ML082680192
| ML082680192 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 09/24/2008 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| Download: ML082680192 (104) | |
See also: IR 05000261/2008301
Text
Final Submittal
(Blue Paper)
FINAL RO/Si(.O
WRITTEN EXAMINATION
AND 11/1/~{;JE~ kEy
HLC-08 NRC Written Exam
1 000008 AK1.01 1 D
2 000011 EA1.12 1 D
3 000015 AK2.10 1 A
4 000022 AA1.01 1 C
5 000025 AA2.06 1 C
6 000026 AA1.02 1 B
7 000029 G2.1.28 1 D
8 000038 G2.1.20 1 B
9 000040 AA1.02 1 A
10 000054 AA1.02 1 B
11 000056 AA2.67 1 A
12 000057 G2.2.22 1 A
13 000058 G2.2.36 1 C
14 000062 AK3.02 1 C
15 000065 AA2.05 1 D
16 WE04EK3.11 B
17 WEll EK1.2 1 B
18 000077 AK2.06 1 D
19 000001 AK2.08 1 D
20 000005 AK3.01 1 D
21 000028 G2.4.4 1 C
22 000032 AK1.01 1 D
23 000037 AA1.06 1 B
24 000068 AA2.05 1 C
25 000069 AK1.01 1 D
26 WE13 EK2.2 1 B
27 WE15 G2.2.38 1 C
28 003 K6.04 1 C
29 004 A1.05 1 A
30 005 K1.06 1 B
31 006 K2.01 1 B
32 007 K4.011 B
33 008 A4.05 1 B
34 010 K5.011 B
35 012 K6.011 C
36 013 G2.2.38 1 C
37 022 A3.011 A
38 026A1.011 B
39 039 G2.4.20 1 D
40 059 A2.05 1 B
41 061 A3.011 B
42 062 K2.011 D
43 063 K3.02 1 B
44 064 G2.1.7 1 C
45 073 A4.011 A
46 076 A2.011 B
47 078 K1.03 1 B
1
HLC-08 NRC Written Exam
48 103 K3.01 1 A
49 004 K3.08 1 D
50 007 Al.02 1 B
51 039 Kl.0ll B
52 062 A3.05 1 C
53 039 K3.06 1 C
54 026 A2.04 1 C
55 064 K6.07 1 B
56 002 K6.07 1 B
57 014 Kl.0ll C
58 015 K4.011 B
59 017K3.011 C
60 027 Kl.0l 1 B
61 034 A4.02 1 A
62 035 A2.06 1 B
63 041 A4.06 1 C
64 045 Kl.18 1 A
65 075 K2.03 1 A
66 G2.1.261 D
67 G2.1.28 1 B
68 G2.2.6 1 A
69 G2.2.40 1 C
70 G2.3.4 1 C
71 G2.3.131 B
72 G2.3.7 1 B
73 G2.4.16 1 C
74 G2.4.221 A
75 G2.4.231 A
76 000008 G2.4.11 1 B
77 000022 AA2.03 1 B
78 000025 AA2.07 1 B
79 000026 G2.2.38 1 D
80 000055 EA2.01 1 D
81 000058 G2.1.32 1 A
82 000024 AA2.02 1 A
83 000033 AA2.10 1 A
84 000059 G2.2.14 1 A
85 000074 G2.4.21 1 A
86 003 A2.03 1 B
87 013 G2.1.7 1 A
88 061 G2.1.27 1 B
89 010 A2.03 1 A
90 103 G2.4.30 1 B
91 002 G2.2.40 1 B
92 011 G2.4.50 1 D
93 071 G2.2.25 1 D
94 G2.1.411 B
2
HLC-08 NRC Written Exam
95 G2.2.181 B
96 G2.2.151 D
97 G2.2.361 C
98 G2.4.6 1 D
99 G2.4.81 B
100 G2.4.181 B
3
1
HLC*i08 NRC Written Exam
1. Given the following:
- The plant is operating at 1000/0 RTP.
- The PRT is at 74°h and 110 of.
- A load rejection results in a Reactor Trip.
- Following the trip, a Pressurizer Safety valve opens, and will NOT reseat.
- The PRT rupture disks function as designed.
- Containment pressure peaks at 18 PSIG.
Which ONE (1) of the following is the MAXIMUM temperature indicated by the Safety Valve
tailpiece RTD during the entire event?
A. 222 of.
B. 254 of.
C. 328 of.
D. 338 of.
1
HLC-08 NRC Written Exam
2. Given the following:
- The plant was operating at 100 % RTP when a Large Break LOCA occurred.
- All systems functioned as designed.
- The crew has transitioned to EPP-10, TRANSFER TO LONG TERM RECIRCULATION.
How was the Charging Header SEALED and why?
A. IVSW initiation automatically sealed the Charging Header.
To prevent leakage by seating the RCP Seal Injection line check valves.
B. A manual valve alignment of IVSW was performed to seal the Charging Header.
To prevent leakage by seating the RCP Seal Injection line check valves.
C. IVSW initiation automatically sealed the Charging Header.
To prevent leakage from Containment.
D. A manual valve alignment of IVSW was performed to seal the Charging Header.
To prevent leakage from Containment.
2
HLC-08 NRC Written Exam
3. The plant is operating at 8% RTP and ready to synchronize to the grid when the following
conditions are noted:
- APP-001-B2, RCP LABYRTH SEAL LO DP is illuminated.
- APP-001-D2, RCP #1 SEAL LEAKOFF HI FLOW is illuminated.
- Seal Leakoff Flow for RCP "All is pegged HIGH.
- Seal Leakoff Flow for RCPs "B" and IIC" have decreased slightly.
- FCV-626, THERM BARRIER OUTLET, indicates CLOSED.
Which ONE (1) of the following describes the failure that has occurred and what actions are
required?
A. #1 seal has failed;
Trip the reactor, trip RCP "All; enter PATH-1.
B. The Thermal Barrier has failed;
Trip the reactor, trip RCP "A"; enter PATH-1.
C. #1 seal has failed;
Place plant in MODE 3 lAW GP-006, NORMAL PLANT SHUTDOWN FROM POWER
OPERATION TO HOT SHUTDOWN, and trip RCP "A".
D. The Thermal Barrier has failed;
Place plant in MODE 3 lAW GP-006, NORMAL PLANT SHUTDOWN FROM POWER
OPERATION TO HOT SHUTDOWN, and trip RCP "A".
3
HLC-08 NRC Written Exam
4. Given the following:
- The plant is operating at 100% RTP.
- RCS boron concentration is 600 ppm.
- Earlier in the shift, VCT level transmitter, LT-115, failed LOW.
- All actions of AOP-003, MALFUNCTION OF REACTOR MAKEUP CONTROL, have been
completed.
- VCT level transmitter, LT-112, is currently 30 inches and stable.
Subsequently:
- I&C reports they have inadvertently deenergized LT-112.
Which ONE (1) of the following describes how the ACTUAL VCT level and T AVG will respond?
(Assume no operator action)
A. VCT level increases; T AVG increases.
B. VCT level decreases; T AVG increases.
C. VCT level increases; TAVG decreases.
D. VCT level decreases; T AVG decreases.
4
HLC-08 NRC Written Exam
5. A Large Break LOCA has occurred and Cold Leg Recirculation is being established lAW
EPP-9, TRANSFER TO COLD LEG RECIRCULATION.
- RHR Pump "A" has just been started.
- RHR Pump discharge pressure is fluctuating by 40 PSIG and flow is approximately 3350
GPM and oscillating.
- APP-001-A7, RHR HX LO FLOW, has alarmed and cleared numerous times.
- APP-003-D3, PRT HI/LO LVL, has just illuminated and is verified HIGH.
Which ONE (1) of the following malfunctions would cause the above event?
A. ECCS Sump screens are clogging.
B. SI-871, CS PUMP SUCTION RELIEF VALVE is cycling.
C. RHR-706, RHR RELIEF VALVE is cycling.
D. SI-887, RHR RECIRCULATION TO RWST VALVE disc has separated from its valve stem.
5
HLC-08 NRC Written Exam
6. Given the following:
- The Crew is responding to a LBLOCA lAW PATH-1.
- ALL attempts to start CCW Pumps have failed.
- AOP-014, CCW SYSTEM MALFUNCTION, Section "C", CCW PUMP DISCHARGE
PRESSURE LOW is being performed.
- An AO was dispatched to perform Attachment 1, EMERGENCY COOLING TO
CHARGING PUMPS.
- Charging Pump IIBII is running with speed controller in MANUAL set at 75°;6.
- All RCP Thermal Barrier DP indications are at approximately 3.5 inches.
- Step 9 of AOP-014, Section "C" directs increasing Charging Pump speed to obtain RCP
Thermal Barrier DP of > 5 inches.
Which ONE (1) of the following is the basis for INCREASING the RCP Thermal Barrier DP?
A. The increased charging ensures RCP Seal leakage will be minimized.
B. To provide adequate seal injection for RCP Seal cooling.
C. The increased charging ensures the Charging Pump temperatures remain low until
Attachment 1 is completed.
D. Increasing the Thermal Barrier DP is in preparation for restarting the RCP(s) after CCW is
restored.
6
HLC-08 NRC Written Exam
7. Which ONE (1) of the following conditions must be met to ACTUATE AMSAC AND what is the
result of the actuation?
A. 2/3 S/G Levels < 11% for 25 seconds;
Direct Reactor Trip.
B. 1/3 S/G Levels < 11% for 25 seconds;
Direct Turbine Trip.
C. 1/3 S/G Levels < 11% for 25 seconds;
Direct Reactor Trip.
D. 2/3 S/G Levels < 11% for 25 seconds;
Direct Turbine Trip.
7
HLC-08 NRC Written Exam
8. Given the following:
- The crew is responding to a SGTR in S/G "A" with a loss of offsite power.
- Supplement G is in progress.
- ALL S/G pressures are 1025 PSIG.
- The step in Supplement G which requires Steam Flow to be isolated from the ruptured
S/G has just been reached.
Which ONE (1) of the following describes the action that is required regarding the ruptured S/G
PORV lAW Supplement G?
A. Raise the RUPTURED S/G PORV controller's setpoint to MAXIMUM.
B. Verify the RUPTURED S/G PORV controller's setpoint at 1035 PSIG.
C. Isolate Instrument Air to the RUPTURED S/G PORV.
D. Verify the RUPTURED S/G PORV controllers' setpoint is 15 PSIG less than the INTACT
S/G PORV controllers.
HLC-08 NRC Written Exam
9. Given the following:
- The plant was operating at 1OOO~ RTP when S/G "A" Steamline severs inside
Containment.
Which ONE (1) of the following describes the Feed Water valves that will CLOSE as a result of
the above conditions?
A. FRVs for ALL THREE S/Gs (FCV-478, 488, 498)
FRV BYPs for ALL THREE S/Gs (FCV-479, 489, 499)
FW HDR SECTION Valves for ALL THREE S/Gs (V2-6A/B/C)
B. FRVs for ALL THREE S/Gs (FCV-478, 488, 498)
FRV BYPs for ALL THREE S/Gs (FCV-479, 489,499)
FW HDR SECTION Valve for S/G "A" ONLY (V2-6A)
C. FRV for S/G "A" ONLY (FCV-478)
FRV BYP for S/G "A" ONLY (FCV-479)
FW HDR SECTION Valve for S/G "A" ONLY (V2-6A)
D. FRV for S/G "A" ONLY (FCV-478)
FRV BYP for S/G "A" ONLY (FCV-479)
FW HDR SECTION Valves for ALL THREE S/Gs (V2-6A/B/C)
9
HLC-08 NRC Written Exam
10. Given the following:
- The Reactor is at 4°k> RTP in preparation for Turbine startup.
- Main Feedwater Pump "A" is under clearance for maintenance.
11
- Main Feedwater Pump "8 is operating.
- Narrow range Steam Generator levels are at 44%.
Which ONE (1) of the following statements describes the AFW Pump status immediately after
Main Feedwater Pump "8" trips?
A. The MDAFW and SDAFW Pumps must be manually started.
B. The MDAFW Pumps have auto started but the SDAFW Pump must be manually started if
required.
C. The SDAFW Pump has auto started but the MDAFW Pumps must be manually started if
required.
D. The MDAFW and SDAFW Pumps have auto started.
10
HLC-08 NRC Written Exam
11. During a Loss of All AC Power event, EPP-1, LOSS OF ALL AC POWER, directs the isolation
of seal cooling for events of 15 minutes or more without RCP seal cooling.
Which ONE (1) of the following is the basis for isolating seal cooling?
A. RCP seals and shafts may be damaged by thermal shock when power is restored to the
OS Bus.
B. RCP thermal barriers are susceptible to rupture from thermal shock when power is restored
to the OS Bus.
C. Steam binding of the Charging Pumps from RCP seal leakoff flashing when a Charging
Pump is restarted.
D. RCP Thermal Barriers are susceptible to rupture from water hammer when power is
restored to the OS Bus.
11
HLC-08 NRC Written Exam
12. Given the following:
- The plant is in MODE 6 with refueling in progress.
- Instrument Bus 2 trips.
Which ONE (1) of the following Limiting Conditions for Operation (LCO) REQUIRED ACTIONS
is applicable?
A. Verify one PAM Source Range monitor provides indication in the CR within 15 minutes
AND Log indicated SR count rate every 30 minutes.
B. Verify one PAM Source Range monitor provides indication in the CR within 15 minutes,
suspend core alterations AND suspend positive reactivity additions.
C. IMMEDIATELY initiate action to restore one SR monitor to OPERABLE AND suspend core
alterations AND suspend positive reactivity additions.
D. IMMEDIATELY initiate action to restore one SR monitor to OPERABLE AND log indicated
SR count rate every 30 minutes.
12
HLC-08 NRC Written Exam
13. Given the following:
- The plant is operating at 100% RTP.
- Two electricians are performing MST-902, "A" and "B" STATION BATTERY TEST,
obtaining battery pilot cell temperatures, electrolyte levels and battery ground checks.
- During the battery checks, Battery Charger "B" was inadvertently tripped.
Which ONE (1) of the following describes the effect on Battery Bus "B" and any LCOs that are
applicable?
Battery Bus "B" is...
A. de-energized. An LCO is in effect to restore power to the bus.
B. de-energized. LCO 3.0.3 is in effect.
C. at -120VDC. An LCO is in effect to restore a battery charger to service.
D. at -120VDC. NO LCO is in effect due to Battery Bus "B" energized within normal
parameters.
13
HLC-08 NRC Written Exam
14. Given the following:
- The Unit was operating at 100 % RTP, when a Pressurizer PORV failure caused a
- APP-008-F7, SOUTH SW HDR LO PRESS, is received.
- South SW header pressure is 29 PSIG and slowly decreasing.
- North SW header pressure is 42 PSIG and stable.
Valve Nomenclature:
V6-16A, SW NORTH HEADER SUPPLY TO TURBINE BUILDING.
V6-16B, SW SOUTH HEADER SUPPLY TO TURBINE BUILDING.
V6-16C, SW ISOLATION TO TURBINE BUILDING.
Based on the above conditions, which ONE (1) of the following describes the correct pressure
and the response of the Service Water system?
After ONE (1) minute with South SW header pressure less than ...
A. 40 PSIG,
ONLY valves V6-16B, and V6-16C will close.
B. 40 PSIG,
Valves V6-16A, V6-16B and V6-16C will close.
c. 31 PSIG,
ONLY valves V6-16B and V6-16C will close.
D. 31 PSIG,
Valves V6-16A, V6-16B and V6-16C will close.
14
HLC-08 NRC Written Exam
15. Given the following:
- The plant is operating at 12°k> RTP.
- A line break in the Instrument Air header has occurred.
- IA header pressure is 82 PSIG and decreasing slowly.
- The crew has implemented AOP-017, LOSS OF INSTRUMENT AIR.
In accordance with AOP-017, which ONE (1) of the following REQUIRES the crew to manually
trip the reactor and enter PATH-1?
A. Letdown isolates.
B. FCV-1740, IA DRYER BYPASS Valve has OPENED.
C. RCP seal injection flows increase to 20 GPM/Pump.
D. IA header pressure decreases to 58 PSIG.
15
HLC-08 NRC Written Exam
16. Given the following:
- The Reactor has tripped due to a LOCA.
- The crew has entered PATH-1.
Which ONE (1) of the following would justify entry into EPP-20, LOCA OUTSIDE
CONTAINMENT?
A. Auxiliary Building Sump level rapidly increasing.
B. Abnormal radiation in the Auxiliary Building.
C. RWST level at 27°k.
D. Decreasing CV Pressure with a decreasing RCS pressure.
16
HLC-08 NRC Written Exam
17. Given the following:
- The plant has experienced a Reactor Trip and LOCA.
- RHR is NOT available.
- The crew has implemented EPP-15, LOSS OF EMERGENCY RECIRCULATION, and is
ready to perform Step 18, III nitiate RCS Cooldown to Cold Shutdown",
EPP-15, Step 18 directs the crew to cooldown the RCS at _(a)_, using _(b)_ S/Gs.
A. (a) maximum rate
(b) only intact
B. (a) less than 100 of/hour
(b) any intact preferred, but faulted if necessary
C. (a) maximum rate
(b) any intact preferred, but faulted if necessary
D. (a) less than 100 of/hour
(b) only intact
17
HLC-08 NRC Written Exam
18. Which ONE (1) of the following is the reason for placing the Governor valves on the Limiter
while at 100 0h RTP?
A. Reduce the effects of turbine overspeed in the event of a load rejection or Generator output
breaker trip.
B. Prevent Generator overload resulting from Turbine Impulse channel failures and
malfunctions.
c. Prevent Generator load fluctuations induced from Impulse stage pressure fluctuations.
D. Minimize Generator load fluctuations to prevent Reactor power from exceeding license
limit.
18
HLC-08 NRC Written Exam
19. Given the following:
- The plant is at 45% power, with power escalation to 100% RTP in progress.
- Control Bank "0" rods are at 185 steps on the step counters.
- Rod Control is in AUTOMATIC.
- The RO observes ONLY Control Bank "0" rods' IRPI indicators are increasing.
- T AVG is 1.5 of lower than T REF.
The described conditions indicate ...
A. an electrical problem on Instrument Bus 7 A.
B. a Control Bank "0" Signal Conditioning Module fault.
C. a Normal Rod Withdrawal.
D. an Uncontrolled Rod Withdrawal.
19
HLC-08 NRC Written Exam
20. Given the following:
- The plant has experienced a Reactor/Turbine Trip from 1000k RTP.
- The crew is performing EPP-4, REACTOR TRIP RESPONSE.
- Rod Bottom Light for Control Rod M6 is NOT lit.
- IRPI shows Control Rod M6 at 225 steps.
Which ONE (1) of the following action(s), if any, must be performed lAW EPP-4 and why?
A. Borate to 1950 ppm.
To restore adequate shutdown margin.
B. Borate for worth of most reactive rod.
To maintain adequate shutdown margin.
C. Initiate boration to Cold Shutdown requirements.
To restore adequate shutdown margin.
D. No action required.
Adequate shutdown margin exists.
20
HLC-08 NRC Written Exam
21. Given the following:
- The plant is operating at 50% RTP following a 50% load rejection from 100°;6 RTP.
- APP-003-C8, PZR PROT HI LEVEL is illuminated.
- All Pressurizer Level channels, LI-459A, 460, and 461 , indicate 92%.
- RTB A & B CLOSED (RED) indication is illuminated.
Which ONE (1) of the following is the NEXT procedure the crew should implement?
A. AOP-015, SECONDARY LOAD REJECTION.
B. AOP-025, RTGB INSTRUMENT FAILURE.
C. PATH-1.
D. FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION / ATWS.
21
HLC-08 NRC Written Exam
22. I&C has just completed a surveillance on the high voltage power supply to the Source Range
nuclear instruments. The surveillance determined the as-found voltage was 1400 VDC,
instead of the normal 1600 VDC.
Which ONE (1) of the following describes the effect and reason the lower voltage has on SR
N-31 and N-32 instrument response?
N-31 and N-32 indication will. ...
A. decrease because a lower input voltage to the Pre-Amplifier results in overall reduced
detector efficiency.
B. increase due to a reduction of pulse height discriminations that allows more ionization
events to pass through the discriminator circuit.
C. increase due to a reduction in gamma compensation, allowing more, lower energy events
to pass through the pulse height discriminator circuit.
D. decrease because reduced voltage results in fewer ion pairs reaching the detector
electrodes due to lower potential applied to the detector.
22
HLC-08 NRC Written Exam
23. Given the following:
- The plant is at 30% RTP, with a power escalation in progress.
- APP-036-C7, R-24 MONITOR HI has just alarmed.
Which ONE (1) of the following describes the R-24, MAIN STEAM LINE N-16 DETECTOR
alarm and what actions are required for current plant conditions?
A. The R-24 alarm is valid, crew must enter AOP-005, RADIATION MONITORING SYSTEM.
B. R-24 information is useful only for trending. If R-15, CONDENSER AIR EJECTOR OR
R-19, STEAM GENERATOR BLOWDOWN confirms evidence of leakage, refer to
AOP-035, S/G TUBE LEAKAGE.
C. The R-24 alarm is valid, crew must enter AOP-035, S/G TUBE LEAKAGE.
D. R-24 information is useful only for trending. Adjust R-24 leakage model firmware to
support leakage confirmation and leak location determination lAW EMP-034, OPERATION
OF R-24 A, Band C.
23
HLC-08 NRC Written Exam
24. Which ONE (1) of the following describes the type of indication available and location
OUTSIDE of the Control Room to monitor the availability of Heat Sink?
A. Steam Flow and Feedwater Flow for all 3 S/Gs at the Secondary Control Panel.
B. All 3 S/G Levels and Pressures at the Charging Pump Room Panel.
C. All 3 S/G Levels and Pressures at the Secondary Control Panel.
D. Steam Flow and Feedwater Flow for all 3 S/Gs at the Charging Pump Room Panel.
24
HLC-08 NRC Written Exam
25. Given the following:
- A Large Break LOCA has occurred.
- Leakage has been identified from Containment to the Auxiliary Building.
- Containment pressure peaked at 36 PSIG and has lowered to 18 PSIG.
Current leakage is approximately of the peak leak rate.
25
HLC-08 NRC Written Exam
26. Given the following:
- A Reactor trip has occurred. The crew is preparing to transition from PATH-1 after
checking SI NOT actuated OR required.
- ALL S/G levels are 10-14°h Narrow Range.
- AFW flow indicates 400 GPM.
- S/G IIA II and IIB II pressures indicate 1080 PSIG.
- S/G IICII pressure indicates 1150 PSIG.
Which ONE (1) of the following describes the status of CSF-3, HEAT SINK and the initial crew
actions to address the event?
A. RED; Check total feedwater flow less than 300 GPM due to operator action, lAW FRP-H.1,
RESPONSE TO LOSS OF SECONDARY HEAT SINK.
B. YELLOW; Isolate feedwater to affected S/G lAW FRP-H.2, RESPONSE TO S/G
OVERPRESSURE.
C. YELLOW; Check any S/G level greater than 75% lAW FRP-H.3, RESPONSE TO S/G
HIGH LEVEL.
D. YELLOW; Check level in affected S/G less than 160/0 lAW FRP-H.5, RESPONSE TO
STEAM GENERATOR LOW LEVEL.
26
HLC-08 NRC Written Exam
27. Given the following:
- A Large Break LOCA has occurred.
- ALL systems automatically resp-ond as expected.
- CV Sump level indicates 378 inches and is increasing slowly.
Which ONE (1) of the following identifies the MAJOR concern or license limitation associated
with this condition lAW FRP-J.2, RESPONSE TO CONTAINMENT FLOODING?
A. Containment integrity is compromised due to reduced volume and potentially increased CV
pressure.
B. Dilution of sump water with CCW or Fire Water may cause a return to criticality.
C. Water introduced into the ECCS sump beyond capacity can potentially affect the operation
of vital equipment.
D. Loss of inventory from interfacing cooling systems can potentially result in a loss of ability
to remove heat from the reactor core.
27
HLC-08 NRC Written Exam
28. During Containment isolation valve testing, CCW-716A, CCW to RCP ISOLATION VALVE,
was inadvertently CLOSED with RCP "B" running.
Which ONE (1) of the following RCP components suffered a loss of cooling water flow?
A. Motor Bearing Oil Coolers ONLY.
B. Thermal Barrier Heat Exchangers ONLY.
C. Thermal Barrier Heat Exchangers and Motor Bearing Oil Coolers.
D. Motor Air Coolers, Thermal Barrier Heat Exchangers, and Motor Bearing Oil Coolers.
28
HLC-08 NRC Written Exam
29. Given the following:
- A S/G Tube Rupture has occurred.
- An RCS Cooldown has been performed lAW PATH-2.
- Rapid RCS depressurization is in progress.
Which ONE (1) of the following describes how Charging Flow will be controlled during
subsequent actions lAW PATH-2?
A. Reduce Charging Flow to MINIMUM when PZR level exceeds 100/0.
B. Reduce Charging Flow to MINIMUM ONLY when PZR level exceeds 24%.
C. Maintain MAXIMU,M Charging Flow until PZR level exceeds 24% AND SI Pumps are
stopped.
D. Maintain MAXIMUM Charging Flow until RCS pressure is less than ruptured S/G pressure.
29
HLC-08 NRC Written Exam
30. Given the following:
- A Small Break LOCA occurred 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago.
- The alignment of the ECCS for Cold Leg Recirculation is complete lAW EPP-9,
TRANSFER TO COLD LEG RECIRCULATION.
Which ONE (1) of the following describes the current RHR/ECCS alignment?
ONE (1) RHR Pump and ONE (1) SI Pump operating in series (Piggy-back mode), with the ...
A. RHR AND SI Pump suctions from the CV sump, discharging to RCS cold legs via RHR HX
(RHR Pump), and the BIT.
B. RHR Pump suction from the CV sump, discharging through RHR HX to SI Pump suction,
SI Pump discharging to RCS cold legs via the BIT.
C. RHR Pump suction from the CV sump, discharging through RHR HX to RCS cold legs AND
to SI Pump suction, SI Pump discharging to RCS cold legs via the BIT.
D. RHR Pump suction from the CV sump, discharging through RHR HX to SI Pump suction,
SI Pump discharging to RCS hot legs.
30
HLC-08 NRC Written Exam
31. The plant is operating at 100 % RTP with a normal electrical lineup.
- Breaker 52/10, 4kV Bus 1-2 Tie Bkr, trips OPEN.
- An inadvertent 8afety Injection signal occurs.
Which ONE (1) of the following describes the source of power to the 81 Pumps?
A. 81 Pumps "A" and "C" are powered from off-site power.
B. 81 Pump "A" is powered from EDG "A", 81 Pump "C" is powered from off-site power.
C. 81 Pump "A" is powered from off-site power, 81 Pump "C" is powered from EDG "B".
D. 81 Pumps "A" and "C" are powered from EDG "A" and "B", respectively.
31
HLC-08 NRC Written Exam
32. Given the following:
- The plant is in MODE 3 following a load rejection and Reactor Trip from 100% RTP.
- During the load rejection/trip event, a Pressurizer PORV opened for several seconds and
reseated.
- Pressurizer Relief Tank Pressure, Temperature and Level have increased:
- Pressure = 4.8 PSIG.
- Temperature = 153 of (APP-003-B3, PRT HI TEMP is illuminated.)
- Level = 80%
- The CRSS directs implementation of OP-103, PRESSURIZER RELIEF TANK CONTROL
SYSTEM to reduce PRT temperature.
Which ONE (1) of the following methods will be used to reduce PRT temperature?
A. Continuously fill the PRT with Primary Water and drain the PRT via the RCDT Pump as
necessary to maintain level between 70%-80%.
B. Drain the PRT via the RCDT Pump to 70 0k, then alternately refill with Primary Water and
drain via the RCDT Pump.
C. Fill the PRT with Primary Water to 90%, then alternately drain the PRT via the RCDT Pump
and refill with Primary Water.
D. Monitor Automatic Primary Water spray, drain PRT via the RCDT Pump as necessary to
maintain level between 70%-80%.
32
HLC-08 NRC Written Exam
33. Given the following:
- The plant is in EPP-10, TRANSFER TO LONG TERM RECIRCULATION.
- APP-002-E5, SI PMP COOL WTR LO FLOW alarm is received.
Which ONE (1) of the following describes the cause and effect of the alarm?
A. Loss of CCW to the SI Pump Bearing Heat Exchangers; can result in overheating the pump
bearings.
B. Loss of CCW to the SI Pump Seal Coolers; can result in loss of SI Pump seals.
c. Loss of SW to the SI Pump Bearing Heat Exchangers; can result in overheating the pump
bearings.
D. Loss of SW to the SI Pump Seal Coolers; can result in loss of SI Pump seals.
33
HLC-08 NRC Written Exam
34. Given the following:
- The plant is in MODE 3.
- The crew is performing a plant heatup.
- Pressurizer level is 50°k>.
- BOTH Pressurizer Liquid Space and Steam Space temperature indicators read 622 of.
Which ONE (1) of the following indicates actual Pressurizer Pressure?
A. PI-444 = 1783 PSIG.
B. PI-445 = 1798 PSIG.
C. PI-455 = 1813 PSIG.
D. PI-456 = 1828 PSIG.
34
HLC-08 NRC Written Exam
35. Given the following:
- The plant is operating at 6% RTP preparing for Turbine roll.
- PZR level channel LT-459 failed 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago. The bistables have been tripped and all
actions are complete per AOP-025, RTGB INSTRUMENT FAILURE.
- PZR level is currently 25°k on Channels LT-460 and 461.
Which ONE (1) of the following describes the effects on the plant if PZR level channel LT-461
fails HIGH?
A. A Reactor Trip due to high PZR level.
B. A Reactor Trip due to low PZR pressure.
C. The Reactor will NOT trip, signal is blocked by P-7.
D. The Reactor will NOT trip, signal is blocked by P-10.
35
HLC-08 NRC Written Exam
36. Given the following:
- The plant is operating at 100% RTP when PT-455, PZR PRESSURE fails LOW.
- Prior to OWP-029, PPT-1 implementation, a loss of power to INSTRUMENT BUS 2
occurs.
What effect does this have on the PZR Pressure ESFAS bistables? (Assume NO operator
action)
A. PZR Pressure ESFAS bistables on Train IIA II ONLY are tripped.
Enter LCO 3.3.2, Condition D, Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
B. PZR Pressure ESFAS bistables on Train IIB II ONLY are tripped.
Enter LCO 3.3.2, Condition D, Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c. PZR Pressure ESFAS bistables on Train IIAII AND Train IIB II are tripped.
Enter LCO 3.0.3, Place plant in MODE 4 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.
D. PZR Pressure ESFAS bistables on Train IIAII AND Train IIBII are tripped.
ALL Instrumentation LCOs are currently met.
36
HLC-08 NRC Written Exam
37. Given the following:
- The plant is operating at 100 % RTP.
- HVH-3 has been experiencing intermittent problems and the fan has been stopped.
- APP-002-E6, HVH-1/2/3/4 EMERGENCY CONTROL is illuminated.
- CV RECIRC FAN HVH-3 indication on the RTGB is extinguished.
- An inadvertent Safety Injection is received.
Which ONE (1) of the following describes the current status of HVH-3?
The Fan ...
A. is stopped and will NOT AUTO start.
B. is stopped and can be started from the RTGB.
C. has Auto started due to the SI signal.
D. has Auto started due to a Low Air Flow signal.
37
HLC-08 NRC Written Exam
38. Given the following:
- A Reactor Trip and Safety Injection have occurred due to a Faulted S/G.
- 480V Bus E-1 fault occurred coincident with the Reactor Trip and remains deenergized.
- The crew is performing actions of PATH-1 and direction has just been given to OPEN the
breaker for HVS-1 on MCC-5.
- Containment pressure is 17 PSIG and increasing.
Which ONE (1) of the following is the impact on the plant and the action required?
Accident analysis has determined that Containment pressure...
A. MAY exceed design. Immediately transition to FRP-J.1, RESPONSE TO HIGH
CONTAINMENT PRESSURE, due to an ORANGE condition.
B. will NOT exceed design. Continue in PATH-1 until SPDS is reset and transition as directed.
C. MAY exceed design. Continue in PATH-1 until SPDS is reset and transition as directed.
D. will NOT exceed design. Transition to FRP-J.1 if 480V Bus E-1 CANNOT be restored.
38
HLC-08 NRC Written Exam
39. Given the following:
- A SGTR has occurred and the crew is performing actions lAW PATH-2.
- Prior to ReS cooldown to target temperature, a NOTE warns against exceeding Steam
Line flow rates in excess of the High Steam Line flow setpoint.
What condition is the NOTE written to prevent?
A. MSIVs isolation on High Steam Line Delta P.
B. An SI initiation on High Steam Line Delta P.
C. An SI initiation on High Steam flow coincident with Low T AVG"
D. MSIVs isolation on High Steam flow coincident with Low T AVG.
39
HLC-08 NRC Written Exam
40. Given the following:
- The plant is operating at 50°k> RTP for maintenance on MFP IIB II.
- The following Main Feedwater Pump IIA II parameters are reported:
- Feed pump suction pressure is 225 PSIG.
- DP indication on FS-1444A equates to Main Feedwater Pump Flow of 2850 GPM.
What is the expected response of the Feedwater System and what actions are required lAW
AOP-010, MAIN FEEDWATERICONDENSATE MALFUNCTION.?
MFP "A" will. ..
A. trip on low suction pressure ONLY, trip the Reactor and enter PATH-1.
B. trip on low suction pressure coincident with low flow, trip the Reactor and enter PATH-1.
C. remain running; verify FCV-1444, MFP nAil RECIRC VALVE is OPEN.
D. remain running; verify HCV-1459, FEEDWATER HEATER BYPASS is OPEN.
40
HLC-08 NRC Written Exam
41. Given the following:
- The plant is operating at 30% RTP.
- A loss of the Startup Transformer occurs concurrent with a Reactor Trip and Safety
Injection.
- All S/G levels indicate approximately 20%.
Which ONE (1) of the following describes the AFW system status?
A. MDAFW Pumps ONLY are running at 325 GPM each.
B. MDAFW Pumps are running at 325 GPM each AND SDAFW Pump is running at 500 GPM.
C. MDAFW Pumps ONLY are running at 300 GPM each.
D. MDAFW Pumps are running at 300 GPM each AND SDAFW Pump is running at 630 GPM.
41
HLC-08 NRC Written Exam
42. Which ONE (1) of the following describes the power supplies for the Circulating Water Pumps?
A. CW Pump "A" - 4KV Bus 1
CW Pump "B" - 4KV Bus 2
CW Pump "C" - 4KV Bus 3
B. CW Pump "A" - 4KV Bus 5
CW Pump "B" - 4KV Bus 4
CW Pump "C" - 4KV Bus 1
C. CW Pump "A" - 4KV Bus 2
CW Pump "B" - 4KV Bus 3
CW Pump "C" - 4KV Bus 4
D. CW Pump "A" - 4KV Bus 1
CW Pump "B" - 4KV Bus 4
CW Pump "C" - 4KV Bus 5
42
HLC-08 NRC Written Exam
43. ONE (1) minute following a Reactor Trip, BOTH 52/8, SOUTH OCB and 52/9, NORTH OCB
breakers remain CLOSED.
Which ONE (1) of the following describes the failure that caused BOTH of these breakers to
remain CLOSED?
A. Loss of DC Bus IIAII.
B. Loss of DC Bus 118 11.
C. Loss of the Auxiliary Panel DC.
D. Loss of the Auxiliary Panel GC.
43
HLC-08 NRC Written Exam
44. Given the following:
- The plant is operating at 1000/0 RTP.
- 480V Bus E-1 Main Breaker trips on overcurrent.
- EDG "A" starts and re-energizes 480V Bus E-1.
- The EDG "A" Jacket Water Coolant Pump shaft shears during EDG start.
- APP-01 O-F2, EDG A COOL WTR HI/La TEMP illuminates.
- APP-01 O-A2, EDG A TROUBLE illuminates.
Which ONE (1) of the following is the impact of the pump shaft failure on EDG Automatic
operation?
EDG "A" will. ...
A. shutdown when coolant water pressure decreases to 9 PSIG.
B. shutdown when coolant water temperature reaches 205 of.
C. continue to operate due to ALL EDG engine trips being defeated.
D. continue to operate due to run priority from the Undervoltage start.
44
HLC-08 NRC Written Exam
45. Given the following:
- The plant is operating at 1OOo~ RTP.
- A release of Waste Condensate Tank (WCT) "A" is in progress.
- APP-036-E7, RAD MONITOR TROUBLE, is received.
- The BOP Operator reports the FAIL light for R-18, LIQUID WASTE DISPOSAL
EFFLUENT monitor, is ON.
Which ONE (1) of the following describes the status of RCV-018, LIQUID WASTE RELEASE
ISOLATION VALVE?
RCV-018 will ...
A. NOT automatically close. The release must be manually terminated from the Waste
Disposal Panel.
B. automatically close, and R-18 Rad Monitor must be reset to reopen.
C. NOT automatically close, and must be CLOSED manually from the RTGB.
D. automatically close, and must be reset by cycling the valves controller.
45
HLC-08 NRC Written Exam
46. Given the following:
- The plant is operating at 100% RTP.
- APP-008-E8, N SW HDR STRAINER PIT HI LVL has illuminated.
- APP-008-F8, NORTH SW HDR LO PRESS has illuminated.
Which ONE (1) of the following are Immediate Actions lAW AOP-022, LOSS OF SERVICE
WATER?
A. Close V6-12D, NORTH SW HEADER ISOLATION VALVE, then Go to Section F, SERVICE
WATER PITS FLOODING IN INTAKE AREA.
B. Close V6-12B AND V6-12C, SW X-CONN Valves, then Go to Section F, SERVICE
WATER PITS FLOODING IN INTAKE AREA
C. Close V6-12B AND V6-12C, SW X-CONN Valves, then Go to EPP-28, LOSS OF
D. Close V6-12D, NORTH SW HEADER ISOLATION VALVE, then Go to EPP-28, LOSS OF
46
HLC-08 NRC Written Exam
47. Given the following:
- A line break on the Instrument Air header inside Containment has resulted in a full
depressurization of Containment Instrument Air.
- The crew has closed PCV-1716, INSTRUMENT AIR TO CONTAINMENT.
Based on the above conditions, which ONE (1) of the following can be operated from the
RTGB?
A. Pressurizer Spray valves.
B. Pressurizer PORVs.
C. Letdown Line Isolation valves.
D. Charging Line Isolation valves
47
HLC-08 NRC Written Exam
48. Given the following:
- The plant is in MODE 4, cooling down lAW GP-007, PLANT COOLDOWN FROM HOT
SHUTDOWN TO COLD SHUTDOWN.
- A spurious R-11 alarm causes a CV Ventilation Isolation signal.
- V12-8 and V12-9, CV PURGE OUTLET VALVES, both have dual OPEN/CLOSED
indications.
Which ONE (1) of the following, if any, is required to satisfy LCO 3.6.3, CONTAINMENT
ISOLATION VALVES?
A. Close and deactivate EITHER V12-8 OR V12-9 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
B. Close and deactivate BOTH V12-8 AND V12-9 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
C. Override EITHER V12-8 OR V12-9 CLOSED within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, using CV Purge Valve blocking
mechanism.
D. Plant is in MODE 4; No action required.
48
HLC-08 NRC Written Exam
49. Given the following:
- Charging Pump IIAII is being recirculated following maintenance.
- During the restoration, CVC-291, CHARGING PUMP IIAII TO SEAL INJECTION Valve
was opened prior to closing CVC-277C, CHARGING PUMP IIAII RECIRC ROOT valve.
Which ONE (1) of the following is the impact on the CVC System?
A. This operation will have NO effect on the CVC System.
B. ONLY Charging flow on FI-122A decreases to minimum.
C. ONLY Seal Injection on FI-124, FI-127 and FI-130 decreases to minimum.
D. Seal Injection on FI-124, FI-127 and FI-130 AND Charging flow on FI-122A decreases to
minimum.
49
HLC-08 NRC Written Exam
50. Given the following:
- The plant is operating at 100 ok> RTP.
- PCV-455C, PZR PORV was leaking by and has caused the following conditions in the
PRT:
- APP-003-C3, PRT HI PRESS illuminates and PRT pressure is 6 PSIG.
- PRT level is 69°k> and stable.
- PRT Temperature is 115 of and stable.
Which ONE (1) of the following actions would be used to reduce PRT pressure lAW OP-103,
PRESSURIZER RELIEF TANK CONTROL SYSTEM?
A. Open RC-523, PRT DRAIN, to reduce pressure to 1-2 PSIG.
B. Open RC-549, PRT VENT, to reduce pressure to 3-5 PSIG.
C. Open RC-523, PRT DRAIN, to reduce pressure to 3-5 PSIG.
D. Open RC-549, PRT VENT, to reduce pressure to 1-2 PSIG.
50
HLC-08 NRC Written Exam
51. Which ONE (1) of the following describes the design feature(s) which act to limit S/G blowdown
rate for a Steam Break accident?
A. Swirl Vane Separators in the upper S/G internals.
B. A set of 7 venturis within each S/G outlet nozzle.
C. A Steam Flow venturi in each Main Steam line, located at the operating floor.
D. MSIVs are required to close within 5 seconds.
51
HLC-08 NRC Written Exam
52. Given the following:
- A Loss of Instrument Bus 1 has occurred.
- The crew is performing actions contained in AOP-024, LOSS OF INSTRUMENT BUS.
- The Pressurizer Pressure Controller (PC-444J) AUTO light illuminates for approximately
15 seconds, then extinguishes, and then the MANUAL light is illuminated.
Which ONE (1) of the following correctly describes the status of Instrument Bus 1 and method
of control?
A. Instrument Bus 1 power is NOT restored. Operate Pressurizer Heaters and Spray valves
manually.
B. Instrument Bus 1 power is restored. PC-444J AUTO control has failed, continue to operate
in MANUAL.
C. Instrument Bus 1 power is restored. Restore PC-444J to AUTO control.
D. Instrument Bus 1 power is NOT restored. Continue to operate PC-444J in MANUAL.
52
HLC-08 NRC Written Exam
53. Given the following:
- The plant is operating at 100% RTP.
- The Reactor Operator reports the following:
- RCS Temperature is lowering rapidly.
- RCS Subcooling is increasing.
- Pressurizer level is lowering rapidly.
- A Reactor Trip and Safety Injection occurs.
- Containment pressure is now reported as 11 PSIG and increasing.
Which ONE (1) of the following describes the event in progress and the current status of the
Condenser Steam Dumps?
A. Steam Line Break;
Condenser Steam Dumps are available.
B. Large Break LOCA;
Condenser Steam Dumps are available.
C. Steam Line Break;
Condenser Steam Dumps are NOT available.
D. Large Break LOCA;
Condenser Steam Dumps are NOT available.
53
HLC-08 NRC Written Exam
54. Given the following:
- A LOCA has occurred coincident with a loss of the Startup Transformer.
- EDG "A" has failed to start.
- The crew is performing actions lAW PATH-1.
- Containment pressure is at 12 PSIG and increasing.
- CV Spray Pump "B" was inadvertently stopped.
Which ONE (1) of the following describes the status of CV Spray Pump "B"?
A. The pump will restart because CV pressure is above 10 PSIG.
B. The pump is stopped, but can be manually restarted by taking the switch to START.
C. The pump is locked out and can be restarted by placing the Containment Spray Key Switch
in the OVRD/RESET Position.
D. The pump is locked out and can ONLY be restarted if the CV Spray Pump Breaker control
power fuses are removed and reinstalled.
54
HLC-08 NRC Written Exam
55. Given the following:
- A leak in the EDG "A" Air Start Receiver is reducing starting air pressure.
Which ONE (1) of the following is the FIRST pressure at which the EDG Air Receiver LeO is
entered?
A. < 100 PSIG.
B. < 210 PSIG.
c. < 216 PSIG.
D. < 220 PSIG.
55
HLC-08 NRC Written Exam
56. Given the following:
- The plant has been restarted following a forced outage.
- Loop flow measurements have determined that RCP "B" impeller has degraded such
that its RCS loop flow has DECREASED by 5°k from its original value.
- The other RCS loop flows remain UNCHANGED.
Which ONE (1) of the following would be a result of the decreased flow rate in Loop "B"?
A. Demand on the PZR Control Group heaters at 2235 PSIG will be lower.
B. The reactor core will operate closer to DNB when at full power.
C. Core Delta-T at full power will be lower.
D. The reactor core will operate further from DNB when at full power.
56
HLC-08 NRC Written Exam
57. During withdrawal of the Control Banks, APP-005-F2, ROD BOTTOM / ROD DROP will
CLEAR when Control Bank "A" reaches ...
A. 20 steps as sensed by the Pulse To Analog Converter.
B. 35 steps as sensed by the Pulse To Analog Converter.
C. 20 steps as sensed by the IRPls.
D. 35 steps as sensed by the IRPls.
57
HLC-08 NRC Written Exam
58. During MODE 6, I&C requests permission to remove two (2) Power Range NI Channels from
service at the same time to expedite calibrations.
What impact, if any, will this have on NI System operations?
Simultaneously removing two (2) Power Range Channels from service will. ..
A. have no impact. All trip and interlock signals from the Power Ranges are blocked during
the shutdown and prior to entry into MODE 6.
B. insert a P-10 signal which will de-energize both Source Ranges.
C. initiate a Reactor Trip signal, which will result in a Feedwater Isolation Signal being
generated.
D. have no impact. Power Range Channels are not required to be OPERABLE in MODE 6,
and Source Ranges and Gammametrics provide full range core monitoring.
58
HLC-08 NRC Written Exam
59. Given the following:
- Both Inadequate Core Cooling Monitors (lCCM) have been deenergized.
- A Loss of Offsite Power and Reactor Trip occur.
- Natural Circulation conditions are being verified in Supplement E, NATURAL
CIRCULATION VERIFICATION.
Which ONE (1) of the following indications verifies that Natural Circulation has been
established?
A. T HOT is decreasing.
T COLD is stable.
S/G pressure is stable.
B. T HOT is stable.
T COLD is decreasing.
S/G pressure is stable.
c. T HOT is decreasing.
T COLD is decreasing.
S/G pressure is decreasing.
D. T HOT is stable.
T COLD is stable.
S/G pressure is decreasing.
59
HLC-08 NRC Written Exam
60. Given the following:
- An RCS LOCA has occurred which resulted in a Containment Spray Actuation.
- ALL ESF equipment has functioned as designed.
- NO ESF signals have been reset.
- Containment pressure is 8 PSIG.
The CRSS has directed that SI-845A, SAT DISCH VLV be CLOSED.
Which ONE (1) of the following action(s) must the crew perform to allow SI-845A to be
CLOSED?
Reset. ..
A. SI Signal, and then reset the Containment Spray Actuation Signal.
B. Containment Spray Actuation Signal ONLY.
C. Containment Isolation Phase B Signal ONLY.
D. SI Signal, and then reset the Containment Isolation Phase B Signal.
60
HLC-08 NRC Written Exam
61. Given the following:
- The plant is in MODE 6.
- Refueling activities are in progress.
- APP-005-C1, SR HI FLUX AT SHUTDOWN is illuminated.
Which ONE (1) of the following describes the High Flux at Shutdown alarm setpoint and the
system response?
SR counts are greater than ...
A. 3 times AII-Rods-In background and the CV Evacuation horn will sound.
B. 3 times AII-Rods-In background and the LOCAL Evacuation alarm will sound.
C. 2 times AII-Rods-In background and the CV Evacuation horn will sound.
D. 2 times AII-Rods-In background and the LOCAL Evacuation alarm will sound.
61
HLC-08 NRC Written Exam
62. Given the following:
- The plant was operating at 100% RTP when a Small Break LOCA occurred.
- Safety Injection has been actuated.
- RCPs were tripped due to loss of subcooling.
- Containment pressure is at 4.5 PSIG.
Which ONE (1) of the following describes the REQUIRED action lAW PATH-1 to ensure that
core cooling is maintained during this event?
A. Maintain ALL S/G levels> 8%.
B. Maintain ONE S/G level> 18%.
C. Maintain ALL S/G levels> 18%.
D. Maintain ONE S/G level> 8%.
62
HLC-08 NRC Written Exam
63. Given the following:
- A Steam Generator Tube Rupture has occurred.
- The crew is preparing to cooldown to a target temperature of 480 of lAW PATH-2.
- A Loss of Off-Site Power occurs.
- All equipment functions as required.
Which ONE (1) of the following describes how the cooldown to target temperature will be
accomplished?
A. Intact S/G PORVs controllers set to 6.2 (553 PSIG).
B. Steam Dumps in Pressure Control mode set to 3.95 (553 PSIG).
C. Intact S/G PORVs controllers set to maintain full OPEN valve position.
D. Steam Dumps in Pressure Control mode set to maximum rate.
63
HLC-08 NRC Written Exam
64. Which ONE (1) of the following describes how the Reactor Protection System provides
Runback signals to the Turbine Generator?
The RPS initiates a Turbine (1) runback when 2/3 OT Delta T (2) 2/3 OP Delta T signals
reach their runback setpoints.
A. (1) Reference
(2) OR
B. (1) Valve Limiter
(2) OR
C. (1) Reference
(2) AND
D. (1) Valve Limiter
(2) AND
64
HLC-08 NRC Written Exam
65. Given the following:
- EPP-1, LOSS OF ALL AC POWER, is being performed.
- The RGS has been isolated.
- The Inside AO and maintenance technicians are working on starting an EOG.
- There is NO SI signal present or required.
Subsequently, EOG "A" was started.
Which ONE (1) of the following actions is necessary following the energization of 480V Bus
E-1 ?
Verify Service Water Pumps ...
A. "A" and "B" are running.
B. "A" and "G" are running.
C. "B" and "0" are running.
D. "G" and "0" are running.
65
HLC-08 NRC Written Exam
66. Given the following:
- Operators are performing valve lineups to support BOP Flush.
- Several valves above Heater Drain Tank IIB II are to be repositioned.
- The valves are approximately 15 feet above the floor level.
In accordance with SAF-NGGC-2172, what fall protection or safety measure(s) is/are required
to perform the valve manipulations safely?
A. Tie or secure an extension ladder to structural components at BOTH the top and bottom,
use 3-point contact while on the ladder.
B. Don a full body harness and attach it to the Extraction Steam line support or snubber rods.
C. Secure a step ladder to a structural component at the bottom, use 3-point contact while on
the ladder.
D. Don a full body harness and attach it to an approved anchorage point.
66
HLC-08 NRC Written Exam
67. Given the following:
- The plant is operating at 100% RTP.
- A failure of PT-444 input to PC-444J, PZR PRESSURE controller has resulted in an
actual Pressurizer pressure increase to 2273 PSIG.
- PC-444J has been placed in MANUAL.
Which ONE (1) of the following describes the action required to return pressure to 2235 PSIG?
A. Decrease the controller output.
B. Increase the controller output.
C. Decrease the pressure setpoint potentiometer.
D. Increase the pressure setpoint potentiometer.
67
HLC-08 NRC Written Exam
68. Given the following:
- The crew has discovered an error in an AOP. The AOP identified the proper title of a
pressure indicator, but describes the indicator as PI-2098 instead of the correct number
PI-2089.
- A temporary procedure change has been initiated to correct the error.
Which ONE (1) of the following statements applies to the temporary procedure change process
lAW PRO-NGGC-0204, PROCEDURE REVIEW AND APPROVAL?
A. The temporary change expires after 21 days unless made permanent by the procedure
owner (Operations Manager).
B. The change must be processed as an INTENT change.
C. The procedure owner (Operations Manager) must approve the temporary change prior to
use in the field.
D. The expiration date of the temporary change is set at 4 months from the approval date.
68
HLC-08 NRC Written Exam
69. With the plant operating at 1000k RTP, which ONE (1) of the following equipment failures
requires the EARLIEST ACTION per Technical Specifications?
Failure of ...
A. EDG "A".
B. Battery Charger "A".
C. RC-551C, PZR SAFETY VALVE.
D. PCV-456, PZR PORV.
69
HLC-08 NRC Written Exam
70. Given the following:
- A 25 year old female started working at Robinson as a permanent employee on July 2nd
of this year and has an NRC Form 4 on file.
- She previously worked at Salem and had received 200 mRem exposure for this year.
- She has NOT declared pregnancy.
- She has received NO management exposure extensions and NO emergency exists.
Which ONE (1 ) of the following is the additional exposure she can receive without
management concurrence at Robinson this year?
A. 300 mRem.
B. 1800 mRem.
C. 2000 mRem.
D. 3800 mRem.
70
HLC-08 NRC Written Exam
71. Given the following:
- You are in the Spent Fuel Pit performing fuel handling operations.
- A fuel handling accident occurs, and an evacuation is ordered via a PA announcement.
Which ONE (1) of the following is the area designated as the assembly point for this event lAW
AOP-013, FUEL HANDLING ACCIDENT?
A. Immediately outside the Spent Fuel Pit Building door.
B. Landing halfway down the stairs outside the Spent Fuel Pit Building.
C. Immediately outside the New Fuel Handling Building door.
D. At the bottom of the stairs outside the Spent Fuel Pit Building.
71
HLC-08 NRC Written Exam
72. Given the following:
- While entering the plant to relieve the shift, you notice smoke coming from the Auxiliary
Building.
- You have NOT logged onto any RWP or obtained proper dosimetry (EAD).
- Your assistance is required in the Auxiliary Building.
Which ONE (1) of the following is allowed/required lAW FP-001, FIRE EMERGENCY for the
stated conditions?
A. An exception to the requirement for obtaining an EAD AND RWP login is allowed for
qualified members of the Fire Brigade.
B. An EAD must be obtained AND RWP login must be completed prior to Auxiliary Building
entry.
C. An exception to the requirement for obtaining an EAD AND RWP login is allowed ONLY IF
an RC Tech is present to monitor personnel entry/exit to the Auxiliary Building.
D. RWP login is NOT required, and emergency dosimetry (EAD) is obtained from the Work
Control Center.
72
HLC-08 NRC Written Exam
73. Given the following:
- A loss of Component Cooling Water has occurred.
- The crew has implemented AOP-014, COMPONENT COOLING WATER SYSTEM
MALFUNCTION.
- A Reactor Trip has occurred.
Which ONE (1) of the following describes the continued use of AOP-014 after the Reactor
Trip?
A. Use of AOP-014 is NOT allowed during EOP performance. Continue use of AOP-014 upon
exiting the EOP network.
B. Use of AOP-014 may ONLY be used concurrently with actions of PATH-1. Use must be
suspended upon transition to any other EOP.
C. Use of AOP-014 may ONLY be used concurrently with EOPs if NO RED or ORANGE path
FRPs are being performed.
D. Use of AOP-014 may be used concurrently as necessary under ALL conditions of EOP
use, as long as use of the AOP does NOT delay the mitigation of the event.
73
HLC-08 NRC Written Exam
74. Given the following:
- The crew is responding to a RED PATH lAW FRP-P.1.
- The STA has just reported a RED PATH on the Heat Sink CSFST AND an ORANGE
PATH on Core Cooling CSFST. (Assume ALL conditions have been validated)
FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK.
FRP-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION.
FRP-C.2, RESPONSE TO DEGRADED CORE COOLING
Which ONE (1) of the following is the crew's response?
A. Immediately transition to FRP-H.1.
B. Immediately transition to FRP-C.2.
C. Continue with FRP-P.1 until complete, then transition to the highest priority CSF.
D. Continue with FRP-P.1, while concurrently implementing the highest priority CSF.
74
HLC-08 NRC Written Exam
75. Which ONE (1) of the following is the basis for checking for a Faulted S/G prior to checking
Containment conditions for other possible major accidents during performance of PATH-1?
A. Indications could potentially mask other failures.
B. Early isolation of AFW is required to prevent challenging the RCS Integrity CSFST.
C. Because of the potential for personnel injury during Steam Break accidents outside of
Containment.
D. Because of the increased potential for Containment failure if all S/Gs are faulted.
75
HLC-08 NRC Written Exam
76. Given the following:
- The plant is performing a controlled shutdown from 100°(0 RTP.
- A PZR Safety valve has momentarily lifted and continues to leak by.
- APP-003-F6, PZR SAFETY VLV LINE HI TEMP, has illuminated and the crew has
performed the applicable actions.
- The crew has stopped the controlled shutdown at 95% power and has entered AOP-016,
EXCESSIVE PRIMARY PLANT LEAKAGE.
Which ONE (1) of the following describes the strategy, in the proper order, the crew will use to
address the event before tripping the Reactor and entering PATH-1? (Assume the actions
performed do NOT stop the level decrease)
A. (1) Maximize charging on ALL three Charging Pumps.
(2) Isolate Letdown.
B. (1) Maximize charging on two Charging Pumps.
(2) Isolate Letdown.
(3) Start and maximize Charging on the remaining Charging Pump.
C. (1) Isolate Letdown.
(2) Maximize charging on ALL three Charging Pumps.
D. (1) Isolate Letdown.
(2) Maximize charging on two Charging Pumps.
(3) Start and maximize Charging on the remaining Charging Pump.
76
HLC-08 NRC Written Exam
77. Given the following:
- The plant is operating at 100 % RTP.
- VCT makeup is in progress.
- The following indications are noted:
- BA Transfer Pump IIAII is running.
- PW Pump IIA" is running.
- FCV-113A, BA FLOW, OPEN.
- FCV-113B, BLENDED MU TO CHG SUCT, CLOSED.
- FCV-114A, PRIMARY WTR FLOW DILUTE MODE, OPEN.
- FCV-114B, BLENDED MU TO VCT, CLOSED.
- 45 seconds later:
- APP-003-D5, BA FLOW DEV alarm has illuminated.
- APP-003-E5, MAKEUP WATER DEV alarm has illuminated.
- BOTH VCT level channels have decreased to 15 inches and continue to decrease.
Which ONE (1) of the following has caused the alarms and what actions are required to
mitigate the event?
A. The Charging Pump suction has swapped to the RWST. Isolate Letdown and minimize
Charging flow.
B. The air supply line to FCV-113B has failed, causing the valve to fail CLOSED.
Attempt to establish Makeup to the VCT via FCV-114B.
C. The Charging Pump suction has swapped to the RWST. Reduce Turbine load as
necessary to maintain T AVG within +/- 1.5 of of T REF.
D. The air supply line to FCV-113B has failed, causing the valve to fail CLOSED. Attempt to
establish Makeup via CVC-356, BORIC ACID BLENDER BYPASS TO CHARGING PUMP
SUCTION.
77
HLC-08 NRC Written Exam
78. During Mid-Loop operations, the following indications and conditions are noted:
- RHR Pump IIA II is operating, FCV-605, RHR HEAT EXCHANGER BYPASS is in AUTO.
- FI-605 indicates 3600 GPM and is oscillating +/- 100 GPM.
- RHR Pump discharge pressure is oscillating +/- 30 PSIG.
- RCS standpipes indicate -73 inches (RTGB) and -74 inches (LOCAL).
Which ONE (1) of the following is the NEXT action required lAW AOP-020, LOSS OF
A. Reduce total RHR flow by throttling FCV-605 to 2850 GPM.
B. Stop RHR Pump "A" to prevent pump damage.
c. Establish Charging flow to restore RCS level? -68 inches.
D. Isolate Letdown flow by adjusting HIC-142, PURIFICATION FLOW CONTROLLER to 0%.
78
HLC-08 NRC Written Exam
79. Given the following:
- The plant is in MODE 3.
- The plant experiences a loss of 480V Bus E-1 and EDG "A" does NOT start.
- CCW Pump "C" breaker has tripped on overload.
- CCW Pump IIAII is running.
Which ONE (1) of the following describes the required actions?
A. Enter LCO 3.7.6, COMPONENT COOLING WATER SYSTEM; Place the plant in MODE 5
within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
B. Enter LCO 3.0.3; Place the plant in MODE 4 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
C. Enter LCO 3.7.6, COMPONENT COOLING WATER SYSTEM; Restore 1 CCW Train to
operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
D. Enter LCO 3.0.3; Place the plant in MODE 5 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
79
HLC-08 NRC Written Exam
80. Given the following:
- The plant is in MODE 5 with RHR Pump "A" in service.
- A loss of the Startup Transformer has occurred.
- The Instrument Air Header is depressurized.
- RCS Temperature is increasing.
- RHR Pump "A" is NOT running.
- The crew has implemented:
- AOP-017, LOSS OF INSTRUMENT AIR
AND
- AOP-020, LOSS OF RESIDUAL HEAT REMOVAL (SHUTDOWN COOLING)
In addition to restarting RHR Pump "A", which ONE (1) of the following describes the actions
required to restore core cooling to normal operation?
A. Cross-connect IA with SA by OPENING SA-220 AND 221, SA TO IA CROSS CONNECT
FILTER ISOLATION Valves to restore IA pressure.
Reposition FCV-605 and HCV-758 from their Failed SHUT positions.
B. Start Compressor A and/or B to restore IA pressure.
Reposition FCV-605 and HCV-758 from their Failed OPEN positions.
C. Cross-connect IA with SA by OPENING SA-220 AND 221, SA TO IA CROSS CONNECT
FILTER ISOLATION Valves to restore IA pressure.
Reposition FCV-605 and HCV-758 from their Failed OPEN positions.
D. Start Compressor A and/or B to restore IA pressure.
Reposition FCV-605 and HCV-758 from their Failed SHUT positions.
80
HLC-08 NRC Written Exam
81. Prior to Step 13 of EPP-26, LOSS OF DC BUS "A", a CAUTION describes a safety issue that
prohibits closing the 4160V load breakers onto an energized bus.
Which ONE (1) of the following describes the safety issue?
A. A personnel hazard exists because the Load Breaker must be closed locally, using a test
tool and breaker contact explosion is likely.
B. An equipment hazard exists because electrical fault conditions at the energized equipment
could cause non-isolable faults on the ESF busses.
C. A personnel hazard exists because local, manual 4160V breaker manipulations have NOT
been fully analyzed.
D. An equipment hazard exists because the test tool used for locally closing the breaker
prevents remote breaker operation for several seconds while the tool is engaged.
81
HLC-08 NRC Written Exam
82. Given the following:
- An ATWS condition has occurred from 1000/0 RTP.
- The crew is implementing FRP-S.1, RESPONSE TO NUCLEAR POWER
GENERATION/ATWS.
- While attempting to borate, MOV-350, BA TO CHARGING PMP SUCT, has failed to
reposition from the RTGB.
Which ONE (1) of the following is required lAW FRP-S.1 to begin boration?
A. OPEN LCV-115B, EMER MU TO CHG SUCT AND CLOSE LCV-115C, VCT OUTLET.
B. OPEN FCV-113A, SA FLOW and FCV-113B, BLENDED MU TO CHG SUCT.
C. Dispatch an operator to Manually OPEN MOV-350, BA TO CHARGING PMP SUCT.
D. OPEN FCV-113A, SA FLOW and FCV-114B, BLENDED MU TO VCT.
82
HLC-08 NRC Written Exam
83. Given the following:
- Plant startup is in progress lAW GP-005, POWER OPERATION.
- Reactor is at B°tlc> RTP.
- Reactor Engineering has notified the SSO that BOTH Intermediate Range High Flux Trip
setpoints were determined to be set non-conservative.
- The SSO has declared BOTH IR Channels INOPERABLE.
Which ONE (1) of the following describes the action(s) that must be taken in order to comply
with Technical Specification requirements?
A. Immediately suspend operations involving positive reactivity additions AND reduce thermal
power to < P-6 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
B. Increase thermal power to > P-10 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
C. Immediately OPEN the Reactor Trip Breakers.
D. Restore BOTH channels to OPERABLE status prior to increasing thermal power to > P-10.
83
HLC-08 NRC Written Exam
84. Given the following:
- The plant is operating in MODE 3. \
- A release is in progress from Monitor Tank "A".
- CW Pump IIA II is running.
- U1 has ONE CW Pump running.
- The release permit states a release rate of 80 GPM with ONE U2 CW Pump running.
Subsequently:
- CW Pump IIA II trips.
Based on current plant conditions, what is the impact on the release?
A. 10CFR20 limits may be exceeded. The release must be stopped.
B. 10CFR20 limits will NOT be exceeded. NPDES Discharge limits for pH may be exceeded.
Terminate the release.
C. 10CFR20 limits will NOT be exceeded. The release may continue.
D. 10CFR20 limits may be exceeded. Release may continue provided 2 independent samples
were obtained during permit generation.
84
HLC-08 NRC Written Exam
85. Given the following:
- A LOCA has occurred.
- RCS Subcooling is 0 of.
- RCPs are secured.
- RCS temperature by CETC is 750 of.
- RVLIS Full Range is 40%.
The mitigative strategy required for this event is to depressurize the S/Gs to (1) AND
verify at least 2 of 3 RCS Hot Legs are less than (2) prior to isolating the SI
A. (1) 140 PSIG
(2) 365 of
B. (1) 140 PSIG
(2) 350 of
C. (1) atmospheric pressure
(2) 365 of
D. (1) atmospheric pressure
(2) 350 of
85
HLC-08 NRC Written Exam
86. Given the following;
- The plant is operating at 100% RTP.
- CCW temperature has increased to 102 of due to CCW Heat Exchanger "A" being out of
service for scheduled maintenance.
- RCP "C" thrust bearing temperature has reached 220 of and stabilized.
- APP-001-B5, RCP HIGH VIB and APP-001-F3, RCP C BEARING HI TEMP are
illuminated.
- RCP "C" vibration analysis shows that FRAME vibrations have increased from 2.0 to 3.0
mils in the last 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
What actions are required lAW AOP-018, REACTOR COOLANT PUMP ABNORMAL
CONDITIONS?
Trip the Reactor and trip RCP "C" because the ...
A. Thrust bearing has exceeded the bearing temperature limit, close CVC-303C, SEAL
RETURN ISOLATION Valve, within 3-5 minutes.
B. Thrust bearing has exceeded the bearing temperature limit, close PCV-455B, PZR SPRAY
Valve.
c. Pump bearing has exceeded the bearing temperature limit, close PCV-455B, PZR SPRAY
Valve.
D. Pump bearing has exceeded the bearing temperature limit, close CVC-303C, SEAL
RETURN ISOLATION Valve, within 3-5 minutes.
86
HLC-08 NRC Written Exam
87. Given the following:
- The plant is operating at 100% RTP.
- MST-023, Train 118 11 SAFEGUARDS testing is in progress.
- I&C reports a condition that would prevent Train 118 11 ESFAS from actuating.
What ONE (1) of the following describes the effect on the plant?
A. Containment Isolation Phase A and Phase B will actuate if required.
Enter LCO 3.3.2 and place the plant in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
B. Containment Isolation Phase A and Phase B will actuate if required.
Train IIBII Safeguards LCO may be delayed for testing for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided Train IIA II
Safeguards is OPERABLE.
C. Containment Isolation Phase A will actuate. Phase B will NOT actuate.
Enter LCO 3.3.2 and place the plant in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D. Containment Isolation Phase A will actuate. Phase B will NOT actuate.
Train IIB II Safeguards LCO may be delayed for testing for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided Train IIA II
Safeguards is OPERABLE.
87
HLC-08 NRC Written Exam
88. What is the basis for the Condensate Storage Tank minimum volume required by LCO 3.7.5,
CONDENSATE STORAGE TANK?
A. Ability to remove decay heat for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in MODE 3 using Condenser Steam Dump valves.
B. Ability to remove decay heat for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in MODE 3 by steaming through the Main Steam
Safety Valves.
C. Ability to maintain at least 1 S/G at 8% level for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in MODE 3.
D. Ability to remove decay heat for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in MODE 3 using Steam Line PORVs.
88
HLC-08 NRC Written Exam
89. Given the following:
- A Reactor Trip and Safety Injection has occurred.
- The crew has entered FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK.
- The crew is attempting to establish RCS bleed and feed.
- PCV-456, PZR PORV, failed to open.
Which ONE (1) of the following identifies whether the bleed path is adequate and the required
procedural action lAW FRP-H.1?
A. 1 PORV is NOT an adequate bleed path, OPEN ALL RCS and PZR vent valves.
B. 1 PORV is NOT an adequate bleed path, depressurize ALL S/Gs to atmospheric pressure.
C. Adequate bleed path exists, depressurize ONE S/G to atmospheric pressure.
D. Adequate bleed path exists, verify SI flow is established.
89
HLC-08 NRC Written Exam
90. Given the following:
- The plant is operating at 50% RTP.
- Power ascension in progress lAW GP-005, POWER OPERATION, following a refueling
outage.
- During paperwork reviews, Maintenance Supervision has discovered that the blind flange
on the Refueling Transfer Tube was installed but has NOT been properly torqued.
- The Containment has been declared INOPERABLE and the plant must be placed in
MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Based on current plant conditions, notification to the NRC Operations Center will be required ...
A. within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> due to invoking 10 CFR 50.54(x), Deviation or Departure from License
Condition.
B. within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> due to the initiation of a shutdown required by the ITS.
C. within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> because a Safety System will NOT function as required.
D. within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> due to the failure, degradation, or discovered vulnerability in a safeguard
system.
90
HLC-08 NRC Written Exam
91. Given the following:
- The Plant is in MODE 3 at 547 of following a reactor trip from 100 ok> RTP.
- RCS chemistry sample indicates DOSE EQUIVALENT 1-131 is 73 Micro-Curies/gram.
Which ONE (1) of the following is the REQUIRED action lAW ITS and the basis for that
requirement?
A. Be in MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, to place the plant in a MODE where the 1-131 limit is NOT
APPLICABLE.
B. Reduce T AVG to < 500 of within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, to ensure ReS saturation pressure is below the
S/G Safety Valve lift setpoint.
C. Be in MODE 4 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, to place the plant in a MODE where the 1-131 limit is NOT
APPLICABLE.
D. Reduce T AVG to < 500 of within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, to place the plant in a MODE where the MSIVs
AND PZR PORV Block valves can be closed.
91
HLC-08 NRC Written Exam
92. Given the following:
- The plant is operating at 1000/0 RTP.
- APP-003-E8, PZR CONTROL HI/LO LVL is illuminated.
- APP-003-F4, CHG PMP HI SPEED is illuminated.
- RCS Pressure is 2215 PSIG and decreasing.
- T AVG is equal to T REF.
Which ONE (1) of the following is the correct procedure to implement and the appropriate
actions for the event in progress?
A. AOP-019, MALFUNCTION OF RCS PRESSURE CONTROL.
Place PC-444J, PZR PRESS in MANUAL and control Heaters and Spray to restore
pressure.
B. AOP-019, MALFUNCTION OF RCS PRESSURE CONTROL.
Control Charging and Letdown to stabilize PZR level.
C. AOP-016, EXCESSIVE PRIMARY LEAKAGE.
Place PC-444J, PZR PRESS in MANUAL and control Heaters and Spray to restore
pressure.
D. AOP-016, EXCESSIVE PRIMARY LEAKAGE.
Control Charging and Letdown to stabilize PZR level.
92
HLC-08 NRC Written Exam
93. Which ONE (1) of the following describes the TRM limitation on the quantity of radioactivity
permitted in the Waste Gas Decay Tank(s) AND the basis for that limit?
The quantity contained in ill shall be ~ 1.9 X 104 Curies (Xe-133 Noble Gas) to ensure
an uncontrolled release will (2)
A. (1) ALL Waste Gas Decay Tanks combined
(2) NOT result in exceeding the annual total body exposure to offsite personnel
B. (1) EACH Waste Gas Decay Tank
(2) result in onsite exposures that remain within the Accident Analysis
C. (1) ALL Waste Gas Decay Tanks combined
(2) result in onsite exposures that remain within the Accident Analysis
D. (1) EACH Waste Gas Decay Tank
(2) NOT result in exceeding the annual total body exposure to offsite personnel
93
HLC-08 NRC Written Exam
94. Given the following:
- The plant is in MODE 6 for Refueling.
- Core offload is in progress with a *Fuel Assembly on the Manipulator.
- The Transfer Cart is loaded with a Fuel Assembly, enroute to the SFP.
- You are the Refueling SRO.
You observe that Refueling Cavity level is decreasing.
In the current plant conditions, which ONE (1) of the following is the required action lAW
AOP-020, LOSS OF RESIDUAL HEAT REMOVAL (SHUTDOWN COOLING)?
Place the Fuel Assembly from the Manipulator in the ...
A. RCC change fixture.
B. core, in it's original location.
C. Upender.
D. core, in any location that is bordered by 2 other assemblies.
94
HLC-08 NRC Written Exam
95. Given the following:
- RC personnel need to use Demin Water for decon activities for a spent fuel cask.
- They will need to operate one valve for about an hour AND will finish before shift turnover.
- The valve manipulation is NOT covered by an approved procedure.
Which ONE (1) of the following describes how this manipulation will be tracked and controlled
lAW OMM-001-11, LOGKEEPING?
A. A temporary procedure must be approved prior to manipulation of the valve.
B. The valve manipulation must be entered in the Start/Stop Log of Autolog.
C. A Caution Tag must be issued for the valve being manipulated.
D. The portion of the system to be realigned must be taken out of service and controlled with
Danger Tags.
95
HLC-08 NRC Written Exam
96. Given the following:
- Earlier in the shift, a Clearance was established for maintenance activities on the CV
Spray system.
- An operator is now restoring the system to normal alignment.
- During system restoration, a valve which was inside the Clearance boundary was found
out of alignment.
- It is believed that the valve was mispositioned during maintenance activities.
- There are other valves within the Clearance boundary within close proximity to the
mispositioned valve.
What minimum procedural actions are REQUIRED by OMM-001-8, CONTROL OF
EQUIPMENT AND SYSTEM STATUS?
A. The event shall be considered as a Deliberate Misposition Event until the cause is
investigated and established.
B. ONLY the mispositioned valve must be verified in the correct position lAW the system
Operating Procedure.
C. A full system lineup is required lAW the system Operating Procedure.
D. A valve lineup is required for ALL valves within the Clearance boundary lAW the system
Operating Procedure.
96
HLC-08 NRC Written Exam
97. Given the following:
- The plant is operating at 1000/0 RTP.
- SI Pump "A" is INOPERABLE due to failed motor be'arings.
- While aligning SI Pump "B" to replace SI Pump "A", the E-1 supply breaker 52-22B
breaker racking mechanism was found broken, preventing the breaker from being racked
in and closed.
- An audit of surveillance procedures has determined the last quarterly
surveillance on SI Pump "C" was missed.
Which ONE (1) of the following describes the appropriate action?
A. Operability Determination is required for SI Pump "C" lAW OPS-NGGC-1305,
B. Perform a Safety Function Determination for SI Pump "C" lAW OMM-007, EQUIPMENT
INOPERABLE RECORD.
C. Demonstrate the operability of SI Pump "C" within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OR be in MODE 4 within 13
hours.
D. Demonstrate the operability of SI Pump "C" within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR be in MODE 3 within 6
hours.
97
HLC-08 NRC Written Exam
98. Given the following:
- The Reactor has tripped from 1000/0 RTP.
- RCS temperature is 430 of.
- S/G "A II pressure is 100 PSIG.
- S/G "B II pressure is 50 PSIG.
- S/G "CII pressure is 50 PSIG.
- CV pressure is 38 PSIG.
Which ONE (1) of the following describes the correct mitigation strategy?
A. Throttle Feedwater to ALL S/Gs to 80 to 90 GPM lAW Foldout A.
B. Isolate Feedwater to S/Gs "B II and "CII, continue to feed S/G IIA II lAW Foldout A.
C. Isolate Feedwater to S/Gs "B" and "CII, continue to feed S/G "A" lAW EPP-16,
UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS.
D. Throttle Feedwater to ALL S/Gs to 80 to 90 GPM lAW EPP-16, UNCONTROLLED
DEPRESSURIZATION OF ALL STEAM GENERATORS.
98
HLC-08 NRC Written Exam
99. Given the following:
- The plant was operating at 100°;{, RTP
- A major rupture occurs in the CCW Common Discharge Header.
- The crew has implemented AOP-014, COMPONENT COOLING WATER SYSTEM
MALFUNCTION.
- The Reactor Operator reports that CCW Surge Tank Level is 5% and lowering.
Which ONE (1) of the following describes, in order, the actions required in response to this
event?
A. 1) Verify the Reactor is tripped
2) Perform the Immediate Actions of PATH-1
3) Trip the RCPs.
4) Lockout the CCW Pumps
B. 1) Verify the Reactor is tripped
2) Trip the RCPs
3) Perform the Immediate Actions of PATH-1
4) Lockout the CCW Pumps
C. 1) Lockout the CCW Pumps
2) Verify the Reactor is tripped
3) Perform the Immediate Actions of PATH-1
4) Trip the RCPs
D. 1) Lockout the CCW Pumps
2) Verify the Reactor is tripped
3) Trip the RCPs
4) Perform the Immediate Actions of PATH-1
99
HLC-08 NRC Written Exam
100. Which ONE (1) of the following is the strategy and basis for Reactor Coolant Pump (RCP)
operation in FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK?
A. Verify ONLY ONE RCP is operating prior to initiating bleed and feed to ensure maximum
bleed flow through the PZR PORVs.
B. Stop ALL RCPs to eliminate the heat input from the RCPs extending the time available to
restore feed flow before bleed and feed criteria is met.
C. Verify ONLY ONE RCP is operating to reduce the heat input from the RCPs extending the
time available to restore feed flow before bleed and feed criteria is met.
D. Stop ALL RCPs to establish Natural Circulation cooling in preparation for bleed and feed.
100