operating at 100% power with ICs in full automatic.
Event:
- MAP L-1-6, Gen H2 Seal Oil Trouble alarm actuates.
- Local Hydrogen Seal Oil System alarm: Machine Gas Pressure High.
- Local Hydrogen Seal Oil System alarm: Machine Gas Purity Low.
- Generator hydrogen gas analyzer is verified to be operating correctly.
- Gas purity is 90%, and slowly lowering.
From the list below identify the ONE selection that describes the concern if hydrogen GAS PURITY continues to lower, and the action to be taken.
A. Contamination of the hydrogen seal oil, verify operation of the air detraining tank.
B. Development of a flammable gas mixture, commence fill and vent using H2 banks.
C. Accelerated corrosion of Main Generator components, monitor stator cooling for leaks.
D. Reduction in Generator gas pressure requiring a load reduction, reduce below capability curve limits.
Q 037 NRC SRO 03-1 Licensing Examination Q 037 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor at 100% power, with ICs in automatic EXCEPT ULD (in HAND).
- RCS boron concentration is 700 ppm.
- Operator completed adding 100 gallons of water to the Makeup Tank 10 minutes ago.
- The batch calculation, blending water from two RC Bleed Tanks, intended to match RCS boron concentration.
Event:
- Automatic control rod withdrawal raises reactor power to 101 YO.
- Loop A and Loop B FW flows increase, corresponding to the reactor power
- Main Generator output is reducing at 2 MW per minute.
- RCS Tave is constant at 579 degrees F.
increase.
Identify the ONE selection below that describes how all these indications could be true for one single event.
A. Increase in Main Condenser back pressure due to air in-leakage.
B. Increase in Main Generator MVARs due to grid voltage reduction.
C. Reactivity management event due to inadvertent control rod withdrawal.
D. Reactivity management event due to inadvertent RCS boron concentration increase.
Q 038 NRC SRO 03-1 Licensing Examination Q 038 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor operating at 100% power with ICs in full automatic.
- RB Purge in progress for Containment Building pressure control.
Event:
- Significant FUEL PIN LEAK develops.
- RM-G-20 (RCDT Discharge Monitor) HIGH ALARM actuates.
Based on these conditions identify the ONE statement below that describes components affected during this situation.
A. AH-V-1 A, 1 B, 1 C and 1 D, Purge Isolation Valves, all close.
B. WDG-V-3, RB Vent Header Containment Isolation Valve, closes.
C. MU-V-2A, 2B, Letdown Cooler Outlet Isolation Valves, both close.
D. WDL-V-534, RB Sump Drain to Auxiliary Building Sump Valve, closes.
Q 039 NRC SRO 03-1 Licensing Examination Q 039 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor operating at 100% power with ICs in full automatic.
Event:
- Turbine trip due to high main condenser pressure.
- Operator depressed the Reactor Trip and DSS pushbuttons.
- All main turbine stop valves closed.
Current conditions:
- Reactor power is 25% and slowly lowering.
- All 3 EFW Pumps are operating.
- OTSG atmospheric dump valves and some main steam safety valves are open.
- RCS Pressure has stabilized at 2350 psig.
Based on these conditions identify the ONE selection below that describes proper implementation of OP-TM-EOP-001, Reactor Trip.
A. Immediately initiate HPI, and then continue on to perform the next procedure action step.
B. IAAT RCS Pressure exceeds 2500 psig, initiate HPI, and then continue performing procedure steps.
shutdown is confirmed.
C. Immediately initiate HPI, and then hold further procedure action(s) until reactor D. IAAT power stabilizes at >5%, initiate HPI, and then hold further procedure action(s) until reactor shutdown is confirmed.
Q 040 NRC SRO 03-1 Licensing Examination Q 040 Three Mile Island Nuclear Station May 2005 Plant conditions;
- Reactor is operating at 100% power with ICs in full automatic.
- Parameters indicate an increase of 0.25 gpm leakage into the RC Drain Tank.
- RCS pressure steady at 2155 psig.
- Ambient temperature condition at RC-RV-2 PORV tailpipe is 100 degrees F.
Based on these conditions identify the ONE selection below that describes the operation and sensitivity of computer alarm A0517, RC-RV-2 TAILPIPE DELTA TEMP set at 30 degrees F.
(1) If hot fluid is flowing from the PORV, A0517 will alarm at an actual tailpipe (2) This system (idis NOT) sensitive enough to alarm with this amount of leakage.
temperature of A. (1) 130 degrees F.
- 6. (1) 618 degrees F.
(2) Is sensitive enough to alarm on this amount of leakage.
(2) Is sensitive enough to alarm on this amount of leakage.
C. (1) 130 degrees F.
(2) Is NOT sensitive enough to alarm on this amount of leakage.
D. (1) 618 degrees F.
(2) Is NOT sensitive enough to alarm on this amount of leakage.
Q 041 NRC SRO 03-1 Licensing Examination Q 041 Three Mite Island Nuclear Station May 2005 Plant conditions:
- Reactor tripped from full power.
- RCS pressure 1680 psig, lowering at 10 psig per minute.
- NO ES Actuations.
- Pressurizer level 85 inches, lowering at 1 inch per minute.
- Makeup valve MU-V-17 full open.
- Makeup Tank level lowering at 5 inches per minute.
- RCP labyrinth seal dP indications normal.
- Core exit incore thermocouple temperatures 535 degrees F, lowering at
- RM-A-2 containment airborne radiation levels are rising slowly.
- Containment pressure 1.5 psig rising at 0.1 psig per minute
- Startup FW flow indicated to both OTSGs.
- OTSG 1A level 25 inches, steady.
- OTSG 1B level 27 inches, rising slowly.
- OTSG pressures both 950 psig, lowering at 10 psig per minute.
1 deg reelm i n u te.
Based on these conditions identify the ONE selection below that describes the event in progress inside the Containment Building.
A. Small break LOCA.
B. OTSG 1B tube rupture.
D. Combined RCP seal # I leak-off line leak.
Q 042 NRC SRO 03-1 Licensing Examination Q 042 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor trip due to loss of coolant inside the RB.
- RCS subcooled margin 5 degrees F.
- Both Core Flood Tanks discharging water into the RCS.
- RB pressure 37 psig, rising at 1 psig per minute.
- All 4 RCPs tripped.
- Train A and Train B LPI flow is 2800 gpm EACH.
- OTSG 1A and OTSG 1B levels &%, rising at 1% per minute.
Based on these conditions identify the ONE selection below that describes operational requirements as described in procedures for:
(1) Emergency Feedwater Pumps.
(2) Nuclear River Water Service Pumps.
A. (1) Operation of EFW pumps is NOT required.
(2) 3 NR Pumps are required to operate.
B. (1) If possible operate all 3 EFW pumps.
(2) 3 NR Pumps are required to operate.
C. (1) Operation of EFW pumps is NOT required.
(2) If possible operate 2 NR Pumps.
D. (1) If possible operate all 3 EFW pumps.
(2) If possible operate 2 NR Pumps.
Q 043 NRC SRO 03-1 Licensing Examination Q 043 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor operating at 100°/~ power with ICs in full automatic.
- RC-P-1A motor amps and temperatures rising.
Based on these conditions identify the ONE selection below that describes indications provided by RC-P-IA status lamps as motor current continues to rise to the automatic trip setpoint and then trips - specifically:
(1) When MAP F-1-2, RCP Motor Overload, actuates due to high motor current.
(2) Following RC-P-1A automatic breaker trip due to motor overload.
A. (I)
Amber lamp will light.
(2) Green and Amber lamps (only) will be lit.
B. (I) Amber light will NOT light.
(2) Green and Amber lamps (only) will be lit.
(2) Red, Green and Amber lamps will be lit.
C. (1) Amber lamp will light.
D. (1) Amber lamp will NOT light.
(2) Red, Green and Amber lamps will be lit.
Q 044 NRC SRO 03-1 Licensing Examination Q 044 Three Mile Island Nuclear Station May 2005 Initial Conditions:
- Reactor operating at 100% power with ICs in full automatic.
- Intermediate Closed Cooling pump IC-P-1 A operating.
Event:
- Makeup pump MU-P-1B trip.
Based on these conditions, identify the pressurizer level that requires isolating letdown, and the reason normal makeup is restored slowly.
A. 200" To avoid starving seals.
- 6. 200" To minimize RCS pressure transients.
C. 150" To avoid starving seals.
D. 150" To minimize RCS pressure transients.
Q 045 NRC SRO 03-1 Licensing Examination Q 045 Three Mile Island Nuclear Station May 2005 Initial plant conditions:
- Reactor at Cold Shutdown conditions.
- RCS pressure 50 psig, controlled by Pressurizer heaters.
- Decay Heat Removal (DHR) Train A is operating.
Activities in progress:
- Securing DHR cleanup flow through the Liquid Waste Disposal System.
- DH-V-1, DHR dropline isolation valve, surveillance test.
- Local venting of DH-P-1A pump casing.
Event:
- Electrical fault trips normal feeder breaker to 1 R 480V Bus.
Current condition:
- Computer alarm indicates rising DH Suction temperature.
Based on these conditions, identify the ONE selection below that describes the cause for the rising DHR suction temperature.
A. Closure of DH-V-1.
B. Trip of 1R 480V Bus.
C. DH-P-1A pump venting.
D. Securing DHR cleanup flow.
Q 046 NRC SRO 03-1 Licensing Examination Q 046 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor is operating at 100% power with ICs in full automatic.
- Intermediate Closed Cooling pump IC-P-1 A operating.
- Both Intermediate Service Coolers IC-C-1A and IC-C-1B in service.
- Both Letdown Coolers MU-C-1A and MU-C-1B in service.
- Nuclear Services River Water pumps NR-P-1A and NR-P-1C operating.
- Intermediate Closed Cooling radiation monitor RM-L-9 indication at 1 E3 CPM due
- RM-L-7 plant effluent monitor is in service.
to an earlier operational problem.
Event:
- MAP C-3-2, IC Surge Tank Level Hi/Lo actuated.
Current conditions:
- IC-T-1 level is 7 inches, LOWERING at 1 inch per minute.
- There have been NO CHANGES in any radiation monitor readings.
Based on these conditions, identify the ONE selection below that describes the location of the leak.
A. Inside one of the Letdown Coolers.
C. Intermediate Service Cooler (IC-C-INB).
D. Inside one of the RCP Thermal Barrier Heat Exchangers.
Q 047 NRC SRO 03-1 Licensing Examination Q 047 Three Mile Island Nuclear Station May 2005 Initial plant conditions:
- Reactor operating at 100%.
- ICs in automatic EXCEPT Steam GeneratodReactor Master (in MANUAL).
- DSS Diverse Scram System manual pushbutton is NOT operable.
Event:
- Main Turbine trip and both FW Pumps trip due to Main Condenser air in-leakage.
- EFW actuation due to low level in OTSG 1A and OTSG 1B.
- OTSG pressures are both oscillating, responding to MSSV operation.
- Atmospheric Dump Valve MS-V-4A is wide open.
- Atmospheric Dump Valve MS-V-4B is FAILED closed.
- RCS pressure is 2400 psig.
- Manual reactor trip pushbutton has FAILED to initiate a reactor trip.
Based on these conditions identify the ONE selection below that describes:
(1) Most limiting parameter with regards to Primary-to-Secondary heat removal (2) Controlling procedure actions to be used to expedite reactor power reduction.
CAPACITY.
A. (1) ADV and MSSV combined steam flow capacity.
(2) Initiate HPI.
- 8. (1) ADV and MSSV combined steam flow capacity.
(2) Manually reduce SG/Rx Master to 0% output.
C. (1) EFW system flow capacity.
(2) Initiate HPI.
D. (1) EFW system flow capacity.
(2) Manually reduce SG/Rx Master to 0% output.
Q 048 NRC SRO 03-1 Licensing Examination Q 048 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Forced plant shutdown is in progress due to OTSG tube leakage, Based on this condition identify the ONE selection below that describes conditions requiring the operator to manually trip the reactor, based on the relationship between Pressurizer level and reactor power.
A. Pressurizer level 140 inches;
- 6. Pressurizer level 140 inches; Reactor power 30%.
Reactor power 20%.
C. Pressurizer level 160 inches; Reactor power 30%.
D. Pressurizer level 160 inches; Reactor power 20%.
Q 049 NRC SRO 03-1 Licensing Examination Q 049 Three Mile Island Nuclear Station May 2005 Initial plant conditions:
- Plant startup in progress with reactor at 15% power Sequence of events:
- Reactor trip due to low RCS pressure.
- EOP-001 Reactor trip immediate actions completed.
- Operators diagnosed excessive primary-to-secondary heat transfer at OTSG 1 6.
- Automatic EFW actuation.
- OTSG 1B Phase 1 isolation performed.
C u rrent conditions :
- OTSG 1B level is 3 inches, steady.
- OTSG 1B pressure is 500 psig, steady.
Based on these conditions identify the ONE selection below that represents a steam leak which requires the operator to continue with Phase 2 isolation of OTSG 1 B.
A. FW Pipe rupture at Main FW nozzle header B. Stuck open Main Steam safety valve MS-V-17B.
C. FW-P-1 B steam supply line rupture upstream of MS-V-56.
D. Failed open turbine bypass valves MS-V-3D, MS-V-3E and MS-V-3F.
Q 050 NRC SRO 03-1 Licensing Examination Q 050 Three Mile Island Nuclear Station May 2005 Plant conditions:
- ReactorlTurbine tripped due to low vacuum in the Main Condenser.
- Both FW Pumps tripped.
- All 3 EFW Pumps operating.
- OTSG levels at automatic level control setpoints.
- Atmospheric Dump Valves MS-V4A/B controlling OTSG pressures at 101 0 psig.
Event:
- MAP J-3-3, Condensate Stor Tk A Lvl Lo-Lo, actuates.
- MAP J-3-4, Condensate Stor Tk B Lvl Lo-Lo, actuates.
Based on these conditions identify the ONE selection below that describes:
(I) Next source of water to be used for EFW suction.
(2) When the water supplies are required to be changed.
NOTE:
For purposes of this question, immediately means within the next 2-3 minutes.
A. (1) Main Condenser Hotwell (CO-C-1).
B. (1) Demineralized Water Storage Tank (DW-T-2).
C. (1) Main Condenser Hotwell (CO-C-1).
(2) Immediately.
(2) Immediately.
(2) When Condensate Storage Tank levels are reduced to 2 feet.
D. (1) Demineralized Water Storage Tank (DW-T-2).
(2) When Condensate Storage Tank levels are reduced to 2 feet.
Q 051 NRC SRO 03-1 Licensing Examination Q 051 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor tripped due to loss of offsite power (LOOP).
- Emergency Generators EG-Y-1A and EG-Y-1 B failed.
- EF-V-30A/B/C/D are full open, and EFW flow is balanced between the two OTSGs.
- Parameter Value Trend RCS Pressure 1985 psig Lowering 20 psi/minute OTSG Pressures 1010 psig Lowering 10 psijminute OTSG 1A Level (Operate Range) 10%
Rising 1% per minute OTSG 1B Level (Operate Range) 8%
Rising 1% per minute Core Outlet Temperature*
603 Degrees Steady LOOP N B T-Hot 595 Degrees Steady LOOP NB T-Cold 565 Degrees Lowering 2 degreedminute Average of the five highest incore thermocouples.
Based on these conditions, identify the ONE selection below that describes status of:
(1) RCS natural circulation.
(2) Primary-to-secondary heat transfer (PSHT).
A. (1) Natural circulation is NOT occurring.
(2) PSHT is NOT occurring.
B. (1) Natural circulation is NOT occurring.
(2) PSHT is occurring.
C. (1) Natural circulation is occurring.
(2) PSHT is NOT occurring.
D. (1) Natural circulation is occurring.
(2) PSHT is occurring.
Q 052 NRC SRO 03-1 Licensing Examination Q 052 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor operating at 100% power with ICs in full automatic.
- ES Panel PCR Indicator Lights Power Supply Selector Switch in the "BUS A AND B" Position.
Event:
- Reactor trip with ES actuations due RCS LOCA.
- Inverter 1A failure results in de-energizing 120V AC Vital Bus 1A.
Based on these conditions identify the ONE selection below that describes the impact on control room position indication as the operator attempts to verify LPI valve DH-V-4A travels to the full open position.
A. Blue, Amber lamps are operable.
Red, Green Lamps are operable.
B. Blue, Amber lamps are operable.
Red, Green Lamps are NOT operable.
C. Blue, Amber lamps are NOT operable.
Red, Green Lamps are operable.
D. Blue, Amber lamps are NOT operable.
Red, Green Lamps are NOT operable.
Q 053 NRC SRO 03-1 Licensing Examination Q 053 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor operating at 100% power with ICs in full automatic.
Event:
- Fuse failure at Switch #4 125/250 Volt DC Distribution Panel ?A - DC power to Inverter lA, F U S E B, @ L o ~,
Based on these conditions, identify the ONE selection below that describes the operational impact of this event on Inverter 1A.
A. DC input breaker at the inverter will trip open.
Inverter will FAIL because the inverter AC output breaker will trip open.
- 6. DC input breaker at the inverter will trip open.
Inverter will continue to operate because the AC output breaker will NOT open.
C. DC input breaker at the inverter will NOT trip open.
Inverter will FAIL because the inverter AC output breaker will trip open.
D. DC input breaker at the inverter will NOT trip open.
Inverter will continue to operate because the AC output breaker will NOT open.
Q 054 NRC SRO 03-1 Licensing Examination Q 054 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Manual reactor trip from 100°/~ power due to low Instrument Air pressure.
- Operators have completed applicable emergency procedure immediate actions.
- Primary and Secondary air pressure indications are at 5 and 10 psig respectively.
- OTSG levels are both 8 inches, and slowly lowering.
- EFW Pumps EF-P-1, EF-P-2A and EF-P-2B are all operating.
- EFW control valves EF-V-30A-0 are all closed even though their controller automatic demand signals are all at 100%.
Based on these conditions, identify the ONE selection below that describes why EF-V-30 A-D are closed.
A. Trip of back-up compressor B. Low primary plant air system pressure C. Low 2-hour air supply system pressure.
D. Low secondary plant air system pressure.
Q 055 NRC SRO 03-1 Licensing Examination Q 055 Three Mile Island Nuclear Station May 2005 From the list below, identify the ONE (1) statement that explains why the RCS Loop A/B subcooling margin meters could display values that need to be verified during initial reactor trip transient conditions, so you can ensure transition from EOP-001 to the next (correct) EOP based on the symptom-oriented approach to accident mitigation.
A. The pressure transmitter is slow to respond due to small sensing lines.
B. The temperature transmitter is slow to respond due to the electronics in the C. The function generator takes time to make the calculation of Tsat from the RTD preamp.
pressure signal.
D. The temperature transmitter is slow to respond due to poor thermal coupling between the RCS and the RTD.
Q 056 NRC SRO 03-1 Licensing Examination Q 056 Three Mile Island Nuclear Station May 2005 Identify the ONE selection below that describes an OTSG that can be declared "available" as a heat sink.
A. RCS is subcooled, with RCPs operating in both loops; Main and Emergency FW are both available; OTSG is dry.
B. Main and Emergency feedwater are NOT available, however Primary to Secondary leakage is controlling level.
C. RCS is subcooled with RCPs operating; Main and Emergency FW are both available; OTSG has been isolated because of high level due to OTSG tube leakage.
D. OTSG level and pressure control are possible, but Primary-to-Secondary heat transfer has not been demonstrated; RCS is saturated, with no RCPs operating.
Q 057 NRC SRO 03-1 Licensing Examination Q 057 Three Mile Island Nuclear Station May 2005 In it ial p Ian t conditions :
- Reactor power is loo%, with ICs in full automatic.
- No surveillance testing or maintenance in progress.
- CRD Group 5 is energized from the AUXILIARY power supply.
- Phases A and B are energized.
Based on these conditions identify the ONE failure below that can cause a SINGLE control rod to drop.
A. ONE (Group 1 Rod 1) CRD motor fuse blows on Phase A.
B. ONE {Group 5 Rod 1) CRD motor fuse blows on Phase A.
C. TWO Auxiliary Power Supply Programmer lamp fuses fail.
D. TWO (Group 5 Rod 1) CRD motor fuses blow on Phases A and B.
Q 058 NRC SRO 03-1 Licensing Examination Q 058 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor operating at 100% power with ICs in full automatic.
- RCS T-ave is 579 degrees F, steady.
- Pressurizer level is 218 inches, lowering at 0.5 inches per minute.
- Make up tank level is lowering at 1 inch per minute.
- MU-V-17 is in automatic, with controller output demand at 15%, rising at 2%
- Indicated RCS makeup flow is 0 gpm.
- Letdown flow is constant at 45 gpm.
- MU-V-32 is in automatic.
- Indicated RCP total seal injection flow is 38 gpm, steady.
- RCP labyrinth seal DIP indicators are normal.
- Auxiliary Building airborne activity is rising.
per minute.
Based on these conditions, identify the ONE selection below that descibes the cause for this abnormal event.
A. RCS makeup flow is not reaching the RCS.
B. RCS makeup flow transmitter is failing.
C. RCP seal #I leak-off flow has been isolated by closure of MU-V-26 D. RCP seal #1 leak-off flow is aligned to the Auxiliary Building sump.
Q 059 NRC SRO 03-1 Licensing Examination Q 059 Three Mile Island Nuclear Station May 2005 PI ant conditions :
- Reactor is operating at 100% power, with ICs in full automatic.
- Waste Gas Compressor separator tank fitting leak is releasing radioactive gas into
- Auxiliary Building Exhaust ventilation fans AHE-14NC are operating.
- Auxiliary Building Supply Fan AH-E-1 1 is operating.
the compressor room.
Event:
- Radiation Monitor RM-A-6G high alarm actuates.
Based on these conditions, identify the ONE selection below that describes the response of the ventilation system, AND the reason for that response.
A. Auxiliary Building Exhaust fans AH-E-14NC are tripped to terminate the flow of radioactive gas from the Auxiliary Building.
B. Auxiliary Building Exhaust fans AH-E-14NC are tripped to terminate flow of radioactive gas from the compressor room to the basement hallway to avoid contamination of the Auxiliary Building.
C. Auxiliary Building supply fan AH-E-I 1 is tripped to terminate flow of radioactive gas from the compressor room to the basement hallway to avoid contamination of the Auxiliary Building.
D. Auxiliary Building supply fan AH-E-I 1 is tripped to ensure a negative pressure is established in the Auxiliary Building to avoid release of unmonitored and unfiltered radioactive gas.
Q 060 NRC SRO 03-1 Licensing Examination Q 060 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Plant startup in progress.
- Reactor power is 22%, with ICs in automatic.
Event:
- Operator adjusts ICs control to effect a power increase to 40%.
- Significant rise in Main Condenser off-gas radiation monitor readings with no corresponding symptoms of increasing OTSG tube leak rate.
Based on these conditions, identify the ONE selection below that describes the cause for this event, and the expected automatic response.
A. Increase in RCS activity.
After a time delay due to letdown and sample transport time, RM-L-1 Lo will close letdown isolation valves MU-V-2A and MU-V-26.
- 6. Increase in RCS activity.
After a time delay due to letdown and sample transport time, RM-L-1 HI will close letdown isolation valves MU-V-2A and MU-V-2B.
C. Radioactive crud burst on the secondary side of an OTSG.
Actuation of RM-A-5 or RM-A-15 high alarm will start the condenser off-gas MAP-5 iodine sampler.
Actuation of RM-G-25 (RM-A-5G HI-HI) high alarm will start the condenser off-gas MAP-5 iodine sampler.
D. Radioactive crud burst on the secondary side of an OTSG.
Q 061 NRC SRO 03-1 Licensing Examination Q 061 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Total loss of ICs Hand and Auto Power.
- Reactor tripped.
- NO required immediate manual actions have been completed yet.
Based on these conditions identify the ONE selection below that describes the impact of re-energizing ICS/NNI power prior to completion of the pre-restoration actions.
A. Loss of RCP seal injection due to closure of MU-V-32.
B. RCS pressure and Pressurizer level excursion due to MU-V-17 opening.
C. OTSG overfeed condition due to repositioning of the Main Feedwater valves.
D. Excessive RCS cooldown rate due to repositioning of atmospheric dump valves MS-V-4NB.
Q 062 NRC SRO 03-1 Licensing Examination Q 062 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor is operating at 100% power with ICs in full automatic.
- Fire conditions require Control Room to be evacuated.
- NO immediate actions of OP-TM-EOP-020, Cooldown From Outside of Control Room, were performed prior to the evacuation.
Based on these conditions, identify the ONE selection below that describes how OP-TM-EOP-020 directs you to TRIP THE REACTOR.
A. Open CRD Breakers 10 and 11.
- 6. Open CRD breakers at 1G and I L 480V switchgear C. Pull the Main Turbine Trip handle at the Front Standard.
- 0. Pull the Trip Handles at FW-P-1A and FW-P-16 local control consoles.
Q 063 NRC SRO 03-1 Licensing Examination Q 063 Three Mile Island Nuclear Station May 2005 Identify the ONE selection below that describes how TMI prevents the ability to INSERT or RAISE an irradiated fuel assembly in the New Fuel Elevator.
A. Administrative controls.
B. New Fuel Elevator weight sensing interlock.
C. Fuel Handling overhead crane cable length restriction.
D. Bridge Dillon cell interlock associated with elevator approach corridor
Q 064 NRC SRO 03-1 Licensing Examination Q 064 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor tripped.
- Train A and Train B HPI Actuation Event:
- Loss of RCS subcooled margin.
- URO stops RC-P-lA, RC-P-lB, and RC-P-IC.
- RC-P-1D would NOT trip from the main control panel within the procedurally required time limit.
Based on these conditions identify the ONE selection below that describes actions required at this time.
A. Restart all available RCPs.
B. De-energize 1B 6900V Bus.
C. Restart RC-P-1A or RC-P-1 B.
D. Continue to operate RC-P-1 D.
Q 065 NRC SRO 03-1 Licensing Examination Q 065 Three Mile Island Nuclear Station May 2005 Plant conditions:
- PORV HPI cooling is in progress.
- RCS subcooled margin is 10 degrees F.
- RCPs are all tripped.
- Both OTSG pressure boundaries are intact.
- OTSG 1A 9 inches 240 psig
+62 degrees
- OTSG 1B 7 inches 210 psig
+64 degrees
- Core exit thermocouple temperatures are now steady, no longer rising.
- There are no symptoms of OTSG tube leakage.
Level Pressure Tube-Shell DT Emergency Feedwater (EFW) is now available to re-establish FW to the OTSGs.
Based on these conditions, identify the ONE selection below that describes OP-TM-EOP-010 required actions.
A. Establish EFW to OTSG 1A ONLY, at greater than 185 gpm but less than 430 gpm.
B. Establish EFW to OTSG 1A ONLY, at greater than 430 gpm.
C. Establish EFW to BOTH OTSGs at a MAXIMUM of 435 gpm to each OTSG.
D. Establish EFW to BOTH OTSGs, at greater than 215 gpm to each OTSG with NO upper limit.
Q 066 NRC SRO 03-1 Licensing Examination Q 066 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Maintenance work completed on DC-V-ZA, DHR Heat Exchanger Inlet.
- Control Room Supervisor requests independent verification that DC-V-2A is in its
- A qualified operator is ready to verify locally that DC-V-2A is open.
ES required position.
Identify the ONE selection below that describes required actions for a second individual to complete this type of verification.
A. Verify the Control Room ES Status Panel keyswitch is in the normal operating position.
- 6. Verify DC-V-2A is open from its controller in the Control Room.
C. Visually observe the first individual checking DC-V-2A open.
D. Independently verify locally that DC-V-2A is physically open.
Q 067 NRC SRO 03-1 Licensing Examination Q 067 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Fire in the control room has caused a control room evacuation.
- Operating crew is implementing OP-TM-EOP-020, Cooldown From Outside Of Control Room.
From the list of in-plant actions below identify the ONE selection that is the HIGHEST PRIORITY (FIRST from the list to be performed).
A. Open both BWST suction valves MU-V-14A and MU-V-14B.
B. Trip both Main Feedwater Pumps.
C. Trip all Reactor Coolant Pumps.
D. Close RC-V-2, PORV isolation.
Q 068 NRC SRO 03-1 Licensing Examination Q 068 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor is operating at 100% power.
- ICs Stations in MANUAL:
- Reactor Master.
- Diamond Rod Control.
- Loop A and Loop B FW Loop Masters.
- SG N B Load Ratio.
- Steam Generator Reactor Demand.
Based on these conditions, identify the ONE selection below that describes a condition the operator is required ENSURE prior to returning the Diamond Rod Control panel to automatic.
A. FAULT RESET pushbutton lamp LIT.
C. RUN SPEED selected at the Speed Selector switch.
D. SEQUENCE mode of operation selected at the Sequence/Sequence Override pushbutton.
Q 069 NRC SRO 03-1 Licensing Examination Q 069 Three Mile Island Nuclear Station May 2005 Identify the ONE condition below that PROHIBITS the use of "N/A" for an in service test (IST) procedure step.
A. Performance of a partial test.
B. Skipping the step will result in an incomplete test.
C. Skipping the step will NOT result in missed acceptance criteria.
D. Precaution/Limitation/Prerequisite is NOT met - NO apparent impact on acceptance criteria.
Q 070 NRC SRO 03-1 Licensing Examination Q 070 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor operating at 80% power with ICs in automatic.
- Nuclear engineers collecting NAS data regarding core power distribution.
- Control Rod Index 250.
- Reactor power imbalance NEGATIVE 32%.
Event:
- Uncontrolled rod withdrawal begins.
Based on these conditions identify the ONE selection that describes the FIRST reactor trip setpoint to be exceeded, and the basis for that trip.
A. Nuclear overpower, to protect fuel integrity.
B. High RCS pressure, to maintain RCS pressure boundary integrity.
C. High RCS outlet temperature, to limit coolant temperature during reactor operation.
D. Nuclear overpower based on RCS flow and power imbalance, to maintain DNBR greater than minimum requirements.
Q 071 NRC SRO 03-1 Licensing Examination Q 071 Three Mile Island Nuclear Station May 2005 Plant conditions:
- OTSG 1A tube leak (300 gpm) shutdown in progress using OP-TM-EOP-005.
- Reactor was manually tripped 25 minutes ago.
- RCS T-Hot is 510 degrees F.
- RCS pressure is 980 psig.
- OTSG 1 N l B levels are both 25 inches.
- BWST level is 24 feet.
- Tech Support Center (TSC) is NOT staffed at this time.
The Radiological Assessment Coordinator (RAC) reports that projected off-site doses based on an 8-hour duration release are:
- 360 mrem Whole Body.
- 2160 mrem Child Thyroid.
Based on these conditions, identify the ONE statement below that describes required OTSG 1A isolation status, AND the basis for that status.
A. Must NOT be isolated due to BWST level.
- 6. Isolation is required due to high tube leak rate.
C. Isolation is required due to high dose projections.
D. Must NOT be isolated due to RCS temperature and pressure.
Q 072 NRC SRO 03-1 Licensing Examination Q 072 Three Mile Island Nuclear Station May 2005 Plant conditions:
core cooling.
OP-TM-823-406, RB Purge - Containment Closed.
- Plant cooldown in progress, preparing to establish Decay Heat Removal
- Waste Gas Release Permit has been approved for an RB purge in accordance with Based on these conditions identify the ONE selection that describes the process for initiating this Reactor Building purge.
A. (I)
Set RB Purge Manual Loader to desired value.
(2) Start Purge Supply Fans.
(3) Start Purge Exhaust Fans.
B. (1) Start Purge Supply Fans.
(2) Start Purge Exhaust Fans.
(3) Adjust RB Purge Manual Loader to desired value.
(2) Start Purge Exhaust Fans.
(3) Start Purge Supply Fans.
C. (1) Set RB Purge Manual Loader to desired value.
D. (1) Start Purge Exhaust Fans.
(2) Start Purge Supply Fans.
(3) Adjust RB Purge Manual Loader to desired value.
Q 073 NRC SRO 03-1 Licensing Examination Q 073 Three Mile Island Nuclear Station May 2005 Identify the ONE selection below that describes procedure place keeping requirements during implementation of EMERGENCY OPERATING PROCEDURES (EOPs), IAW OS-24 "Conduct of Operations During Abnormal and Emergency Events", and operations expectations in effect on 5/16/05.
During EOP implementation checked or otherwise marked.
are REQUIRED to be A. only transitions between procedures B. only steps provided with check-off spaces C. all EOP steps, whether or not check-off spaces are provided D. all steps with check-off spaces, and ALL EOP Rule/Guide steps
Q 074 NRC SRO 03-1 Licensing Examination Q 074 Three Mile Island Nuclear Station May 2005 Plant Conditions:
- 100% power
- Report of a small body to bonnet leak on MS-V-2A, TBV and ADV isolation.
- A OTSG calculated leak rate 0.5 gpm
- B OTSG calculated leak rate 0.7 gpm
- MS-V-13B declared 00s and tagged closed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> ago.
Based on the conditions and failures above, identify the CONTROLLING procedure from the list below.
A. 11 02-4 Power Operations B. 1203-24 Steam Leak C. OP-TM-EOP-001 Reactor Trip D. OP-TM-EOP-005 OTSG Tube Leakage
Q 075 NRC SRO 03-1 Licensing Examination Q 075 Three Mile Island Nuclear Station May 2005 Initial conditions:
- Reactor operating at 100% power with ICs in full automatic.
Event:
- Circulating Water tube leak on B side of the Main Condenser Current conditions:
- CE-6A (corrected feedwater cation conductivity) control room indication is
- Chemistry has validated the following sample readings:
pegged high at 3.0 micromho/cm.
- CE-6A (corrected feedwater cation conductivity) is 6.5 micromholcm
- CE-6 (feedwater cation conductivity) is 7.5 micromho/cm Based on these conditions identify the ONE statement below that describes required act ions.
A. Secure all Moisture Separator Drain Pumps and continue power operation.
B. Reduce power to less that 50% and isolate the "B" side Circulating Water loop.
C. Perform a normal plant shutdown and cooldown to Decay Heat Operations.
D. Trip the reactor and go to OP-TM-EOP-001, Reactor Trip.
Q 076 NRC SRO 03-1 Licensing Examination Q 076 Three Mile Island Nuclear Station May 2005 Initial plant conditions:
- Maintenance outage in progress.
- Reactor vessel head is removed
- DHR Train "A" aligned for RCS cooling.
- lncore thermocouple temperatures steady at 100 degrees F.
Event:
- Decay Heat Removal Pump discharge pressure and DHR system flow rate begin to
- lncore thermocouple temperatures are now 11 5 degrees F, continuing to rise.
oscillate excessively.
Based on these conditions identify the ONE selection below that describes required operator actions, and the appropriate procedure to be implemented.
A. Stop any procedure in progress which could be reducing RCS inventory and initiate EOP-010 Guide 9, RCS Inventory Control.
B. Reduce DH Train A flow using OP-TM-212-451, Control of DH Train A Flow and temperatures, until the flow and pressure oscillations stop.
C. Place DH Train B in service IAW OP-TM-212-901, Emergency DHR Operations, and then vent DH-P-1A using OP-TM-212-553, Vent of DH-P-1 A.
- 0.
Stop OH-P-?A and evacuate all personnel from the Reactor Building (RB) by actuating the RB Evacuation alarm IAW EOP-030, Loss of Decay Heat Removal.
Q 077 NRC SRO 03-1 Licensing Examination Q 077 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor operating at 100% power with ICs in full automatic.
- RC-1 LTI and RC-2 TEI are selected for inputs to the Pressurizer level recorder.
- RCS-Pressurizer boron equalization in progress using OP-TM-220-461, Equalize RCS and Pressurizer Boron Concentration.
- Pressurizer Spray Valve RC-V-1 is partially open in manual.
- Console Right selector switches for Pressurizer Heater Banks 1-5 turned to the ON POSITION.
Event:
- SUBFEEDS - AUTO/HAND lamp de-energizes (NOT lit).
- MAP G-3-5, Pzr level Lo-Lo actuates.
- Operator determines this alarm is invalid, based on redundant indications.
Based on these conditions identify the ONE selection below that describes:
(1) Lo-Lo Pressurizer level heater cut-out setpoint.
(2) Impact on Console Right Bank 1-5 heater control lamps.
(3) Applicable procedure.
A. (1) < 63.5 inches.
(2) Red lamps remain LIT due to manual control mode.
(3) 1202-41, Total or Partial Loss of ICS/NNI HAND Power.
B. (1) < 63.5 inches.
(2) Red lamps NOT lit.
(3) 1202-42, Total or Partial Loss of ICS/NNI AUTO Power C. (1) < 80 inches.
(2) Red lamps remain LIT due to manual control mode.
(3) 1202-41, Total or Partial Loss of ICS/NNI HAND Power.
D. (I) < 80 inches.
(2) Red lamps NOT lit.
(3) 1202-42, Total or Partial Loss of ICS/NNI AUTO Power.
Q 078 NRC SRO 03-1 Licensing Examination Q 078 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor trip due to non-bomb steam explosion inside the Intermediate Building.
- Train A and Train B ES actuations due to low RCS pressure.
- All 3 Emergency Feedwater pumps are operating.
- EOP-001 Reactor Trip immediate actions are complete.
- RCS pressure is 1500 psig, lowering.
- Core exit thermocouple temperature 520 degrees F, lowering at 5 degrees
- OTSG I A pressure 400 psig, rapidly lowering.
- OTSG 1B pressure 800 psig, slowly lowering.
per minute.
Based on these conditions identify the ONE selection that describes:
(1) Controlling procedure to be implemented next.
(2) Plant announcement that meets OS-24 procedural requirements.
A. (1) 1203-24, Steam Leak.
(2) Announce the reactor trip, and direct Auxiliary Operators to report to their post trip stations.
B. (1 ) OP-TM-EOP-003, Excessive Primary-to-Secondary Heat Transfer.
(2) Announce the reactor trip, and direct Auxiliary Operators to report to their post trip stations.
(2) Announce:
C. (1) 1203-24, Steam Leak.
- a. Reactor trip with EFW and ES actuation.
- b. Secondary Auxiliary Operator should NOT report to EF-V-30 area.
D. (1) OP-TM-EOP-003, Excessive Primary-to-Secondary Heat Transfer.
(2) Announce:
- a. Reactor trip with EFW and ES actuation.
- b. Secondary Auxiliary Operator should NOT report to EF-V-30 area.
Q 079 NRC SRO 03-1 Licensing Examination Q 079 Three Mile Island Nuclear Station May 2005 Initial plant conditions:
- Reactor at Hot Shutdown conditions.
- 120V AC bus ATB de-energized in accordance with 1107-2B, 120 Volt AC Vital Electrical System.
Event:
- LOSS Of 120V AC bus ATA.
Current conditions:
- Pressurizer Level H/A controller indications:
- Hand and Auto lamps NOT lit.
- Demand and Measured Variable indications at mid-scale.
- Pressurizer heater control indications:
- Console Right Heater Bank ON/OFF lamps are NOT lit.
Based on these conditions identify the ONE selection below that describes:
(1) Status of Pressurizer level and RCS pressure control systems.
(2) Appropriate method of controlling Pressurizer level.
A. (I)
Automatic controls NOT operable.
Manual controls NOT operable.
(2) Use MU-V-217 to control Pressurizer level.
B. (1) Automatic controls operable.
Manual controls NOT operable.
(2) Use Automatic control of MU-V-17.
C. (1) Automatic controls NOT operable.
Manual controls operable.
(2) Use Manual control of MU-V-17.
D. (1) Automatic controls operable.
Manual controls operable.
(2) Use Automatic or Manual control of MU-V-17.
Q 080 NRC SRO 03-1 Licensing Examination Q 080 Three Mile Island Nuclear Station May 2005 Initial conditions:
- Reactor operating at 90% power with ICs in automatic.
- Control rod index 290.
- Makeup Tank water addition in progress.
- Ten (1 0) gallons of 100 gallons has been added from RC Bleed Tank A.
Event:
- Reactor trip.
- Safety Rods in Groups 1-4 did NOT trip.
- Both Main Feedwater Pumps tripped.
Current conditions:
- Reactor power is 2%, lowering slowly.
- RCS pressure is 2000 psig, lowering at 30 psig per minute.
Identify the ONE selection below that describes required actions for these conditions.
A. Trip the Main Turbine, and initiate 1202-8, CRD Equipment Failure.
- 8. Ensure EFW is actuated, and initiate 1203-1 0, Unanticipated Criticality.
C. De-energize 1 G and 1 L 480V busses, and terminate the RCS dilution in progress D. Initiate EOP-010 Rule 5, Emergency Boration, and terminate the RCS dilution in progress.
Q 081 NRC SRO 03-1 Licensing Examination Q 081 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Manual reactor trip due to high RB pressure (OTSG 1A steam leak).
- Reactor Trip EOP immediate actions complete.
- EOP-010 Rule 3, Excessive Heat Transfer complete.
- BOTH isolation phases were performed on OTSG IA.
- OTSG 1 B pressure is 800 psig, steady.
Based on these conditions identify the ONE selection below that describes operability status for turbine driven Emergency Feedwater pump EF-P-1.
A. OPERABLE because Auxiliary Steam can be aligned as a redundant steam B. OPERABLE because minimium degree of (steam supply) redundancy is maintained by two lines from OTSG 1 B.
C. INOPERABLE because all steam sources from OTSG 1A are isolated.
supply.
D. INOPERABLE because steam flow to the turbine will be less than design basis assumptions.
Q 082 NRC SRO 03-1 Licensing Examination Q 082 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor operating at 100% power with ICs in full automatic.
Event:
- Reactor trip from 100% power
- RCS letdown flow 70 gpm.
Current plant conditions:
- EOP-001 Reactor Trip immediate actions complete.
- All Pressurizer level channels at 180 inches, rising slowly.
- Makeup Tank level 85 inches, lowering slowly.
- Makeup flow 50 gpm.
- RCP Seal Injection flow 38 gpm.
Based on these conditions identify the ONE selection below that describes required action.
A. Isolate makeup flow using EOP-010 Guide 9, RCS Inventory Control.
B. Verify Pressurizer level stabilizes between 200-240 inches IAW EOP-001, Reactor Trip.
C. Select a Bleed Tank and shift MU-V-8 to the BLEED position using OP-TM-21 1-462, Lowering RCS/MU Volume - Bleed.
D. Transfer MU-V-17 control to HAND and maintain Makeup Tank level constant using 1202-29, Pressurizer System Malfunction.
Q 083 NRC SRO 03-1 Licensing Examination Q 083 Three Mile Island Nuclear Station May 2005 Identify the ONE selection below that describes a plant condition that has Technical Specification required action(s).
A. RCS cooldown, Tave 270 degrees F.
Main condenser vacuum 22 inches Hg.
B. Reactor at hot shutdown conditions.
Motor breaker trips when operator manually starts MU-P-1 A.
NI-3 Log Amp failure.
Pressurizer level 330 inches.
C. Reactor operating at 10% power.
D. Reactor operating at 100% with ICs in full automatic.
Q 084 NRC SRO 03-1 Licensing Examination Q 084 Three Mile Island Nuclear Station May 2005 Plant conditions:
- WDL-T-1 I A (A WECST) radioactive liquid release has just been started using
- Your Process Instruction Data Sheet did NOT prescribe any abnormal tankhalve normal procedures and valve alignments.
configuration for the release flow path.
Event:
- You are performing a verification of the valve alignment to ensure no accidental
- You are verifying the following valve positions:
liquid release is occurring.
- WDL-V-257, WDL-P-14NB discharge to MDCT.
- WDL-V-124, WDL-P-14A outlet to the MDCT.
- WDL-V-125, WDL-P-14B outlet to the MDCT.
- WDL-V-128, WDL-P14A outlet to the A WECST Identify the ONE selection below that describes the correct valve alignment for this planned release.
A. WDL-V-257 - Full open.
WDL-V-124 - Throttled for flow control.
WDL-V-125 - Closed.
WDL-V-128 - Full open.
B. WDL-V-257 - Throttled for flow control.
WDL-V-124 - Full open.
WDL-V-125 - Closed.
WDL-V-128 - Full open.
C. WDL-V-257 - Full open.
WDL-V-124 - Closed.
WDL-V-125 - Throttled for flow control.
WDL-V-128 - Full open.
D. WDL-V-257 - Full open WDL-V-124 - Throttled for flow control.
WDL-V-125 - Closed.
WDL-V-128 - Throttled for flow control.
Q 085 NRC SRO 03-1 Licensing Examination Q 085 Three Mile Island Nuclear Station May 2005 Plant conditions:
- RCS LOCA caused ESAS actuation.
- Operating crew implementing EOP-006, LOCA Cooldown.
- HPI Pumps were NOT secured in accordance with TS requirements.
- 1 OCFR50.54X was invoked.
- RCS subcooled margin 2 degrees.
- All 4 HPI Valves MU-V-16A-D wide open.
Event:
- Pressurizer level begins to rise rapidly due to RCS system re-filling.
- RCS pressure is rising rapidly, approaching the TS 3.1-1 limit on EOP-010 Figure 1.
- Operator is experiencing difficulty gaining control of the HPI Valves.
- EOP-010 Guide 23, RCS Pressure & Temperature Limits directs you to open RC-RV-2 (PORV).
Based on these conditions, identify the ONE selection below that describes the basis for directing this pressure reduction to prevent exceeding the limits of the referenced curve.
A. Prevent Pressurizer Safety Valves from opening.
B. Prevent non-ductile fracture of the reactor vessel.
C. Prevent Reactor Coolant System pressure from exceeding 11 0% of design pressure.
D. Limit RCS subcooled margin to 250 degrees F to restrict cyclic stresses on RCS components.
Q 086 NRC SRO 03-1 Licensing Examination Q 086 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor operating at 100% power, with ICs in full automatic.
- MU-V-17 in automatic.
Event:
- Selected Pressurizer Level Indication FAILS HIGH over a 1-second period.
Based on these conditions, identify the ONE selection below that describes:
(1) Automatic response.
(2) Controlling procedure.
A. (1) MU-V-17 position remains the same, actual Pressurizer level is not affected.
(2) OP-TM-L2278, SASS Actuation.
B. (1) MU-V-17 opens, actual Pressurizer level rises.
(2) 1202-29, Pressurizer System Failure.
C. (1) MU-V-17 opens, actual Pressurizer level rises.
(2) OP-TM-MAP-G0205, Pzr Level Hi/Lo.
D. (1) MU-V-17 closes, actual Pressurizer level lowers.
(2) 1202-29, Pressurizer System Failure.
Q 087 NRC SRO 03-1 Licensing Examination Q 087 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor is operating at 100% power with ICs in full automatic.
0900 Event:
- Operator discovered 1 M DC Bus power supply selected to B DC System.
- 1M DC Bus power supply was promptly selected to A DC System.
- Discharge header disconnects are open between MU-P-1A and MU-P-1 B.
0930 Event:
- Overflow of Decay Heat Surge Tank DC-T-1 B during operation of DR-P-1 B to
- Decay Heat Services Cooler 2A is out of service due to vibration-induced support planned radioactive liquid release to the river.
tube failures.
- DC-T-1 B water overflow stopped when DR-P-I B was secured.
Based on these conditions identify the ONE selection below that describes:
(I)
Event requiring EARLIEST notification to the NRC.
(2) Actions to comply with NRC notification REQUIREMENTS.
A. (1) 0900 Event.
(2) Contact NRC Operations Center via ENS.
B. (1) 0930 Event C. (1) 0900 Event.
(2) Contact NRC Operations Center via ENS.
(2) Inform the resident inspector by telephone.
D. (1) 0930 Event (2) Inform the resident inspector by telephone.
Q 088 NRC SRO 03-1 Licensing Examination Q 088 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor triped due to RCS LOCA.
- Loss of off-site power (LOOP).
- All ECCS equipment operating.
- Off-site power has been re-established to Bus ID.
- Emergency Diesel Generator EG-Y-1A loaded to 1.8 MW Based on these conditions identify the ONE selection below that describes actions required to shutdown EG-Y-1A and the basis for those actions.
A. Gradually reduce load to approximately 0.3 MW then open the generator breaker to prevent a reverse power trip using OP-TM-861-901, Diesel Generator EG-Y-1 A Emergency Operations.
- 6. Raise load to approximately 3 MW then run the diesel at that load for one hour to reduce unburned fuel oil, lube oil, and carbon in the cylinders using 1107-3, Diesel Generator.
C. Reduce load to ZERO MW and then trip the diesel within 5 minutes to prevent blower failure; then verify alignment for ES Standby using 1303-4.16, Emergency Power System.
D. Trip the diesel to prevent simultaneous alignment of both diesel generators to the grid when AOP-020, Loss of Station Power, Attachment 2 - Restoration of Off-Site Power, has been completed.
Q 089 NRC SRO 03-1 Licensing Examination Q 089 Three Mile Island Nuclear Station May 2005 Initial plant conditions:
- Reactor operating at 100% power with ICs in full automatic.
- Nuclear River Service Water Pumps NR-P-1A and NR-P-1 B have tripped.
- Standby NR-P-IC is operating.
- NR-P-IC discharge pressure is 17 psig, slowly lowering.
Current conditions:
- Nuclear River Service Water (NR) and Secondary Services (SR) River Water
- NR-P-IC discharge pressure is 25 psig, and slowly rising.
systems have been cross-connected.
Based on these conditions identify the ONE selection below that describes required act ions.
A. Commence and perform a Technical Specification required shutdown per TS 3.01.
B. Enter OP-TM-AOP-005, monitor IPSH Bay levels, and if less than 271 foot elevation then trip the reactor and enter OP-TM-EOP-001, Reactor Trip.
C. Start a third SR pump and reduce reactor power as necessary to limit SCCW temperatures.
D. Throttle SR discharge valve SR-V-2 until pressure indicator SR-PI-134 is approximately 20 psig and monitor SCCW temperatures.
Q 090 NRC SRO 03-1 Licensing Examination Q 090 Three Mile Island Nuclear Station May 2005 Plant Conditions:
- Plant operating at 100% power.
- RR-P-1A is 00s for repairs.
- Design Basis LOCA occurs.
- B train ESAS block timing relays fail to actuate.
Based on the above conditions and equipment failures, identify the ONE selection that describes the effect on Reactor Building pressure.
A. Reactor Building pressure would be controlled by, ONE (1) Building Spray pump and TWO (2) AH-E-I Containment recirculation fans, in slow.
B. Reactor Building pressure would be controlled by, TWO (2) Building Spray pumps, independent of containment recirculation fans.
C. Reactor Building pressure would exceed predicted limits for this accident, with only TWO (2) Building Spray pumps and TWO (2) containment recirculation fans, in slow.
D. Reactor Building pressure would exceed predicted limits for this accident, with only ONE (1) Building Spray pump and TWO (2) containment recirculation fans, in slow.
Q 091 NRC SRO 03-1 Licensing Examination Q 091 Three Mile Island Nuclear Station May 2005 Initial plant conditions:
- Reactor operating at 100% power with ICs in full automatic.
Event:
- OTSG 1B develops a large steam rupture.
- Reactor tripped due to low RCS pressure.
Current plant conditions:
- In-core thermocouples 532 degrees F and lowering.
- OTSG 1A pressure 885 psig and lowering slowly.
- OTSG 1B pressure 585 psig and lowering rapidly.
- RB pressure 1.5 psig and slowly rising.
Based on these conditions identify the ONE selection below that describes:
(1) Automatic OTSG level responses.
(2) Applicable procedure for OTSG level control.
A. (1) OTSG 1A stabilizes at Low Level Limits; OTSG 1 B continues to lower to EFW actuation setpoint.
(2) OP-TM-EOP-010 Guide 15, EFW Actuation Response.
C. (1) OTSG 1A stabilizes at Low Level Limits; (2) OP-TM-EOP-010 Guide 15, EFW Actuation Response.
OTSG 1 B continues to lower to EFW actuation setpoint.
(2) OP-TM-EOP-010 Rule 4, Feedwater Control.
D. (1) Both OTSGs lower to EFW actuation setpoint.
(2) OP-TM-EOP-010 Rule 4, Feedwater Control.
Q 092 NRC SRO 03-1 Licensing Examination Q 092 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor is operating at 60% power, with ICs in automatic.
- All 4 RCPs are operating.
- Group 7 Rod 1 dropped 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> ago.
- Quadrant power tilt exceeds the COLR limit by 6% for the past 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
Based on these conditions identify the ONE selection below that describes:
(1) Required adjustment to the normal rod position limit.
(2) Actions required if that limit is violated.
(3) Procedure that provides guidance for actions identified in (2) above.
A. (1) RAISE rod index limit.
(2) INCREASE RCS boron concentration to withdraw rods.
(3) 1 102-4, Power Operation.
- 6. (1) REDUCE rod index limit.
(2) REDUCE RCS boron concentration to insert rods.
(3) 1 102-4, Power Operation.
C. (1) RAISE rod index limit.
(2) REDUCE RCS boron concentration to insert rods.
(3) 1203-7, Hand Calculations for Quadrant power Tilt and Core Power Imbalance.
D. (1) REDUCE rod index limit.
(2) INCREASE RCS boron concentration to withdraw rods.
(3) 1203-7, Hand Calculations for Quadrant power Tilt and Core Power Imbalance.
Q 093 NRC SRO 03-1 Licensing Examination Q 093 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor tripped 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.
- Due to equipment failures at time of the trip:
- Only EF-P-2A is operating to supply FW to the OTSGs.
- FW-P-1A and FW-P-16 are both tripped.
- RCS T-Hot is 316 degrees F.
- RCS pressure is 150 psig.
- OTSG pressures are 70 psig.
- OTSG levels have been raised to 40% on the Operating Range.
- RCS cooldown in progress.
- CO-P-1A and CO-P-2A are operating.
- Decay Heat Removal system is NOT operating.
Event:
- EF-P-2A trip.
- RCS cooldown has been suspended to conserve OTSG secondary inventory.
- Turbine Bypass valves have been throttled to maintain RCS pressure and temperature steady.
Based on these conditions identify the ONE selection below that describes:
(1) Method of core cooling to be established.
(2) Applicable procedure.
A. Actuate HPI.
B. Initiate HPI COOLING.
OP-TM-EOP-004, Lack of Primary-to-Secondary Heat Transfer.
OP-TM-EOP-009, HPI Cooling.
C. Feed the OTSGs with Main FW.
EOP-010 Guide 16, EFW Failure.
D. Initiate Decay Heat Removal Cooling.
OP-TM-212-11 l(112) Shifting DHR Train A(B) from Standby Mode to DHR Operating Mode.
Q 094 NRC SRO 03-1 Licensing Examination Q 094 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor tripped due to RCS LOCA.
- OP-TM-EOP-001 immediate actions are complete.
- You are the Control Room Supervisor (CRS), directing implementation
- EOP guidance directs you to INITIATE an additional Emergency
- You hand that EP to a Control Room Operator and direct him to perform this procedure in parallel as you continue with the controlling EOP.
of the controlling Emergency Operating Procedure (EOP).
Procedure (EP).
Event:
- The CRO states that Step 14 (check-off space is assigned) of the EP is NOT applicable.
Based on these conditions, identify the ONE selection below that describes:
(1) Actions required prior to proceeding to the next step of the EP.
(2) Documentation requirements this EP step is deemed to be NOT APPLICABLE.
A. (1) Direct the CRO to obtain concurrence from the other CRO prior to proceeding.
Abnormal and Emergency Events.
(2) Mark the step NA in accordance with OS-24, Conduct of Operations During B. (I)
Inform the CRO that after obtaining your concurrence he is required to verbalize the step to the Control Room team to verify non-applicability.
Abnormal and Emergency Events.
(2) Mark the step NA in accordance with OS-24, Conduct of Operations During C. (1) Direct the CRO to obtain concurrence from the other CRO prior to proceeding.
(2) Invoke 10 CFR 50.54X.
D. (1) Inform the CRO that after obtaining your concurrence he is required to verbalize the step to the Control Room team to verify non-applicability.
(2) Invoke 10 CFR 50.54X.
Q 095 NRC SRO 03-1 Licensing Examination Q 095 Three Mile Island Nuclear Station May 2005 The Plant has tripped from 100% power due to a Loss of Offsite Power (LOOP) with the following component conditions present:
- ES AUTOMATIC actuation due to a LOCA.
- Emergency Diesel Generator, EG-Y-1A has failed to start.
- Both Core Flood Tanks (CFT's) level at two (2) feet.
The following indications are noted:
- RCS pressure is 260 psig and relatively steady.
- Pressurizer level is currently off-scale LOW.
- RCS temperature is 180 degrees F and lowering very slowly.
Which ONE of the following identifies a condition that requires NRC notification regarding violation of a Technical Specification Limiting Condition for Operation (LCO)?
A. RCS temperature at 180 degrees F with HPI operating.
- 6. Diesel, EG-Y-1A failure to start, C. Pressurizer level off-scale LOW.
D. Low level in both Core Flood Tanks.
Q 096 NRC SRO 03-1 Licensing Examination Q 096 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Reactor is at HOT SHUTDOWN.
- Preparing to start up 2 days from now.
- The seals of a pump required to be operable for power operations was
- The pump section of the system Technical Specification Surveillance
- The normal Tech Spec Surveillance is scheduled for 10 days from today.
replaced today.
is required for post maintenance testing requirements.
Identify the ONE selection below that describes MINIMUM testing requirements to satisfy 1001 J.l, Technical Specification Testing Program.
A. ENTIRE surveillance test is REQUIRED to be performed PRIOR TO criticality.
B. The PUMP SECTION of the surveillance test is REQUIRED to be completed prior to criticality.
C. It is permissible to complete the ENTIRE surveillance test following criticality on its normally scheduled date.
D. It is permissible to complete the PUMP SECTION of the surveillance test following criticality on its normally scheduled date.
Q 097 NRC SRO 03-1 Licensing Examination Q 097 Three Mile Island Nuclear Station May 2005 Identify the ONE temporary change below that requires processing and approval using CC-AA-112, Temporary Configuration Changes.
A. Installation of rigging to support maintenance.
- 6. Installation of temporary lead shielding to reduce radiation dose.
C. Installation of an inflatable plug to seal a concrete pipe penetration.
D. Jumper installation to support performance of a surveillance procedure.
Q 098 NRC SRO 03-1 Licensing Examination Q 098 Three Mile Island Nuclear Station May 2005 Plant conditions:
- Control room staff is limited to MINIMUM STAFFING requirements.
- Reactor tripped from 100% power.
- Loss of ICS/NNI HAND Power due to breaker trip.
- Primary-to-secondary leakage: OTSG 1A = 0.7 gpm, OTSG 16 = 0.4 gpm.
- Core exit thermocouple temperatures are 540 degrees F.
- RCS pressure is 950 psig.
- RB pressure is 2.5 psig.
- Loss of 230 KV lines 1091 AND 1092, due to fault at Middletown Junction Substation.
Based on these conditions at the time of trip, from the list below identify the FIRST (highest priority) PROCEDURE to be implemented, when reactor trip immediate actions have been completed.
A. OP-TM-EOP-005, OTSG Tube Leakage.
B. MAP NN-1-3, 230 KV Substation Trouble.
C. 1202-41, Total or Partial Loss of ICS/NNI Hand Power D. OP-TM-EOP-002, Loss of 25 Degrees Subcooled Margin.
Q 099 NRC SRO 03-1 Licensing Examination Q 099 Three Mile Island Nuclear Station May 2005 During a primary side tour to check for recurring hot spots, data was recorded to be evaluated for Hot Spot posting and prioritization for flushing operations.
From the list below identify the ONE selection that requires this type of posting and reporting for radiation source elimination.
A. WDL-V-160, inlet to 'B' Precoat Filter:
- Contact dose is 90 mRem/hour.
- Dose rate at 30 cm is 12 mRem/hour B. WDL-V-55, MWST inlet from vent header to RCBT:
- Contact dose is 105 mRemlhour.
- Dose rate at 30 cm is 16 mRem/hour.
C. WDL-V-376, WDL-V-304 isolation/test and drain:
- Contact dose is 110 mRem/hour.
- Dose rate at 30 cm is 30 mRem/hour.
D. Low point piping downstream of WDL-V-240, MWST inlet header:
- Contact dose is 120 mRem/hour.
- Dose rate at 30 cm is 35 mRem/hour.
Q ?OO NRC SRO 03-1 Licensing Examination Q 100 Three Mile Island Nuclear Station May 2005 Initial plant conditions:
- Reactor tripped from 100% power.
- OP-TM-EOP-001 immediate actions are complete.
Sequence of events:
- Loss of offsite power (LOOP), with EG-Y-1A start failure.
- EF-P-1 tripped.
- Major Main Steam system leak inside the RB.
- ESAS actuation.
- Total EFW flow indication is 510 gpm.
- Current Parameters Value Trend RCS Temperature 51 5°F Lowering RCS Pressure 1600 psig Lowering Pressurizer Level 30 inches Lowering RB Pressure 1.5 psig Rising OTSG 1A Pressure 850 psig Lowering OTSG 16 Pressure 415 psig Lowering OTSG 1A Level 5%
Rising OTSG 16 Level 6 inches Lowering Based on these conditions, identify the ONE selection below that describes the HIGHEST PRIORITY action(s) to be performed by the Control Room team and identify the applicable section of EOP-IO.
A. Isolate the affected OTSG using Rule 3, XHT, B. Reduce RCS subcooled margin using Rule 6, PTS.
C. Raise Pressurizer level using Guide 9, RCS Inventory Control.
D. Reduce EFW flow using Guide 15, EFW Actuation Response.
SRO 03-1 NRC Exam Three Mile Island Nuclear Station May 2005 Written Examination Answer Key 001 c.
002 c.
003 A.
004 B.
005 D.
006 A.
007 s: B 008 D.
009 C.
010 C.
011 B.
012 B.
013 C.
014 A.
015 A.
016 B.
017 C.
018 D.
- m--k-020 D.
021 B.
022 A.
023 D.
024 X A 025 C.
026 A.
027 C.
028 D.
029 C.
030 B.
031 D.
032 A.
E. JLLt 034 C.
035 B.
036 B.
037 A.
038 B.
039 C.
040 A.
041 A.
042 D.
043 A.
044 D.
045 B.
046 B.
047 c.
048 A.
049 A.
050 C.
051 D.
052 C.
053 B.
054 C.
055 D.
056 D.
057 D.
058 A.
059 D.
060 B.
061 C.
062 B.
063 A.
064 D.
065 D.
066 D.
067 B.
068 D.
069 B.
070 B.
071 C.
072 D.
-07:
- 3. #44?4x 074 D.
075 D.
076 D.
077 D.
078 D.
079 A.
080 D.
081 C.
082 A.
083 A.
084 A.
085 B.
086 D.
087 B.
088 A.
089 A.
090 D.
091 C.
092 A.
093 C.
094 B.
095 A.
096 B.
097 C.
098 D.
099 B.
100 A.