ML072200490
| ML072200490 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 06/26/2007 |
| From: | Carolina Power & Light Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 50-261/07-301 50-261/07-301 | |
| Download: ML072200490 (78) | |
Text
Final Submittal (Blue Paper)
FINAL RO WRITTEN EXAMINATION AND REFERENCES H. B. ROBINSON STEAM ELECTRIC GENERATING PLANT 05000261/2007301 FEBRUARY 5 - 9, 2007 JUNE 26, 2007 (WRITTEN RE-ADMINISTERED)
I ES-401 Site-Specific RO Written Examination
..- Cover Sheet
- Form ES-401-7 U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:
Date:
eo /u lo, Facilitv/Unit: IlD.ICD' I U~ rJ U~ \\TL Region:
10 1100 1I10lVO Reactor Tvoe:
W~ CEO BWO GEO Start Time:
Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least80.00 percent. Examination paperswill be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> afterthe examination begins.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results Examination Value Points Applicant's Score Points Applicant's Grade Percent ES-401, Page 30 of 33
PT-951:
9.5 psig PT-953: 10.5 psig PT-955:10.7 psig HLC-06 NRC Replacement Exam The plant was operating at 100% RTP when a ReactorIrip_and_Main_St~arn~__
Line Break on "A" SG inside the CV occurred.
CV Pressure is presently reading: PT-950: 10.8 psig PT-952:
9.7 psig PT-954: 10.5 psig 1.
Given the following:
Which ONE (1) of the following describes the RCP #1 sealleakoff flow path?
A. Flow path is to the CV Sump.
B. Flow path is to the PRT.
C. Flow path is to the VCT.
D. Flow path is to the RCDT.
1
HLC-06 NRC Replacement Exam 2.
Given the following:
The plant is in Mode 3 at 5470F.
APP-001-A2, SEAL WTR INJ FILTER HI DELTA P, alarms.
lAO reports that seal injection flows are 5 GPM to each RCP and that Seal Injection Filter Delta P is 22 psid.
What actions are required to restore normal conditions for RCP operation lAW APP-001-A2 and OP-301?
A. Place the standby seal injection filter in service and restore flow as stated in the precautions and limitations of OP-301 to 6-13 GPM.
B. Place the standby seal injection filter in service and restore flow as stated in the precautions and limitations of OP-301 to 8-13 GPM.
C. Bypass the seal injection filter and restore flow as stated in the precautions and limitations of OP-301 to 6-13 GPM.
D. Bypass the seal injection filter and restore flow as stated inthe precautions and limitations of OP-301 to 8-13 GPM.
2
HLC-06 NRC Replacement Exam 3.
Given the following:
'"__ The Unit is at 100% RTP.
VCT level transmitter, LT-115, fails HIGH.
Assuming no action by the crew, what impact will this failure have on the Pressurizer Level Control System?
A. PZR level will be maintained at program level due to VCT Auto Makeup System.
8.
PZR level will decrease below the letdown isolation setpoint and valves LCV-460A and 8 will close.
C. PZR level will decrease to the letdown isolation setpoint and valves LCV-460A and 8 will cycle to maintain that level..
D. PZR level will be maintained at program level due to LCV-1158 operation.
3
HLC-06 NRC Replacement Exam 4.
Given the following:
The plant is in Mode 4.
RHR Train "A" is in service.
FCV-605 is set to maintain 3400 GPM.
HCV-758 demand position set at 30%.
The Instrument Air supply line to RHR Heat Exchanger Flow Control Valve HCV-758 becomes severed and is completely detached.
No other air operated valves are impacted by the failure.
Which ONE (1) of the following describes the RHR system parameter changes from the initial steady state conditions? _
A.
B.
C.
D.
Higher Higher Lower Lower 4
Total RHR flow Remains constant Lower Higher Remains constant
e_
HLC-06 NRC Replacement Exam 5.
Initial Conditions:
RCS at 380°F and 650 psig with a plant cooldownJn_progr_es_sJl\\\\(lLGP-OO},
Plant Cooldown from Hot Shutdown to Cold Shutdown.
Current Conditions:
A LOCA has occurred.
Safety Injection was manually initiated (pushbutton) by the RO.
RCS pressure is 90 psig and lowering slowly.
Which ONE (1) of the following describes the status of operating ECCS equipment?
A. SI Accumulator level is lowering; RHR injection flow is zero.
B. SI Accumulator level is stable; RHR injection flow is increasing.
C. SI Accumulator level is stable; RHR injection flow is zero.
D. SI Accumulator level is lowering; RHR injection flow is increasing.
5
HLC-06 NRC Replacement Exam 6.
Given the following:
The plant is at 100% RTP.
"A" Charging Pump is inoperable.
RCS leakage of 120 GPM has been identified from an increasing trend in PRT level.
Letdown was isolated in accordance with AOP-016, Excessive Primary Plant Leakage.
What is the expected response of the following parameters or controllers due to this increase in leakage?
PZR Level A. Cannot be maintained B. Cannot be maintained C. Can be maintained D. Can be maintained VCT Level Cannot be maintained above swapover setpoint Can be maintained above swapover setpoint Cannot be maintained above swapover setpoint Can be maintained above swapover setpoint 6
HLC-06 NRC Replacement Exam 7.
Given the following:
~ -U n i t in Mode 2.
The crew is performing actions of AOP-014, Component Cooling Water System Malfunction, Section D, due to low CCW System flow and rising temperature.
- Which ONE (1) of the following requires tripping the affected RCP?
A. RCP motor bearing temperatures exceed 185°F.
B. RCP pump bearing temperatures exceed 185°F.
C. RCP pump bearing temperatures exceed 200°F.
D. RCP motor bearing temperatures exceed 200°F.
7
HLC-06 NRC Replacement Exam 8.
Given the following:
- ..._ A loss of off-site power has occurred.
The crew has entered PATH-1.
Immediate actions of PATH-1 are complete.
The following parameters are noted:
RCS pressure is 2110 psig.
SG pressures are all 910 psig and lowering slowly.
CV pressure is 0.7 psig and rising slowly.
~~ ~ - ~. --
~
Which ONE (1) of the following describes the CCW Pump indication in the control room?
A. "B" and "C" CCW Pump control switch RED indicating lights are lit.
"A" CCW Pump control switch GREEN and RED indicating lights are extinguished.
B. "A" and "C" CCW Pump control switch RED indicating lights are lit.
"B" CCW Pump control switch GREEN and RED indicating lights are extinguished.
C. "B" and "C" CCW Pump control switch RED indicating lights are lit.
"A" CCW Pump control switch GREEN indicating light is lit.
D. "A" and "C" CCW Pump control switch RED indicating lights are lit.
"B" CCW Pump control switch GREEN indicating light is lit.
8
HLC-06 NRC Replacement Exam 9.
Which ONE (1) of the following states the power supplies to the PZR PORVs PCV-455C and PCV-456 and their associated position indicating lights?
PORVs A. 120 VAC Instrument Busses 1 and 2 B. DC Distribution Panels A and B C. DC Distribution Panels A and B D. 120 VAC Instrument Busses 1 and 2 9
PORV Indication 120 VAC Instrument Busses 1 and 2 120 VAC Instrument Busses 1 and 2 DC Distribution Panels A and B DC Distribution Panels A and B
HLC-06 NRC Replacement Exam 10.
Given the following:
-_ The ReS is on RHR and solid.
RCS pressure is 350 psig.
Preparations to start the initial RCP are in progress.
Which ONE (1) of the following states the SG to RCS Delta T limit and basis for RCP start?
A. 250F; Violation of RCS LTOPP limits.
B. 25°F; Rapid ReS depressurization.
C. 50°F; Violation of RCS LTOPP limits.
D. 500F; Rapid RCS depressurization.
,I 10
HLC-06 NRC Replacement Exam 11.
Given the following:
t,__ The plant is at 100% RTP.
Instrument Bus #2 is on its alternate power supply.
-- - -- -~-
The crew is preparing to transfer Instrument Bus #2 to its normal power supply in accordance with OP-001, Reactor Control and Protection System.
Which ONE (1) of the following describes the plant response during and after the transfer of the power source?
The electrical transfer is.....
A. make before break. The "B" Train safeguards sequencer will require manual reset to restore operability.
B. make before break. Control Room Ventilation will remain in its present state of operation.
C. break before make. The "B" Train safeguards sequencer will be momentarily inoperable.
D. break before make. Control Room Ventilation will shift to the Pressurization Mode when the associated RMS rack is de-energized.
11
HLC-06 NRC Replacement Exam
- 12. '
Given the following:
- _ The crew is currently in GP-005, Power Operation, and Rower has been stabilized at 8% with the turbine rolling at synchronousspeed:-
Reactor power indicates the followinq:
IR N 2 X1 0-5 amps.
IR N 2 X1 0-5 amps.
PR N 8%.
PR N-42 -7%.
PR N-43 -7%.
PR N-44 -7%.
Inverter A output breaker trips open.
Which ONE (1) of the following describes the effect on the unit?
A. A reactor trip due to the de-energization of Intermediate Range Channel N-36.
B. Reactor does NOT trip; Power Range Rod Stop signal received on N-42.
C. A reactor trip due to the de-energization of Intermediate Range Channel N-35.
,I D. Reactor does NOT trip; Power Range Rod Stop signal received on N-41..
12
HLC-06 NRC Replacement Exam 13.
Which ONE (1) of the following describes the plant parameters required to initiate the Degraded Grid Protection scheme for the 480 Volt Emergency Busses?
A.
< 440 Volts for 10 seconds as sensed by 2/3 relays.
B. < 440 Volts for 10 seconds as sensed by 1/2 relays.
C. < 430 Volts for 10 seconds as sensed by 2/3 relays.
D. < 430 Volts for 10 seconds as sensed by 1/2 relays.
13
HLC-06 NRC Replacement Exam 14.
Given the following:
The plant is operating at100% RTP.
~
Due to a loss of Containment HVAC, Containment temperature has risen from 970F to 119°F.
If the temperature continues to rise in Containment, which ONE (1) of the following describes the effect on Pressurizer level indication and controls?
LT-459, PZR Level channel, will indicate.....
A. lower than actual level and will cause charging pump speed to initially increase to restore indicated level to program.
B. higher than actual level and will cause charging pump speed to initially decrease to restore indicated level to program.
C. lower than actual level, which results in a continuous level deviation signal that drives the charging pump to maximum speed.
D. higher than actual level, which results in a continuous level deviation signal that drives the charging pump to minimum speed.
,I 14
HLC-06 NRC Replacement Exam 15.
Given the following:
The plant is at 100% RTP.
CV Spray Pump "A" is being run for surveillance testing.
The following alarm is received:
- APP-002-E1, CV SRY PMP COOL WTR La FLOW Which ONE (1) of. the following describes the condition present, and the action required?
The alarm indicates that CCW flow to CV Spray Pumps is less than......
A. 7 GPM. Stop CV Spray Pump "A".
B. 7 GPM. Identify the source of the problem by isolating CCW to each CV Spray Pump one at a time.
C. 30 GPM. Stop CV Spray Pump "A".
D. 30 GPM. Identify the source of the problem by isolating CCW to each CV Spray Pump one at a time.
15
HLC-06 NRC Replacement Exam 16.
Given the following:
~ - - ~ ~- The plant is at 100% RTP with all systems in normal aliglJments.~~~~
The RO has recently performed a small dilution for Tavg control.
The following indications are noted in the Control Room:
Power Range Nls are increasing.
Tavg is decreasing.
Steam flow and feed flow are slightly elevated.
Power Limit Warning alarm on ERFIS has been received.
Reactor power is 100.3% and rising slowly.
Which ONE (1) of the following describes the event in progress and the action required?
A. Main steam line leak; reduce power by reducing turbine load as necessary.
B. Inadvertent RCS dilution; reduce power by inserting control rods.
C. Main steam line leak; trip the reactor and enter PATH-1, Reactor Trip Or Safety Injection.
D. Inadvertent RCS dilution; trip the reactor and enter PATH-1, Reactor Trip Or Safety Injection.
16
HLC-06 NRC Replacement Exam 17.
Given the following:
The plant is at 68% RTP.
"A" Main Feedwater Pump trips.
Condensate and Heater Drain Pumps are in a normal lineup..
AOP-010, Main Feedwater / Condensate Malfunction, has been implemented.
Which ONE (1) of the following actions is required in accordance with AOP-01O?
A. Trip the reactor and enter PATH-1.
B. Reduce turbine load at 1% to 5% per minute using Attachment 1 until reactor power is less than 60%.
C. Reduce turbine load using load limiter until reactor power is less than 50%.
D. Verify Feedwater Regulating valves respond as required and SG levels are maintained on program. Maintain power at 68%.
17
HLC-06 NRC Replacement Exam 18.
Given the following:
The plant is at 30% RTP and stabilized for seconc:lClry~~rnJstryl~iHJlr~rnents.
08T-401-1 is in progress with "A" EDG loaded at 2500 KW.
The running Main Feedwater Pump trips.
8G NR levels are currently 36% in all 8Gs.
Which ONE (1) of the following describes the operation of the MDAFW Pumps?
A. No MDAFW Pumps are running.
B. "B" MDAFW Pump is running.
C. "A" and "B" MDAFW Pumps are running.
D. "A" MDAFW Pump is running.
18
HLC-06 NRC Replacement Exam 19.
Given the following:
-.- The plant is in Hot Standby (MODE 3).
"A" MDAFW pump is running.
A break occurs between valve FCV-1424, MDAFW PUMP "A" FLOW CONTROL VALVE, and AFW-V2-16B, AFW HEADER DISCH TOSG "B".
The control board operator closes valve FCV-1424.
A clearance is hung to isolate the break from all water sources.
Which ONE (1) of the following describes an outcome of this event?
AFW flow from the Steam Driven AFW pump will be available to (1) and MDAFW Pump "A" will be available to (2)
A.
(1) all S/Gs; (2)"A" and "C" S/Gs ONLY.
B.
(1) "A" and "C" S/Gs ONLY; (2) "A" and "C" S/Gs ONLY.
C.
(1) all S/Gs; (2) NO S/Gs.
D.
(1) "A" and "C" S/Gs ONLY; (2) NO S/Gs.
19
HLC-06 NRC Replacement Exam 20.
Given the following:
. --.----The plant.is at50%.RTP. _
SDAFW Pump is OOS and will be returned to service in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
A loss of 480V Bus E-1 and a controller failure on "A" Feedwater Regulating valve causes a reactor trip.
480V Bus E-1 has a fault and cannot be energized.
The crew is performing actions of PATH-1.
SPDS has been reset.
"B" MDAFW Pump has started but FCV-1425 has dual indication in the Control Room and local inspection reveals that the valve is physically bound at 20%
open.
"B" MDAFW Pump flow is 200 GPM.
All SG NR levels are at 5% and lowering.
Which ONE (1) of the following describes the status of the Secondary Heat Sink CSF Status Tree and the actions that will establish Secondary Heat Sink?
A. A Red Path exists on Secondary Heat Sink; AFW flow is NOT adequate to restore Secondary Heat Sink.
B. A Red Path exists on Secondary Heat Sink; AFW flow is adequate to restore Secondary Heat Sink.
C. A Red Path does NOT exist on Secondary Heat Sink; AFW flow is adequate to maintain Secondary Heat Sink.
D. A Red Path does NOT exist on Secondary Heat Sink; AFW flow is NOT adequate to maintain Secondary Heat Sink.
20
HLC-06 NRC Replacement Exam 21.
VYhich ONE (1) of the following describes the 4160 Volt power supplies to the "A and "B" RCPs?
-~-- --- --
- ~~- --- -
Bus 1 Bus 2 B.
Bus 2 Bus 4 C.
Bus 1 Bus 4 D.
Bus 2 Bus 1 21
HLC-06 NRC Replacement Exam 22.
Given the following conditions:
The unit is at 100% RTP. -
Battery Charger 'A' is supplying Battery 'A' and its associated DC Bus loads.
Annunciator APP-036-D1 IBATT CHARGER AlA 1 TROUBLE' has just alarmed.
The AO reports the cause of the trouble is a ground on DC Bus IA'.
Based upon visual inspection, the AO believes the ground may be on Battery IA'.
Engineering recommends that Battery lA' be disconnected from DC Bus IA'.
Which ONE (1) of the following describes the appropriate action while attempting to isolate the ground lAW APP-036-D1?
A. Supply the lA' DC Bus with the lA' Battery Charger because it is the preferred supply lAW OP-601, DC Supply System.
B. Supply the 'A' DC Bus with the IA-1' Battery Charger because it is the preferred supply lAW OP-601, DC Supply System.
.1 C. Supply the lA' DC Bus with the 'A' Battery Charger because it has the capability to stand alone to supply DC Bus lA' while disconnected from Battery IA'.
D. Supply the 'A' DC Bus with the IA-1 ' Battery Charger because it has the capability to stand alone to supply DC Bus lA' while disconnected from Battery 'A'.
22
HLC-06 NRC Replacement Exam 23.
Given the following:
-- - A reactor trip hasoccurred.____
The crew is performing IMMEDIATE ACTIONS of PATH-1.
SI is actuated.
52/18B, 480V Bus E-1 Normal Supply Breaker, shows GREEN breaker indication.
60 seconds following SI actuation, the RO reports that Bus E-1, Instrument Bus 1 and MCC-5 are de-energized and the EDG "A" white START light is NOT lit.
There is NO indication of a bus fault.
Which ONE (1) of the following describes the action required lAW PATH-1?
A. Energize MCC-5 from the DS Bus iAW Foldout "A" to restore power for starting the EDG. All loads required for SI sequence will be automatically started in sequence when Bus E-1 is energized.
B. Place Instrument Bus 1 on its alternate supply lAW Foldout "A" to restore power for starting the EDG. All loads required for SI sequence must be manually started.
C. Start EDG "A" and close its output breaker. Instrument Bus 1 and MCC-5 will re-energize when Bus E-1 energizes. All loads required for SI sequence will be automatically started in sequence.
D. Start EDG "A" and close its output breaker. Transfer Instrument Bus 1 to MCC-8 and MCC-5 to the DS Bus lAW Foldout 'A". All loads required for SI sequence must be manually started.
23
HLC-06 NRC Replacement Exam 24.
Given the following:
T he plant is at 100% RTP.
An approved radioactive liquid waste release is in progress.
Which ONE (1) of the following correctly describes plant response if detector high voltage is lost to RMS Monitor R-18, Liquid Effluent Waste Disposal?
A. APP-036-E7 uRAD MONITOR TROUBLE" actuates and the release automatically terminates.
B. APP-036-E7 RAD MONITOR TROUBLE" actuates and the release continues.
C. Local Waste Disposal Panel alarm actuates and the release automatically terminates.
D. Local Waste Disposal Panel alarm actuates and the release continues.
,I 24
HLC-06 NRC Replacement Exam 25.
Given the following:
A Reactor Trip has occurred.
30 seconds following the trip, Service Water pressure is 31 psig and slowly decreasing.
40 seconds following the decrease of Service Water pressure, Safety Injection actuates.
Which ONE (1) of the following describes the status of the Service Water System?
Service Water to the Turbine Building will isolate...
A. 60 seconds after the Reactor Trip.
B. 60 seconds after Service Water pressure decreases below 31 psig.
C. immediately upon Service Water pressure decreasing below 31 psig.
D. immediately upon the Safety Injection actuation.
25
HLC-06 NRC Replacement Exam 26.
Upon a loss of Instrument Air, what is the expected response of the MSIVs ?
A. The MSIVs will remain open due to the Nitrogen backup source that is automatically__ ~_
provided to the MSIVs upon a loss of Instrument Air.
B. The MSIVs will remain open due to the check valves in the Instrument Air lines and valve accumulators that ensure an extended air source to each MSIV.
C. The MSIVs will close once Instrument Air system header pressure decays to 80 psig.
D. The MSIVs will close once Instrument Air system header pressure decays to 60 psig.
. 1 26
HLC-06 NRC Replacement Exam 27.
Given the following:
Mode 1 at 100% RTP.
- -~ --~
APP-002-B7, CV NAR RANGE HI/LO PRESS illuminates.
CV Pressure indicates - 0.4 psig and lowering slowly.
Which ONE (1) of the following describes the action necessary to clear the alarm lAW OP-921, Containment Air Handling?
A. Open Containment Pressure Relief Valves V12-1 Oand V12-11 until pressure is restored.
B. Stop HVH-1 and HVH-3 to increase CV pressure gradually.
C. Open Containment Vacuum Relief Valves V12-12 and V12-13 until pressure is restored.
D. Start CV Purge to equalize the CV pressure with atmospheric pressure.
27
HLC-06 NRC Replacement Exam 28.
Given the following conditions:
Mode 1 at 100% RTP.
PLP-118, Hot Weather Operations, is in effect.
CV temperature is 118°F and has been rising over the past several days.
CV Purge has been initiated and you have been instructed to open the normal suction dampers on the HVH units to assist in controlling CV temperature rise.
What controls are available to reposition the normal suction dampers to the HVH units lAW OP-921, Containment Air Handling?
A. HVH Unit normal suction dampers are controlled by placing the HVH unit Local /
Remote control switch to LOCAL.
B. HVH Unit normal suction dampers are controlled by key switches mounted on the Auxiliary Relay Racks.
C. Removing and re-installing the HVH Unit breaker control power fuses will open the normal suction dampers.
D. Starting the HVH Unit will cause the normal suction dampers to open.
28
29.*
HLC-06 NRC Replacement Exam Unit has been reduced to 75% RTP due to N-41 inoperable from a power supply failure.
--N-41 has been removed from service lAW OWP-O-Lt,-NbJ. - -
All remaining controls are in Automatic.
The operator inadvertently adds 30 gallons of boric acid to the ReS instead of 3.0 gallons as he intended.
What effect will this have on the Rod Control system?
A. Rods will step out to maintain Tave within 1°F of Tref.
B. Rods will NOT step out due to procedural actions taken for N-41 being inoperable.
C. Rods will step out initially due to the rate circuit seeing a step change in power.
D. Rods will NOT step out due to defeat of the AUTO rod withdrawal circuitry.
29
30.
HLC-06 NRC Replacement Exam During a power increase in accordance with GP-005, Power Range Nls and Calorimetric power indicate 28% power.
-'---~~-----
Which ONE (1) of the following is the expected RCS Core Delta T for the indicated power level?
A. 8.1°F B. 8.7oF C. 16.1oF D. 21°F 30
HLC-06 NRC Replacement Exam 31.
Given the following:
Mode 1 at 100% RTP.
PZR level transmitter LT-459 fails LOW and has been removed from service lAW OWP-030, PLT-1.
PZR level channel selector switch LM-459 is selected to "461 REPL 459".
Which ONE (1) of the following describes the function provided by PZR level transmitter LT-461 with the level channel selector switch LM-459 selected to "461 REPL 459"?
A. Provides control input for PZR low level letdown isolation to allow letdown restoration and prevent isolation at 14.4% PZR level.
B. Provides control function to de-energize the Backup Group heaters upon 5% level deviation.
C. Provides control input for PZR low level letdown isolation to allow letdown restoration to prevent exceeding 63.3% PZR level.
D. Provides control function to energize the Control Group heaters upon 5% level deviation.
31
HLC-06 NRC Replacement Exam 32.
Which ONE (1) of the following describes the effect of depressing the Rod Control START-UP pushbutton on the RTGB?
Resets...
A. Group Step Counters and P-A Converter ONLY.
B. Group Step Counters and Bank Overlap Unit ONLY.
C. Bank Overlap Unit and P-A Converter ONLY.
D. Group Step Counters, Bank Overlap Unit, and P-A Converter.
32
HLC-06 NRC Replacement Exam 33.
Which ONE (1) of the following describes an alternate location for reading Core Exit Thermocouple temperatures lAW GP-008?
_.~-
A. Charging Pump Room Dedicated Shutdown Panel meter indication.
B. Charging Pump Room Dedicated Shutdown Panel via M&TE connections in panel.
C. Rod Control Room meter indication.
D. Rod Control Room via M&TE connections in panel.
33
e-HLC-06 NRC Replacement Exam 34.
Which ONE (1) of the following lists the correct power supplies for HVE-3 and HVE-4, CV Iodine Removal Unit fans?
A. MCC-2 and MCC-3. :
B. MCC-10 and MCC-9.
C. MCC-5 and MCC-6.
D. 480V Bus 2B and 3.
e
.1 34
HLC-06 NRC Replacement Exam 35.
Given the following:
. Mode 1 at 1000/0 RTP.
--~
_-- - - -- - ~-----.---.~---~---------..-._--
LT-496, Steam Generator "C" Narrow Range Level transmitter, fails LOW.
Which ONE (1) of the following provides the plant response to this failure if no operator actions are taken?
A "C" FRV will OPEN and a turbine trip will occur at 60% S/G level.
B.
"C" FRV will OPEN and a turbine trip will occur at 75% S/G level.
C.
"C" FRV will CLOSE and a reactor trip will occur at 30% S/G level.
D.
"C" FRV will CLOSE and a reactor trip will occur at 16% S/G level.
35
HLC-06 NRC Replacement Exam 36.
Which ONE (1) of the following describes the MINIMUM condition(s) required to initiate CV Vent~ation I~olat~~~?
Note:
R-2, Containment radiation monitor.
R-11, Containment Particulate radiation monitor.
R-12, Containment Noble Gas radiation monitor.
R-14C, Main Vent Stack (Low Range Noble Gas) radiation monitor.
A. R-2 OR R-14C in ALARM status.
B. R-2 AND R-14C in ALARM status.
C. R-11 OR R-12 in ALARM status.
D. R-11 AND R-12 in ALARM status.
- 1 36
e -
HLC-06 NRC Replacement Exam 37.
Given the following:
- ---The-plant-is-at-62%-power-during a load increase.-
The following alarm is received:
APP-007-A2, CONO PMP B MOTOR OVLOrrRlp*
The BOP operator determines that "B" Condensate Pump has tripped.
"A" Condensate Pump is running.
"A" and "B" Main Feed Pumps are running.
Feed Pump suction pressure is approximately 350 psig and lowering slowly.
The crew enters AOP-010, Main Feedwater/Condensate Malfunction.
Which ONE (1) of the following describes the actions required in accordance with AOP-010?
A. Trip the reactor and enter PATH-1.
B. Maintain power stable and check that SG level is at or trending to program.
C. Trip ONE (1) Main Feed Pump and then initiate a plant load reduction to less than 50% power.
O. Trip ONE (1) Main Feed Pump and then initiate a plant load reduction to less than
,I 60% power.
37
HLC-06 NRC Replacement Exam 38.
Given the following:
-- -- The plant is operating at 100% RTP.
The following radiation monitors go into alarm:
R-15, Condenser Air Ejector Gas Monitor R-19A, SG Sample Radiation Monitor R-37, Condensate Polisher Waste Effluent Monitor All other Radiation Monitors are normal.
Which ONE (1) of the following describes the plant response to these indications?
A. FCV-1933A and B, SG A Blowdown Sample Isolation Valves, CLOSE.
RCV-10549, Condensate Polisher Discharge to storm drains, CLOSES.
B. Condensate Polishing Building sump pumps TRIP.
V1-31, Blowdown Isolation Valve to catch basin, CLOSES.
C. V1-31, Blowdown Isolation Valve to catch basin, CLOSES.
RCV-10549, Condensate Polisher Discharge to storm drains, CLOSES.
D. FCV-1933A and B, SG A Blowdown Sample Isolation Valves, CLOSE.
Condensate Polishing Building sump pumps TRIP.
38
HLC-06 NRC Replacement Exam 39.
Given the following:
"A" and "C" SI Pumps are TRIPPED.
RCS pressure is 1250 psig.
CV pressure is 13 psig.
All other equipmentis operating per design.
The crew is performing actions of PATH-1.
Which ONE (1) of the following describes the required action and reason for the action with respect to the RCPs?
A. Leave all RCPs running to prevent phase separation of RCS liquid.
B. Stop all RCPs to minimize fluid mass loss out of the break.
C. Leave all RCPs running to provide forced cooling flow of the RCS.
.D. Stop all RCPs to prevent mechanical damage to the pump and motor.
39
HLC-06 NRC Replacement Exam 40.
Given the following:
... - --- -A loss ofoff-site power occurred-15-minutes ago.-~-.
The crew is performing EPP-4, Reactor Trip Response.
The crew is verifying Natural Circulation in accordance with Supplement E.
RCS pressure is 2100 psig and stable.
SG pressures are all at 1000 psig and stable.
RCS Thot is 586°F and trending down.
RCS Tcold is 5520F and trending down.
Core Exit Thermocouple temperature is 5910F and trending down.
Which ONE (1) of the following describes the status of Natural Circulation verification, and the trend of RCS temperature over the next 60 minutes?
The Natural Circulation criteria in Supplement E is...
A. met; RCS Core Delta T will lower as decay heat load is reduced.
B. met; RCS Core Delta T will continue to rise, providing additional driving head for Natural Circulation flow.
C. NOT met; RCS Core Delta T will lower as decay heat load is reduced.
D. NOT met; RCS Core Delta T will continue to rise as Natural Circulation is established.
40
HLC-06 NRC Replacement Exam
Unit 2 isat-*1 OO%-fi:rR.---
--- --.---.~
All control systems are in normal alignments.
Charging flow has been rising and is currently at 50 GPM.
Letdown temperature downstream of the Regenerative Heat Exchanger has lowered slightly from its steady state value.
VCT level is lowering.
RCS temperature is stable.
41.
Given the following:
Which ONE (1) of the following describes the location of the RCS leak and the action required by AOP-016, Excessive Primary Plant Leakage?
A. RCS leak is from the charging line downstream of the Regenerative Heat Exchanger.
Isolation of charging is NOT required to isolate the leak.
B. RCS leak is from the charging line downstream of the Regenerative Heat Exchanger.
Isolation of charging is required to isolate the leak.
C. RCS leak is from the charging line upstream of the Regenerative Heat Exchanger.
Isolation of charging is required to isolate the leak.
D. RCS leak is from the charging line upstream of the Regenerative Heat Exchanger.
Isolation of charging is NOT required to isolate the leak.
41
-~- - - - - -
HLC-06 NRC Replacement Exam The plant is in Mode-5;- -
"A" RHR Pump is in service.
Reduced Inventory operations are in progress.
RCS level has been slowly lowering and indicates-74 inches.
RHR flow and "A" RHR Pump discharge pressure begins oscillating.
The crew enters AOP-020, Loss of Residual Heat Removal.
42.
Given the following:
Which ONE (1) of the following describes the FIRST action required in accordance with AOP-020?
A. Stop "A" RHR Pump.
B. Isolate Letdown.
C. Start all available Charging pumps.
D. Allow "A" RHR Pump to continue to run, but decrease RHR flow to stabilize oscillations.
42
C--.._
HLC-06 NRC Replacement Exam 43.
Which ONE (1) of the following describes the indication that will exist if there is a tube I~ak~~_the NOn-Regene ~ativeHeat Exchanger?
A. Letdown flow will increase; B. TCV-143, VCT/Demineralizer Diversion valve, will automatically divert to the VCT.
C. PCV-145, LETDOWN, will open to maintain letdown pressure.
D. Letdown flow will decrease.
43
HLC-06 NRC Replacement Exam 44.
Which ONE (1) of the following Pressurizer Pressure Control System malfunctions will cause Pressurizer Saturation Temperature to RISE?
A. PZR Pressure transmitter, PT-444, fails HIGH.
B. PZR Master Pressure Controller (PC-444J) setpoint fails LOW.
C. PZR Master Pressure Controller (PC-444J) output fails LOW.
D. PZR Pressure transmitter, PT-445, fails HIGH.
,I 44
HLC-06 NRC Replacement Exam 45.
Given the following:
An ATWS-has-occurred.
Actions of FRP-S.1 are in progress.
The RO is inserting control rods.
Which ONE (1) of the following describes a subset of local actions required by procedure FRP-S.1?
A. Open Reactor Trip Breakers in the South Cable Vault.
Open Rod Drive MG Set supply breakers in the South Cable Vault.
B. Open Reactor Trip Breakers in the 4160V Switchgear Room.
Open Rod Drive MG Set supply breakers in the 4160V Switchgear Room.
C. Open Reactor Trip Breakers in the South Cable Vault.
Open Rod Drive MG Set supply breakers in the 4160V Switchgear Room.
D. Open Reactor Trip Breakers in the 4160V Switchgear Room.
Open Rod Drive MG Set supply breakers in the South Cable Vault.
45
HLC-06 NRC Replacement Exam 46.
Given the following:
- --- The crew-is performing actionsof-FRP-H.1, Response-to Loss -of-Secondary-Heat Sink.
RCS bleed and feed is in progress.
Auxiliary Feedwater capability is restored.
All SGs indicate approximately 8% Wide Range level and approximately 50 psig.
Which ONE (1) of the following describes the strategy used to re-establish feed under these conditions?
Feed at least ONE (1) SG to....
A. ensure RCS cooldown rates are established within Technical Specification limits.
B. establish a heat sink to allow subsequent termination of RCS bleed and feed when subcooling requirements are met.
C. minimize thermal shock to SG components.
D. allow termination of RCS bleed and feed due to RWST Inventory concerns.
,I 46
HLC-06 NRC Replacement Exam 47.
Given the following:
--- A StationBlackout.has.occurred.Lc....
The crew is performing actions of EPP-1, Loss of All AC Power.
The CRSS has directed performance of OP-603 Section 8.4.2, "Restoration of Normal Power After Loss of All A.C. Power and Turbine Trip with DSDG Operating."
STARTUP TRANSF ENERGIZED White light on RTGB is illuminated.
Which ONE (1) of the following describes the relay(s) that must be RESET by the crew prior to re-energizing the plant electrical busses, in accordance with OP-603?
A. 115 KV Span Bus Lockout Relays.
B. Main Generator Primary and Backup Lockout Relays.
C. Station Service Transformer to 480V Bus E-2 Overcurrent Relay.
D. Startup Transformer to 4160V Bus 2 Breaker Overcurrent Relay.
47
HLC-06 NRC Replacement Exam 48.
Initial Plant Conditions:
. --- ----The plant-was at-l OO%-RTP.-
"A" lAC was running in MANUAL, with "B" lAC in Standby.
"0" lAC and the Primary Air Compressor are UNAVAILABLE.
Current Plant Conditions:
A loss of off-site power has occurred.
All equipment has responded as designed.
NO actions have been taken by the operating crew.
Which ONE (1) of the following is the setpoint for operation of the in-service air compressor, and the indication currently observed on PI-1702, Instrument Air Header Pressure?
A.
B.
C.
D.
Loading/Unloading Setpoints 98 -102 psig 98 -102 psig 90 -105 psig 90 -105 psig 48 Current Pressure Decreasing Stable Decreasing Stable
HLC-06 NRC Replacement Exam 49.
Given the following:
.. -* *--T h e* p l an t-i s-at*-75%~RT P-;~
A loss of Instrument Bus #1 has occurred.
The crew is responding in accordance with AOP-024, Loss of Instrument Bus.
A fault on the transfer switch prevents IB #1 from being transferred to its alternate power source.
Which ONE (1) of the following describes the effect on Pressurizer Pressure Control, and the action required?
A. Pressurizer Backup Group Heater control is lost. Backup Heaters cannot be operated from remote or local control stations.
B. Pressurizer Backup Group Heater control is lost. Backup Heaters can be operated from the local control stations.
C. The Pressurizer Pressure Controller, PC-444J, fails HIGH. Close RC-536 block valve to isolate the open PZR PORV.
D. The Pressurizer Pressure Controller, PC-444J, fails HIGH. PZR Pressure Control must be established by manual operation of PZR heaters and spray valves.
,i 49
HLC-06 NRC Replacement Exam 50.
Given the following:
...--- The Unit is in Mode 1 in a normal electrical lineup. ----
The following alarms are received:
- APP-036-D2, BATT CHARGER B/B-1 TROUBLE
- APP-036-D3, BATT AlB LO VOLT DC Bus "B" voltage is 120V DC and decreasing slowly.
Which ONE (1) of the following describes the status of the DC Bus and Battery Charger "B" ?
Battery Charger "B" has.....
A. tripped. Battery Charger "B-1" will be placed in service with the float / equalize switch set in the float position.
B. tripped. Battery Charger "B-1" will be placed in service with the float / equalize switch set in the equalize position.
C. not tripped. Operator will adjust Battery Charger "B" potentiometer equalize setting to raise voltage.
D. not tripped. Operator will adjust Battery Charger "B" potentiometer float setting to raise voltage.
50
HLC-06 NRC Replacement Exam 51.
Given the following:
--- The plant was at 100% RTP when a Loss of Service Water occurred.
A reactor trip was initiated due to loss of all Service Water Pumps.
While performing PATH-1, the following conditions are observed:
RCS pressure is 1700 psig and lowering.
Pressurizer level is 6% and lowering.
Containment pressure is 0.4 psig and stable.
SG pressures are 700 psig and lowering.
SWBP suction pressure is 12 psig.
The crew takes all required actions.
Which ONE (1) of the following describes the status of the Service Water Booster Pumps (SWBPs) based on these conditions?
A. SWBPs start but then trip because of low suction pressure.
B. SWBPs start and remain running.
C. SWBPs receive a start signal but do not start because of low suction pressure.
D. SWBPs do not start because they do not receive a start signal.
51
HLC-06 NRC Replacement Exam 52.
The unit is in Mode 1 at 100% RTP.
___ During a complete loss of Instrument Air pressure, which ONE(1) of the.Jollowinqwill, be the FIRST to reach its RPS trip setpoint?
A. PZR Level B. SG Level C. PZR Pressure D. Turbine Trip 52
HLC-06 NRC Replacement Exam 53.
Given the following:
A LOCA outside containment has occurred.
The crew is performing the actions in EPP-20, LOGA-Outside Containment.
Auxiliary Building radiation levels are lowering.
Safety Injection flow is 80 GPM and decreasing.
PZR level is off scale LOW.
RCS pressure is 1450 psig and rising.
Which ONE (1) of the following criteria dictates the leak status lAW EPP-20?
The leak is.....
A. isolated because RCS pressure is increasing.
B. isolated because Auxiliary Building radiation levels are lowering.
C. NOT isolated because SI pump flow still exists.
D. NOT isolated because PZR level is not on scale.
.1 53
HLC-06 NRC Replacement Exam 54.
Given the following:
- - -A loss of BOTH Main Feedwater Pumps has resultedlnareactcr.trlp.
A blockage in the AFW supply line from the CST has lead to all 3 AFW Pumps being disabled.
The crew is performing actions of FRP-H.1, Loss of Secondary Heat Sink.
PCV-1716, INSTRUMENT AIR ISO TO CV, has failed closed and will not open.
Wide Range SG levels are at 25% and decreasing.
Which ONE (1) of the following describes the operation of the PZR PORVs, if needed, during this event?
A. NOT required. PZR Spray valves will be used to depressurize the RCS so that Hi Steam Line DP and PZR Pressure SI signals can be blocked prior to performing action to establish Condensate flow.
B. Required. PZR PORVs will be used to depressurize the RCS so that Hi Steam Line DP and PZR Pressure SI signals can be blocked prior to performing action to establish Condensate flow.
C. NOT required. Bleed and feed cooling will not be required as long as 8% WR S/G level is maintained.
D. Required. ONE (1) PZR PORV will be opened to establish bleed and feed cooling.
54
HLC-06 NRC Replacement Exam 55.
Given the following:
~
A LOCA has occurred.
Due to subsequent RHR system failures, the crew is performing EPP-15, Loss of Emergency Coolant Recirculation.
APP-002-A3, RWST HI/LO LVL, is extinguished.
The RO is evaluating Containment Cooling requirements.
Containment pressure peaked at 27 psig and is presently 8 psig and lowering.
Which ONE (1) of the following describes the action taken with respect to the CV Spray Pumps? (REFERENCE PROVIDED)
A. BOTH pumps may be stopped to conserve RWST inventory, since Containment Fan Coolers are adequate for the current conditions.
B. BOTH CV Spray pumps must remain in operation to provide Containment cooling function.
C. ONE (1) CV Spray pump is required to be stopped, with ONE (1) remaining in service until CV pressure is below 4 psig.
D. ONE (1) CV Spray pump is required to be stopped, with ONE (1) remaining in service to ensure minimum safeguards until a recirculation flowpath can be restored.
55
HLC-06 NRC Replacement Exam 56.
Given the following:
_=__ The crewis re§QQD9iOg t~aSt~C!.IJ1_Lin~ BreakJD~ Lde the _CV:
Due to equipment failures, EPP-16, Uncontrolled Depressurization of All Steam Generators, is in progress.
RCS cooldown rate was 1180F in the last 60 minutes.
Which ONE (1) of the following describes the MINIMUM AFW flow for this condition, and the basis in accordance with EPP-16?
A. 80 GPM to ensure adequate secondary heat sink to maintain natural circulation in the RCS.
B. 300 GPM to ensure adequate secondary heat sink to maintain natural circulation in the RCS.
C. 80 GPM to ensure components remain wet so that thermal stresses are minimized upon a feed flow increase.
D. 300 GPM to ensure components remain wet so that thermal stresses are minimized upon a feed flow increase.
56
HLC-06 NRC Replacement Exam 57.
Given the following:
.The plant is at 95% RTP.
_.~
While withdrawing Control Bank D rods to maintain Tave, Rod H12 continues to withdraw.
When the rod motion is stopped, the rod is 18 steps above the remainder of Control Bank D.
APP-005-F3, PR UPPER CH HI FLUX DEV / AUTO DEFEAT is ILLUMINATED.
QPTR has been calculated at 1.028.
Which ONE (1) of the following states the power limitation or reduction for this condition?
A. Power is limited to 97.6% RTP.
B. Power must be reduced to 92.6% RTP.
C. Power must be reduced to 91.6% RTP.
D. Power must be reduced to 86.6% RTP.
57
HLC-06 NRC Replacement Exam 58.
Which ONE (1) of the following describes the function of the Intermediate Range Level
. Trip Bypass Switch on the Intermediate Range NI cabinets?
A. Bypasses the Intermediate Range High Flux Reactor Trip ONLY. Placed in BYPASS for testing ONLY.
B. Bypasses the Intermediate Range High Flux Reactor Trip ONLY. Placed in BYPASS for testing OR for channel failures.
C. Bypasses the Intermediate Range Rod Stop and Intermediate Range High Flux Reactor Trip. Placed in BYPASS for testing ONLY.
D. Bypasses the Intermediate Range Rod Stop and Intermediate Range High Flux Reactor Trip. Placed in BYPASS for testing OR for channel failures.
-1 58
HLC-06 NRC Replacement Exam 59.
Which ONE (1) of the following Radiation Monitoring System monitors could cause a potential unanalyzed radioactive release directly to Lake Robinson if its alarm setpoint
-- is set in a non-conservative direction? ---
- -------- - ~-~--~__._..
A. R-17, Component Cooling Water.
R-18, Waste Disposal - Liquid.
S. R-18, Waste Disposal-Liquid.
R ~19C, Steam Generator Slowdown.
C. R-19C, Steam Generator Slowdown.
R-37, Condensate Polisher Liquid Waste.
D. R-17, Component Cooling Water.
R-37, Condensate Polisher Liquid Waste.
59
HLC-06 NRC Replacement Exam 60.
Given the following:
- - -- ---The plant is at 1OO%BTP.
The following alarm is received on the FAC:
-.-- ---~~ - --..-----
APP-044-A72, ZN.,3 FIRE ALARM TRN-B Safety Injection Pump Room The CRT alarm text display is RED.
Which ONE (1) of the following conditions exists, and the action required?
A. An open or faulty circuit exists at the transceiver. Notify the Fire Incident Commander and initiate action to correct the fault.
B. An open or faulty circuit exists at the transceiver. Dispatch a Fire Brigade AO to the area to determine the cause.
C. A valid fire alarm exists. Dispatch a Fire Brigade AO to the area to determine the cause.
D. A valid fire alarm exists. Activate the Fire Brigade to initiate fire fighting activities.
,j 60
HLC-06 NRC Replacement Exam 61.
Given the following:
---~"The reactor has tripped.
Safety Injection is actuated.
The crew has transitioned to EPP-7, SI Termination.
Safety Injection is reset.
SI and RHR Pumps have just been stopped.
While aligning the Charging System, PZR level cannot be maintained above 10% with normal charging.
Which ONE (1) of the following is required in accordance with EPP-7?
A. Open the BIT outlet valves and verify letdown valves isolated.
B. Manually initiate Safety Injection and return to PATH-1, Entry Point A.
C. Start BOTH SI pumps and return to PATH-1, Entry Point C.
D. Start BOTH SI pumps and Go to EPP-8, Post LOCA Cooldown and Depressu rization.
61
HLC-06 NRC Replacement Exam 62.
Given the following:
_A Steam GeneratorTubeRupturehas occurrec..__
During the performance of PATH-2, additional failures have occurred.
The crew is performing EPP-17, SGTR with Loss of Reactor Coolant:
Subcooled Recovery.
The CRSS decides to transition to EPP-18, SGTR with Loss of Reactor Coolant:
Saturated Recovery, to address the decreasing RWST inventory.
Which ONE (1) of the following is a requirement for entry into EPP-18?
A. EPP-18 is entered from EPP-17 anytime that saturated conditions are noted in the RCS.
B. EPP-18 is entered from EPP-17 ONLY after the FIRST 26 steps have been completed in EPP-17.
C. EPP-18 can be directly entered from the actions specified in the Inventory YELLOW Path FRPs.
D. EPP-18 can be directly entered from the actions specified in the Core Cooling YELLOW Path FRPs.
- 1 62
HLC-06 NRC Replacement Exam 63.
Given the following:
The reactor has tripped due to a loss of off-site power.
ARCS cooldown to Mode 5 must be performed.
A Natural Circulation cooldown is in progress in accordance with EPP-5,
NATURAL CIRCULATION COOLDOWN.
80TH CRDM Cooling Fans, HVH-5A and 58, are running.
TSC has determined that RCS cooldown must be performed at 50°F/hr.
Which ONE (1) of the following states the correct mitigation strategy and the Technical Specification RCS Cooldown rate limit?
A. Transition to EPP-6; Cooldown limit is 100°F/hr.
8. Transition to EPP-6; Cooldown limit is 60oF/hr.
C. Remain in EPP-5; Cooldown limit is 100°F/hr.
D. Remain in EPP-5; Cooldown limit is 60°F/hr.
,I 63
HLC-06 NRC Replacement Exam 64.
Given the following:
A LOCA has occurred. The crew is performing the actionsotPATH:l.
The following conditions exist:
RCS Pressure is 200 psig.
RCS temperature is 4100F.
SG NR levels are Off-Scale Low.
SG Pressures are 650 psig and trending down.
AFW flow is 450 GPM.
Pressurizer level is Off-Scale Low.
CV Pressure is 43 psig.
SPDS has been reset.
Which ONE (1) of the following procedures will the crew perform next for this event?
A. Continue in PATH-1 for the LOCA.
B. FRP-J.1, Response to High Containment Pressure.
C. FRP-H.1, Response to Loss of Secondary Heat Sink.
D. EPP-16, Uncontrolled Depressurization of All Steam Generators.
64
HLC-06 NRC Replacement Exam 65.
Given the following:
",_ A LOCA_hasoccurred. __ __
The crew has performed actions of PATH-1.
The CRSS has transitioned to FRP-J.2, Response to Containment Flooding.
APP-002-A8, HVH-1 WTR OUTLET LO FLOW, is LIT.
Which ONE (1) of the following actions is required?
A. Refer to AOP-022, Loss of Service Water, to determine the cause of the alarm.
B. Stop HVH-1 and isolate Service Water flow to the cooler as directed by FRP-J.2.
C. Exit FRP-J.2 and isolate Service Water flow to HVH-1 as directed by the APP.
D. Start the Standby Service Water Booster Pump as directed by the APP and verify the alarm condition clears.
,I 65
66.
Given the following:
HLC-06 NRC Replacement Exam
. ~-A plant cooldown.is.In.proqress.
RCS temperature is 357°F.
RCS Pressure is 370 psig.
Both PZR PORV OVERPRESSURE PROTECTION Permissive switches have been placed in LOW PRESSURE position.
Following the switch alignment, the following alarm is received in the control room:.
APP-003-A3, PCV-456 LP PROT ACTITROUB.
Which ONE (1) of the following is the cause of this alarm?
A. RC-535, PORV BLOCK, is open.
B. RCS temperature is too high to place LTOPP in service.
C. RC-535, PORV Block Valve, breaker tripped open.
D. RCS Pressure is too high to place LTOPP in service.
66
HLC-06 NRC Replacement Exam 67.
Which ONE (1) of the following choices contains ONLY personnel allowed to manipulate RTGB controls under the direct supervision of the Reactor Operator at the
_ Controls?
~__
._._~.
A. I & C Technicians during the performance of approved procedures.
Auxiliary Operators that have been selected to enter Initial License class.
B. 1& C Technicians during the performance of approved procedures.
Licensed operators standing watch to reactivate their license.
C. Licensed operators standing watch to reactivate their license.
Instructors enrolled in an approved SRO Certification program.
D. Instructors enrolled in an approved SRO Certification program.
Auxiliary Operators that have been selected to enter Initial License class.
- 1 67
- t HLC-06 NRC Replacement Exam 68.
Given the following:
Reactor tripped from 100% RTP.
ECP has been calculated for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the trip.
Estimated critical rod position is Control Bank 0 at 100 steps.
Startup is delayed for TWO (2) hours.
What is the effect on 11M plot data taken during the approach to critical?
The 11M plot will predict criticality at a.....
A. LOWER rod height due to Xenon concentration less than that assumed in ECP calculation.
B. HIGHER rod height due to Xenon concentration greater than that assumed in ECP calculation.
C. HIGHER rod height due to Xenon concentration less than that assumed in ECP calculation.
D. LOWER rod height due to Xenon concentration greater than that assumed in ECP calculation.
68
HLC-06 NRC Replacement Exam 70.
Given the following:
. --Plant is-in Mode 1 at 100% RTF? -.
Maintenance is preparing to enter the CV and repair steam leak on "A" S/G secondary manway.
CV Pressure Relief is in progress in preparation for purging the CV.
CV pressure is currently at 0.05 psig.
CV Purge Gaseous Waste Release Permit has been issued to Operations to allow the CV Purge to commence.
What is the proper sequence for starting the CV Purge lAW OP-921, Containment Air Handling?
A. Verify closed the CV Pressure Relief and CV Vacuum Relief valves. Start CV Purge by placing the HVE-1A control switch to start.
B. Start CV Purge by placing the HVE-1A control switch to start. CV Pressure Relief valves can be closed after purge flow is established.
C. CV Purge and CV Pressure Relief can be performed concurrently due to both releasing the CV.
D. CV Purge cannot be started until CV pressure is reduced to 0 psig.
70
HLC-06 NRC Replacement Exam 71.
Given the following:
-- ---A Progress Energy employee has received 325-mBem-radiation_dose_at the Robinson Plant this year.
He has not received any Non-Progress Energy dose this year.
He has received no Progress Energy management exposure extensions and no emergency exists.
Which ONE (1) of the following is the additional total effective dose equivalent that the individual can receive this year without management concurrence and without exceeding Progress Energy Annual Administrative Dose Limits?
A. 175 mRem.
B. 1675 mRem.
C. 3675 mRem.
D. 4675 mRem.
71
HLC-06 NRC Replacement Exam 72.
Given the following:
~---The plant has experienced a Reactor Trip and Steam-Line Breakinside.the.Cv.
CV Pressure reached a maximum of 18 psig and has now decreased to 2 psig.
When are adverse setpoints within the EOP network required to be used and when will the operating crew return to the use of normal setpoints as described in OMM-022, EOP Users Guide?
A. CV adverse setpoints are used when CV Pressure reaches 4 psig and will be used from that point forward, regardless of CV Pressure.
B. CV adverse setpoints are used when CV Pressure reaches 4 psig and will be used until CV Pressure is reduced below 1 psig.
C. CV adverse setpoints are used when CV Pressure reaches 10 psig and will be used from that point forward, regardless of CV Pressure.
D. CV adverse setpoints are used when CV Pressure reaches 10 psig and will be used until CV Pressure is reduced below 4 psig.
72
HLC-06 NRC Replacement Exam 73.
Given the following:
--- --A LOCAhas occurred.
~ _ ~
~
Both SI pumps have tripped and other equipment problems have complicated the recovery of the plant.
The crew is performing FRP-C.1, Response to Inadequate Core Cooling.
The RWST Low Level Alarm has been received.
RWST level is 27% and lowering slowly.
Wh ich ONE (1) of the following describes when the crew will transition to EPP-9, Transfer to Cold Leg Recirculation?
A. Immediately.
B. When RWST level reaches 9%.
C. When at least 1 RCP has been started to restore core cooling.
D. When all actions of FRP-C.1 have been completed.
-i 73
HLC-06 NRC Replacement Exam 74.
Given the following:
~ ~
__At 1320,_a Reactor_Irip_aod_SafetyJnjectiona~1ornatLc.~l1Y_QQc =ur=s-,-;
~_ _
At 1327, the crew identifies SG "A" as the ruptured SG:
At 1330, an ALERT is declared by the Site Emergency Coordinator (SEC).
At 1340, the Emergency Notification Form was completed and signed by the SEC.
Which ONE (1) of the following describes the latest time that the initial notification to State/County officials is due?
A.
1335 B. 1342 C. 1345 D. 1355 74
75.
HLC-06 NRC Replacement Exam Given the following:
Mode 1 at 68% RTP.
__~~ _ __ __
One Shutdown Bank A, Group 2 Rod has dropped into the core.
The crew is recovering the dropped rod.
APP-005-E2, ROD CONT SYSTEM URGENT FAILURE, is received.
Which ONE (1) of the following describes the Rod Control System Urgent Failure alarm and the plant response?
The alarm is......
A. unexpected. Rod withdrawal will not occur until the alarm is reset atthe Logic Cabinet.
B. unexpected.
Rod withdrawal will not occur until the alarm is reset at the Power Cabinet..
C. expected. The alarm will have to be reset to allow rod recovery to continue.
D. expected. Rod withdrawal is unaffected and recovery may continue.
75
,1 References 1.
EPP-15, Revision 16, Page 11 of 33.
Rev.
16 EPP -15 LOSS OF EMERGENCY COOLANT RECIRCULATION Page 11 o f 33 I NSTRUCTIONS 24.
Determine Number Of CV Spra y Pumps Required Us ing The Following Table :
RESPONSE NOT OBTAI NED RWST CONTAINMENT FAN COOLERS SPRAY PUMPS LEVEL PRESSURE RUNNING REQUIRED GREATER THAN 42 PSIG
- 2 GREATER THAN 27 %
BETWEEN 0 or 1 2
4 0
LESS THAN 4 PSIG 0
GREATER THAN 42 PSIG
- 2 BETWEEN BETWEEN 0,
1, or 2 1
9% and 27 %
LESS THAN 4 PSIG 0
LESS.THAN 9%
0 a.
Ve r i f y CV Spray Pump s r unning EQUAL TO NUMBER REQUIRED
- b. Close CV SPRAY PUMP DISCH Valves on a ny s t opp e d pump :
1)
CV SPRAY PUMP A SI-880A SI -880B 2)
CV SPRAY PUMP B
SI -880C SI-B80D