ML101970325
| ML101970325 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 06/28/2010 |
| From: | Progress Energy Carolinas |
| To: | NRC/RGN-II |
| References | |
| 50-261/08-301 | |
| Download: ML101970325 (151) | |
Text
HLC-08 NRC Written Exam
- 1. AKI.01 OOIIPZR 000008 AKl.OI 001/PZR VAPOR SPACE SPACE ACCIII/l/3.2/3.7IRO/HIGHfN/A/NEW ACCII1/1/3.2/3.71R0/HIGHJN/AJNEW - 2008/THERMO
- 2008/THERMO CHAP 3-008 3-008 Given the following:
- The plant is operating at 100% RTP.
- The PRT is at 74% and 110
- 110°F.
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 RTD during the entire event?
tailpiece RTO A. 222 of.F.
0 254°F.
B. 254 of.
328°F.
C. 328 of.
D~ 338 of.
D °F.
The correct answer is O. D.
Using Steam Tables to determine the correct saturation temperature for the conditions listed.
The maximum pressure in the PRT will be 100 PSIG, which corresponds to a saturation temperature of 338 of. °F. The PRT rupture disks will relieve pressure to Containment (rupture) at 100 PSIG.
A: Incorrect - Saturation temperature for Containment pressure of 18 PSIG as listed in the question stem, without converting to PSIA.
B: Incorrect - Saturation temperature for Containment pressure of 32.7 PSIA (18 ++ 14.7
- 14.7 == 32.7 PSIA).
C: Incorrect - Saturation temperature for 100 PSIA.
D:
0: Correct -- Saturation temperature for 100 ++ 14.7 == 114.7 114.7 PSIA.
Exam Question Number: 11
Reference:
Steam Tables; SD-059SO-059 PZR/PRT, Page 12. 12.
KA Statement: Knowledge of the operational implications of the following concepts as they apply to a Pressurizer Vapor Space Accident: Thermodynamics and flow characteristics of open or leaking valves.
History: New - Written for HLC-08 NRC Exam.
11
HLC-08 H LC-08 NRC Written Exam FINAL 2
HLC-08 HLC-08 NRC NRC Written Written Exam Exam
- 2. 000011 000011 EA1.l2 EA1.12 001ILBLOCAllflf4.lf4.4fROILOW/N/A/NEW 001[LBLOCAII/1/4.1/4.4/RO/LOWIN/A/NEW - 200S/EPP-9-005
- 20081EPP-9-005 Given the Given the following:
following:
The plant
- The
- plant was operating at was operating at 100%
100% RTP RTP when when aa Large Large Break Break LOCA LOCA occurred.
occurred.
All systems
- All
- functioned as systems functioned as designed.
designed.
crew has
- The crew
- has transitioned transitioned to EPP-10, EPP-10, TRANSFER TRANSFER TO LONG LONG TERM RECIRCULATION.
RECIRCULATION.
How was the Charging Header How Header SEALED SEALED and why?
A. IVSW initiation automatically sealed the Charging Header. Header.
To prevent leakage by seating the RCP Seal InjectionInjection 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.
Dv D~ A manual valve alignment of IVSW was performed to seal the Charging Header.
To prevent leakage from Containment.
The correct answer is D.
Upon initiation of a Safety Injection, the IVSW system is automatically actuated. This system has 4 seperate headers, three which actuate automatically upon SI and one that must be manually aligned if required. The isolation of the Charging Header is performed manually, during EPP-9, to prevent potential leakage if the Containment is pressurized above Charging Pump header pressure and the Charging Pumps are stopped.
A: Incorrect - IVSW is applied to the Charging Header between the pump discharge and the discharge check valves, but it is applied manually. This would also open the valves, NOT seat them.
B: Incorrect - IVSW
- IVSW is manually aligned to the Charging header during EPP-9, however it is applied to the Charging Header between the pump discharge and the discharge check valves. This would open the check valves, NOT seat them.
C:
C: Incorrect - IVSW
- IVSW is applied to the Charging Header Header between between the pump pump discharge and the discharge discharge check valves, but it is applied manually. IVSW IVSW is applied to the Charging Pump lines to prevent leakage from Containment.
D:
D: Correct Correct -- During During EPP-9, EPP-9, IVSW IVSW isis manually manually aligned aligned toto the the Charging Charging header.
header. IVSW IVSW isis applied to applied to the the Charging Pump lines Charging Pump lines to to prevent prevent leakage leakage ifif Continament Continament is is pressurized pressurized above above Charging Charging Pump Pump header header pressure and the pressure and the Charging Charging Pumps Pumps are are stopped.
33
HLC-08 NRC HLC-08 NRC Written ExamExam Exam Question Exam Question Number:
Number: 22
Reference:
EPP-9,
Reference:
EPP-9, Pages Pages 32, 32, 33; 33; EPP-9 EPP-9 BO BD Page Page 37; 37; SO-021 SD-021 CVCS, CVCS, Figure Figure 10.
10.
KA Statement: Ability to operate and monitor the following as they apply to a Large Break LOCA: Long-term containment of radioactivity.
History: New - Written for HLC-08 NRC Exam.
FINAL 44
HLC-08 NRC Written Exam
- 3. 000015 AK2.1O 3.000015 00 1JRCP MALFUNCTIONS/1/1/2.8/2.8IRO/HIGHINIA/ROBINSON AK2. 10 001IRCP MALFUNCTIONS! 1/ 1!2.8!2.8/RO!HIGHIN!AJROB INSON - 2002/AOP-018-004
- 2002!AOP-0 18-004 is operating at 8% RTP and ready to synchronize to the grid when the following The plant is conditions are noted:
APP-OO1-B2, RCP LABYRTH SEAL LO DP is illuminated.
- APP-001-B2, APP-OO1-D2, RCP #1 SEAL LEAKOFF HI FLOW is illuminated.
- APP-001-D2, A is pegged HIGH.
- Seal Leakoff Flow for RCP "A"
- Seal Leakoff Flow for RCPs "B"
- B and "C" C 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; A't A; enter PATH-1.
Trip the reactor, trip RCP "A"; PATH-i.
B. The Thermal Barrier has failed; PATH-i.
A; enter PATH-1.
Trip the reactor, trip RCP "A";
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". 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". A.
55
HLC-08 H LC-08 NRC NRC Written Written ExamExam The correct The correct answer answer is is A.
A.
During aa RCP During RCP #1 #1 Seal Seal failure, failure, APP-001-D2 APP-001 -D2 will will be be received received indicating indicating aa higher higher than than normal normal seal seal leakoff. When leakoff. When thisthis occurs, occurs, seal seal injection will also injection will also flow flow up the seal up the stack and seal stack and could could cause cause APP-001 -B2 alarm.
APP-001-B2 alarm. During During aa Thermal Thermal Barrier Barrier failure, flow reverses failure, flow and flows reverses and flows from from thethe RCS RCS toto the ruptured ruptured thermal barrier. barrier. This result in will result in APP-001-B2 APP-OOi -B2 alarming, alarming, however, however, this robs robs flow flow from the #1 Seal from Seal leakoff, leakoff, therefore APP-001-D2 APP-00i-D2 will NOT NOT alarm.
alarm. Actions Actions of AOP-018 specifyspecify that ifif the plant is the plant is in in MODE MODE 1, 1, the Reactor Reactor shall shall be be tripped, the affected RCP RCP isis tripped and and PATH-i entered.
PATH-1 entered.
A: Correct - - APP-OOi -B2 could have been caused by either a Thermal Barrier failure or a #1 APP-001-B2 Seal failure. The only possible possible cause for an APP-001-D2APP-aOl -D2 alarm is a #1 seal failure. Since the plant plant is is in in MODE MODE 1, 1, the affected RCP RCP must be be tripped and PATH-i entered.
PATH-1 B: Incorrect - A failure of the Thermal Barrier will NOT cause APP-001-D2
- APP-OOi -D2 to alarm, #1 Seal Leakoff flow would have gone down and APP-001-D2 APP-aol -D2 would have NOT been received.
C: Incorrect - Allthough the failure is correct, with plant in MODE 1, the required action is to trip the Reactor instead of entering GP-006. If the plant were in any other MODE this action would be correct following further investigation of plant parameters.
D: Incorrect - A failure of the Thermal Barrier will NOT cause APP-001-D2
- APP-OOi -D2 to alarm, #1 Seal Leakoff flow would have gone down and APP-001-D2 APP-OOi -D2 would NOT have been received. If the plant were in any other MODE this action would be correct following further investigation of plant parameters.
Exam Question Number: 3
Reference:
APP-OOi APP-001-B2 -B2 and D2; AOP-O1 AOP-018, 8, Pages 5, 10; 10; SD-OOi, SD-001, RCS, Figures 22, 23 and 25.
KA Statement: Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following: RCP indicators and controls.
History: Direct from Bank.
FINAL 66
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 4. 000022 AAl.Ol 4.000022 AA1.01 OOllLOSS 001/LOSS OF OF RX RX COOL COOL MAKE/l/1/3.4/3,3IROIHIGHINIAIFARLEY MAKE/1/1/3.4/3.3/ROIHIGHIN/A[FARLEY - 2001/CVCS-004
- 200 1/CVCS-004 Given the Given the following:
following:
The plant
- The
- plant isis operating operating atat 100%
100% RTP.RTP.
- RCS
- boron concentration concentration is is 600 600 ppm.
ppm.
Earlier in
- Earlier
- in the shift, shift, VCT level level transmitter, LLT-1 15, failed LOW.
T -115, LOW.
MALFUNCTION OF
- All actions of AOP-003, MALFUNCTION
- OF REACTOR REACTOR MAKEUP MAKEUP CONTROL, CONTROL, have have been been completed.
completed.
level transmitter, LLT-1
- VCT level
- 12, is T -112, is currently 30 inches and stable.
Subsequently:
- I&C reports they have inadvertently deenergized LLT-112.
- T -112.
Which ONE (1) of the following describes how the ACTUAL VCT level and T AVG will respond?
TAVG (Assume no operator action)
A. VCT level increases; T AVG increases.
TAVG B. VCT level decreases; T AVG increases.
TAVG C~
Cy VCT level increases; T TAVG AVG decreases.
D. VCT level decreases; T AVG decreases.
TAVG The correct answer is C.
A: Incorrect - RWST will be supplying the charging pump suction with water of 2000+ ppm boron, this will cause TAVG T AVG to decrease.
B: Incorrect - TAVG
- T AVG will NOT increase due to boration of the RCS from the RWST.
C:
C: Correct - Letdown
- Letdown will still be going going to the VCT causing level to increase; boration boration from the RWST RWST will be be causing causing TAvGT AVG to decrease.
decrease. Having Having both both level level transmitters low low will open LCV-115B and shut shut LCV-115C.
LCV-115C. This swaps charging pump suction from the VCT to the RWST.
D:
D: Incorrect Incorrect - VCT- VCT level level will NOT NOT decrease, decrease, there is is no no outlet outlet flow from the VCTVCT due due to to LCV-1 LCV-115C1 5C going going shut shut and and letdown letdown still still going going to to the the VCT.
VCT.
77
HLC-08 HLC-08 NRC NRC Written Exam Written Exam Exam Question Exam Number: 44 Question Number:
Reference:
SO-021,
Reference:
CVCS, Pages SD-021, CVCS, Pages 41, 41, 56, 56, Figures Figures 1, 1, 17a, 17a, 6; OWP-005, CVCS, 6; OWP-005, CVCS, Page Page 53.
53.
KA Statement: Ability to operate KA operate and I/ or monitor the following as or monitor they apply as they apply to to the the Loss Loss of of Reactor Coolant Makeup:
Reactor Coolant Makeup: CVCS CVCS letdown letdown and charging.
charging.
History: Modified History: Modified from from Farley Farley 2001 2001 NRC NRC exam, exam, Changed Changed distractors/answer distractors/answer to to TTAVG vs Rx AVG VS Rx power.
power.
FINAL FINAL 88
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 5. 000025
- 5. 000025 AA2.06 AA2.06 OOllLOSS 001/LOSS OF OF RHRJ1/1/3.2/3.4IROIHIGHININNEW RHRI1/1/3.2/3.4/ROIHIGHJN/AJNEW - 200S/AOP-020-004
- 2008/AOP-020-004 A Large Break A Large Break LOCA LOCA hashas occurred occurred and and Cold Cold Leg Leg Recirculation Recirculation isis being being established established lAW lAW EPP-9, TRANSFER EPP-9, TRANSFER TO COLD LEG TO COLD LEG RECIRCULATION.
RECIRCULATION.
RHR Pump
- RHR
- Pump "A"A has has just been been started.
started.
RHR Pump
- RHR
- Pump discharge discharge pressure pressure is is fluctuating fluctuating by by 40 40 PSIG PSIG and and flow flow is is approximately approximately 3350 3350 GPM and GPM and oscillating.
oscillating.
- APP-001-A7,
- HX LO LO FLOW, FLOW, has has alarmed and cleared cleared numerous numerous times.
APP-003-D3, PRT
- APP-003-03,
- PRT HI/LO HI/LO LVL, has just illuminated illuminated and is verified HIGH.
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~
C RHR-706, RHR RELIEF REIJEF VALVE is cycling.
D. SI-887, RHR RECIRCULATION RECIRCULATION TO RWST VALVE disc has separated from its valve stem.
The correct answer is C.
A: Incorrect - Sump screen clogging could cause RHR flow to fluctuate. PRT level indicators make this condition NOT the cause.
B: Incorrect - SI-871 relief valve could cycle and cause system fluctuations, but this relief valve is ONLY used when in Piggyback mode and relieves to Containment through the CV Spray line, NOT to the PRT.
C: Correct -
- Normal flow rate (NOT a suction problem), with pressure oscillations and PRT level indications.
0: Incorrect - S1-887 D: -
SI-887 is a butterfly valve and if the stem were to be disconnected from the disc, the disc could cause fluctuations as it opened and closed from the force of system flow. However, this valve is isolated from RHR during Cold Leg Recirc.
(SI-863A and 863B are closed) 99
HLC-08 NRC HLC-08 NRC Written Written Exam Exam Exam Question Exam Question Number:
Number: 55
Reference:
APP-001-A7;
Reference:
APP-OO1-A7; APP-003-D3; APP-003-D3; SD-003, SD-003, RHR, RHR, Figure Figure 3.
3.
KA Statement:
KA Statement: Ability to determine and to determine and interpret interpret the the following following as they apply as they apply to to the the Loss Loss of of Residual Heat Removal Residual Heat Removal System:
System: Existence Existence of of proper proper RHR RHR overpressure overpressure protection.
protection.
History: New History: New - Written
- Written for for HLC-08 HLC-08 NRC NRC exam.
exam.
FINAL 10 10
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 6. 000026 AAl.02
- 6. 000026 AA1.02 OOlILOSS 001/LOSS OF CCW/1/l/3.2/3.3/RO/LOW/N/AINEW - 2008/AOP-014-003 OF CCW/l/l/3.2/3.3fROILOW/N/A/NEW - 2008/AOP-014-003 Given the Given the following:
following:
The Crew
- The
- Crew isis responding responding to to aa LBLOCA LBLOCA lAWlAW PAPATH-i.
TH-1.
- ALL
- attempts to ALL attempts to start start CCW CCW Pumps Pumps have have failed.
failed.
- AOP-014,
- CCW SYSTEM SYSTEM MALFUNCTION, MALFUNCTION, Section Section "C",
C, CCW PUMP DISCHARGE CCW PUMP DISCHARGE PRESSURE LOW PRESSURE LOW is is being being performed.
performed.
- An AO was dispatched
- dispatched to to perform perform Attachment Attachment 1, 1, EMERGENCY EMERGENCY COOLING COOLING TO TO CHARGING PUMPS.PUMPS.
Charging Pump
- Charging
- Pump "B"B is is running running with speed controller controller in in MANUAL set at at 75%.
75%.
RCP Thermal Barrier
- All RCP
- Barrier DPDP indications indications are at approximately 3.5 inches.
inches.
AOP-0i4, Section "C"
- Step 9 of AOP-014,
- C directs increasing Charging Pump speed to obtain RCP Thermal Barrier DP of 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.
B:t C. The increased charging ensures the Charging Pump temperatures remain low until Attachment 11 is completed.
D. Increasing the Thermal Barrier DP is in preparation for restarting the RCP(s) after CCW COW is restored.
The correct answer is B.
A: Incorrect - RCP Seal leakage is NOT a concern for LBLOCA, but is a step for increased seal leakage.
B: Correct - - Thermal Barrier Delta PP is the only means of ensuring pump seals are receiving adequate cooling.
C: Incorrect - Step 99 RNO has direction to wait until Attachment 11 is complete before reducing Charging Pump speed to minimum, minimum, but NOT for Charging Pump temperature.
D: Incorrect - Raising Thermal Barrier
- Barrier Delta PP to minimum is a step step to start start RCPs, but no restart of RCP will occur in this situation.
11 11
HLC-08 NRC Written Exam Exam Question Number: 6
Reference:
AOP-014, Section C, Page 40; AOP-014 SD, BD, Page Page 24.
KA Statement: Ability to operate and / or monitor the following as they apply to the Loss of Component Cooling Water: Loads on the CCWS in the control room.
History: New - Written for HLC-08 NRC exam.
FINAL 12 12
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 7. 000029
- 7. G2. 1.28 001/ATWS/l/1/4.
000029 G2.1.28 00 1/ATWS/ 1/1/4.1/4. 1/RO/LOW/N/A/NEW - 2008/AMSAC-006 114. lIROILOW/N/A/NEW - 2008/AMSAC-006 Which ONE Which ONE (1) (1) ofof the the following following conditions conditions must must be met to be met to ACTUATE ACTUATE AMSACAMSAC AND AND what what isis the the result of result of the the actuation?
actuation?
A. 2/3 S/G A. 2/3 Levels << 11 S/G Levels 11 % for 25
% for 25 seconds; seconds; Direct Reactor Direct Reactor Trip.Trip.
B. 1/3 S/G B. 1/3 Levels << 11 S/G Levels 11% for 25
% for 25 seconds; seconds; Direct Turbine Direct Turbine Trip. Trip.
C. 1/3 S/G C. 1/3 Levels << 11 S/G Levels 11% for 25
% for 25 seconds; seconds; Direct Reactor Reactor Trip.
Dr 2/3 S/G DY 2/3 Levels << 11 S/G Levels 1 1% seconds;
% for 25 seconds; Direct Turbine Trip.
The correct answer is D.
When power is increased above 35% (191 PSIG First Stage Turbine Pressure) on both First Stage Pressure channels, the AMSAC actuation circuit is armed. When 2 of 3 S/G levels decrease below 11 % Narrow Range level, an AMSAC actuation will occur after a 25 second Time Delay. When power decreases below 35% on one channel, the AMSAC circuit is disarmed following a 360 second Time Delay.
A: Incorrect - Once armed, AMSAC actuates on 2/3 S/G levels <
< 11 11%% for> 25 seconds.
This actuation results in a Direct Turbine Trip, NOT a Direct Reactor Trip.
B: Incorrect - Once armed, AMSAC actuates on 2/3 S/G levels << 11 % for> 25 seconds.
113 SIG 1/3 S/G level coincidence is associated with causing a Reactor Trip and AFW actuation at 16% SIG S/G level.
C: Incorrect - Once armed, AMSAC actuates on 2/3 S/G levels << 11%
- 11 % for> 25 seconds.
seconds. 1/3 113 S/G level coincidence is associated with causing a Reactor Trip and AFW actuation 16% S/G level.
actuation at 16% level. This actuation results inin a Direct Direct Turbine Trip, NOT NOT aa Direct Direct Reactor Trip.
Trip.
D:
D: Correct Correct - Once
- Once armed, armed, AMSAC actuates actuates on 2/3 S/G levels on 2/3 levels << 11 11 %
% for> 25 25 seconds seconds and and causes causes aa Direct Direct Turbine Turbine Trip.
Trip.
Exam Exam Question Question Number:
Number: 77
Reference:
Reference:
APP-005-F6; APP-005-F6; SD-062, SD-062, AMSAC, AMSAC, Figure Figure 1.
1.
KA Statement:
KA Statement: Knowledge Knowledge of of the the purpose purpose and and function function of of major major system system components components and and controls.
controls.
History:
History: New New - Written Written forfor HLC-08 HLC-08 NRC NRC exam.
exam.
13 13
HLC-08 NRC Written Exam FINAL 14 14
HLC-08 HLC-08 NRC NRC Written Written Exam Exam
- 8. 000038 G2.1.20
- 8. 000038 G2. 1.20 00 1/SGTRJ1/1/4.6/4.6[RO/LOW/N/AIRNP 00lISGTRf11 BANKIPATH-2-003 1/4. 6/4. 6IROILOW/NIAIRNP BANKIPATH-2-003 Given the Given following:
the following:
The crew
- The
- responding to crew isis responding to aa SGTR SGTR inin S/G A with S!G "A" with aa loss loss of offsite power.
of offsite power.
Supplement G
- Supplement
- is in G is in progress.
progress.
ALL S/G
- ALL
- pressures are S/G pressures are 1025 1025 PSIG.
PSIG.
The step
- The
- step inin Supplement Supplement G which requires G which requires Steam Steam Flow Flow toto be be isolated isolated from from the the ruptured ruptured S/G has just been S/G has been reached.
reached.
Which ONE (1) of the following describes the action that is required regarding regarding the ruptured S/G PORV lAW PORV lAW Supplement Supplement G? G?
A. Raise the RUPTURED S/G PORV controller's controllers setpoint to MAXIMUM.
BY Verify the RUPTURED S/G PORV controller's B:I controllers setpoint at 1035 PSIG.
C. Isolate Instrument Air to the RUPTURED S/G PORV.
D. Verify the RUPTURED S/G PORV controllers' controllers setpoint is 15 PSIG less than the INTACT S/G PORV controllers.
The correct answer is B.
A: Incorrect - Placing the ruptured S/G PORV to MAXIMUM is undesirable as the PORV will NOT OPEN and pressure will be controlled by S/G Safety Valves, which may NOT reseat if they lift.
B: Correct - -
The setpoint on the ruptured S/G PORV is verified at 1035 PSIG. This minimizes the potential for radiological release and ensures the PORV is maintained available to prevent challenging the S/G Safety Valves.
C: Incorrect - Isolating Instrument Air to the ruptured S/G PORV will prevent an inadvertent release but could challenge the S/G safeties if pressure in the S/G is elevated. It is desired to maintain the S/G PORV operable to allow it to function as designed and provide a controlled release path if steam release is required.
D: Incorrect - Reducing the RUPTURED S/Gs
- S/G's PORV setpoint to less than the intact S/Gs would result in more steam flow from the contaminated S/G, rather than from the intact S/Gs.
15 15
HLC-08 NRC HLC-08 NRC Written Written Exam Exam Exam Question Exam Number: 88 Question Number:
Reference:
Supplement
Reference:
Supplement G, Page 37; G, Page 37; Supplement Supplement G G BD, BD, Pages Pages 44 and and 7.
7.
KA Statement:
KA Statement: Ability Ability to to interpret interpret and and execute execute procedure procedure steps.
steps.
History: Direct History: Direct from from Bank.
Bank.
FINAL FINAL 16 16
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 9. 000040
- 9. 000040 AAl.02 AA1.02 OOl/STM 00l/STM LINE LINE RUPTURE/l/l/4.S/4.S/RO/HIGH/N/A/NEW RUPTURE/l/l/4.514.5/RO[HIGHJN/AINEW - 20081ESF-00S
- 2008/ESF-005 Given the Given following:
the following:
The plant
- The
- plant waswas operating operating atat 100%
100% RTP RTP when when S/G SIG "A" A Steamline Steamline severs severs inside inside Containment.
Containment.
Which ONE Which ONE (1) of the (1) of the following following describes describes the the Feed Feed Water Water valves valves that that will will CLOSE CLOSE as as aa result result of of the above the above conditions?
conditions?
A FRVs A'I FRVs for ALL THREE S/Gs (FCV-478, 488, 498)
FRV BYPs for ALL THREE S/Gs (FCV-479, 489, 499)
FW HDR FW HDR SECTION SECTION Valves for ALL THREE THREE S/Gs S/Gs (V2-6A/B/C)
(V2-6AIBIC)
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 FW SIG "A" A ONLY (V2-6A)
C FRV for S/G C. SIG "A" A ONLY (FCV-478)
FRV BYP for S/G SIG "A" A ONLY (FCV-479)
FW HDR SECTION Valve for S/G SIG "A" A ONLY (V2-6A)
D. FRV for S/G "A" A ONLY (FCV-478)
FRV BYP for S/G SIG "A" A ONLY (FCV-479)
FW HDR SECTION Valves for ALL THREE S/Gs SIGs (V2-6A/B/C)
(V2-6AIBIC)
The correct answer is A.
A: Correct - - A SIG S/G steamline severing inside Containment would cause CV pressure to increase to above the CV SI setpoint. When Safety Injection actuates, feedwater will be isolated to ALL S/Gs.
B: Incorrect - Safety Injection isolates ALL FW HDR Section valves.
C: Incorrect - Correct answer for FRV and FRV Bypass valves if there were a high S/G level.
FW HDR Section valves do NOT go CLOSED on a SIG S/G high level. For an SI, feedwater will be isolated to ALL SIGs.
S/Gs.
D: Incorrect - Correct answer for FRV and FRV Bypass valves if there were a high SIG
- S/G level.
FW HDR Section valves do NOT go CLOSED on a SIG S/G high level. For an SI, feedwater will be isolated to ALL SIGs.
S/Gs.
17 17
HLC-08 HLC-08 NRCNRC Written Written Exam Exam Exam Question Exam Number: 99 Question Number:
Reference:
SD-006,
Reference:
SD-006, ESF, ESF, Figure Figure 12.SD-027, 12.SD-027, FW,FW, Page Page 20.
20.
KA Statement:
KA Statement: Ability to operate operate and and /I or monitor the following as or monitor as they apply apply to the Steam Steam Line Line Rupture: Feedwater isolation.
Rupture: Feedwater isolation.
History: New History: New - Written for HLC-08
- HLC-08 NRC NRC Exam.
Exam.
FINAL 18 18
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 10. 000054
- 10. 000054 AAl.02 001/LOSS OF AA1.02 OOllLOSS MFW/1/1/44/4.4/ROJHIGHJN/AICOOK - 2002/AFW-008 OF MFW/1/1/4.4/4.4IROIHIGH/N/A/COOK - 2002/AFW-008 Given the Given the following:
following:
The Reactor
- The
- Reactor isis atat 4%
4% RTP RTP in in preparation preparation for for Turbine Turbine startup.
startup.
Main Feedwater
- Main
- Feedwater Pump Pump "A"A isis under under clearance clearance for for maintenance.
maintenance.
Main Feedwater
- Main
- Feedwater Pump Pump "B"B isis operating.
operating.
Narrow range
- Narrow
- range Steam Steam Generator Generator levels levels are are at 44%.
at 44%.
Which ONE (1) of the following statements describes the AFW Pump status immediately after Main Feedwater Pump Pump "B"B trips?
MDAFW and SDAFW Pumps A. The MDAFW Pumps must must be be manually manually started.
B 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.
The correct answer is B.
Since MFP "A" A is under clearance and the breaker is OPEN, when MFP "B" B trips the circuit detects a loss of feedwater. Both MDAFW pumps will Auto start on a Loss of Feedwater, but the SDAFW Pump will NOT. The SDAFW Pump Auto starts on S/G LO-LO-level, Bus Undervoltage and AMSAC, but NOT on both MFP breakers being La-La-level, OPEN.
A: Incorrect - Both MDAFW Pumps will AUTO start on loss of Feedwater, therefore they will NOT need to be started manually. The SDAFW Pump will NOT start and must be manually started.
B: Correct - Both MDAFW Pumps will AUTO start on loss of Feedwater, the SDAFW Pump will NOT start and if required must be manually started.
C: Incorrect - The SDAFW Pump will only start on Lo-Lo S!G
- S/G level, AMSAC, and MFP Bus UV. MDAFW Pumps will start on Lo-Lo Level, AMSAC, loss of Main FW, Blackout, & SI.SI.
D: Incorrect - SDAFW Pump
- Pump will NOT auto start. AMSAC will NOT NOT ARM until until power has been raised to>
to > 35% andand the pump will NOT start unlessunless S/G levels levels are << 11%.
11 %.
19 19
HLC-08 NRC HLC-08 NRC Written Written Exam Exam Exam Question Exam Number: 10 Question Number: 10
Reference:
SO-042;
Reference:
SD-042; AFW; AFW; Pump Start Logics, Pump Start Logics, Figure Figure 11.
11.
KA Statement:
KA Statement: Ability Ability to to operate and /I or operate and or monitor monitor the the following following as as they they apply apply to to the the Loss Loss of of Main Main Feedwater (MFW):
Feedwater (MFW): Manual Manual startup startup ofof electric electric and steam-driven AFW and steam-driven AFW pumps.
pumps.
History: Changed History: Changed correct correct answer answer to to BB from from O.
D.
FINAL FINAL 20 20
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 11. 000056
- 11. 000056 AA2.67 AA2.67 OOlfLOSS 001/LOSS OF OF OFFSITE POWRJ1/1/2.913.1/RO/LOW/N/AINEW - 200S/EPP-I-004 OFFSITE POWR/1I112.9/3.1/ROfLOW/N/A/NEW - 2008/EPP-1-004 During aa Loss During Loss of All AC of All AC Power Power event, event, EPP-1, EPP-1, LOSS LOSS OF OF ALL ALL AC AC POWER, POWER, directs directs the the isolation isolation of seal of seal cooling cooling for for events events ofof 15 15 minutes minutes oror more more without without RCP RCP seal seal cooling.
cooling.
Which ONE Which ONE (1) (1) ofof the the following following isis the the basis basis for for isolating isolating seal seal cooling?
cooling?
A A~ RCP seals RCP seals and and shafts shafts may may bebe damaged damaged by thermal shock by thermal shock when power isis restored when power restored to to the the DS Bus.
DS Bus.
B. RCP thermal B. RCP thermal barriers barriers are susceptible to are susceptible to rupture from thermal rupture from thermal shock shock when when power power isis restored restored to the DS Bus.
Steam binding C. Steam binding of of the Charging Charging Pumps Pumps from from RCP RCP seal seal leakoff leakoff flashing when aa Charging Charging Pump is Pump is restarted.
restarted.
D. RCP Thermal Barriers are susceptible to rupture from water hammer when power is restored to the DS Bus.
The correct answer is A.
A: Correct - - Injection loss lasting> 15 minutes may allow seals and shaft to heatup to RCS temperature. Engineering and manufacturer will be consulted prior to restoration.
B: Incorrect - - It is the seal themselves (NOT the Thermal Barrier) which are susceptible to failure from thermal shock.
C: Incorrect - Steam binding is a possibility due to no CCW, but NOT a reason for isolation after a loss of of>> 15 minutes.
D: Incorrect - Water hammer may occur if voids or steam formation in seal injection lines occurs, but it is NOT a reason for isolation after a loss of of>> 15 minutes.
Exam Question Number: 11
Reference:
EPP-1 Page 5; EPP-1 BD, Pages 4-6, 64.
4-6,64.
KA Statement: Ability to determine and interpret the following as they apply to the Loss of Offsite Power: Seal injection flow (for the RCPs).
History: New - Written for HLC-08 NRC Exam.
FINAL 21 21
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 12. 00005702.2.22
- 12. 000057 G2.2.22 OOl/LOSS 001/LOSS OF VITAL AC OF VITAL INS/1/1/4.0/4.7/RO/HIGHIN/AINEW - 2008/0P-01O-002 AC INS/l/l/4.0/4.7/RO/HIGH/N/AINEW - 2008/GP-010-002 Given the Given the following:
following:
The plant
- The
- in MODE plant isis in MODE 66 with with refueling refueling in in progress.
progress.
Instrument Bus
- Instrument
- Bus 22 trips.
trips.
Which ONE Which ONE (1)(1) ofof the the following following Limiting Limiting Conditions Conditions forfor Operation Operation (LCO)
(LCO) REQUIRED REQUIRED ACTIONS ACTIONS is applicable?
is applicable?
A Verify A'f' Verify one PAM PAM Source RangeRange monitor provides indication in the CR within 15 15 minutes AND Log indicated SR rate every 30 SR count rate 30 minutes.
B. Verify one PAM Source Range Range monitor provides indication in CR within 15 in the CR 15 minutes, minutes, suspend core alterations AND suspend positive reactivity additions.
IMMEDIATELY initiate action to restore one SR monitor to OPERABLE AND suspend core C. IMMEDIATELY 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.
The correct answer is A.
When Instrument Bus 2 trips, the plant will suffer a loss of N-32, SRNI. In MODE 6, LCO 3.9.2, Condition A applies.
A: Correct - LCO 3.9.2, Condition A, ONE REQUIRED SOURCE RANGE NEUTRON FLUX MONITOR INOPERABLE. The actions states to verify ONE PAM SR monitor is providing indication within 15 minutes and log SR count rate every 30 minutes.
B: Incorrect - LCO 3.9.2, Condition B, Required actions and completion times of Condition A not met.
C: Incorrect - LCO 3.9.2, Condition C, BOTH SR monitors INOPERABLE. This requires core alterations and positive reactivity additions to be suspended IMMEDIATELY.
D: Incorrect - Correct statement for 2 SR INOPERABLE, but logging SR count rate assumes that NI-51AINI-52A NI-51A1NI-52A PAM instruments can be substituted for SR monitors.
Exam Question Number:
Exam Question Number: 12 12
Reference:
Reference:
ITS ITS 3.9.2; 3.9.2; GP-010, GP-01 0, Pages 11 11 and and 56.
56.
KA KA Statement:
Statement: Knowledge Knowledge of of limiting limiting conditions for operations conditions for and safety operations and safety limits.
limits.
History:
History: NewNew - Written for HLC-08
- HLC-08 NRCNRC Exam.
Exam.
22 22
HLC-O8 NRC Written Exam HLC-08 FINAL 23
HLC-08 NRC HLC-08 NRC Written Exam Written Exam
- 13. 00005802.2.36
- 13. 000058 G2.2.36 OOllLOSS 001/LOSS OF OF DC DC POWER/1/1/3.1/4.2IROIHIOHfN/A/NEW 2008/DC-010 POWERJ1/1/3.1/4.2/RO/HIGH/N/A/NEW - 20081DC-01O Given the Given the following:
following:
The plant
- The
- plant is is operating operating at at 100%
100% RTP.
RTP.
- Two electricians
- Two electricians are are performing performing MST-902, MST-902, "A" A and and "B" B STATION STATION BATTERY BATTERY TEST, TEST, obtaining battery obtaining battery pilot pilot cell cell temperatures, temperatures, electrolyte electrolyte levels levels and and battery battery ground ground checks.
checks.
During the
- During
- the battery battery checks, checks, Battery Battery Charger Charger "B"B was was inadvertently inadvertently tripped.
tripped.
Which ONE (1) of Which of the following describes the effect on Battery Bus "B" B and any LCOs that are applicable?
Battery Bus Battery Bus "B"B is 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.
CY at -120VDC.
C~ 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" B energized within normal parameters.
The correct answer is C.
A: Incorrect - Bus B is still OPERABLE at 120 VDC, only the charger is tripped. Battery "B" B is supplying the bus.
B: Incorrect - Bus B is still energized from the battery. LCO 3.8.4 would be applicable, NOT LCO 3.0.3 C: Correct - - Voltage is still at 120VDC, 1 2OVDC, only the charger has tripped. 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> LCO in effect.
(LCO 3.8.4, Condition A)
D:
0: Incorrect - Voltage is still at 1120VDC,
- 2OVDC, only the charger has tripped. LCO 3.8.4 should be entered. This is the correct answer for MODE 5. MODE 5 does NOT require an LCO entry for loss of a battery charger if the Bus is energized.
Exam Question Number: 13 13
Reference:
Reference:
SD-038, ITS 3.8.4; ITS ITS 3.8.4 BD,BD, Page B3.8-41.
B3.8-41.
KA Statement:
Statement: Ability to analyze analyze the effect effect of maintenance maintenance activities, activities, such such as as degraded power power sources, on on the status of of limiting limiting conditions for operations.
History: New - Written History: New - Written for HLC-08 NRC for HLC-08 NRC Exam.
Exam.
FINAL FINAL 24 24
HLC-08 NRC HLC-08 NRC Written Written Exam Exam 14.
- 14. 000062 000062 AK3.02 AK3.02 OOllLOSS 001/LOSS OFOF SERV WATER/1!1!3.6/3.9/ROIHIGH!N/AIRNP 2007/SW-008 SERV WATERIl/1/3.6/3.9/ROIHIGH/N/AIRNP 2007/SW-008 Given the Given the following:
following:
The Unit
- The
- Unit was was operating operating atat 100%
100% RTP, RTP, when when aa Pressurizer Pressurizer PORV PORV failure failure caused caused aa Reactor Trip.
Reactor Trip.
- APP-008-F7, SOUTH SW
- SW HDRHDR LO PRESS, is LO PRESS, is received.
received.
South SW
- South
- SW header pressure pressure is 29 29 PSIG PSIG and and slowly slowly decreasing.
decreasing.
North SW
- North
- SW header pressure is header pressure is 42 PSIG and 42 PSIG and stable.
stable.
Nomenclature:
Valve Nomenclature:
V6-16A, SW NORTH NORTH HEADER HEADER SUPPLY TO TURBINE BUILDING. 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. 404OPSIG, PSIG, ONLY valves V6-16B, and V6-16C will close.
B. 404OPSIG, PSIG, Valves V6-16A, V6-16B and V6-16C will close.
C 31 PSIG, CY' ONLY valves V6-16B and V6-16C will close.
D. 31 PSIG, Valves V6-16A, V6-16B and V6-16C will close.
The correct answer is C.
A: Incorrect - V6-16B and C
- C will close. 40 PSIG setpoint is is alarm setpoint for APP-008-F7 and incorrect for SW isolation.
isolation.
B: Incorrect - V6-1
- V6-16B 6B and C C will close, V6-1V6-16A6A will NOT because there is NO isolation signal for the North North SW header.
header. 40 PSIG setpoint is alarm setpoint for APP-008-F7 and and incorrect SW isolation.
incorrect for SW C:
C: Correct Correct - - V6-16B V6-16B andand C will close at C will at << 31 PSIG SW 31 PSIG Header pressure SW Header pressure coincident with with aa Turbine trip.
D:
D: Incorrect Incorrect - - V6-16B V6-16B and and CC will close at will close at << 31 PSIG SW 31 PSIG Header pressure SW Header pressure coincident coincident with with aa Turbine trip. V6-16A will Turbine trip. V6-16A will NOT NOT close.
close.
25 25
HHLC-08 LC-08 NRCNRC Written Written Exam Exam Exam Question Exam Number: 14 Question Number: 14
Reference:
SD-004,
Reference:
SD-004, SWS, SWS, Page 18, Figures Page 18, Figures 3,4; APP-008-F7.
3,4; APP-008-F7.
KA Statement:
KA Statement: Knowledge Knowledge of of the reasons for the reasons for the the following following responses responses as as they they apply apply to to the the Loss Loss of Nuclear of Nuclear Service Water: The Service Water: The automatic automatic actions actions (alignments)
(alignments) within within the the nuclear nuclear service water service water resulting resulting from from the the actuation actuation of of the the ESFAS.
History: Changed History: Changed Stem/answer Stem/answer toto question question valve valve realignment.
realignment. (vs.
(vs. SWB SWB Pump Pump status) status)
Note: Repeat question from last last RNP exam, Modified as listed in History.
History.
FINAL FINAL 26 26
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 15. 000065
- 15. 000065 AA2.05 AA2.05 OOlfLOSS 001/LOSS OF OF INSTR INSTR AIRJlIl/3.4/4.1IROfLOW/N/A/NEW AIRJ1/1/3.4/4.1/RO/LOW/N/AJNEW - 2008/AOP-017-004
- 2008/AOP-017-004 Given the Given the following:
following:
The plant
- The
- plant is is operating operating at at 12%
12% RTP.
RTP.
-A
- A line line break break in in the the Instrument Instrument Air Air header header has has occurred.
occurred.
- IA
- IA header header pressure pressure is 82 PSIG is 82 PSIG and decreasing slowly.
slowly.
- The crew
- crew has has implemented implemented AOP-017, LOSS LOSS OF OF INSTRUMENT INSTRUMENT AIR. AIR.
In accordance with AOP-017, which ONE (1) of the following REQUIRES the crew to manually trip the reactor and and enter PA PATH-i?
TH-1 ?
Letdown isolates.
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.
DY' The correct answer is D.
A: Incorrect - AOP-017, Section A has operators check if letdown has isolated, but does NOT direct a Rx trip.
FCV-1 740 OPENS automatically at 80 PSIG, AOP-017 directs the operator B: Incorrect - FCV-1740 to check it OPEN, but the Reactor is NOT tripped until air header pressure reaches 60 PSIG.
C: Incorrect - AOP-017, Section A is for MODE 1/2 operation, Step directs operators to check Seal Injection flow between 8-13 GPM, but allows expanded range of 6-20 GPM.
D: Correct - AOP-017 directs an immediate Rx Trip if IA header pressure decreases to 60 PSIG.
Exam Question Question Number:
Number: 15 15
Reference:
AOP-01AOP-017, 7, Pages 4, 5, 11-12.
11-12.
KA Statement:
Statement: Ability to determine and interpret the following as they apply to the Loss of Instrument Instrument Air: When to to commence plantplant shutdown ifif instrument instrument air is air pressure is decreasing.
decreasing.
History: New New - Written
- Written for HLC-08 NRC NRC Exam.
Exam.
FINAL FINAL 27 27
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 16. WE04
- 16. WEO4 EK3.l EK3.l OOllLOCA 001/LOCA OUTSIDE OUTSIDE CONTAIN/l/l/3.2/3.5/ROILOW/N/A/NEW CONTAIN/1/1/3.2/3.5/ROILOWIN/AINEW - 2008IEPP-20-002
- 2008!EPP-20-002 Given the Given the following:
following:
The Reactor
- The
- Reactor has has tripped tripped due to aa LOCA.
due to LOCA.
The crew
- The
- crew has has entered entered PATH-1.
PATH-i.
Which ONE Which ONE (1) (i) of the following of the following would would justify entry into EPP-20, entry into EPP-20, LOCA LOCA OUTSIDE OUTSIDE CONTAINMENT?
CONTAINMENT?
Building Sump level rapidly A. Auxiliary Building rapidly increasing.
B B~ radiation in Abnormal radiation in the Auxiliary Building.
Building.
C. RWST level at 27%.
D. Decreasing CV Pressure with a decreasing RCS pressure.
The correct answer is B.
A: Incorrect - Many different systems could cause a sump level increase. Rising sump level is NOT an entry condition for EPP-20.
B: Correct - -
The ONLY entry condition to enter EPP-20 is abnormal radiation in the Aux Building that is due to a loss of inventory from the RCS. (LOCA)
C: Incorrect - 27% is the entry condition for EPP-9, TRANSFER TO COLD LEG R EC I RC U LATI ON.
RECIRCULATION.
D: Incorrect - Increasing RCS pressure is the correct parameter used to ensure that the RCS leak outside Containment is isolated.
Exam Question Number: 16 16
Reference:
EPP-20, Page 3.
KA Statement: Knowledge of the reasons for the following responses as they apply to the (LOCA Outside Containment): Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.
History: New New - Written for HLC-08 NRC
- NRC Exam.
FINAL 28 28
HLC-08 NRC HLC-08 NRC Written Written Exam Exam 17.
- 17. WEll WEll EK1.2 EK1.2 OOllLOSS 001/LOSS OF OF EMER EMER RECIRC/1/1/3.6/4.1IROILOW/N/A/NEW RECIRC/1/1/3.6/4.1/RO/LOW/N/AINEW - 200S/EPP-15-003
- 2008/EPP-15-003 Given the Given the following:
following:
The plant
- The
- plant has has experienced experienced aa Reactor Reactor Trip Trip and and LOCA.
LOCA.
RHR isis NOT
- RHR
- available.
NOT available.
The crew
- The
- crew hashas implemented implemented EPP-15, EPP-15, LOSS LOSS OF OF EMERGENCY EMERGENCY RECIRCULATION, RECIRCULATION, and and isis ready to ready to perform perform Step Step 18, Initiate RCS 18, "Initiate RCS Cooldown Cooldown toto Cold Cold Shutdown".
Shutdown.
EPP-1 5, Step 18 EPP-15, 18 directs the crew crew toto cooldown the RCS at at _(a)_, using _(b)_ S/Gs. SIGs.
A. (a)(a) maximum maximum rate rate intact (b) only intact (b)
By B (a) less than 100 of/hour °F/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 F/hour 0
(b) only intact The correct answer is B.
A: Incorrect - Cooldown at the maximum rate is used to get the RCS at target temperature for a SGTR per FRP-C.1, Step 21 and in PATH-2.
B: Correct - Maintain cooldown rate in RCS cold legs less than Step 18 directs the crew to "Maintain
°F in the last 60 minutes."
100 of minutes. and to "Check Check at least one S/G available for cooldown.
cooldown". Step 18 18 RNO specifies that if RHR is NOT available, then a faulted S/G may be used.
C: Incorrect - Rate is incorrect, but S/G to use is correct.
D: Incorrect - Rate is correct, but may
- may use a faulted S/G if NO intact S/G is available.
Exam Question Number: 17 17
Reference:
EPP-15; EPP-15-BD; FRP-C.1, Page 10. 10.
KA Statement: Knowledge of the operational implications of the following concepts as they apply to the (Loss of Emergency Coolant Recirculation): Normal, Normal, abnormal abnormal and emergency emergency operating procedures associated with (Loss of Emergency Emergency Coolant Coolant Recirculation).
History:
History: NewNew - Written Written for for HLC-08 HLC-08 NRC NRC Exam.
Exam.
29 29
HLC-08 NRC Written Exam FINAL 30 30
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 18. 000077
- 18. 000077 AK2.06 AK2.06 OOl/GEN 001/GEN VOLT VOLT & GRID DIST/l/1/3.9/4.OIROILOW/N/A/NEW
& GRID DIST!1/1/3.9/4.0/RO/LOW/N/A/NEW - 2008/EHC-006
- 2008/EHC-006 Which ONE Which ONE (1) (1) of of the the following following isis the the reason reason for for placing placing the the Governor Governor valves valves on on the the Limiter Limiter while at while at 100%
A. Reduce the A. Reduce the effects effects of of turbine turbine overspeed overspeed inin the the event event ofof aa load load rejection rejection oror Generator Generator output output breaker trip.
breaker trip.
B. Prevent Generator B. Prevent Generator overload overload resulting resulting from from Turbine Turbine Impulse Impulse channel channel failures failures and and malfunctions.
malfunctions.
C. Prevent Generator C. Prevent Generator load load fluctuations fluctuations induced induced from from Impulse Impulse stagestage pressure pressure fluctuations.
fluctuations.
D~ Minimize Generator Minimize Generator load load fluctuations fluctuations toto prevent prevent Reactor Reactor power power from from exceeding exceeding license license limit.
limit.
The correct correct answer answer is D. D.
A: Incorrect - Overspeed and /I or Load Rejection will NOT be affected by the position of the Limiter.
B: Incorrect - Impulse channel effects are prevented by placing control to "IMP S: -
IMP OUT" OUT C: Incorrect - Load fluctuations can occur regardless of valve position limit.
D: Correct - - Placing the Governor Valves on the Limiter after reaching steady state load prevents the Turbine Generator's Generators Internal Speed Control from trying to maintain 60 Hz if Grid frequency drops.
Exam Question Number: 18
Reference:
KA Statement: Knowledge of the interrelations between Generator Voltage and Electric Grid Disturbances and the following: Reactor power.
History: New New - Written for HLC-08 NRC exam.
FINAL FINAL 31 31
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 19. 000001 AK2.08 19.000001 AK2.08 OOl/CONT.
001/CONT. ROD ROD WITHDRAWALIlI2/3.l/3.0IRO/HIGH/N/A/NEW WITHDRAWAL/1/2/3.1/3.OIRO/HIGH/N/AJNEW - 2008/AOP-001-005
- 2008/AOP-001-005 Given the Given the following:
following:
The plant
- The
- plant isis atat 45% power, with 45% power, with power power escalation escalation toto 100%
100% RTPRTP in in progress.
progress.
Control Bank
- Control
- Bank "D"D rods rods are are at at 185 185 steps steps on on the the step step counters.
counters.
Rod Control
- Rod
- Control is is in in AUTOMATIC.
AUTOMATIC.
The RO
- The
- observes ONLY RO observes ONLY Control Control Bank Bank "D" D rods' rods IRPI IRPI indicators indicators are are increasing.
increasing.
-T
- AVG is 1.5 TAVG 1 .5 of lower than TTREE.
°F lower REF' The described conditions indicate indicate...
A. an electrical problem on Instrument Bus 77A. A.
B. a Control Bank "D" D Signal Conditioning Module fault.
C. a Normal Rod Withdrawal.
D~ an Uncontrolled Rod Withdrawal.
The correct answer is D.
With TTAVG AVG 1.51 .5 of
°F lower than T REF the bistables for outward rod motion are calling rods to TREE move. Several years ago RNP disconnected the control circuitry to allow for actual rod movement, but the bistables still remain functional. No outward rod motion will occur when the Rod Control switch is in Automatic.
A: Incorrect - Instrument Bus 7
- A does supply power to ALL IRPls, 7A IRPIs, but since ONLY CB "D" D IRPIs are changing this CANNOT be the cause. If the candidate misunderstood IRPls misunderstood the power supply configuration they could choose this as a correct answer.
B: Incorrect - Each IRPI has its own SCM, if the candidate misunderstoo misunderstood d that there is NO single SCM for a rod bank or group, they could select this as a correct answer.
C: Incorrect - The temperature deviation is sufficient for tripping the bistables for outward rod motion, but since RNP has NO automatic Rod Withdrawal, Rods should NOT be moving.
D: Correct -- Since RNP normally has NO Automatic Rod Withdrawal, rods should NOT be moving.
moving.
32 32
HLC-08 NRC HLC-08 NRC Written Exam Written Exam Exam Question Exam Question Number:
Number: 19 19
Reference:
SD-009,
Reference:
SD-009, IRPI, IRPI, Figure Figure 22.
22.
KA Statement: Knowledge KA Knowledge of of the interrelations interrelations between between thethe Continuous Continuous RodRod Withdrawal and and Individual rod the following: Individual display lights rod display lights and and indications.
indications.
History: New History: New - Written
- Written for HLC-08 NRC for HLC-08 exam.
NRC exam.
FINAL FINAL 33 33
HLC-08 HLC-08 NRCNRC Written Written Exam Exam 20.
- 20. 000005 000005 AK3.01 AK3 .01 OOI/INOPERABLE/STUCK 00 1/INOPERABLE/STUCK RODI1I2/4.0/4.3IROIHIGHIN/AIFARLEY RODII/214.0/4. 3/RO/HIGH/N/A/FARLEY - 200lIEPP-4-004
- 200 1IEPP-4-004 Given the Given the following:
following:
The plant
- The
- plant has experienced aa Reactorrrurbine has experienced Reactor/Turbine Trip Trip from from 100%
100% RTP.
RTP.
The crew
- The
- crew is is performing performing EPP-4, EPP-4, REACTOR REACTOR TRIP TRIP RESPONSE.
RESPONSE.
Rod Bottom
- Rod
- Bottom Light Light for for Control Control Rod Rod M6M6 is is NOT NOT lit.
lit.
IRPI shows Control
- IRPI
- Control Rod Rod M6M6 at at 225 steps.
steps.
Which ONE (1) (1) of the following action(s), if any, mustmust be be performed lAW lAW EPP-4 EPP-4 and why?
Borate to 1950 A. Borate 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 D~ No action required.
Adequate shutdown margin exists.
The correct answer is O. D.
A: Incorrect - Boration to 1950 PPM boron is required for refueling shutdown boron concentration. This is required in FRP-S.1 when 2 or more control rods are stuck out. Only 1 1 control rod is stuck out.
B: Incorrect - Adequate SOM
- SDM does exist, accident analysis assumes the most reactive rod is stuck out, NO action is required.
C: Incorrect - Adequate SDM
- SOM does exist, this is the required action for TWO or more rods stuck out as directed by EPP-4.
D:
0: Correct - - Accident Analysis supports adequate shutdown margin with one rod stuck out.
Exam Exam Question Question Number:
Number: 20 20
Reference:
EPP-4, Pages 10 10 and 11; 11; EPP-4 EPP-4 BD,BO, Pages 88 and 9.
KA Statement:
Statement: Knowledge Knowledge of of the reasons for the following responses as as they apply apply toto the Inoperable Inoperable / Stuck Stuck Control Rod: Boration and Control Rod: and emergency boration boration inin the the event event of of aa stuck stuck rod rod during during trip or or normal normal evolutions.
evolutions.
History:
History: Modified Modified answer answer to to meet meet RNP RNP procedures, procedures, changed changed answer answer from boration boration required required (Farley requirement) to (Farley requirement) to no no boration boration required.
required.
34 34
HLC-08 NRC Written Exam FINAL 35 35
HLC-08 NRC Written Exam
- 21. 000028 G2.4.4 OOllPZR 21.00002802.4.4 OO1JPZR LVL MALFUNCTION/lI2l4.S/4.7IROIHIOH/N/A/NEW MALFUNCTION/1/2/4.5/4.7/RO/HIGHIN/AINEW - 2008IPATH-I-002
- 2008/PATH-1-002 Given the following:
- The plant is operating at 50% RTP
- RTP following a 50% load rejection from 100% 100% RTP.
RTP.
- APP-003-C8, PZR
- PZR PROT 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.
CY' PATH-i.
FRP-S.i, RESPONSE TO NUCLEAR POWER GENERATION / ATWS.
D. FRP-S.1, The correct answer is C.
PATH-i would take priority over AOP-015 A: Incorrect - PATH-1
- AOP-01 5 due to having high PZR levels.
B: Incorrect - No instrument failure is indicated.
C: Correct - - Pressurizer Levels above 91 % (2/3 while greater than P-7) should have initiated a reactor trip. According to OMM-022, EMERGENCY OPERATING PROCEDURES USER'S USERS GUIDE, Section 8.2.1, "Entry Entry into the EOP Network will be required when the following conditions occur: If at any time a reactor trip or PATH-i safety injection occurs or is required, the Operator will enter PATH-1."
PATH-i is required, FRP-S.1 D: Incorrect - PATH-1
- FRP-S.i is NOT a direct entry procedure.
Exam Question Number: 21
Reference:
APP-003-C8; OMM-022, Page 10, Step 8.2.1.1.
KA Statement: Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
History: New - Written for HLC-08 NRC exam.
FINAL 36 36
HLC-08 NRC Written Exam
- 22. 000032 AKl.OI 22.000032 AK1.01 OOIILOSS 001/LOSS OF SR NI/l/2/2.5/3.IIROIHIGHINIA/TURKEY NII1/2/2.5/3.1IROIHIGH!N/AJTURKEY POINT - 200l/COMPON
- 2001/COMPON CHAP 2-020 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 1400 VDC, instead of the normal 16001600 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 willwill....
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~
D decrease because reduced voltage results in fewer ion pairs reaching the detector electrodes due to lower potential applied to the detector.
The correct answer is D.
A: Incorrect - Detector high voltage is ONLY applied to the detector, NOT the amplifier circuits. Any reduction in detector high voltage will NOT affect the operation of the Pre-amplifier.
B: Incorrect - Pulse height discriminator circuit has no relation to the High Voltage applied to the detector.
C: Incorrect - There is NO gamma compensation circuit (IR Detector Only).
D:
0: Correct -- The high voltage is set at 1600 1600 VDC in the Proportional Region of the detector curve, such that a significant reduction in applied voltage will result in a reduced count rate.
Exam Question Number: 22
Reference:
SD-010, SD-OlO, NI, Pages 16-17, Figure 7.
KA Statement: Knowledge of the operational implications of the following concepts as they apply to Loss of Source Range Nuclear Instrumentation:
Instrumentation: Effects of voltage changes on performance.
History: Modified by changing three distractors and updating to RNP equipment voltages.
FINAL 37 37
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 23. 000037 AAl.06 23.000037 AA1.06 OOl/SO TUBE LEAK/l/2/3.S/3.9/RO/HIGH/N/A/NEW OO1ISG TUBE LEAK/1/2/3.8/3.9/RO/HIGHIN/AJNEW - 200S/AOP-035-002
- 2008/AOP-035-002 Given the Given the following:
following:
The plant
- The
- plant isis at at 30%
30% RTP, RTP, with with aa power power escalation escalation in in progress.
progress.
APP-036-C7, R-24
- APP-036-C7,
- R-24 MONITOR MONITOR HI HI has has just alarmed.
alarmed.
Which ONE (1) of the the following describes the R-24, MAIN the R-24, MAIN STEAM STEAM LINE N-16 DETECTOR LINE N-16 DETECTOR alarm and what alarm what actions are are required required for current current plant plant conditions?
R-24 alarm is valid, crew must enter AOP-005, RADIATION A. The R-24 RADIATION MONITORING MONITORING SYSTEM.
B R-24 information is useful only for trending. IfIf R-15, CONDENSER AIR EJECTOR Br' 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 B and C.
The correct answer is B.
A: Incorrect - AOP-005 is to be entered when "one
- one or more Plant Process, Area, or Accident Monitors are in alarm. R-24 is NOT an entry condition for AOP-005.
Radiation Monitors" R-24 is an N-16 monitor.
B: Correct - - Entry into AOP-035 is NOT justified unless R-15 R-1 5 or R-19 R-1 9 indication confirms primary to secondary leakage, due to the limitations of R-24 when power is less than 40%.
C: Incorrect - Confirmation of S/G Tube Leakage is required for AOP entry. This would be confirmed by an increasing trend.
D: Incorrect - Action to adjust leakage model firmware is to make R-24 valid below 40%
power. This may be performed during extended low power operation.
Adjustment Adjustment of of firmware does does NOT NOT provide provide confirmation of S/G leakage, of S/G leakage, itit must must be confirmed by be by diverse diverse indications from other other plant parameters.
Exam Question Number:Number: 23
Reference:
Reference:
AOP-035, Page Page 3;3; APP-036-C7.
APP-036-C7.
KA KA Statement: Ability to Statement: Ability to operate operate and or monitor and / or monitor the the following following asas they they apply apply to to the the Steam Steam Generator Generator TubeTube Leak: Main steam Leak: Main steam line line rad rad monitor monitor meters.
meters.
History:
History: New New - Written
- Written forfor HLC-08 HLC-08 NRCNRC Exam.
Exam.
FINAL FINAL 38 38
HLC-08 HLC-08 NRC NRC Written Written Exam Exam 24.
- 24. 000068 000068 AA2.05 AA2.05 OOl/CONTROL 001/CONTROL ROOM ROOM EVAC/l/2/4.2/4.3IROILOW/N/A/NEW EVAC/1/2/4.2/4.3[ROILOW/N/A1NEW - 2008/AOP-004-005
- 2008/AOP-004-005 Which ONE Which ONE (1) (1) of of the the following following describes describes the the type type of of indication indication available available and and location location OUTSIDE of OUTSIDE of the the Control Control Room Room to to monitor monitor the the availability availability of of Heat Heat Sink?
Sink?
A. Steam Flow A. Steam Flow andand Feedwater Feedwater Flow Flow for for all all 33 S/Gs SIGs atat the the Secondary Secondary Control Control Panel.
Panel.
B. All B. All 33 S/G S/G Levels Levels and and Pressures Pressures at at the the Charging Charging PumpPump Room Room Panel.
Panel.
C'r All 33 S/G C All Levels and S/G Levels and Pressures at the Pressures at the Secondary Secondary Control Control Panel.
Panel.
D. Steam Flow Flow and and Feedwater Flow for all 3 S/Gs at at the Charging Pump Room Panel.
The correct answer is is C.
A: Incorrect - There are NO Steam Flow/Feed Flow indications available outside of the Control Room at the Secondary Control Panel.
B: Incorrect - S/G Pressure is NOT available at the Charging Pump Room Panel.
C: Correct - -
WR S/G Levels and S/G PORVs and PICs are available at the Secondary Control Panel.
D: Incorrect - There are NO Steam Flow/Feed Flow indications available outside of the Control Room at the Charging Pump Room Panel.
Exam Question Number: 24
Reference:
AOP-004, Pages 18 and 26.
KA Statement: Ability to determine and interpret the following as they apply to the Control Room Evacuation: Availability of heat sink.
History: New - Written for HLC-08 NRC exam.
FINAL 39 39
HLC-08 NRC Written Exam
- 25. 000069 AKl.Ol AK1.01 OOlILOSS INTEG/1/2/2.6/3.1/RO/HIGH/N/A/NEW - 200S/COMPON 001/LOSS OF CONT INTEG/lI2I2.6/3.1/ROIHIGHJN/A/NEW - 2008/COMPON CHAP 2-010 Given the following:
Large Break LOCA
- A Large
- 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.
A. 25%
B. 30%
C. 50%
C.50%
D 70%
DY<
The correct answer is D.
A: Incorrect - Square of the ratio of current CV pressure to initial CV pressure.
B: Incorrect - Algebraic inverse of the correct answer. Candidate calculates a 70% reduction.
C: Incorrect - The direct ratio of pressure reduction, without allowing for the square root.
D: Correct -- The pressure reduction is 18 PSIG, 70% is the square root of initial pressure over current pressure.
Exam Question Number: 25 G FES, Detectors section of Components, Equation 2-2.
Reference:
GFES, KA Statement: Knowledge of the operational implications of the following concepts as they apply to Loss of Containment Integrity: Effect of pressure on leak rate.
History: New - Written for HLC-08 NRC exam.
FINAL 40
HLC-08 NRC Written Exam
- 26. WE 13 EK2.2 OOl/SG WEl3 00 1/SO OVERPRESSURE/1/2/3.0/3.2IROIHIGHIN/A/NEW OVERPRESSURE/1/2/3 .0/3.2/RO/HIGHIN/A/NEW - 200S/FRP-H.2-002
- 2008/FRP-H.2-002 Given the following:
Reactor trip has occurred. The crew is preparing to transition from PATH-1
- A Reactor
- PATH-i after checking SI NOT actuated OR required.
- ALL S/G levels are 10-14%
- 10-i 4% Narrow Range.
- AFW flow indicates 400 GPM.
- S/G "A"
- A and "B" B pressures indicate 11080080 PSIG.
- S/G "c"
- C 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, FRP-H.i, RESPONSE TO LOSS OF SECONDARY HEAT SINK.
B~
B YELLOW; Isolate feedwater to affected S/G lAW FRP-H.2, RESPONSE TO S/G OVERPRESSU RE.
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 16% lAW FRP-H.5, RESPONSE TO STEAM GENERATOR LOW LEVEL.
The correct answer is B.
A: Incorrect - No RED status, but correct actions for FRP-H.1.
B: Correct -- Any S/G pressure> 1140 PSIG is YELLOW status, entry condition for FRP-H.2, initial action is to ISOLATE flow to affected S/G.
C: Incorrect - FRP-H.3 YELLOW would apply IF affected S/G Level was high.
D:
0: Incorrect - Incorrect entry, S/G levels are required to be less than 8% for FRP-H.5 entry.
Exam Question Number: 26
Reference:
FRP-H.2, Pages 3-4; H.1, H.i, Page 3; H.3, Page 3; H.5, Page 3; CSFST, Page 5.
KA Statement: Knowledge of the interrelations between the (Steam Generator Overpressure) and the following: Facilitys Facility's heat removal systems, including inCluding primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
History: New - Written for HLC-08 NRC Exam.
FINAL 41
HLC-08 NRC HLC-08 Written Exam NRC Written Exam 27.
- 27. WE15 WE15 02.2.38 02.2.38 OOl/CTMT OO1!CTMT FLOODINO/l/2/3.6/4.5IRO/LOW/NINRNP FLOODING/1/2/3.6/4.5/RO/LOWIN/AIRNP AUDIT AUDIT - 20011FRP-J.2-003
- 2001/FRP-J.2-003 Given the Given the following:
following:
-A
- A Large Large Break Break LOCA LOCA hashas occurred.
occurred.
ALL systems
- ALL
- systems automatically respond respond asas expected.
expected.
CV Sump level
- CV
- indicates 378 level indicates 378 inches inches and and is is increasing increasing slowly.
Which ONE (1)
Which (1) of the following identifies identifies the MAJOR MAJOR concern or license license limitation limitation associated associated with this condition lAW FRP-J.2,FRP-J.2, RESPONSE RESPONSE TO CONTAINMENT FLOODING? 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~
CY 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.
The correct answer is C.
A: Incorrect - ITS Bases addresses Containment Integrity as part of OPERABILITY and more water inside the Containment would reduce the total volume, but analysis assumptions already takes this into account and the Bases does NOT address an increased pressure as a concern.
B: Incorrect - AOP-032, RESPONSE TO FLOODING FROM THE FIRE PROTECTION SYSTEM Bases addresses the dilution of the CV Sump as an unanalyzed "unanalyzed condition that would dilute LOCA water before a sump recirc condition.
condition." The Basis for FRP-J.2, CONTAINMENT FLOODING does NOT address reactivity as a concern. Both CCW and Firewater are isolated on Phase A and Phase BB Containment isolation which would occur during a LBLOCA.
C: Correct - - The purpose purpose ofof the sump is to collect and divert water in areas that will NOTNOT affect vital plant equipment. Flooding may jeopardize that function.
D: Incorrect Incorrect - A loss of ability to remove heat is dealt with in other procedures.
- procedures. The major major concern in FRP-J.2 in FRP-J.2 isis Containment Containment flooding.
42 42
HLC-08 NRC Written Exam Number: 27 Exam Question Number:
Page 3; AOP-032 BD, Page 4 and 6.
Reference:
FRP-J.2 BD, Page KA Statement: Knowledge of conditions and limitations in the facility license.
History: Direct from Bank.
FINAL 43
HLC-08 NRC Written Exam
- 28. 003 K6.04 28.003 K604 OOIIREAC COOL PUMP/2/1/2.8/3.1/RO/LOW/N/AINEW - 200SJCCW-009 001/REAC COOLPUMP/2J1/2.SJ3.IIRO/LOW/NJA/NEW - 2008/CCW-009 During Containment isolation valve testing, CCW-716A, CCW During COW to RCP ISOLATION VALVE, was inadvertently CLOSED with RCP RCP "B" B running.
Which ONE (1) of the following RCP POP components suffered a loss of cooling water flow?
A. Motor Bearing Oil Coolers ONLY.
B. Thermal Barrier Heat Exchangers ONLY.
C!"
C Thermal Barrier Heat Exchangers and Motor Bearing Oil Coolers.
D. Motor Air Coolers, Thermal Barrier Heat Exchangers, and Motor Bearing Oil Coolers.
The correct answer is C.
A: Incorrect - Motor Oil Cooler is correct, but NOT a complete answer as Thermal Barrier HX is also cooled by CCW.
B: Incorrect - Thermal Barrier HX is correct, but NOT a complete answer as the Motor Oil Cooler is also cooled by CCW.
C: Correct -- CCW -71 6A is the CCW COW -716A COW supply to all RCP cooling. Discharge lines have seperate isolation valves.
D: Incorrect - Motor Air Coolers are CV HVH units which are cooled with Service Water.
0: -
Exam Question Number: 28
Reference:
SD-013, CCW, COW, Pages 20-21, Figure 3.
KA Statement: Knowledge of the effect of a loss or malfunction on the following will have on the ROPS: Containment isolation valves affecting RCP RCPS: ROP operation.
History: New - Written for HLC-08 NRC exam.
FINAL 44
HLC-08 NRC HLC-08 NRC Written Written Exam Exam 29.
- 29. 004 A1.05 00l/CVCS/2/l/2.9/3.2IROIHIGH/N/A/NEW 004 Al.OS 001/CVCS/2/1/2.9/3.2/RO[HIGHIN/AJNEW - 2008/CVCS-008
- 2008/CVCS-008 Given the Given the following:
following:
-A
- A S/G SIG Tube Tube Rupture Rupture has has occurred.
occurred.
- An RCS
- RCS Cooldown Cooldown has has been been performed performed lAW lAW PATH-2.
PATH-2.
Rapid RCS
- Rapid
- RCS depressurization depressurization is in progress.
is in progress.
Which ONE (1) of the following describes how Charging Flow Flow will be controlled during subsequent actions lAW PATH-2?
A':I Reduce Charging A Reduce Charging Flow Flow to MINIMUM MINIMUM when PZR level exceeds 10%.
PZR level 10%.
B. Reduce Charging Flow to MINIMUM ONLY when PZR level exceeds 24%.
C. Maintain MAXIMUM 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 SIG pressure.
The correct answer is A.
During rapid depressurization of the RCS to equalize RCS and ruptured S/G SIG pressure as directed by PATH-2, PZR level will be regained rapidly. Charging flow is reduced to minumum to allow RCS depressurization while attempting to maintain PZR level less than 71 71%.
A: Correct - - Reducing Charging flow to minimum will allow the RCS to be depressurized and provide additional time prior to exceeding 71% 71 % PZR level which will cause the depressurization to be stopped. This is performed when PZR level returns to scale at 10% level.
B: Incorrect - Reducing Charging flow to minimum will allow the RCS to be depressurized and provide additional time prior to exceeding 71% 71 % PZR level which will cause the depressurization depressurization to be stopped. This is performed when PZR level returns to scale at 10% level, NOT at 24% level.
C: Incorrect Incorrect - Charging flow will be minimized at 10%
- 10% PZR level, level, NOT left at maximum flow until 24% PZR level is until 24% is reached.
D: Incorrect - Charging flow will be minimized at 10%
- 10% PZR level, NOT left at maximum flow until RCS pressure is less than ruptured SIG S/G pressure.
45 45
HLC-08 NRC Written HLC-08 NRC Written Exam Exam Exam Question Exam Number: 29 Question Number: 29
Reference:
PATH-2.
Reference:
PATI+2.
KA Statement:
KA Statement: Ability to to predict predict and/or monitor changes and/or monitor changes inin parameters parameters (to (to prevent prevent exceeding exceeding design limits) associated with operating the CVCS controls including:
CVCS controls including: S/G S/G pressure and level.
pressure level.
History: New History: New - Written
- Written for for HLC-08 HLC-08 NRC NRC exam.
exam.
FINAL 46 46
HLC-08 HLC-08 NRC NRC Written Written Exam Exam
- 30. 005 Kl.06
- 30. 005 OO1IRHRI2/1/3.5/3.6/RO/HIGHJN/AJNEW - 200SIRHR-00S K1.06 001IRHRJ2/1/3.5/3.6IROIHIGHINIA/NEW - 2008/RHR-008 Given the Given the following:
following:
-A
- A Small Small Break Break LOCA LOCA occurred occurred 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> hours ago.
ago.
RCS pressure
- RCS
- pressure is is 210 210 PSIG.
PSIG.
The alignment
- The
- alignment of of the the ECCS ECCS for for Cold Cold Leg Leg Recirculation is complete Recirculation is complete lAW lAW EPP-9, EPP-9, TRANSFER TO TRANSFER TO COLD COLD LEG LEG RECIRCULATION.
RECIRCULATION.
Which ONE (1) of the following describes the current RHRlECCS RHR/ECCS alignment?
ONE (1)(1) RHR RHR PumpPump andand ONE ONE (1) SI Pump (1) SI Pump operating operating in in series series (Piggy-back (Piggy-back mode),
mode), with the ...
the...
A. RHR AND SI Pump 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 B:I 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.
The correct answer is B.
A: Incorrect - No CV sump suction to the SI pumps.
B: Correct - - This is the proper alignment and injection path due to RCS pressure being greater than the RHR Pump shutoff head (110 PSIG).
C: Incorrect - RCS pressure is above RHR Pump shutoff head.
D:
0: Incorrect - Correct alignment for Hot leg recirculation 11
- 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> after the accident.
Exam Question Number: 30
Reference:
SD-002, SI, Pages 9, 10, 10, 11, 11, Figure 5.
KA Statement:
Statement: Knowledge of the physical connections and/or cause-effect relationships between between the RHRS and the foiJowing following systems: ECCS.
History: New - Written for HLC-08 NRC exam.
- exam.
FINAL FINAL 47 47
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 31. 006 K2.01 31.006 K2.01 OOlIEMERG OO1IEMERG CORE CORE COOLING/2/113.6/3.9IROIHIGHINIA/NEW COOLING/2/1/3.6/3.9/RO/HIGH/N/AINEW - 2008/SI-006
- 20081S1-006 The plant The plant isis operating operating at at 100%
100% RTPRTP with with aa normal electrical lineup.
normal electrical lineup.
Breaker 52/10,
- Breaker
- 4kV Bus 52/1 0, 4kV Bus 1-2 Tie Bkr, 1-2 Tie Bkr, trips trips OPEN.
OPEN.
An inadvertent
- An
- inadvertent Safety Injection signal Safety Injection signal occurs.
occurs.
Which ONE Which ONE (1) (1) ofof the the following describes the following describes the source source ofof power power to to the the SI SI Pumps?
Pumps?
A. SI A. SI Pumps Pumps "A" and "c" A and C are powered from are powered from off-site off-site power.
power.
B SI Pump "A" B!'" A is powered from EDG A, SI Pump "c" EDG "A", C is powered from off-site power.
C. SI SI Pump Pump "A" A isis powered powered from off-site power, power, SI PumpPump "c" C isis powered powered from EDG EDG "B".
B.
D. SI Pumps "A" A and "c"C are powered from EDG "A" A and "B",
B, respectively.
The correct answer is B.
A: Incorrect - When breaker 52/10 trips, 4kV Bus 2 de-energizes, this de-energizes 480V Bus 11 and E-1. EDG "A" A starts and energizes 480V Bus E-1. ONLY E-1 is energized from the EDG B: Correct - - When breaker 52/10 trips, 4kV Bus 2 de-energizes, this de-energizes 480V Bus 11 and E-1. EDG "A" A starts and energizes 480V Bus E-1. Bus E-2 remains energized from off-site power.
C: Incorrect - EDG "B"
- B starts on SI signal but does NOT energize 480V Bus E-2.
D: Incorrect - EDG "B"
- B starts on SI signal but does NOT energize 480V Bus E-2.
Exam Question Number: 31
Reference:
OP-603, Page 15; 15; GP-005, Page 54, Section 8.4.42; SD-039 KVAC, Pages 12-14, 12-14, Figure 2.
KA Statement: Knowledge of bus power supplies to the following: ECCS pumps.
History: New - Written for HLC-08 NRC exam.
FINAL 48 48
HLC-08 NRC HLC-08 NRC Written Written ExamExam
- 32. 007 K4.01 32.007 K4.01 OOlIPRT/QUENCH 001/PRT/QUENCH TANKl2/1/2.6/2.9/ROIHIGH/N/A/NEW TANKI2/1/2.6!2.9/RO/HIGHIN/A!NEW - 20081PZR-008
- 2008/PZR-008 Given the Given the following:
following:
The plant
- The
- plant is is in in MODE MODE 33 following following aa load load rejection rejection and and Reactor Reactor Trip Trip from from 100%
100% RTP.
RTP.
During the
- During
- the load load rejection/trip rejection/trip event, event, aa Pressurizer Pressurizer PORV PORV opened opened for for several several seconds seconds and and reseated.
reseated.
Pressurizer Relief
- Pressurizer
- Relief Tank Pressure, Pressure, Temperature and and Level Level have increased:
have increased:
- Pressure =
- = 4.8 PSIG.
PSIG.
- Temperature =
- 153°F
= 153 of (APP-003-B3, PRT 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%, then alternately refill with Primary Water and B!'"
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%.
The correct answer is B.
A: Incorrect - A continuous drain and fill is incorrect because the tank will fill faster than the drain capability. NO procedures support this action.
B:
B: Correct - - For high high PRT temperature, OP-103OP-103 directs directs draining the PRT PRT to 70%-74%, then to fill with PW PW to cool the PRT.
PRT.
C: Incorrect Incorrect - For rapid cooling and if level allows,
- allows, the PRT is filled first then allowed to soak
'soak' for 1010 minutes and then drained.
drained. Precautions and Limitations state that the tank should should NOT NOT bebe filled above 80% level.
above 80% level.
D:
D: Incorrect Incorrect - RNP
- RNP has has NO NO automatic automatic Primary Primary Water Water Spray Spray available to the available to the PRT.
PRT.
49 49
HLC-08 HLC-08 NRC NRC Written Written Exam Exam Exam Question Exam Question Number:
Number: 3232
Reference:
Reference:
OP-103, Pages Pages 6-10; 6-10; APP-003-83, APP-003-83, SO-059 SD-059 PZR/PRT, PZR/PRT, Figure Figure 1.
1.
KA Statement: Knowledge KA Knowledge of PRTS PRTS design feature(s) and/or and/or interlock(s) interlock(s) which provide provide for the Quench tank cooling.
following: Quench cooling.
History: New History: New - Written
- Written for for HLC-08 HLC-08 NRC NRC exam.
exam.
FINAL 50 50
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 33. 008 A4.05 33.008 A4.05 001JCCWI2J1I2.712.5IROILOWfNJA/NEW 001/CCW/2/1/2.7/2.51R0/LOWIN/AINEW - 2008JCCW-009
- 2008/CCW-009 Given the Given the following:
following:
The plant
- The
- plant isis in in EPP-10, EPP-10, TRANSFER TRANSFER TO TO LONG LONG TERMTERM RECIRCULATION.
RECIRCULATION.
APP-002-E5, SI
- APP-002-E5,
- SI PMP PMP COOL COOL WTR WTR LOLO FLOW FLOW alarm is received.
alarm is received.
Which ONE (1) (1) of of the following describes describes the cause and effect cause and effect of of the alarm?
alarm?
A. Loss of CCW COW to the SI Pump Bearing Heat Heat Exchangers; Exchangers; can result result in in overheating the pump bearings.
B!'" Loss of CCW B Loss COW to the SI Pump Pump Seal Coolers; can result result in in loss loss of SI Pump 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.
The correct answer is B.
A: Incorrect - CCW
- COW supplies SI Pump Seal Coolers, NOT Bearing Heat Exchangers.
B: Correct - - COW Low flow (50 GPM) to the Seal Coolers initiates the alarm.
CCW C: Incorrect - SW does NOT supply SI Pump Bearing Heat Exchangers. SW does supply SI Pump Thrust Bearing cooling bath, but has NO alarm.
D: Incorrect - SW does NOT supply SI Pump Seal Coolers. SW does supply SI Pump Thrust 0: -
Bearing cooling bath, but has NO alarm.
Exam Question Number: 33
Reference:
APP-002-E5; SD-013 SO-013 CCW, Page 13. 13.
KA Statement: Ability to manually operate and/or monitor in the control room: Normal COW-header CCW -header total flow rate and the flow rates to the components cooled by the COWS.
CCWS.
History: New New - Written for HLC-08 NRC
- NRC exam.
exam.
FINAL 51 51
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 34. 010
- 34. 010 K5.0l K5.01 OOllPZR 001!PZR PRESSURE PRESSURE CONTROLl2/l/3.5/4.0IROIHIGHIN/A/NEW CONTROL/2/1/3.5/4.01R0/HIGH!N/AJNEW - 2008ITHERMO
- 2008/THERMO CHAP CHAP 3-008 3-008 Given the Given the following:
following:
The plant
- The
- plant isis in in MODE MODE 3. 3.
The crew
- The
- performing aa plant crew isis performing plant heatup.
heatup.
Pressurizer level
- Pressurizer
- level is is 50%.
50%.
BOTH Pressurizer
- BOTH
- Pressurizer Liquid Liquid Space Space andand Steam Steam Space temperature indicators Space temperature indicators read 622 of.
read 622 °F.
Which ONE (1) of the following indicates actual Pressurizer Pressure? Pressure?
P1-444 == 1783 A. PI-444 PSIG.
1783 PSIG.
Bk PI-445 B:I P1-445 == 1798 PSIG.
P1-455 == 1813 C. PI-455 1813 PSIG.
P1-456 == 1828 PSIG.
D. PI-456 The correct answer is B.
A: Incorrect - Subtracted 14.7 PSI from corrected answer.
B: Correct - - Using Steam Tables, interpolate for 622 of. F. 620 of 0 °F == 1786.9 PSIA, 624 0 F=
°F=
1839.0 PSIA. Therefore 622 of °F =
1812.95 PSIA. Convert 1812.95 PSIA to PSIG: 1812.95 PSIA - 14.7 PSI
- = 1798.25 PSIG C: Incorrect - Listed answer without adjusting for PSIA.
D: Incorrect - Added 14.7 PSI instead of subtracting to obtain PSIG.
0: -
Exam Question Number: 34
Reference:
Steam Tables; SD-059 PZR/PRT, Figure 1. 1.
KA Statement: Knowledge of the operational implications of the following concepts as the apply to the PZR PCS: Determination of condition of fluid in PZR, using steam tables.
History: New New - Written for HLC-08 NRC exam.
FINAL 52 52
HLC-08 NRC Written Exam
- 35. K6.01 OOllRX 012 K6.0l PROTECTION/2/1/2.8!3.3/RO/HIGHJN/AICOOK - 20021RPS-006 OO1IRX PROTECTIONI2!1I2.8/3.3IROIHIGHJN/A/COOK - 2002IRPS-006 Given the following:
- The plant
- is operating at 6% RTP plant is preparing for Turbine roll.
RTP preparing 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
- PZR actions are complete per AOP-025, RTGB INSTRUMENT FAILURE.
- PZR level is currently 25% on Channels LT-460 and 461.
Which ONE (1) of the following describes the effects on the plant if PZR level channel LLT-461 T-461 fails HIGH?
A. A Reactor Trip due to high PZR level.
B. A Reactor Trip due to low PZR pressure.
CY' C The Reactor will NOT trip, signal is blocked by P-7.
D. The Reactor will NOT trip, signal is blocked by P-10. P-b.
The correct answer is C.
A: Incorrect - A High Level trip signal is generated from the channel failure, but it is blocked by P-7.
B: Incorrect ncorrect - A trip will NOT occur due to low PZR pressure due to being blocked by P-7.
C: Correct - - With Channel LT-459 in the tripped condition the High level Rx Trip signal will be made up for 1 1 channel (1/2 coincidence on remaining channels). The level control selector switch for the Pressurizer is in the 461 REPLACE 459 position with channel LLT-461 T -461 as the controlling channel. When it fails high a High Level Rx Trip signal is generated but it is blocked by P-7 (Reactor and Turbine power both below 10%).
10%).
D: Incorrect - Signal is blocked by Permissive P-7, (Turbine Power) NOT P-iC,
- P-10, (NI Power).
Exam Question Number: 35 SD-Cl 1 RPS, Pages 20-21, 29, Figure 31.
Reference:
SD-011 KA Statement: Knowledge of the effect of a loss or malfunction of the following will have on the RPS: Bistables and bistable test equipment.
History: Modified; removed LCO actions.
FINAL 53
HLC-08 NRC HLC-08 NRC Written ExamExam 36.
- 36. 013 013 G2.2.38 G2.2.38 001/ESFASI2/l/3.6/4.5IRO/HIGH/NIAfNEW 00 1/ESFAS/2/1/3 .614.5/ROIHIGHINIAJNEW - 2008/ESF-008
- 2008/ESF-008 Given the Given the following:
- The plant
- is operating plant is operating at at 100%
100% RTP RTP when PT-455, PT-455, PZR PZR PRESSURE PRESSURE fails LOW.
LOW.
Prior to OWP-029,
- Prior OWP-029, PPT-1 PPT-1 implementation, implementation, a loss loss of power to INSTRUMENT 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 "A" A 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 "B" B 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 />.
CY PZR Pressure ESFAS bistables on Train "A" C~ A AND Train "B"B 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 "A" A AND Train "B"B are tripped.
ALL Instrumentation LCOs are currently met.
The correct answer is C.
PT-455 feeds BOTH high and low pressure RPS on BOTH Train "A" A and Train "B" B and low pressure bistables for ESFAS. When PT-455 fails LOW, ONLY the low pressure RPS and ESFAS bistables are actuated. When Instrument Bus 2 fails, ALL three of the PZR pressure bistables (high and low) deenergize to actuate.
A: Incorrect - The ESFAS bistables provide input to BOTH Trains, so BOTH would be tripped.
B: Incorrect - The ESFAS bistables provide input to BOTH Trains, so BOTH would be tripped.
C: Correct - - The ESFAS bistables provide input to BOTH Trains, so BOTH are tripped.The loss of Instrument Bus 22 will cause a Reactor Trip and Safety Injection signal to be generated. Due to the failure of 2 PZR pressure transmitters, the bistables CANNOT be tripped in the Hagan Racks, thus the plant must be placed in a mode where the LCO is NOT applicable.
D: Incorrect - The ESFAS bistables are tripped for PT-455 and PT-456. Instrumentation LCOs are NOT met until the bistables have been placed in the tripped position in the Hagan Racks. Due to the failure of 22 PZR pressure transmitters, the bistables CANNOT be tripped in the Hagan Hagan Racks, thus the plant must be placed in aa mode where the LCO is is NOT applicable.
applicable.
54 54
HLC-08 NRC HLC-08 NRC Written Written Exam Exam Exam Question Exam Question Number:
Number: 3636
Reference:
ITS Section
Reference:
ITS Section 3.3.2, 3.3.2, ITS ITS LCO LCO 3.0.3 3.0.3 KA Statement:
KA Statement: Knowledge Knowledge of of conditions conditions and and limitations limitations in in the facility license.
license.
History: New History: New - Written for HLC-08
- HLC-08 NRCNRC exam.
exam.
FINAL FINAL 55 55
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 37. 022
- 37. 022 A3.01 A3.01 OOllCTMT 001/CTMT COOLING/2/114.1/4.3/ROIHIGH/N/A/NEW COOLING/2/1/4.1/4.31R0/HIGHJN/A/NEW - 200S/CVHVAC-00S
- 2008/CVHVAC-008 Given the Given the following:
following:
The plant
- The
- plant isis operating operating at at 100%
100% RTP.
RTP.
HVH-3 has
- HVH-3
- has been experiencing intermittent been experiencing intermittent problems problems and and the the fan fan has has been been stopped.
stopped.
APP-002-E6, HVH-1/2/3/4
- APP-002-E6,
- HVH-1/2/3/4 EMERGENCY EMERGENCY CONTROLCONTROL isis illuminated.
illuminated.
CV RECIRC
- CV
- RECIRC FAN FAN HVH-3 HVH-3 indication indication on the RTGB on the RTGB is is extinguished.
extinguished.
inadvertent Safety Injection
- An inadvertent
- Injection is is received.
received.
Which ONEONE (1) (1) of following describes of the following describes the current current status status of of HVH-3?
HVH-3?
The Fan ...
A is stopped and will NOT AUTO start.
A'f 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.
The correct answer is A.
A: Correct -- The Local-Remote Local-Remote switch inhibits automatic starts of the HVH-3 fan when in LOCAL.
B: Incorrect - In LOCAL, the only place that component can be operated is the Local Control Station.
C: Incorrect - LOCAL-REM LOCAL-REMOTE OTE Switch must be placed in REMOTE for ANY Auto signals to actuate equipment.
D: Incorrect - Low Air flow will alarm (APP-002-C (APP-002-C5),5), but provides NO Auto start feature of the Fan.
Exam Question Number: 37
Reference:
APP-002-APP-002-E6; E6; APP-002-C5 APP-002-C5..
KA Statement:
Statement: Ability to monitor automatic automatic operation of the CCS, including:
including: initiation Initiation of safeguards mode mode of operation.
operation.
History: New - Written for HLC-08 NRC Exam.
History: New -
FINAL FINAL 56 56
HLC-OS HLC-08 NRC NRC Written Written Exam Exam
- 38. 026 3S. 026 Al.OI A1.0l OOl/CTMT 00l/CTMT SPRAY/2/l/3.9/4.2JROIHIGHINIA/RNP SPRAYI2/113.914.21R0/HIGHINJAIRNP AUDIT AUDIT BANKlCSS-005 BANKJCSS-005 Given the Given following:
the following:
-A
- A Reactor Reactor TripTrip and and Safety Safety Injection Injection have have occurred occurred due to aa Faulted due to Faulted S/G.
SIG.
480V Bus
- 480V
- Bus E-1E-1 fault fault occurred occurred coincident coincident with with the the Reactor Reactor Trip and remains Trip and remains deenergized.
deenergized.
The crew
- The
- crew is is performing performing actions actions of of PATH-1 PATH-i andand direction direction has just been has just been given given to to OPEN OPEN the the breaker for HVS-1 breaker HVS-i on on MCC-S.
MCC-5.
Containment pressure
- Containment
- pressure is is 17 17 PSIG PSIG and and increasing.
increasing.
Which ONEONE (1) of the following is the impact on (1) of on the plant plant and the action action required?
required?
Accident analysis has has determined that Containment Containment pressure pressure...
A. MAY exceed design. Immediately transition to FRP-J.1, FRP-J.i, RESPONSE TO HIGH CONTAINMENT PRESSURE, due to an ORANGE condition.
B will NOT exceed design. Continue in PATH-1 B:t PATH-i until SPDS is reset and transition as directed.
C. MAY exceed design. Continue in PATH-1 PATH-i until SPDS is reset and transition as directed.
D. will NOT exceed design. Transition to FRP-J.1 FRP-J.i if 480V Bus E-1 E-i CANNOT be restored.
The correct answer is B.
A: Incorrect - Minimum safeguards equipment (1 train of CV Spray and 2 HVH units) is required to maintain design parameters. CV Spray Pump "B" B and all other Train B
"B" ECCS equipment is operating.
B: Correct - - Pressure will NOT exceed design if 1 1 train of CV Spray and 2 HVH units are operating. The crew should continue in PATH-1 PATH-i until told to transition to another procedure if applicable.
C: Incorrect - Minimum safeguards equipment (1 train of CV Spray and 2 HVH units) is required to maintain design parameters. CV Spray Pump B "B" and all other Train "B" ECCS equipment is operating.
B D: Incorrect - Transition to FRP-J.i
- FRP-J.1 does NOT depend on the restart of CV Spray Pump A. "A". ItIt depends on CV pressure exceeding 42 PSIG or NO NO CV Spray Spray available above 10 PSIG.
10 57 57
HLC-08 NRC HLC-08 NRC Written Written Exam Exam Exam Question Exam Number: 38 Question Number: 38
Reference:
PATH-1
Reference:
PATH-i SO, BD, Pages Pages 7, 7, 88 for grid grid location location E-3 E-3 (E-1 (E-i AND E-2 E-2 energized);
energized); SO-024, SD-024, Containment Spray, Containment Spray, Page Page 7. 7.
KA Statement: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including:
Containment pressure.
History: Modified; removed operator actions to restart CV Spray.
FINAL 58 58
HLC-08 NRC HLC-08 Written Exam NRC Written Exam 39.
- 39. 03902.4.20 039 G2.4.20 OOllMAINIREHEAT 001/MAIN/REHEAT STEAMJ2/l/3.S/4.3IROILOW/N/A/NEW STEAM/211/3.8/4.3/RO/LO W/N/A/NEW - 200S/PATH-2-003
- 2008/PATH-2-003 Given the Given the following:
following:
-A
- A SGTR SGTR has has occurred occurred and and the the crew crew isis performing performing actions actions lAW lAW PATH-2.
PATH-2.
Prior to
- Prior
- to RCS RCS cooldown cooldown toto target target temperature, aa NOTE NOTE warns against against exceeding exceeding Steam Steam Line flow rates Line rates in in excess excess ofof the High High Steam Line flow setpoint.
Steam Line condition is What condition is the NOTE NOTE written to prevent?
prevent?
A. MSIVs isolation on High Steam Line Delta P.
B. An SI initiation on High Steam Line Delta P.
B.
C. An SI initiation on High Steam flow coincident with Low TTAVG. AVG' D MSIVs isolation on High Steam flow coincident with Low T DY' TAVG.
AVG' The correct answer is D.
Rapid RCS cooldown is expected during this event, cooldown rates will be exceeded. The note provides a warning that the Main Steam Line Isolation actuation will still occur if High Steam Line flow setpoints are exceeded during the RCS rapid cooldown.
A: Incorrect - MSIV isolation does NOT occur from High Steam Line Delta P signal.
B: Incorrect - SI initiation will occur from High Steam Line Delta P
- P signal during normal conditions. During this evolution in PATH-2, SI has already been blocked by the Low PZR Pressure I/ High Steam Line Delta P P manual block switch.
C: Incorrect - SI setpoint will be exceeded, however SI is blocked lAW actions of PATH-2 prior to commencing RCS cooldown.
D: Correct - - MSIVs will isolate if the setpoint is exceeded, potentially stopping the cooldown if the crew is using Condenser Steam Dumps.
Exam Question Number:
Exam Question Number: 39 39
Reference:
PATH-2, Grid locations D-2 and and D-3; PATH-2 BD, Pages 69-70.
KA KA Statement:
Statement: Knowledge of of the the operational operational implications of of EOP EOP warnings, cautions, cautions, and and notes.
notes.
History:
History: New New - Written for HLC-08
- HLC-08 NRCNRC Exam.
Exam.
FINAL FINAL 59 59
HLC-08 NRC HLC-08 NRC Written Written Exam Exam 40.
- 40. 059 A2.05 OOllMAIN 059 A2.05 001/MAIN FEEDWATERl2/1/3.1/3.4IRO/LOW/N/A/NEW FEEDWATERJ2/1/3.1/3.41R0/LOW/N/A!NEW - 200S/FW-007
- 2008/FW-007 Given the Given the following:
following:
The plant
- The
- plant is is operating operating at at 50% RTP for 50% RTP for maintenance maintenance on on MFP MFP "B".
B.
The following
- The
- following Main Main Feedwater Feedwater Pump Pump "A"A parameters parameters are are reported:
reported:
Feed pump
- Feed
- pump suction suction pressure pressure isis 225 PSIG.
PSIG.
DP indication
- DP
- indication on ES-i 444A equates on FS-1444A equates to to Main Main Feedwater Feedwater Pump Pump Flow Flow of of 2850 2850 GPM.
GPM.
What is the expected response of the Feedwater System and what actions are required required lAW AOP-0i 0, MAIN FEEDWATERICONDENSATE AOP-010, FEEDWATER/CONDENSATE MALFUNCTION.?
A. trip on low suction pressure ONLY, trip the Reactor and enter PATH-1. PATH-i.
B trip on low suction pressure coincident with low flow, trip the Reactor and enter PATH-1.
8:1 PATH-i.
C. remain running; verify FCV-1444, FCV-i 444, MFP "A" A RECIRC VALVE is OPEN.
HCV-1 459, FEEDWATER HEATER BYPASS is OPEN.
D. remain running; verify HCV-1459, The correct answer is B.
A: Incorrect - Symptoms of a FWP suction line break. Both setpoints needed for FWP trip.
AOP-Oi O.
Enter AOP-01 0.
B: Correct - - Main Feedwater Pump will trip on low suction pressure coincident with low flow.
With NO feedwater pumps operating, proper action is to trip the reactor and PATH-i.
enter PATH-1.
C: Incorrect - MEP
- MFP trips, therefore first part is incorrect. FCV-i444 FCV-1444 OPENS at 1475 1475 GPM and CLOSES at 3i003100 GPM.
D:
0: Incorrect - MFP trips, therefore first part is incorrect. HCV-i459
- HCV-1459 OPENS at 300 PSIG MFP suction pressure. HCV-i HCV-1459459 will be OPEN in an attempt to supply the MFP more flow.
60 60
HLC-08 NRC HLC-08 NRC Written Written Exam Exam Exam Question Exam Number: 40 Question Number: 40
Reference:
APP-007-B3
Reference:
APP-007-B3 and and 05; D5; AOP-01 AOP-010, Page 3.
0, Page 3.
KA Statement:
KA Statement: Ability Ability to to (a)
(a) predict predict the the impacts impacts of the following of the following malfunctions malfunctions or or operations operations on on the MEW; and the MFW; and (b) (b) based based onon those those predictions, predictions, useuse procedures procedures to to correct, correct, control, or control, or mitigate mitigate the the consequences consequences of of those those malfunctions malfunctions or or operations:
operations:
Rupture in Rupture in the the MFW MEW suction suction or or discharge discharge line.
line.
History: New History: New - Written for HLC-08 NRC
- NRC exam FINAL FINAL 61 61
HLC-08 NRC HLC-08 Written Exam NRC Written Exam 41.
- 41. 061 061 A3.01 00l/AFWI2/114.214.2/RO[HIGHINIAJRNP AUDIT A3.0l 001/AFW/2/1/4.2/4.2IROIHIGH/N/A/RNP AUDIT - 2001lAFW-008
- 2001IAFW-008 Given the Given the following:
following:
The plant
- The
- plant is is operating operating atat 30%
30% RTP.
RTP.
- A
- A loss loss of the Startup of the Startup Transformer Transformer occurs occurs concurrent concurrent with with aa Reactor Reactor Trip Trip and and Safety Safety Injection.
Injection.
- All S/G
- SIG levels levels indicate indicate approximately approximately 20%.
20%.
Which ONE (1) of the following describes the AFW system status?
MDAFW Pumps A. MDAFW Pumps ONLYONLY areare running running at at 325 325 GPM GPM each.
B MDAFW BY' MDAFW Pumps Pumps are running at 325 325 GPM GPM each AND SDAFW Pump is 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.
The correct answer is B.
There are 2 pieces of information required to answer this question correctly. The MDAFW Pumps started from the SI sequencer and the SDAFW Pump started from the undervoltage signal from 4160V Busses 11 and 4.
A: Incorrect - MDAFW Pumps are operating at 325 GPM each. The SDAFW Pump started 41 60V Busses 11 and 4.
from the undervoltage signal of 4160V B: Correct - - MDAFW Pumps are operating at 325 GPM each and were started from the SI sequencer after 480V Busses E-1 and E-2 were energized from their respective EDG. SDAFW Pump started from the undervoltage signal from 4160V Busses 1 1 and 4 and is operating at 500 GPM.
C: Incorrect - MDAFW Pumps and SDAFW Pump are operating. MDAFW Pumps are operating at 325 GPM, NOT 300 GPM. 300 GPM is the minimum flow required for Heat Sink requirements in the CSFSTs.
D: Incorrect - MDAFW Pumps and SDAFW Pump are operating. MDAFW Pumps are operating at 325 GPM, NOT 300 GPM. 300 GPM is the minimum flow required for Heat Sink requirements in the CSFSTs. SDAFW Pump is operating at 500 GPM. 630 GPM is the flow restriction setpoint for the cavitating venturi on the discharge of of the SDAFW SDAFW Pump to limitlimit flow to aa faulted S/G.
S/G.
62 62
HLC-08 NRC HLC-08 NRC Written Written Exam Exam Exam Question Exam Number: 41 Question Number: 41
Reference:
Heat
Reference:
Heat Sink Sink CSFST, CSFST, SO-042, SD-042, AFW, AFW, Page Page 15.
15.
KA Statement:
KA Statement: Ability Ability to to monitor monitor automatic automatic operation operation of of the the AFW, AFW, including:
including: AFW AFW startup startup and and flows.
flows.
History: Direct History: Direct from from Bank.
Bank.
FINAL 63 63
HLC-08 NRC HLC-08 Written Exam NRC Written Exam 42.
- 42. 062 062 K2.01 K2.01 OOlJAC 001/AC ELECTRICAL ELECTRICAL DIST/2J1/3.3J3.4IROILOW/NJA/NEW DIST/2/1/3.3/3.4/RO/LOW/N/AINEW - 2008JCW-007
- 2008/CW-007 Which ONE Which ONE (1) (1) of of the the following following describes describes the the power power supplies supplies for the Circulating for the Circulating Water Water Pumps?
Pumps?
A. CW A. CW Pump Pump "A" A -- 4KV Bus 4KV Bus 11 CW Pump "B" CW Pump B -
- 4KV Bus 4KV Bus 22 CW Pump "c" OW Pump C -- 4KV Bus 4KV Bus 33 B. OW Pump B. CW Pump "A" A -- 4KV Bus 4KV Bus 55 CW Pump CW Pump "B" - B - 4KV Bus 44 4KV Bus CW Pump "c" CW Pump C - 4KV Bus 4KV Bus 11 C. CWOW Pump "A" A - 4KV Bus 2 OW Pump "B" CW B - 4KV Bus
- Bus 3 CW Pump "c" CW Pump C - 4KV Bus
- Bus 4 D
D~ OW CW Pump "A" A -- 4KV Bus 11 CW Pump "B" B -*
4KV Bus 4 CW Pump "c" 0 --
4KV Bus 5 The correct answer is O. D.
A: Incorrect - CW
- OW Pump "A" A is powered from 4KV Bus 1, CW OW Pump "B" B is powered from 4KV Bus 4, CWOW Pump "C" C is powered from 4KV Bus 5.
B: Incorrect - CW
- OW Pump "A" A is powered from 4KV Bus 1, CW Pump "B" B is powered from 4KV Bus 4, CWOW Pump "C" C is powered from 4KV Bus 5.
C: Incorrect - CW
- OW Pump "A" A is powered from 4KV Bus 11,, CW Pump "B" B is powered from 4KV Bus 4, CWOW Pump "c" C is powered from 4KV Bus 5.
D: Correct -
0: - CW Pump "A" A is powered from 4KV Bus 1, CW Pump "B" B is powered from 4KV Bus 4, CWOW Pump "c" C is powered from 4KV Bus 5.
Exam Question Number: 42
Reference:
EDP-OO1, EOP-001, Pages 4, 4,7 7 and 8; SD-057, SO-057, CW, Page 10.10.
KA Statement: Knowledge of bus power supplies to the following: Major system loads.
History: New - Written for HLC-08 NRC Exam.
FINAL 64 64
HLC-08 NRC HLC-08 NRC Written Exam Exam
- 43. 063
- 43. 063 K3.02 K3.02 OOllDC 001/DC ELECT ELECT DIST/2/l/3.S13.7IROILOW/NIAlRNP DIST/2/l/3.5/3.7/RO/LOW/N/AJRNP AUDIT AUDIT - 2001/KVAC-006
- 2001/KVAC-006 ONE (1)
ONE (1) minute minute following following aa Reactor Reactor Trip, Trip, BOTH BOTH 52/8, 52/8, SOUTH SOUTH OCBOCB and and 52/9, 52/9, NORTH NORTH OCB OCB breakers remain breakers remain CLOSED.
CLOSED.
Which ONE ONE (1) (1) of the following describes the failure that caused BOTH BOTH ofof these breakers breakers to to remain CLOSED?
A. Loss of DC Bus "A". A.
B Loss of DC Bus "B".
B~ B.
C. Loss of the Auxiliary Panel DC.
D. Loss of the Auxiliary Panel GC. GO.
The correct answer is B.
A: Incorrect - OCB 52/8 and OCB 52/9 receive their control power from DC Bus B.
B: Correct -- OCB 52/8 and OCB COB 52/9 receive their control power from DC Bus B C: Incorrect - Loss of Auxiliary Panel DC deenergizes numerous loads from DC Bus A but Unit OCBs 52/8 and 52/9 are fed from DC Bus B.
D: Incorrect - Loss of Auxiliary Panel GC deenergizes numerous loads from DC Bus B B but Unit OCBs 52/8 and 52/9 are fed directly from a breaker on DC Bus B instead of from Auxiliary Panel GC.GO.
Exam Question Number: 43
Reference:
SD-039, KVAC, Page 11; EPP-27, Pages 3-4; EPP-27 BD, Page 4.
KA Statement: Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following: Components using DC control power.
History: Direct from Bank.
FINAL 65 65
HLC-08 NRC HLC-08 NRC Written Exam Exam
- 44. 064 G2.1.7 44.064 G2.1.7 OOllEMERG 00l/EMERG DIESEL DIESEL GEN/2/1/4.4/4.7/ROIHIGH/NIAJNEW GEN/21114.414.7/RO[HIGH]NIAJNEW - 200SIEDG-007
- 2008/EDG-007 Given the following:
Given plant is
- The plant
- is operating operating at at 100%
100% RTP.
RTP.
Bus E-1
- 480V Bus
- E-1 Main Main Breaker Breaker trips on overcurrent.
A starts and re-energizes 480V Bus E-1.
- EDG "A"
- The EDG "A"
- A Jacket Water Coolant Pump shaft shears during EDG start.
APP-01O-F2,
- APP-01
- 0-F2, EDG A COOL WTR HIILO HI/LO TEMP illuminates.
- APP-01 0-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"A wilL will....
A. shutdown when coolant water pressure decreases to 9 PSIG.
B. shutdown when coolant water temperature reaches 205 of. °F.
C~
CY continue to operate due to ALL EDG engine trips being defeated.
D. continue to operate due to run priority from the Undervoltage start.
The correct answer is C.
A: Incorrect - With the EDG in a standby condition, the engine trips (9 PSIG is an actual engine trip setpoint) are defeated to prevent spurious trips from affecting the EDG operation during emergency conditions.
B: Incorrect - With the EDG in a standby condition, the engine trips (205 °F
- of is an actual engine trip) are defeated to prevent spurious trips from affecting the EDG operation during emergency conditions.
C: Correct -- Diesel engine trips are defeated to prevent spurious trips during emergency operation and the EDG will continue to run.
D:
0: Incorrect - EDG starts on Undervoltage, however UV has no input to engine trips or run priority.
Exam Question Number:
Exam Question Number: 4444
Reference:
Reference:
OP-604, Page 8, 8, Step Step 3.11; SD-005, SD-005, EDG, EDG, Pages 30-31.
30-31.
KA Statement:
Statement: Ability to evaluate plant performance performance and make operational judgments judgments based on on operating characteristics, reactor behavior, behavior, and and instrument instrument interpretation.
History:
History: New New - Written for HLC-08
- HLC-08 NRC NRC Exam.
66 66
HLC-08 NRC Written Exam FINAL 67
HLC-08 HLC-08 NRCNRC Written Written Exam Exam
- 45. 073
- 45. 073 A4.01 A4.01 OOlJPROCESS 001/PROCESS RAD RAD MONITORJ2/l/3.9/3.9IROIHIGHINIAIRNP MONITOR/2/1/3.9/3.9/RO/HIGH]N/A]RNP AUDIT AUDIT - 20061RMS-009
- 2006/RMS-009 Given the Given the following:
following:
The plant
- The
- plant isis operating operating at at 100%
100% RTP.
RTP.
-A
- A release release of of Waste Waste Condensate Condensate Tank Tank (WCT) A isis in (WCT) "A" in progress.
progress.
APP-036-E7, RAD
- APP-036-E7,
- RAD MONITOR MONITOR TROUBLE, TROUBLE, isis received.
received.
The BOP
- The
- BOP Operator Operator reports reports the the FAIL FAIL light light for R-18, LIQUID for R-18, LIQUID WASTE WASTE DISPOSAL DISPOSAL EFFLUENT monitor, EFFLUENT monitor, is is ON.
ON.
Which ONE ONE (1) (1) of the following describes describes the status status of of RCV-018, LIQUID WASTE RELEASE ISOLATION VALVE?
ISOLATION RCV-018 willwill...
A NOT automatically close. The release must be manually terminated from the Waste A":I 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.
The correct answer is A.
A: Correct - - The FAIL light means the detector has undergone a loss of power and/or loss of indication. The valve will NOT close upon receipt of a FAIL light, and the release must be manually terminated from the local station (Waste Disposal Panel).
B: Incorrect - RCV-018 will close on a High Radiation Alarm, NOT a FAIL light.
C: Incorrect - RCV-01
- RCV-018 8 can be operated at any time with control switch on the Waste Disposal Panel, but CANNOT be operated from the RTGB in the Control Room.
D:
0: Incorrect - RCV-01
- RCV-018 8 will NOT Automatically CLOSE and is controlled by the CLOSE-AUTO-OPEN CLOSE-AUTO-OPEN switch instead of a valve controller (regulator adjustment).
RCV-01 RCV-014, 4, Waste Gas Decay Tank Gaseous Release valve, is controlled by a valve controller (regulator adjustment) located on the Waste Disposal Panel.
Exam Question Number: 45
Reference:
SD-019, RMS, Page 40; 40; APP-036-E7.
APP-036-E7.
KA Statement: Ability to manually operate and/or monitor operate and/or monitor in in the control room: Effluent release.
History:
History: Direct Direct from from Bank.
Bank.
FINAL FINAL 68 68
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 46. 076 A2.0I 46.076 A2.01 OOI/SERVICE 001/SERVICE WATERl2/1/3.5/3.7IROILOW/N/NNEW WATERJ2/1/3.5/3.7/RO/LOWIN/A!NEW - 2008/AOP-022-003
- 2008/AOP-022-003 Given the Given following:
the following:
The plant
- The
- plant is operating at is operating at 100%
100% RTP.RTP.
APP-008-E8, N
- APP-OOS-ES,
- N SW SW HDR HDR STRAINER STRAINER PIT PIT HI LVL has HI LVL has illuminated.
illuminated.
APP-008-F8, NORTH
- APP-OOS-FS,
- NORTH SW SW HDRHDR LO LO PRESS PRESS has has illuminated.
illuminated.
Which ONE Which ONE (1) (1) of of the the following following are are Immediate Immediate Actions lAW lAW AOP-022, LOSS LOSS OF OF SERVICE SERVICE WATER?
WATER?
A. Close V6-12D, NORTH SW HEADER ISOLATION ISOLATION VALVE, then Go to Section F, SERVICE WATER PITS PITS FLOODING FLOODING IN IN INTAKE INTAKE AREA.
B 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-2S, EPP-28, LOSS OF ULTIMATE HEAT SINK.
D. Close V6-12D, NORTH SW HEADER ISOLATION VALVE, then Go to EPP-2S, EPP-28, LOSS OF ULTIMATE HEAT SINK.
The correct answer is B.
A: Incorrect - V6-12D is closed later in the procedure (after the Immediate Actions) after closing V6-12B and V6-12C for header separation.
B: Correct - - Step 1 1 of AOP-022 is an Immediate Action step. (1) Check APP-008-E8,APP-OOS-ES, N N SW HDR STRAINER PIT HI LVL extinguished. (RNO) Then immediately close V6-12B and V6-12C and transition to Section F.
C: Incorrect - Closing the X-connect valves is an Immediate Action Step within AOP-022 to seperate the headers, however transitioning to EPP-28 EPP-2S is ONLY required if NO SW is available.
D: Incorrect - Closing V6-12D is an action within AOP-022, but it is NOT an Immediate Action and transitioning to EPP-28EPP-2S is ONLY required if NO SW is available..
available ..
Exam Question Number: 46
Reference:
AOP-022, Pages 3, 3, 44 and 38; 3S; APP-008-E8; APP-OOS-ES; APP-008-F8.
APP-OOS-FS.
KA Statement:
Statement: Ability to (a) predict predict the impacts impacts of the following malfunctions or operations on the SWS; SWS; andand (b) based on those predictions, predictions, use use procedures to correct, control or mitigate or mitigate the consequences of those malfunctions or operations: Loss of SWS.
History:
History: New New - Written
- Written forfor HLC-08 HLC-OS NRC NRC Exam.
Exam.
69 69
HLC-08 NRC Written Exam FINAL 70
HLC-08 NRC Written Exam
- 47. 078 Kl.03 K1.03 OOI/INSTRUMENT 001/INSTRUMENT AIRl2/l/3.3/3.4IROILOW/N/A/NEW AIRJ2/1/3.3/3.4/RO/LOW/N/AJNEW - 2008/PZR-01O
- 2008/PZR-010 Given the following:
Instrument Air header inside Containment has resulted in a full
- A line break on the Instrument depressurization of Containment Instrument Air.
PCV-1 71 6, INSTRUMENT AIR TO CONTAINMENT.
- The crew has closed PCV-1716, Based on the above conditions, which ONE (1) of the following can be operated from the RTGB?
A. Pressurizer Spray valves.
B Pressurizer PORVs.
BY' C. Letdown Line Isolation valves.
D. Charging Line Isolation valves The correct answer is B.
A: Incorrect - PZR Spray Valves use Instrument Air as motive force. Valves have failed CLOSED.
B: Correct - - PZR PORVs use Nitrogen from SI Accumulator fill line and have a dedicated Nitrogen Accumulator for each valve. Instrument Air serves as backup.
C: Incorrect - Letdown line isolation valves use Instrument Air and ALL fail CLOSED.
D: Incorrect - CVC-310A and 31
- 310B OB fail OPEN. CVC-311 fails CLOSED. ALL charging line isolations CANNOT be operated from the RTGB without Instrument Air.
Exam Question Number: 47
Reference:
AOP-017, Attachment 1, Pages 34, 36; SD-059, PZR, Page 10 and Figure 4.
KA Statement: Knowledge of the physical connections and/or cause-effect relationships between the lAS and the following systems: Containment air.
History: New - Written for HLC-08 NRC Exam.
FINAL 71
HLC-08 NRC HLC-08 Written Exam NRC Written Exam 48.
- 48. 103 103 K3.01 K3 .01 OOl/CONTAINMENT/2/l/3.3/3.7IROILOW/N/A/NEW 00 1/CONTAINMENT/2/ 1/3.3/3 .7/RO/LOW/N/A!NEW - 2008/CV-008
- 2008/CV-008 Given the Given the following:
following:
The plant
- The
- plant isis in MODE 4, in MODE 4, cooling cooling down down lAW lAW GP-007, GP-007, PLANT PLANT COOLDOWN 000LDOWN FROM FROM HOT HOT SHUTDOWN TO SHUTDOWN TO COLD COLD SHUTDOWN.
SHUTDOWN.
spurious R-11
- A spurious
- R-1 1 alarm alarm causes causes aa CV CV Ventilation Isolation Isolation signal.
signal.
- V12-8 and V12-9, CV
- CV PURGE PURGE OUTLET OUTLET VALVES, VALVES, bothboth have have dual dual OPEN/CLOSED OPEN/CLOSED indications.
Which ONE (1) of the following, if any, is is required to satisfy LCO LCO 3.6.3, CONTAINMENT ISOLATION VALVES?
ISOLATION A Close and deactivate EITHER V12-8 OR V12-9 within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
AY' B. Close and deactivate BOTH V12-8 AND V12-9 within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
C. Override EITHER V12-8 OR V12-9 CLOSED within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />, using CV Purge Valve blocking mechanism.
D. Plant is in MODE 4; No action required.
The correct answer is A.
A: Correct - - ITS 3.6.3, CONTAINMENT ISOLATION VALVES, Condition B applies. Either (one) valve must be closed and deactivated within 1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to meet ITS requirements.
B: Incorrect - Only 1
- 1 valve must be closed/deactivated in each line.
C: Incorrect - Blocking mechanisms only block the valves OPEN.
D: Incorrect - CV isolation required in MODES 1,2,3
- 1,2,3 and 4 for Containment integrity to be met.
Exam Question Number: 48
Reference:
ITS 3.6.3;3.6.3; OP-921, Page 49.
KA Statement:
Statement: Knowledge of the effect that a loss loss or malfunction of the containment system will have on the following: Loss of containment integrity under shutdown conditions.
conditions.
History:
History: New New - Written
- Written for for HLC-O8 HLC-08 NRC NRC Exam.
Exam.
FINAL FINAL 72 72
HLC-08 NRC Written Exam
- 49. 001/CVCS/2/1/3.6/3.8IROILOW/N/AJNEW - 2008/CVCS-008 004 K3.08 001lCVCS/2/1/3.6/3.8IROILOW/N/A/NEW - 2008!CVCS-008 Given the following:
- Charging Pump
- Pump "A" A is being recirculated following maintenance.
- During the restoration, CVC-291, CHARGING PUMP "A"
- A TO SEAL INJECTION Valve was opened prior to closing CVC-277C, CHARGING PUMP "A" A 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 Fl-i 22A decreases to minimum.
C. ONLY Seal Injection on FI-124, FI-127 Fl-i 27 and FI-130 Fl-i 30 decreases to minimum.
Dt Seal Injection on FI-124, Dr Fl-124, FI-127 Fl-i 27 and FI-130 Fl-i30 AND Charging flow on FI-122A Fl-i22A decreases to minimum.
The correct answer is D.
There are 2 parallel discharge isolation valves on each charging pump. Normal operation has both valves open, 1 i supplying the charging header and 1i supplying the seal injection line to the RCPs. With the recirc valve open on a charging pump, the flow path is back to the VCT. With the recirc valve open while the pump discharge valve is open, all charging and seal injection flow will follow the path of least resistance and return to the VCT.
A: Incorrect - All charging and seal injection flow will take the path of least resistance and return to the VCT.
B: Incorrect - The charging line flow will decrease to minimum but the seal injection flow to the RCPs will also decrease to minimum.
C: Incorrect - The seal injection flow to the RCPs will decrease to minimum but the charging line flow will also decrease to minimum.
D: Correct - - ALL charging pump discharge flow (charging line flow and seal injection to the RCPs) will decrease to minimum with all of the flow returning to the VCT through the charging pump recirc line path.
Exam Question Number: 49
Reference:
CVCS OP-30i-i, OP-301-1 , Section 8.4.i.
8.4.1.
KA Statement: Knowledge of the effect that aa loss or malfunction of the CVCS will have on the following: RCP seal injection.
History: New - Written for HLC-08 NRC exam.
73
HLC-08 NRC Written Exam FINAL 74
HLC-08 NRC HLC-08 NRC Written Exam Exam
- 50. 007 Al.02 50.007 A1.02 OOlJPRT/QUENCH OO1IPRT/QUENCH TANKl2/1/2.7/2.9/ROIHIGH/N/A/NEW TANKI2/1/2.7/2.9IROIHIGHJN/A]NEW - 2008JPZR-008
- 2008/PZR-008 Given the following:
Given The plant
- The
- plant isis operating operating at at 100%
100% RTP.
RTP.
PCV-455C, PZR
- PCV-455C,
- PZR PORV PORV was leaking leaking by by and has has caused the following conditions inin the P RT:
PRT:
- APP-003-C3, PRT HI PRESS illuminates and PRT pressure is 6 PSIG.
- PRT level is 69% and stable.
- PRT Temperature is 115 of
- F and stable.
0 Which ONE (1) of the following actions would be used to reduce PRT pressure lAW OP-103, OP-i 03, 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.
BY' 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.
The correct answer is B.
A: Incorrect - With the PRT level at the minimum level, opening the PRT drain valve is NOT the correct solution. The PRT pressure range is 3-5 PSIG, NOT 1-2 PSIG.
B: Correct -- With the PRT level at the minimum level and PRT temperature stable and within the normal temperature limits, opening the PRT vent valve to establish 3-5 PSIG is the correct response.
C: Incorrect - With the PRT level at the minimum level, opening the PRT drain valve is NOT the correct solution. The PRT pressure range of 3-5 PSIGis correct.
D:
0: Incorrect - With the PRT level at the minimum level and PRT temperature stable and within the normal temperature limits, opening the PRT vent valve is the proper action.
Establishing a pressure band of 1-21-2 PSIG is incorrect, it should be 3-5 PSIG.
Exam Question Number: 50
Reference:
APP-003-C3; SD-01 8, Compressed SD-018, Compressed Gas, Gas, Pages 19-20, 19-20, Figure 2.
KA Statement:
Statement: Ability to predict and/or monitor monitor changes in parameters (to prevent prevent exceeding design limits) associated with operating operating the PRTS controls including: Maintaining Maintaining quench quench tank pressure.
pressure.
History:
History: New New - Written for HLC-08 NRC
- NRC exam.
exam.
75 75
HLC-08 NRC Written Exam FINAL 76
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 51. 039 Kl.Ol 51.039 K1.01 OOllMAINIREHEAT 001/MAIN/REHEAT STEAM/2/l/3.l/3.2IROILOW/N/A/NEW STEAMJ2/1/3.1/3.21R0/LOW/N/AINEW - 200S/SGS-004
- 2008/SGS-004 Which ONE Which ONE (1) (1) ofof the the following following describes describes the the design design feature(s) feature(s) which which act act to to limit limit S/G S/G blowdown blowdown rate for rate for aa Steam Steam Break Break accident?
accident?
A. Swirl Vane A. Swirl Vane Separators Separators in in the the upper upper S/G internals.
S!G internals.
B A B:I A set set ofof 77 venturis venturis within within each S/G outlet each S/G outlet nozzle.
nozzle.
C. A C. A Steam Steam Flow Flow venturi venturi inin each Main Steam each Main Steam line, line, located located at at the the operating operating floor.
floor.
D. MSIVs are required to close within 5 seconds.
answer is The correct answer is B.
B.
A: Incorrect - Swirl vanes are designed to impart radial motion to the steam to remove moisture.
B: Correct - - S/G Steam nozzles are provided with flow limiting devices to restrict the steam flow resulting from a Steam Line Break.
C: Incorrect - A single Steam Flow venturi is located in each Main Steam line, at the operating floor level adjacent to the S/G, to produce a small delta P relative to steam flow as a means of measuring flow. Pressure drop (and the flow limiting effect) is designed to be small for efficiency reasons.
D: Incorrect - MSIV 0: - M5IV closure time would have NO effect on UPSTREAM breaks.
Exam Question Number: 51 SD-025, Main Steam, Page 9, Figure 1; SO-048,
Reference:
SO-025, SD-048, S/G, SIG, Page 8, Figures 4 and 8.
KA Statement: Knowledge of the physical connections and/or cause-effect relationships between the MRSS and the following systems: S/G. SIG.
History: New - Written for HLC-08 NRC Exam.
FINAL 77 77
HLC-08 NRC Written Exam
- 52. 062 A3.0S 52.062 A3.05 OOllAC 001/AC ELECTRICAL DISTI211/3.S/3.6/RO/HIGHJN/AIRNP DIST/2/1/3.5/3.6/RO/HIGHIN/A/RNP AUDIT - 2001lAOP-024-004
- 2001/AOP-024-004 Given the following:
Instrument Bus 11 has occurred.
- A Loss of Instrument INSTRUMENT BUS.
- The crew is performing actions contained in AOP-024, LOSS OF INSTRUMENT
- 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 11 and method of control?
A. Instrument Bus 11 power is NOT restored. Operate Pressurizer Heaters and Spray valves manually.
B. Instrument Bus 11 power is restored. PC-444J AUTO control has failed, continue to operate in MANUAL.
Cv Instrument Bus 11 power is restored. Restore PC-444J to AUTO control.
C~
D. Instrument Bus 11 power is NOT restored. Continue to operate PC-444J in MANUAL.
The correct answer is C.
A: Incorrect - Instrument Bus 11 power has been restored. The controller has NOT failed, it indicated that power has been restored to the Instrument Bus.
B: Incorrect - Power has been restored to PC-444J which operated through its normal power restoration cycle. The controller does NOT automatically swap to the AUTO mode.
C: Correct -- When power is restored to PC-444J, the AUTO indicator will flash indicating power is returned to the normal mode. The controller will stay in MANUAL control. Operator action is required lAW AOP-024 to restore controller to AUTO.
D: Incorrect - Power is restored. Power restoration will leave the controller in MANUAL.
Controller can be operated in MANUAL or AUTO while on alternate power source.
Exam Question Number: 52
Reference:
AOP-024, Page 5; OP-OO1, OP-001, Pages 23-25.
KA Statement: Ability to monitor automatic operation of the ac distribution system, including:
Safety-related indicators and controls.
History: Direct from Bank.
FINAL 78 78
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 53. 039 K3.06
- 53. 039 K3.06 OOl/MAINIREHEAT 001/MAIN/REHEAT STEAMl2/1/2.8/3.1IROIHIGH/NIAIRNP STEAMI2/l/2.8/3.l/RO/HIGHJN/A/RNP BANKlEPP-11-005 BANK/EPP-1 1-005 Given the Given the following:
following:
The plant
- The
- plant isis operating operating at at 100%
100% RTP.
RTP.
The Reactor
- The
- Reactor Operator Operator reports reports thethe following:
following:
RCS Temperature
- RCS
- Temperature is is lowering lowering rapidly.
rapidly.
RCS Subcooling
- RCS
- Subcooling is is increasing.
increasing.
Pressurizer level is
- Pressurizer
- is lowering rapidly.
rapidly.
- A Reactor Trip and Safety Injection
- Injection occurs.
Containment pressure is
- Containment
- is now now reported reported as 11 11 PSIG PSIG and increasing.
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.
CY Steam Line Break; C'!"
Condenser Steam Dumps are NOT available.
D. Large Break LOCA; Condenser Steam Dumps are NOT available.
The correct answer is C.
A: Incorrect - Condenser Steam Dumps are NOT available due to Phase BB isolation closing the MSIVs.
B: Incorrect - RCS temperature indication shows that a Steam Line break has occurred.
C: Correct - - Steam Dumps are NOT available due to the MSIV closure when the Phase BB signal was generated.
D:
0: Incorrect Incorrect - RCS temperature indication
- indication shows that a steam line break has occurred.
Exam Question Number:
Exam Question Number: 53
Reference:
Reference:
Supplement G, G, Page 37; SD-031, SD-031, Steam Steam Dump, Pages 8, 9 and 19.
8,9 19.
KA KA Statement:
Statement: Knowledge Knowledge of the effect of the effect that loss or that aa loss or malfunction malfunction of of the the MRSS will have MRSS will on the have on the following:
following: SDS.
SDS.
History: Direct from History: Direct from Bank.
Bank.
79 79
HLC-08 NRC Written Exam FINAL 80
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 54. 026
- 54. 026 A2.04 A2.04 OOllCTMT 001/CTMT SPRAY/2/113.9/4.2IROIHIGHJNIA/NEW SPRAY/2/1/3.9/4.2/ROIHIGHIN/A!NEW - 20081 - 2008/
Given the Given the following:
following:
- A
- A LOCA LOCA hashas occurred occurred coincident coincident with with aa loss loss of of the the Startup Startup Transformer.
Transformer.
EDG "A"
- EDG
- A has has failed failed to to start.
start.
The crew
- The
- is performing crew is performing actions actions lAW lAW PATH-1.
PATH-i.
- Containment pressure is
- 12 PSIG and increasing.
is at 12 increasing.
- CV Spray Pump
- Pump "B" B was inadvertently stopped.
Which ONE (1) of the following describes the status of CV Spray Pump Pump "B"?
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~
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.
81 81
HLC-08 NRC HLC-08 NRC Written Written Exam Exam The correct The correct answer answer isis C. C.
The CV The CV Spray system actuates Spray system actuates atat 10 10 PSIG PSG in in Containment, Containment, both both CVCV Spray Spray Pumps Pumps auto auto start.
start. IfIf CV Pressure remains CV Pressure remains above above 1010 PSIG, PSIG, stopping stopping CV CV Spray Spray Pumps Pumps would would prevent prevent them them from from being operated being operated from from the RTGB, (they the RTGB, would be (they would be "locked out). In locked out"). order to In order to restart restart CV CV Spray Spray Pumps, an Pumps, operator would have an operator have toto go go to pump breaker to the pump breaker and physically remove and physically remove control control power fuses to reset reset the control circuit. ToTo allow continued continued operation operation from from the RTGB, RTGB, ifif CV CV Pressure Pressure is> is> 10 PSIG, the Containment 10 PSIG, Containment SpraySpray Key Key Switch Switch must must bebe placed placed inin the OVRD/RESET position.
OVRO/RESET position. This This allows allows manual manual operation operation of of both both CV Spray Pumps CV Spray Pumps from from thethe RTGB RTGB ifif CV CV Pressure Pressure is is> 10 PSIG.
> 10 PSIG.
Incorrect - Resetting SI is a procedure Step to allow for control of AFW, but does NOT A: Incorrect -
have any effect on operation have operation of the CVCV Spray Pumps Pumps ifif CV CV Pressure Pressure is is>> 10 10 PSIG.
PSIG.
B: Incorrect - Resetting SI, Phase A and Phase B are procedure Steps within the EOP network, but they do NOT have any effect on operation of the CV Spray Pumps if CV Pressure is is>> 10 PSIG. CV Spray must be reset prior to resetting Phase B to allow Phase B to reset.
C: Correct - - When CV pressure remains higher than 10 PSIG, the signal must be overridden to allow CV Spray Pump to be stopped and NOT locked out.
D: Incorrect - Resetting SI does NOT have any effect on reset of CV Spray. Unless the Key 0: -
Switch remains in the OVRO OVRD position CV Spray Pump will be locked out due to CV pressure remaining> 10 PSIG. Momentarily placing the key switch to OVRD/RESET will NOT allow the CV Spray Pumps to be operated without being OVRO/RESET locked out.
Exam Question Number: 54
Reference:
SD-024, SO-024, CONTAINMENT SPRAY SYSTEM, Pages 16-17.
KA Statement: Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of spray pump.
History: New - Written for HLC-08 NRC Exam.
FINAL 82 82
HLC-08 NRC HLC-08 NRC Written Written ExamExam
- 55. 064 K6.07 55.064 K6.07 OOlJEMERG 0O1IEMERG DIESEL DIESEL GENI2I1/2.712.9fROfLOW/N/A/NEW GEN/2/1/2.7/2.9/RO/LOW/N/A/NEW - 2008JEDG-009
- 2008/EDG-009 Given the Given the following:
following:
-A
- A leak leak in in the the EOG EDG "A" A Air Air Start Start Receiver Receiver isis reducing reducing starting starting air air pressure.
pressure.
Which ONE Which ONE (1) (1) of of the the following following is is the the FIRST FIRST pressure pressure at at which which the EDG Air the EOG Air Receiver Receiver LCO LCO isis entered?
entered?
A. <<100PSIG.
100 PSIG.
B <<210 By 210 PSIG.
C. <<216PSIG.
216 PSIG.
D. < <220 220 PSIG.
The correct answer is B.
A: Incorrect - < 100 PSIG requires entry into LCO 3.8.3, Condition E and requires the associated EOGEDG to be declared inoperable immediately. LCO 3.8.3 Condition 0D is entered when starting air receiver pressure decreases to < < 210 PSIG, which is the FIRST LCO entry.
B: Correct - - LCO 3.8.3, Condition 0 D is entered when pressure is << 210 PSIG and and> 2:. 100 PSIG.
C: Incorrect - 216 PSIG is the AIR START LO PRESS alarm setpoint.
D: Incorrect - 220 PSIG is the START pressure setpoint for Air Start Compressor in AUTO.
0: -
Exam Question Number: 55
Reference:
ITS 3.8.3, Condition D; 0; ITS Bases 3.8 3. 8 .3, Dl; SD-005,
.3,01; SO-005, EDG, EOG, Page 27.
KA Statement: Knowledge of the effect of a loss or malfunction of the following will have on the ED/G EO/G system: Air receivers.
History: New - Written for HLC-08 NRC Exam.
FINAL 83 83
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 56. 002 002 K6.07 K6.07 001lREAC 001/REAC COOLANT/2/212.S12.8IROILOW/N/A/BYRON-2003/THERMO COOLANTI2I2/2.5/2. 8/RO/LOW/N/AJBYRON-2003/THERMO CHAP CHAP 8-014 8-014 Given the Given the following:
- The plant
- plant has has been been restarted restarted following a forced outage.
Loop flow measurements have
- Loop
- have determined determined that RCP "B" B impeller impeller has degraded such that its RCS loop flow has DECREASED by 5% 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"? 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.
B!""
C. Core Delta-T at full power will be lower.
D. The reactor core will operate further from DNB when at full power.
The correct answer is B.
A: Incorrect - RCPs "B"
- B and "C" C supply PZR spray valves. However, based on plant design, B provides limited flow, plus under steady state/2235 PSIG conditions, RCP "B" the spray valves are closed and bypasses provide minimal flow to keep the lines warm - NOT an impact on current draw on the PZR Control Group heaters.
B: Correct - - Putting out the same MWt with a reduced flow rate means reduced heat transfer capabilities and therefore operation CLOSER to DNB.
C: Incorrect - Delta-T should actually be higher in this situation.
D: Incorrect - Mass flow rate reduction for the same power results in operation CLOSER to DNB.
Exam Question Number: 56
Reference:
Thermodynamics, Chapter 8, Pages 40-41.
KA Statement: Knowledge of the effect or a loss or malfunction on the following RCS components: Pumps.
History:
History: Direct from Bank.
FINAL 84 84
HLC-08 NRC Written Exam
- 57. 014 Kl.01 57.014 K1.01 001IROD 001/ROD POSITION INDICAT/2/2/3.2/3.6IROILOW/N/A/NEW INDICAT/2/2/3.2/3.6/RO/LOWIN/AINEW - 2008/IRPI-007
- 2008/IRPI-007 During withdrawal of the Control During Control Banks, Banks, APP-005-F2, ROD ROD BOTTOM BOTTOM // RODROD DROP DROP will CLEAR when Control Bank "A" CLEAR A reaches ...
A. 2020 steps steps as sensed by the Pulse To Analog Converter.
as sensed B. 35 steps as sensed by the Pulse To Analog Converter.
Cor C 20 steps as sensed by the IRPls. IRPIs.
D. 35 steps as sensed by the IRPls. IRPIs.
The correct answer is C.
A: Incorrect - The P to A converter only inputs to the Rod Bottom Bypass Bistable. Control A does NOT have Rod Bottom Bypass Bistable.
Bank "A" B: Incorrect - The P to A converter only inputs to the Rod Bottom Bypass Bistable. Control Bank "A"A does NOT have Rod Bottom Bypass Bistable. Setpoint of 35 steps is for Bypass Bistable setpoint.
C: Correct -- Control Bank "A" A does NOT have a Rod Bottom Bypass Bistable. APP-005-F2 will clear when ALL Control Bank "A" A RBLs clear at 20 steps.
D: Incorrect - Control Bank "A" 0: - A does NOT have Rod Bottom Bypass Bistable. 35 steps is the Rod Bottom Bypass Bistable setpoint.
Exam Question Number: 57
Reference:
SO-009, SD-009, IRPI, Pages 16, 17 and Figure 2; APP-005-F2.
KA Statement: Knowledge of the physical connections and/or cause-effect relationships between the RPIS and the following systems: CROS.CRDS.
History: New - Written for HLC-08 NRC exam.
FINAL 85
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 58. 015 K4.01 58.015 K4.01 OOlINUCLEAR 001/NUCLEAR INSTRUMENT/2/2/3.1I3.3fROIHIGHIN/A/NEW INSTRUMENT/2/2/3.1/3.3/RO[HIGHJN/A/NEW - 20081NIS-01O- 2008/NIS-010 During MODE During MODE 6, I&C requests 6, I&C requests permission permission to to remove remove two two (2)
(2) Power Power Range Range NI NI Channels Channels from from service at service at the the same same time time to to expedite expedite calibrations.
calibrations.
What impact, What impact, ifif any, any, will will this this have have on on NI NI System System operations?
operations?
Simultaneously removing Simultaneously removing two two (2)
(2) Power Power Range Range Channels Channels from from service service will.
will.....
have no A. have no impact.
impact. AllAll trip trip and and interlock interlock signals signals from from thethe Power Power Ranges Ranges areare blocked blocked during during the shutdown and prior to entry the shutdown and prior to entry into MODE into MODE 6. 6.
B insert a P-1 BY' P-1O signal which will de-energize both Source 0 Signal Source Ranges.
C. initiate Reactor Trip signal, initiate a Reactor signal, which will result result in in aa Feedwater Feedwater Isolation Isolation Signal being 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.
The correct answer is B.
A: Incorrect - Trip and interlock Signals
- signals are NOT all blocked during the shutdown.
B: Correct - - De-energizing 2 power ranges will initiate a P-10 P-iC signal, and de-energize both SRs.
C: Incorrect - A reactor trip signal will be initiated, but in MODE 6, the Rod Drive MG Sets have been placed under clearance to de-energize all of the CRDMs. With T AVG <
TAVG <
554°F 5540 F and the reactor trip breakers open, a feedwater isolation signal has already been generated.
D: Incorrect - While the Power Ranges are not required to be OPERABLE, the NI system 0: -
interlock circuitry is still functional.
Exam Question Number: 58
Reference:
SD-Oil, SD-011, RPS, Figure 18. 18.
KA Statement: Knowledge of NIS design feature(s) and/or interlock(s) provide for the following:
Source-Range detector power shutoff at high powers.
History: Direct from Bank.
FINAL 86 86
HLC-08 NRC Written Exam
- 59. 017 K3.01 OOllIN-CORE 59.017 001/IN-CORE TEMP MONITORl21213.S/3.7IROIHIGH/N/A/NEW MONITORI2/2/3.5/3.7/RO/HIGHJN/AINEW - 200S/ICCM-00S
- 2008IICCM-005 Given the following:
Inadequate Core Cooling Monitors (ICCM) have been deenergized.
- Both Inadequate
- 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 THOT HOT is decreasing.
TCOLD T COLD is stable.
S/G pressure is stable.
B. T THOT HOT is stable.
TCQLD T COLD is decreasing.
SIG pressure is stable.
S/G C T C':'" HOT is decreasing.
THOT T COLD is decreasing.
TCOLD SIG pressure is decreasing.
S/G D. T THOT HOT is stable.
T COLD is stable.
TCOLD SIG pressure is decreasing.
S/G The correct answer is C.
In order to verify Natural Circulation established, three things must be observed; THOTT HOT must be stable or decreasing, T COLD must be decreasing and S/G pressure must be decreasing and TCOLD saturation pressure must be consistent with RCS temperature.
A: Incorrect - TCOLD
- T COLD and S/G SIG pressure is stable, therefore heat is NOT being removed and NC is NOT verified.
B: Incorrect - SIG
- S/G pressure is stable, therefore heat is NOT being removed and NC is NOT verified.
C: Correct - - ALL parameters indicate NC is occurring and verified D:
0: Incorrect - THOT
- T HOT and TCOLD T COLD are stable which indicates that NC is NOT established.
87 87
HLC-08 NRC HLC-08 NRC Written Written Exam Exam Exam Question Exam Number: 59 Question Number: 59
Reference:
Supplement
Reference:
Supplement E, Page 29; E, Page 29; ICCM ICCM Figure Figure 1,27.
1, 27.
KA Statement: Knowledge KA Statement: Knowledge of of the effect that aa loss effect that loss or malfunction of or malfunction of the the ITM system will have ITM system have on the following: Natural on Natural circulation circulation indications.
indications.
History: New History: New - Written
- Written for HLC-08 NRC for HLC-08 Exam.
NRC Exam.
FINAL 88 88
HLC-08 NRC Written Exam
- 60. 027 Kl.Ol K 1.01 OOl/CTMT 00 1/CTMT IODINE IODINE REMOV REMOVAL/2/2/3 .4/3 .7/RO/HIGHJN/AJBRAIDWOOD - 2004JESF-004 AL!2I2/3.4/3.7IRO/HIGH/NIAIBRAIDWOOD - 2004/ESF-004 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.
B:-"
C. Containment Isolation Phase B Signal ONLY.
D. SI Signal, and then reset the Containment Isolation Phase B B Signal.
The correct answer is B.
A: Incorrect - SI reset is unnecessary, therefore it is NOT a required action.
B: Correct - - CV Spray Actuation can be reset since CV pressure is less than 10 PSIG.
C: Incorrect - Resetting Phase BB would have NO effect on CV Spray.
D: Incorrect - Resetting SI and Phase BB would have NO effect on CV Spray.
Exam Question Number: 60
Reference:
SD-006, ESFAS, Pages 13,17 13, 17 and Figure 3.
KA Statement: Knowledge of the physical connections and/or cause-effect relationships between the CIRS CI RS and the following systems: CSS.
History: Direct from Bank.
FINAL 89
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 61. 034 A4.02 61.034 A4.02 OOllFUEL 001/FUEL HANDLING HANDLING EQUIP/2/2/3.S13.9IROILOWINIA/NEW EQUIP/2/2/3.5/3.9/ROILOW/N/AJNEW - 20081NIS-008
- 2008/NIS-008 Given the Given the following:
following:
The plant
- The
- plant isis inin MODE MODE 6. 6.
Refueling activities
- Refueling
- activities are are in in progress.
progress.
APP-005-C1, SR
- APP-005-C1,
- SR HIHI FLUX FLUX AT AT SHUTDOWN SHUTDOWN isis illuminated.
illuminated.
Which ONE Which ONE (1) (1) of of the the following describes describes the the High Flux at High Flux at Shutdown Shutdown alarm alarm setpoint setpoint and and the the system response?
SR counts SR counts are greater than are greater than...
A 33 times AII-Rods-In A'! All-Rods-In background background and the CV Evacuation Evacuation horn horn will sound.
All-Rods-In background and the LOCAL Evacuation alarm will sound.
B. 3 times AII-Rods-In All-Rods-In background and the CV Evacuation horn will sound.
C. 2 times AII-Rods-In D. 2 times AII-Rods-In All-Rods-In background and the LOCAL Evacuation alarm will sound.
The correct answer is A.
A: Correct - - High Flux at Shutdown alarm setpoint is set at 3 times the AII-Rods-In All-Rods-In background count rate to ensure early warning of changing counts. IF the setpoint is exceeded, an automatic initiation of the CV Evacuation Horn will occur.
B: Incorrect - High Flux at Shutdown alarm setpoint is set at 3 times the AII-Rods-In All-Rods-In background count rate to ensure early warning of changing counts. There is NO automatic initiation of the LOCAL evacuation alarm.
C: Incorrect - If SR counts double during any reactivity addition, dilution or rod movement is stopped to ensure positive control over the core. This is an incorrect application of this setpoint.
D: Incorrect Incorrect - If SR counts double during any reactivity addition, dilution or rod movement is stopped to ensure positive control over the core. This is is an incorrect application of this setpoint. There is NO automatic initiation of the LOCAL evacuation alarm.
Exam Question Number: 61
Reference:
GP-002, Page 118; OP-002, Pages 15 118; OP-002, 15 and 16; 16; APP-005-C1.
KA Statement:
Statement: Ability to manually manually operate operate and/or and/or monitor monitor in the control room: Neutron Neutron levels.
History: New - Written History: New -
Written for HLC-08 NRC for HLC-08 NRC Exam.
Exam.
FINAL FINAL 90 90
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 62. 035 A2.06 ~Ol/STEAM 035 A2.06 001/STEAM GENERATORJ2J214.5/4.6IROILOW/NIAINEW GENERATORI2/2/4.5/4.6/RO/LOW/N/AJNEW - 200S/PATH-I-005
- 2008/PATH-1-005 Given the Given the following:
- The plant
- plant was operating at 100%
100% RTP RTP when a Small Small Break Break LOCA LOCA occurred.
occurred.
Injection has
- Safety Injection
- has been 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 PATH-i to ensure that core cooling is maintained during this event?
A. Maintain ALL S/G levels> 8%.
B Maintain ONE S/G level> 18%.
BY' C. Maintain ALL S/G levels> 18%.
D. Maintain ONE S/G level>level > 8%.
The correct answer is B.
A: Incorrect - Maintaining ALL S/Gs
- S/Gs>> 8% level is NOT required to maintain a minimum heat sink requirements. Maintaining at least 11 S/G level>
level > 8% is the minimum requirement when CV adverse numbers are NOT applicable. Maintaining 1 1 S/G level> 18% (CV adverse numbers due to CV pressure being> being > 4 PSIG) ensures Secondary Heat Sink is maintained as long as RCS pressure is greater than S/G pressure. Maintaining 1 1 S/G level>
level > 8% would be correct if CV adverse numbers did NOT apply.
B: Correct -- Maintaining 1 1 S/G level> 18% (CV adverse numbers due to CV pressure being
> 4 PSIG) ensures Secondary Heat Sink is maintained as long as RCS pressure is greater than S/G pressure.
C: Incorrect - Maintaining 1
- 1 S/G level> 18%
18% (CV adverse numbers due to CV pressure being
> 4 PSIG) ensures Secondary Heat Sink is maintained as long as RCS pressure is greater than S/G pressure. Maintaining ALL S/Gs>
S/Gs > 18%
18% level is NOT required.
D: Incorrect - Maintaining 11 S/G level> 18%
- 18% (CV adverse numbers due to CV pressure being
> 4 PSIG) ensures Secondary Heat Sink is maintained as long as RCS pressure is greater than S/G pressure. Maintaining 11 S/G level> 8% would be correct if CV adverse numbers numbers did did NOT NOT apply.
91 91
HLC-08 NRC HLC-08 Written Exam NRC Written Exam Exam Question Exam Number: 62 Question Number: 62
Reference:
PATH-1
Reference:
PATH-i SD,BD, Page Page 37; FRP-H.i SD, 37; FRP-H.1 BD, Page Page 45.
45.
KA Statement:
KA Statement: Ability Ability to to (a) predict the (a) predict the impacts impacts of the following of the following malfunctions malfunctions or operations on or operations on the GS; the GS; andand (b)
(b) based based onon those predictions, use those predictions, use procedures procedures to to correct, correct, control, control, or mitigate the or mitigate the consequences consequences of of those those malfunctions malfunctions or or operations:
operations: Small Small break break LOCA.
LOCA.
History: New - Written History: - Written for HLC-08 HLC-08 NRCNRC Exam.
Exam.
FINAL FINAL 92 92
HLC-08 HLC-08 NRC Written Exam NRC Written Exam
- 63. 041 A4.06 63.041 A4.06 OOl/STM 001/STM DUMP/TURB DUMPJTURB BYPASS121212.9/3.1IROIHIGHINIA/SALEM BYPASS/2/2/2.9/3IJROIHIGHJN/AJSALEM - 2001IPATH-2-005
- 2001/PATH-2-005 Given the Given the following:
following:
-A
- A Steam Steam Generator Generator TubeTube Rupture Rupture has has occurred.
occurred.
crew is
- The crew
- is preparing preparing to cooldown cooldown toto aa target target temperature ofof 480 480 of
°F lAW lAW PATH-2.
PATH-2.
- A Loss
- Loss of Off-Site Power Power occurs.
All equipment
- All
- equipment functions functions as as required.
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).
CY Intact S/G PORVs controllers set to maintain full OPEN valve position.
CY' D. Steam Dumps in Pressure Control mode set to maximum rate.
The correct answer is C.
A: Incorrect - Setting S/G PORVs to 553 PSIG will cooldown the plant, but will throttle closed on the valves as the target temperature and pressure is being approached instead of maintaining the maximum cooldown rate until the target temperature is reached.
B: Incorrect - Condenser Steam Dumps are unavailable due to loss of Condenser from LOOP.
Setpoint is the target temperature saturation pressure.
C: Correct - - Steam Line PORVs on intact S/Gs are set to maximum rate. Condenser Steam Dumps are unavailable due to LOOP.
D:
D: Incorrect Incorrect - Steam
- Steam Dumps are unavailable due to loss unavailable due loss of of Condenser from LOOP.
Exam Question Question Number: 63
Reference:
PATH-2 BD, BD, Page Page 7.7.
KA Statement:
Statement: Ability to to manually manually operate operate and/or and/or monitor monitor in in the the control room: Atmospheric relief valve relief valve controllers.
History:
History: Direct Direct from from Bank.
Bank.
FINAL FINAL 93 93
HLC-08 NRC HLC-08 NRC Written ExamExam
- 64. 045 K1.18 64.045 K1.18 OOllMAIN 001/MAIN TURBINE TURBINE GEN/2/213.6/3.7fROfLOW/N/A/NEW GEN/2/2/3.6/3.7/RO/LOW/N/AINEW - 20081RPS-006
- 2008/RPS-006 Which ONEONE (1)(1) of of the the following describes describes how how the Reactor Reactor Protection Protection System System provides provides Runback signals Runback signals to the Turbine Turbine Generator?
Generator?
The RPS RPS initiates initiates a Turbine (1) (1) runback when 2/3 runback 2/3 OT OT Delta Delta TT (2)
(2) 2/3 2/3 OP OP Delta Delta TT signals signals reach their runback setpoints.
AY (1) Reference A'(
(2) OR B. (1) Valve Limiter (2)OR (2) OR C. (1) Reference (2) AND D. (1) Valve Limiter (2) AND The correct answer is A.
A: Correct -- Turbine Reference runbacks operate from 2/3 OT Delta T OR 2/3 OP Delta T on a 30 second timer. Runback signal is ON for 1.5 1 .5 seconds and OFF for 28.5 seconds until runback signal clears.
B: Incorrect - No valve limiter runback exists.
C: Incorrect - Reference runback from 2/3 OT Delta TOR
- T OR 2/3 OP Delta T, does NOT require BOTH.
D: Incorrect - No valve limiter runback exists.
Exam Question Number: 64
Reference:
SD-01 SD-011, 1, RPS, Page 23, Figure 15.
KA Statement: Knowledge of the physical connections and/or cause-effect relationships between the MT/G system and the following systems: RPS.
History: New - Written for HLC-08 NRC exam.
FINAL 94 94
HLC-08 NRC Written Exam
- 65. 001/CIRCULATING WATER/2/212.612.7IROIHIGH/N/A/RNP 075 K2.03 OOl/CIRCULATING WATER/2/2/2.6/2.7/RO/HIGHIN/AIRNP AUDIT - 200l/SW-009
- 200 1/SW-009 Given the following:
LOSS OF ALL AC POWER,
- EPP-1, LOSS
- POWER, is being performed.
- The RCS has been isolated.
- The Inside AO and maintenance technicians are working on starting an EDG.
- There is NO SI signal present or required.
Subsequently, EDG "A" A was started.
Which ONE (1) of the following actions is necessary following the energization of 480V Bus E-1??
E-1 Verify Service Water Pumps ...
A'I A and "B" A "A" B are running.
A and "c" B. "A" C are running.
B and "0" C. "B" D are running.
D. "c" D are running.
C and "0" The correct answer is A.
A: Correct -- A and "B" "A" B now have power available and should be verified started.
A now has power available and should be verified started. "c" B: Incorrect - "A"
- C does NOT have power.
B now has power available and should be verified started. "0" C: Incorrect - "B"
- D does NOT have power.
D: "c" and D 0: Incorrect - C "0" do NOT have power.
Exam Question Number: 65
Reference:
EDP-002, Page 11; SD-004, SW, Page 21.
KA Statement: Knowledge of bus power supplies to the following: Emergency/essential SWS pumps.
History: Direct from Bank.
FINAL 95
HLC-08 NRC Written Exam
- 66. G2. 1.26001/CONDUCT G2.1.26 OPERATION/3/3 .4/3 .6/RO/LOW/N/A/NEW - 2008/GET-FALL PROT OOl/CONDUCT OF OPERATION/3/3.4/3.6IROILOW/N/A/NEW -
Given the following:
- Operators are performing valve lineups to support BOP Flush.
- Flush.
- Several valves above Heater
- Heater Drain Tank "B" B 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.
DY' The correct answer is D.
A: Incorrect - Procedure requires that extension ladder be attached to structural components at the top of the ladder while the ladder is secured at the bottom by an individual.
B: Incorrect - Fall protection is to be attached to engineered anchorage points. Line or snubber supports are NOT approved anchorage points.
C: Incorrect - Step ladders are NOT allowed to be secured to structural components when used.
D: Correct - - Full body harness properly used and attached to approved anchorage points is required to safely perform work.
Exam Question Number: 66
Reference:
SAF-NGGC-2172, Sect. 9.17.
KA Statement: Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).
History: New - Written for HLC-08 NRC Exam.
FINAL 96
HLC-08 NRC Written Exam 67.
- 67. G2.1.28 OOIlCONDUCT 001/CONDUCT OF OPERATION/3/4.
OPERATION/3/4.1/4.1IRO/HIGHJN/AIRNP 2001/PZR-006 114. IIRO/HIGH/N/A/RNP AUDIT - 20011PZR-006 Given the following:
100% RTP.
- The plant is operating at 100%
- 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.
BY B~ Increase the controller output.
C. Decrease the pressure setpoint potentiometer.
D. Increase the pressure setpoint potentiometer.
The correct answer is B.
A: Incorrect - Decreasing the controller output would cause PC-444J to increase pressure.
B: Correct -- Required to lower pressure, same as pressure deviation for spray valve operation, except it must be done manually. In auto, the input would have to be 25 - 50 PSIG above the setpoint to induce spray. In manual, the input is manually lowered to energize heaters, or raised to de-energize heaters or open spray valves.
C: Incorrect - With PC-444J in MANUAL, adjustment of the POT would NOT have any effect on PC-444J operation.
D:
0: Incorrect - With PC-444J in MANUAL, adjustment of the POT would NOT have any effect on PC-444J operation.
Exam Question Number: 67
Reference:
SD-059, PZR, Pages 17 17 and 18.
KA Statement: Knowledge of the purpose and function of major system components and controls.
History: Direct from Bank.
FINAL 97
HLC-08 H LC-08 NRCNRC Written Written Exam Exam
- 68. G2.2.6
- 68. G2.2.6 OOllEQUIPMENT 00 1/EQUIPMENT CONTROLl3/3.0/3.6IROILOW/NIAINEW CONTROL/3/3 .013.6/RO/LOWINIAJNEW - 2008IPRO-NGGC-0204
- 2008/PRO-NGGC-0204 Given the Given the following:
following:
The crew
- The
- crew has has discovered discovered anan error error in in an an AOP.
AOP. The AOP identified The AOP identified the the proper proper title title of of aa pressure indicator, but pressure indicator, but describes describes the indicator as the indicator as PI-2098 P1-2098 instead instead of the correct number of the correct number P1-2089.
PI-2089.
procedure change has
- A temporary procedure
- has been been initiated initiated to correct the error.
error.
Which ONE ONE (1) (1) of the following statements applies to the the temporary temporary procedure procedure change change process process lAW PRO-NGGC-0204, PROCEDURE REVIEW AND APPROVAL?
A The temporary change expires after 21 days unless made permanent A'I permanent by by the procedure 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.
The correct answer is A.
A: Correct - - RNP requirement is that a temporary change must be approved or disapproved by the procedure owner within 21 days.
B: Incorrect - A change of intent can NOT be processed as a temporary change. Whether the change is to an AOP has NO bearing on whether the change can be processed as a temporary change.
C: Incorrect - A temporary change has to be approved by Management personnel, but it does NOT require the Procedure Owner to approve it before use by the shift operators.
D: Incorrect - Four months is the expiration date for ALL other Progress Energy sites.
Exam Question Number: 68
Reference:
PRO-NGGC-0204, Page 32. 32.
KA Statement:
Statement: Knowledge Knowledge of of the process process for making changes to procedures.
procedures.
History:
History: New New - Written
- Written for HLC-08 HLC-08 NRC NRC Exam.
Exam.
FINAL FINAL 98 98
HLC-08 NRC HLC-08 NRC Written Written Exam Exam G2.2.40 OOllEQUIPMENT
- 69. 02.2.40
- 69. 001/EQUIPMENT CONTROLl3/3.4/4.7IROILOW/N/A/NEW CONTROL/3/3 .4/4.7/RO/LOW/N/AJNEW - 200SIEDO-009
- 2008/EDG-009 With the With the plant plant operating operating atat 100%
100% RTP, RTP, which which ONE ONE (1)
(1) of of the the following following equipment equipment failures failures requires the requires the EARLIEST EARLIEST ACTION ACTION perper Technical Technical Specifications?
Specifications?
Failure of Failure of ...
A.
B. Battery B. Battery Charger Charger "A".A.
Cr RC-551 C, PZR C RC-551C, PZR SAFETY VALVE.
D. PCV-456, D. PCV-456, PZR PZR PORV.
PORV.
The correct answer is C.
A: Incorrect - Action required within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> to verify breaker alignment for off-site power circuit 3.8.1,, Condition B.
per LCO 3.8.1 B: Incorrect - Battery charger failure must be corrected within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> lAW LCO 3.8.4, Condition A.
C: Correct - - Action required LCO 3.4.10, Condition A, Restore valve to OPERABLE status within 15 minutes.
D: Incorrect - Action required for LCO 3.4.11, Condition A, Close and maintain power to 0: -
associated block valve within 1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Exam Question Number: 69
Reference:
ITS 3.8.1, 3.8.4, 3.4.10 and 3.4.11.
KA Statement: Ability to apply Technical Specifications for a system.
History: New - Written for HLC-08 NRC Exam FINAL 99 99
HLC-08 HLC-08 NRC NRC Written Written ExamExam 70.
- 70. G2.3.4 G2.3 .400 1/RADIATION CONTROLl3/3.2/3.7IROILOW/N/A/NEW OOllRADIATION CONTROL/3/3 .2/3 .7/RO/LOW/N/A/NEW - 200S/10CFR20
- 2008/1 OCFR2O Given the Given the following:
following:
A 25
- A
- year old 25 year old female started working female started working at at Robinson Robinson as as aa permanent permanent employee employee on on July July 2nd 2nd of this year and of and has has an an NRC NRC Form on file.
Form 4 on
- She
- previously worked at Salem and She previously and had had received received 200 mRem mRem exposure for this year.
She has
- She
- has NOT NOT declared declared pregnancy.
pregnancy.
- She has received NO management exposure
- exposure extensions and NO emergency exists.
Which ONE (1) of the following is is the additional exposure she can receivereceive without management concurrence at Robinson this year?
A. 300 mRem.
B. 1800 mRem.
C':'"
C 2000 mRem.
D. 3800 mRem.
The correct answer is C.
A: Incorrect - This is the additional exposure that would equal the exposure limit (500 mRem) for a fetus for the full term of a pregnancy if declared.
B: Incorrect - This is the additional exposure that would total 2000 mRem for the year, but the administrative limit is 2000 mRem received at ONLY the Robinson site for the year. As long as the individual does NOT exceed 4000 mRem total exposure, she can receive up to 2000 mRem at Robinson alone.
C: Correct - The individual may receive an administrative limit of 2000 mRem at Robinson as long as the total combined yearly exposure is less than 4000 mRem.
D: Incorrect - This additional exposure would total 4000 mRem for the year, but would ONLY be allowed with aa dose extension.
Exam Exam Question Number: 70
Reference:
DOS-NGGC-0004, ADMINISTRATIVE DOSE LIMITS. LIMITS.
KA KA Statement:
Statement: Knowledge Knowledge of radiation exposure of radiation exposure limits limits under under normal normal oror emergency emergency conditions.
History: NewNew - Written for HLC-08 NRC
- NRC Exam.
Exam.
FINAL FINAL 100 100
HLC-08 NRC HLC-08 NRC Written Written Exam Exam 71.
- 71. 02.3.13 G2.3.13 OOllRADIATION 001/RADIATION CONTROLl3/3.4/3.SIROILOW/N/A/NEW CONTROL/3/3.4/3.8/RO/LOWIN/A/NEW - 200S/AOP-013-004
- 2008/AOP-013-004 Given the Given the following:
following:
You are
- You
- are in in the the Spent Spent Fuel Fuel Pit Pit performing performing fuel fuel handling handling operations.
operations.
-A
- A fuel fuel handling handling accident accident occurs, andand anan evacuation evacuation is is ordered ordered via aa PA PA announcement.
announcement.
Which ONEONE (1) (1) of the following isis the area designated as the assembly point for this event lAW assembly point lAW AOP-013, FUEL FUEL HANDLING HANDLING ACCIDENT?
Immediately outside the Spent Fuel A. Immediately Fuel Pit Pit Building Building door.
BY Landing halfway down the stairs outside the Spent Fuel B!'" 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.
The correct answer is B.
SFP personnel are expected to evacuate the SFP area, and transit to the landing halfway down to ensure shielding is provided and to limit the spread of contamination.
A: Incorrect - This assembly point is a reasonable choice for an accident occurring in the SFP to ensure personnel are away from the source of radiation. Evacuating to outside of the SFP Building and halfway down the stairs provides distance for shielding.
B: Correct - - AOP-O1 AOP-013 3 specifies SFP personnel to stop at the landing halfway down the stairs (shielded, but prevents spread of contamination until cleared.)
C: Incorrect - This is the assembly point for an accident in the New Fuel Handling Building.
D: Incorrect - The procedure specifies to evacuate the SFP Building and proceed to halfway down the stairs to provide distance for shielding but to ensure that there is NOT an unnecessary spread of contaimination by the workers.
Exam Question Number: 71 Exam Question 71
Reference:
AOP-013, Page Page 4.
KA Statement:
Statement: Knowledge of radiological safety procedures pertaining to licensed operator duties, duties, such such asas response to to radiation radiation monitor monitor alarms, alarms, containment containment entry entry requirements, requirements, fuel handling handling responsibilities, access access toto locked locked high-radiation high-radiation areas, aligning areas, aligning filters, etc.
etc.
History:
History: New New - Written for
- for HLC-08 HLC-08 NRC NRC Exam.
Exam.
FINAL FINAL 101 101
HLC-08 NRC HLC-08 NRC Written Written Exam Exam 72.
- 72. G2.3.7 02.3.7 OOllRADIATION 001/RADIATION CONTROLl3/3.5/3.6IROILOW/N/A/NEW CONTROL!3/3.5!3.6/RO!LOW!N/AJNEW - 20081 - 2008!
Given the Given following:
the following:
While entering
- While
- entering the the plant plant to relieve the to relieve the shift, shift, you you notice notice smoke smoke coming coming from from thethe Auxiliary Auxiliary Building.
Building.
You have
- You
- have NOT NOT logged logged onto any RWP onto any RWP oror obtained obtained proper proper dosimetry dosimetry (EAD).
(EAD).
Your assistance
- Your
- assistance is is required required inin the the Auxiliary Auxiliary Building.
Building.
Which ONE (1) of the the following is allowed/required lAW lAW FP-001, FP-OO1, FIRE FIRE EMERGENCY EMERGENCY for the stated conditions?
stated requirement for obtaining A. An exception to the requirement obtaining an EADEAD AND RWP RWP login login is is allowed for qualified members of the Fire Brigade.
Fire Brigade.
B B~ An EAD must be obtained AND RWP 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.
The correct answer is B.
A: Incorrect - Exception for dosimetry and RWP login is NOT allowed. Operations pesonnel are required to obtain proper dosimetry prior to relieving their watchstations.
B: Correct - - RWP login and proper dosimetry is required prior to entry into any RCA.
C: Incorrect - RC Tech being present does NOT relieve personnel of the requirement for proper dosimetry.
D: Incorrect - Emergency dosimetry is NOT available in the Work Control Center.
Exam Question Number: 72
Reference:
OMM-OO1-12, OMM-001-12, Page 8; FP-OO1, FP-001, Pages 7-9.
KA Statement: Ability to comply with radiation work permit requirements during normal or abnormal conditions.
History: New New - Written for HLC-08 NRC Exam.
FINAL FINAL 102 102
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 73. G2.4.16
- 73. G2.4.16 OOlfEMERG OO1/EMERG PROCIPLAN/3/3.8/4.5ISROILOW/43.5IRNP PROCIPLAN/3/3.8/4.5/SROILOW/43.5IRNP AUDITAUDIT - 2007/0MM-022-009
- 2007/OMM-022-009 Given the Given the following:
following:
-A
- A loss loss of of Component Component Cooling Water has Cooling Water has occurred.
occurred.
The crew
- The
- crew has has implemented implemented AOP-014, AOP-0i4, COMPONENT COMPONENT COOLING COOLING WATERWATER SYSTEM SYSTEM MALFUNCTION.
MALFUNCTION.
- A Reactor
- Reactor Trip Trip has has occurred.
occurred.
Which ONE (1) of the following describes describes the continued use of AOP-014 AOP-Oi 4 after the Reactor Reactor Trip?
Use of AOP-014 is A. Use is NOT NOT allowed allowed during during EOP EOP performance.
performance. Continue Continue use use of of AOP-014 upon upon exiting the EOP network.
network.
AOP-01 4 may ONLY be used concurrently with actions of PATH-1.
B. Use of AOP-014 PATH-i. Use must be suspended upon transition to any other EOP.
C~
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.
The correct answer is C.
A: Incorrect - AOP-014 is a concurrent use procedure.
AOP-0i4 may also be used with other EPPs.
B: Incorrect - AOP-014 C: Correct - - AOP-014 is a concurrent use procedure and will be performed by a licensed operator when directed by the CRSS, concurrent with PATH-1 PATH-i actions, provided that NO RED or ORANGE path FRPs are being implemented.
D:
0: Incorrect - ALL other procedure usage stops during performance of RED or ORANGE path FRPs.
Exam Question Number: 73
Reference:
OMM-022, Page 38.
KA Statement: Knowledge of EOP implementation implementation hierarchy and coordination with other support procedures or or guidelines such as, as, operating operating procedures, abnormal abnormal operating procedures, and severe accident management guidelines.
History:
History: Bank question used used for 2007 RNP Audit.
SRO SRO - Assessment
- Assessment of plant conditions of plant and determination conditions and of procedures determination of procedures required for for mitigating mitigating those events.
those events.
FINAL FINAL 103 103
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 74. G2.4.22
- 74. 02.4.2200 1/EMERG PROCIPLAN/3/3.5IRO/LOW/N/A/NEW OOlIEMERG PROC/PLAN/3/3.5IROILOWIN/AINEW - 2008/0MM-022-003 2008/OMM-022-003 Given the Given the following:
following:
The crew
- The
- crew isis responding responding to RED PATH to aa RED PATH lAW lAW FRP-P.1.
FRP-P.1.
The STA
- The
- STA has has just just reported reported aa RED RED PATH PATH onon the the Heat Heat Sink Sink CSFST CSFST AND AND anan ORANGE ORANGE PATH on PATH on Core Core Cooling Cooling CSFST.
CSFST. (Assume (Assume ALL conditions conditions have been validated) have been validated)
FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK.
FRP-H.1, RESPONSE TO IMMINENT FRP-P.1, RESPONSE IMMINENT PRESSURIZED PRESSURIZED THERMAL SHOCK SHOCK CONDITION.
FRP-C.2, RESPONSE FRP-C.2, RESPONSE TO DEGRADED DEGRADED CORE COOLING CORE COOLING Which ONE (1) of the following is the crew's crews response?
A'I 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.
The correct answer is A.
A: Correct - - Heat Sink RED PATH has a higher priority and lAW OMM-022, any lower priority procedures are exited and the higher priority procedure is entered.
B: Incorrect - Core Cooling is a higher priority CSF, however, since it is an ORANGE PATH, thehigher priority RED PATH is addressed (entered) first.
the,higher C: Incorrect - OMM-022 specifically states that when an FRP is entered it will NOT be exited until completion, except when a higher priority CSF is received.
D: Incorrect - Only one FRP is to be implemented at a time, highest priority takes precedence.
Exam Question Number: 74
Reference:
OMM-022, Pages 18, 18, 19.
19.
KA KA Statement:
Statement: Knowledge of the bases of the bases for prioritizing safety safety functions during during abnormal/emergency abnormal/emergency operations.
operations.
History: New - Written History: New - Written for HLC-08 HLC-08 NRC NRC exam.
exam.
FINAL FINAL 104 104
HLC-08 NRC HLC-08 NRC Written ExamExam G2.4.23 OOllEMERG
- 75. G2.4.23 00 1/EMERG PROCIPLAN/3/3.6/4.4IRO/LOW/N/A/NEW PROC/PLAN/3/3 .6!4.4/RO/LOW/N/A/NEW --2008/PATH-i -007 2008IPATH-I-007 ONE (1)
Which ONE (1) of of the the following following is is the the basis basis for checking checking for aa Faulted Faulted S/G SIG prior prior to to checking checking Containment conditions Containment conditions for other other possible possible major major accidents accidents during during performance performance of of PATH-1?
PATH-i?
A'I Indications could potentially mask other failures.
A Indications B. Early isolation of AFW is required to prevent challenging the RCS Integrity ntegrity 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.
The correct answer is A.
A: Correct - - A Main Steam break causes a rapid RCS cooldown and SI SIG blows S until the S/G dry. RCS temperature will stabilize and the RCS will repressurize to restore normal RCS conditions. This allows other accidents to be diagnosed or the EOP network exited if conditions allow.
B: Incorrect - Early isolation of AFW will limit RCS cooldown and CV pressure, but it will NOT prevent challenging the RCS Integrity CSF.
C: Incorrect - Potential for personnel injury is limited to the area adjacent to CV wall. Any steam break downstream of the MSIVs will be terminated by automatic closure of the MSIVs.
EPP-i6 is the procedure that will combat ALL 3 faulted S/Gs D: Incorrect - EPP-16
- S!Gs and bounds the failure within CV analysis.
Exam Question Number: 75
Reference:
PATH-i PATH-1 BD, Page 3.
KA Statement: Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.
History: New - Written for HLC-08 NRC exam.
FINAL 105 105
HLC-08 NRC Written Exam
- 76. 000008 G2.4.11 G2.4. 11 OOllPZR 001/PZR VAPOR SPACE ACCIIlI1I4.0/4.2/SRO/HIGH/43.5/NEW ACCII1/1/4.0/4.2/SRO/HIGHI43.5INEW - 2008/AOP-019-002 Given the following:
performing a controlled shutdown from 100%
- The plant is performing
- 100% 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, AOP-01 6, 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?
PATH-i? (Assume the actions performed do NOT stop the level decrease)
A. (1) Maximize charging on ALL three Charging Pumps.
(2) Isolate Letdown.
B (1)
B:I 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.
The correct answer is B.
The specific steps, in order, are to maximize charging rate on the first two pumps, isolate letdown, then start and maximize charging on the remaining Charging Pump. If level continues to decrease, trip the Reactor and enter PATH-i.
PATH-1. The order is explicit and based on the possibility of three pumps running could challenge the 2500 PSIG Charging Header Relief valves. The third pump will be used ONLY if two pumps and Letdown isolation are NOT sufficient to control level decrease.
A: Incorrect - Procedure order is to maximize charging on TWO pumps, isolate Letdown, then start and maximize charging with the third pump if level continues to decrease.
B: Correct - - This sequence is specifically directed by AOP-Oi 6.
C: Incorrect - Letdown is isolated AFTER the first two pumps are running at maximum flow.
Then the third pump is started and flow maximized.
D:
0: Incorrect - Letdown is isolated AFTER the first two pumps are running at maximum flow.
Then the third pump is started and flow maximized.
106 106
HLC-08 NRC HLC-08 NRC Written Written Exam Exam Exam Question Exam Question Number:
Number: 76 76
Reference:
APP-003-F6;
Reference:
APP-003-F6; AOP-016, AOP-016, Pages Pages 3,6-7; AOP-016 SO, 3, 6-7; AOP-016 BD, Page Page 5.
5.
KA Statement:
KA Statement: Knowledge Knowledge ofof abnormal abnormal condition condition procedures.
procedures.
History: New History: New - Written for HLC-08
- HLC-08 NRC exam.
NRC exam.
SRO - The SRO - The procedural procedural steps steps for for this this event event are are beyond beyond the the entry entry conditions conditions and and relate relate to to the the specific stategy for mitigating the event.
FINAL 107 107
HLC-08 NRC Written Exam
- 77. 000022 AA2.03 OOlILOSS 001/LOSS OF RX COOL MAKE/1/1/3.1/3.6/SRO/HIGH/43.5/NEW - 2008/AOP-003-002 MAKE/1/1/3.1/3.6/SRO/HIGHJ43.5/NEW - 2008/ AOP-003-002 Given the following:
- The plant is operating at 100% RTP.
- VCT makeup is in progress.
- The following indications are noted:
- BA Transfer Pump "A"
- A is running.
- PW Pump "A"A is running.
- FCV-113A, BA FLOW, OPEN.
FCV-1 1 3B, BLENDED MU TO CHG SUCT, CLOSED.
- FCV-113B, FCV-1 14A, PRIMARY WTR FLOW DILUTE MODE, OPEN.
- FCV-114A, FCV-1 14B, BLENDED MU TO VCT, CLOSED.
- FCV-114B,
- 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.
By FCV-1 1 3B has failed, causing the valve to fail CLOSED.
BY The air supply line to FCV-113B Attempt to establish Makeup to the VCT via FCV-114B.
FCV-1 1 4B.
C. The Charging Pump suction has swapped to the RWST. Reduce Turbine load as necessary to maintain T AVG within +/-
TAVG 1 .5 of
+/- 1.5 °F of T TREF.
REF' FCV-1 1 3B has failed, causing the valve to fail CLOSED. Attempt to D. The air supply line to FCV-113B establish Makeup via CVC-356, BORIC ACID BLENDER BYPASS TO CHARGING PUMP SUCTION.
108
HLC-08 HLC-08 NRC Written Exam NRC Written Exam The correct correct answer answer is is B.
B.
A: Incorrect A: Incorrect - Swapover
- Swapover setpoint setpoint isis 12.4 12.4 inches.
inches. NO NO swapover swapover should have occurred.
should have occurred. Action Action isis appropriate for appropriate for swapover swapover toto the the RWST RWST on on aa VCT VCT low low level level to to minimize minimize the the boration rate.
boration rate.
B: Correct Correct -- FCV-1 1 3B is FCV-113B is the ONLY ONLY valve listedlisted that is is out of position.
position. Since Since FCV-113B FCV-1 1 3B is is NOT operating NOT operating as expected, expected, actions actions lAW lAW AOP-003 would be be correct correct and and an an attempt toto restore restore makeup makeup is performed.
is performed.
Incorrect - Swapover setpoint is 12.4 C: Incorrect - 12.4 inches.
inches. NO NO swapover should have have occurred. Action is is appropriate for boration added to the RCS RCS from the RWST.
RWST.
Incorrect - Since FCV-113B D: Incorrect - FCV-1 1 3B is NOT operating as expected, AOP-003 has actions to use CVC-356 to makeup to the VCT. CVC-356 is ONLY to be used if FCV-113B' FCV-1 1 3B FCV-1 14B are unavailable as flowpaths.
AND FCV-114B Exam Question Number: 77
Reference:
APP-003-D5 and E5; AOP-003, Pages 3 and 10, AOP-017, Pages 3 and 34.
KA Statement: Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant Makeup: Failures of flow control valve or controller.
History: New - Written for HLC-08 NRC Exam.
SRO - Requires analysis of plant conditions and selection of mitigating procedure.
FINAL 109 109
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 78. 000025 AA2.07 78.000025 AA2.07 OOllLOSS 001/LOSS OF OF RHRll/1/3.4/3.7/SROIHIGHJ43.5/RNP RHPJ1/1/3.4/3.7/SRO/HIGHJ43.5/RNP BANKIAOP-020-002 BANKJAOP-020-002 During Mid-Loop During Mid-Loop operations, operations, thethe following following indications indications and and conditions conditions are are noted:
noted:
RHR Pump
- RHR
- Pump uN A is is operating, operating, FCV-605, FCV-605, RHR HEAT EXCHANGER RHR HEAT EXCHANGER BYPASS BYPASS isis inin AUTO.
AUTO.
Fl-605 indicates
- FI-605
- indicates 36003600 GPM GPM and and is oscillating +/-
is oscillating 100 GPM.
+/- 100 GPM.
RHR Pump
- RHR
- discharge pressure Pump discharge pressure is oscillating +/-
is oscillating o PSIG.
+/- 30 PSIG.
RCS standpipes
- RCS
- standpipes indicate indicate -73 inches (RTGB)
-73 inches (RTGB) andand -74
-74 inches inches (LOCAL).
(LOCAL).
Which ONE (1) of Which of the following is is the NEXT action required lAW AOP-020, LOSS LOSS OF RESIDUAL HEAT REMOVAL?
Reduce total RHR A. Reduce RHR flow by by throttling FCV-605 FCV-605 to 2850 GPM.GPM.
B Stop RHR Pump "A" B!'" A to prevent pump damage.
C. Establish Charging flow to restore RCS level 2: -68 inches.
D. Isolate Letdown flow by adjusting HIC-142, PURIFICATION FLOW CONTROLLER to 0%.
The correct answer is B.
A: Incorrect - IF RHR flow is high, actions to throttle FCV-605 would be appropriate for runout and lAW GP-008. Flow is NOT excessive or indicative of runout conditions B: Correct - - Standpipe levels below -72 inches are procedurally precluded to prevent vortexing and cavitation (which the oscillations indicate). AOP-020, LOSS OF RESIDUAL HEAT REMOVAL (SHUTDOWN COOLING) directs the RHR Pump to be tripped if cavitation is indicated PRIOR to attempts to restore inventory or eliminate inventory loss.
C: Incorrect - AOP-020 Section A provides directions for restoring RCS level via Charging Pumps, but ONLY after RHR Pump(s) are stopped earlier in the procedure.
D: Incorrect - Isolating letdown flow by closing HIC-142 will prevent potential losses from the RHR system. With RCS level << -72 inches, the first action is to stop the running RHR Pump to protect the pump from cavitation.
Exam Question Number: 78
Reference:
AOP-020, Pages 3-4, 17-18. 17-18.
KA Statement: Ability to determine and interpret interpret the following as they apply to the the Loss of Residual Heat Heat Removal System:System: Pump Pump Cavitation.
History:
History: Bank question.
SRO SRO - Analysis
- Analysis ofof conditions conditions andand indications indications toto conclude that cavitation conclude that cavitation is is the cause of the cause of the the abnormal abnormal indications, indications, andand procedure procedure entry entry directions directions for for mitigating mitigating in in the the appropriate appropriate order order (stop (stop the the pump pump toto prevent prevent damage) damage) 110 110
HLC-08 NRC Written Exam FINAL 111 111
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 79. 000026
- 79. 000026 G2.2.38 G2.2.38 OOllLOSS 001/LOSS OFOF CCW/lJ1/3.6J4.5JSROIHIGHl43.1INEW CCW/1/1/3.6/4.5/SRO/HIGHI43.1/NEW - 2008JCCW-012
- 2008/CCW-012 Given the Given the following:
following:
The plant
- The
- plant isis inin MODE MODE 3. 3.
The plant
- The
- plant experiences experiences aa loss loss of of 480V 480V Bus Bus E-1 E-1 and and EDG EDG "A"A does does NOT start.
NOT start.
COW Pump
- CCW
- Pump "c" breaker has C breaker has tripped on overload.
overload.
COW Pump
- CCW
- Pump "A" A is running.
Which ONE (1) of the following describes the required 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 11 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 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 />.
The correct answer is D.
A: Incorrect - LCO 3.7.6 is correct entry for a single train of CCW
- COW INOPERABLE. LCO LOO 3.7.6 Condition A is actually to restore an OPERABLE train of CCW COW within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
B: Incorrect - BOTH trains INOPERABLE therefore LCO
- LOO 3.0.3 must be entered, but time to get to MODE 4 is actually 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />, 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> is correct time to get to MODE 5.
C: Incorrect - LCO
- LOO 3.7.6 is correct entry and action for a single train of CCW COW INOPERABLE.
D:
0: Correct - - CCW Pump A COW "A" is powered from the DS OS Bus, which is NOT a credited Safeguards power source. Both B "B" and 0 "C" Pumps are INOPERABLE and LCO 3.7.6 does NOT contain aa condition for BOTH trains INOPERABLE, INOPERABLE, therefore LCO 3.0.3 must be entered and the plant must be in MODE 55 in 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
Exam Question Number:
Exam Question Number: 7979
Reference:
ITS ITS 3.7.6; ITS ITS 3.0.3, ITS 3.7.6 BD.
KA KA Statement:
Statement: Knowledge Knowledge of of conditions and limitations conditions and limitations in in the the facility license.
license.
History:
History: New New - Written
- Written for HLC-08 HLC-08 NRCNRC exam.
exam.
SRO SRO - Analysis of
- of current current plant plant conditions and application conditions and application of of generic generic LCO LCO requirements.
requirements.
FINAL FINAL 112 112
HLC-08 NRC HLC-08 NRC Written Written Exam Exam 80.
- 80. 000055 000055 EA2.01 EA2.0 1 OOl/STATION 001/STATION BLACKOUT/l/l/3.4/3.7/SROIHIGHJ43.5INEW BLACKOUT! 1/1/3.4/3 .7/SRO/HIGH/43 .5/NEW - 2008/AOP-024-007
- 2008/AOP-024-007 Given the Given the following:
following:
The plant
- The
- plant is is in in MODE MODE 55 with with RHR RHR Pump Pump "A" A in in service.
service.
- A loss of A loss of the the Startup Startup Transformer Transformer has has occurred.
occurred.
Instrument Air Header
- The Instrument
- Header isis depressurized.
RCS Temperature is increasing.
- RCS
- increasing.
RHR Pump
- RHR
- Pump "A" A is is NOT NOT running.
running.
- The crew has has implemented:
implemented:
- AOP-017, LOSS OF INSTRUMENT
- INSTRUMENT AIR AND
- AOP-020, LOSS OF RESIDUAL HEAT REMOVAL (SHUTDOWN COOLING)
In addition to restarting RHR Pump "A", A, which ONE (1) of the following describes the actions required to restore core COOling 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 D~ Start Compressor A and/or B B to restore IA pressure.
Reposition FCV-605 and HCV-758 from their Failed SHUT positions.
113 113
HLC-08 NRC HLC-08 Written Exam NRC Written Exam The correct The correct answer answer is D.
is O.
A: Incorrect A: Incorrect - Both
- Both FCV-605 FCV-605 andand HCV-758 HCV-758 failfail SHUT SHUT on on loss loss of of lA, but with IA, but with the the Blackout Blackout condition given, condition given, SA SA compressor compressor willwill NOT NOT be running. Air be running. Air Compressors Compressors A A and/or and/or B will B will be be available, available, but but must must be manually (local) be manually (local) started.
started. Cross-connecting Cross-connecting IAIA with SA is is a normal method method of restoring of restoring the IA IA header header in AOP-01 7 for events in AOP-017 events power available with power available to the SA SA compressor.
B: Incorrect B: Incorrect - Restart
- Restart of Air Compressors Compressors AlB NB will be be the success path path to restore restore IA IA pressure, pressure, but both FCV-605 but both FCV-605 and and HCV-758 fail SHUT HCV-758 fail SHUT on on loss loss of of IA.
IA.
Incorrect - With the Blackout condition given, power to SA compressor will NOT C: Incorrect - NOT bebe available. Air Compressors A and/or B will be available, but must be locally HCV-758 fail SHUT on loss of IA.
started. Both FCV-605 and HCV-758 IA.
D: Correct -
0: - Loss of IA results in FCV-605 and HCV-758 failing SHUT. Following the RHR pump restart (de-energized on Blackout), and restoration of IA pressure, the Flow/temperature valves must be repositioned.
Exam Question Number: 80
Reference:
AOP-017, Pages 3 and 36; SO-003, SD-003, RHR, Figure 3.
KA Statement: Ability to determine or interpret the following as they apply to a Station Blackout:
Existing valve positioning on a loss of instrument air system.
History: New - Written for HLC-08 NRC Exam.
SRO - Assessment of facility conditions, then recalling what strategy or action is required.
FINAL 114 114
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 81. 00005802.1.32
- 81. 000058 G2.1.32 OOIILOSS 001/LOSS OF OF DC POWERI1/1/3.8/4.O/SRO/LOW/43.5/NEW - 2008/EPP-26-003 DC POWERllI1I3.8/4.0/SROILOW/43.5/NEW - 2008/EPP-26-003 Prior to Prior to Step Step 13 13 ofof EPP-26, EPP-26, LOSS LOSS OF OF DC DC BUSBUS "A",
A, aa CAUTION CAUTION describes describes aa safety safety issue issue that that prohibits closing prohibits closing the the 4160V 4160V load load breakers breakers onto onto an an energized energized bus.
bus.
Which ONE Which ONE (1) (1) of of the the following following describes describes the the safety safety issue?
issue?
A':I A A A personnel personnel hazardhazard exists because the exists because the Load Breaker must Load Breaker must be closed locally, be closed locally, using using aa test test tool and tool and breaker breaker contact contact explosion explosion is is likely.
likely.
B. An B. An equipment equipment hazard hazard exists exists because because electrical electrical fault fault conditions conditions atat the the energized energized equipment equipment could cause non-isolable faults on the ESF ESF busses.
personnel hazard C. A personnel hazard exists exists because because local, local, manual manual 4160V breaker breaker manipulations manipulations havehave NOT NOT been fully analyzed.
been 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.
The correct answer is A.
A: Correct - - Caution prior to Step 13 states "LocallyLocally closing 4160V 41 60V Load Breakers on an 41 60V Bus could result in explosion of the breaker contacts."
energized 4160V contacts. The 4KV load breakers are NOT designed to be locally closed onto an energized bus. The tool that will be used is a test tool designed to check breaker face alignment. The slow breaker closure using the test tool would result in extreme arcing and contact explosion if the bus is energized.
B: Incorrect - The local closure should ONLY be performed to close onto a de-energized bus.
At this pOint point in the procedure, only de-energized busses and unloaded breakers are involved.
C: Incorrect - The loss of DC IS considered a non-credible event at Robinson, requiring a passive failure and therefore NOT included in Accident Analysis. However, the procedure to recover (EPP-26) has been fully evaluated, including the personnel hazards involved.
D: Incorrect - The step does NOT allow closure onto an energized bus (except under extreme emergency conditions). The breaker test tool does NOT prevent the remote operation of the breaker with the tool engaged.
Exam Question Number: 81
Reference:
Reference:
EPP-26, EPP-26, Page 9; 9; EPP-26-BD, Page Page 3, 6.
KA Statement:
Statement: Ability to explain explain and apply system system limits and precautions.
History: New New - Written
- Written for HLC-08 NRC Exam.
- RO level level forfor entry entry conditions conditions and and any any immediate immediate actions actions of of procedures.
procedures. SRO SRO responsible responsible for for procedure procedure steps steps including Cautions, Notes, including Cautions, Notes, andand their their bases.
bases. System System knowledge alone does not alone does not describe describe thethe hazards hazards ofof the local actions the local actions in in the the procedure.
procedure.
115 115
HLC-08 NRC Written Exam FINAL 116 116
HLC-08 NRC Written Exam
- 82. 000024 AA2.02 OOlJEMERG 001/EMERG BORATION/1/2/3.9/4.4/SROIHIGHl43.5INEW BORATION/1/2/3.9/4.4/SRO/HIGHI43.5/NEW - 2008JEPP-4-003
- 2008/EPP-4-003 Given the following:
- An ATWS condition has occurred from 100%
- RTP.
100% RTP.
- The crew is implementing FRP-S.1, RESPONSE TO NUCLEAR POWER GENE RAT I ON/ATW S.
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'I LCV-1 1 5B, EMER MU TO CHG SUCT AND CLOSE LCV-115C, A OPEN LCV-115B, LCV-1 1 5C, VCT OUTLET.
FCV-1 1 3A, BA FLOW and FCV-113B, B. OPEN FCV-113A, FCV-1 1 3B, BLENDED MU TO CHG SUCT.
C. Dispatch an operator to Manually OPEN MOV-350, BA TO CHARGING PMP SUCT.
FCV-1 1 3A, BA FLOW and FCV-114B, D. OPEN FCV-113A, FCV-1 1 4B, BLENDED MU TO VCT.
The correct answer is A.
A: Correct -- Step 4 of FRP-S.1 provides this as a full-flow boration path via the RWST as the alternative to the MOV-350 from BA pumps path. This also provides a direct path to borate the RCS.
B: Incorrect - This would be a restricted (Approx 10 GPM) flow path, it is one of the alternate paths listed in EPP-4, but is NOT in FRP-S.1.
C: Incorrect - Verify from RTGB is the directed step. FRP-S.1 does NOT direct local operation of MOV-350. The phrase "from RTGB was specifically added to ensure that from the RTGB" the step was NOT interpreted as If"If MOV-350 does NOT open, VERIFY implies local manual manipulation to open it,it", when a faster method was available by way of LCV-1 1 5B.
LCV-115B.
D: Incorrect - Delayed injection to the core (top of VCT) and restricted flow.
117 117
HHLC-08 LC-08 NRC Written Exam Exam Question Number: 82 Exam
Reference:
FRP-S.1,
Reference:
FRP-S.1, Page Page 7; FRP-S.1 FRP-S.1 BD, Page Page 49; SD-021, CVCS, Figure 2; OMM-041 ,Page Page 72.
KA Statement: Ability to determine and interpret the following as they apply to the Emergency Boration: When use of manual boration valve is needed.
History: New - Written for HLC-08 NRC exam.
SRO - Requires procedure knowledge and strategy beyond entry conditions and Steps 11 and 2, Immediate Actions.
FINAL 118 118
HLC-08 NRC Written Exam
- 83. 000033 000033 AA2.10 OOl/LOSS 001/LOSS ON ON IR IR NIIl/2/3.l/3.8/SRO/LOW/43.S/FARLEY-NI/1/2/3.1/3.8/SRO/LOW/43.5/FARLEY- 2001INIS-Oll 2001/NIS-Oll Given the following:
Given Plant startup is
- Plant
- is in lAW GP-005, POWER in progress lAW POWER OPERATION.
Reactor is
- Reactor
- is at 8%
8% RTP.
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 A':"
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 to> P-i 0 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
> P-10 C. Immediately OPEN the Reactor Trip Breakers.
D. Restore BOTH channels to OPERABLE status prior to increasing thermal power to to> P-i 0.
> P-10.
The correct answer is A.
A: Correct - - LCO 3.3.1, Condition G G actions required if TWO IR channels INOPERABLE with power> P-6, but < P-i 0.
< P-10.
B: Incorrect - LCO 3.3.1, Condition F actions if ONE IR channel is INOPERABLE with power>
P-1O. With TWO IR channels INOPERABLE, Condition Gis P-6, but < P-10. G is applicable.
C: Incorrect - Action required if BOTH Source Range instruments are INOPERABLE per ITS LCO 3.3.1 Condition J.
D: Incorrect - LCO 3.3.1, Condition H
- H allows continued operation with ONE or BOTH IR channels INOPERABLE when below P-6, but requires restoration prior to going above P-6. Distractor D is a misapplication of Condition H.
119 119
HLC-08 NRC HLC-08 NRC Written Exam Exam Exam Question Exam Question Number:
Number: 8383
Reference:
Reference:
ITS 3.3.1, 3.3.1, Page Page 3.3-1, 3.3-1 3.3-3 3.3-3 and and 3.3-4.
3.3-4.
KA Statement: Ability to determine and interpret the following as they apply to the Loss of Intermediate Range Nuclear Instrumentation: Tech-Spec limits if both intermediate range channels have failed.
B and D, Removed Subsequent actions and reference History: Modified by changing distractors Band to procedures.
SPO - Application of required actions AND application of ITS Conditions for Table 3.3.1-1 for SRO -
Conditions in excess of LCO.
FINAL 120 120
HLC-08 NRC Written Exam
- 84. G2.2. 14 0011
- 84. 000059 02.2.14 001/ACC RADWASTE ACC RADW RELEASE/1/2/3.9/4.3/SRO/HIGH/43.3/NEW - 2008/
ASTE RELEASE/112/3.9/4.3/SROIHIOH/43.3/NEW -
Given the following:
- The plant is operating in MODE 3.
- A release is in progress from Monitor Tank "A".
- A.
- CW Pump "A"
- A is running.
Ui has ONE CW
- U1
- OW Pump running.
- The release permit states a release rate of 80 GPM with ONE U2 CW Pump running.
Subsequently:
- CW Pump "A"
- A trips.
Based on current plant conditions, what is the impact on the release?
A':I 10CFR2O limits may be exceeded. The release must be stopped.
A 10CFR20 100FR2O limits will NOT be exceeded. NPDES Discharge limits for pH may be exceeded.
B. 10CFR20 Terminate the release.
100FR2O limits will NOT be exceeded. The release may continue.
C. 10CFR20 D. 10CFR20 10CFR2O limits may be exceeded. Release may continue provided 2 independent samples were obtained during permit generation.
The correct answer is A.
A: Correct - - Release rate is based on dilution flow from Unit 2 Circ Water Pump with dilution flow of 160,000 GPM. Although Unit 1 1 has a Circ Water Pump operating, it has a lower capacity (50,000 GPM) than the Unit 2 pump. With the dilution flow being less than the dilution flow that the release was based on, there is a potential that the 10CFR20 100FR2O release limits will be exceeded.
B: Incorrect - Dilution flow of Unit 11 Circ Water Pump is lower than that provided by Unit 2 pump. 10CFR20 1 OCFR2O release limits are impacted based on the assumptions made to authorize the release.
C: Incorrect - 10CFR20
- 1 OCFR2O limits have the potential to be exceeded and the release must be terminated until further analysis has determined that the proper dilution flow is available to support the release.
D: Incorrect - 2 independent samples for the release generation does NOT have any bearing on the release continuing. The release must be terminated until additional analysis has been performed and proper dilution flow is verified.
121 121
HLC-08 HLC-08 NRC NRC Written Written Exam Exam Exam Question Exam Number: 84 Question Number: 84
Reference:
EMP-023,
Reference:
EMP-023, Pages Pages 46, 48 and 46, 48 and 49.
49.
KA Statement:
KA Statement: Knowledge Knowledge of of the the process process for for controlling controlling equipment equipment configuration configuration or or status.
status.
History: New History: - Written for New - Written for HLC-08 HLC-08 NRC NRC Exam.
Exam.
SRO - Requires SRO - Requires analysis analysis ofof plant plant conditions conditions and and selection selection of of mitigating mitigating procedure.
procedure. Mitigating Mitigating actions are beyond entry level knowledge required required of ROs.
ROs.
FINAL FINAL 122 122
HLC-08 NRC Written Exam 85.000074 G2.4.2 1 OOllINAD
- 85. 000074 G2.4.21 CORE COOLING/112/4.0/4.6/SROIHIGH/43.2/43.3/NEW 00 1/INAD CORE COOLING/1/2/4.0/4.6/SRO/HIGHI43 .2/43 .3/NEW - 2008IRCS-013 2008/RCS-0 13 Given the following:
- A LOCA has occurred.
- RCS Subcooling is 0 of.
- °F.
- RCPs are secured.
- RCS temperature by CETC is 750 of.
- °F.
RVLIS Full Range is 40%.
- RVLlS The mitigative strategy required for this event is to depressurize the S/Gs to (1)
!j.... AND verify at least 2 of 3 RCS Hot Legs are less than L (2) prior to isolating the SI Accumulators.
A (1) 140 PSIG At!
°F (2) 365 of (1)14OPSIG B. (1) 140PSIG
°F (2) 350 of C. (1) atmospheric pressure F
0 (2) 365 of D. (1) atmospheric pressure
°F (2) 350 of 123 123
HLC-08 NRC HLC-08 Written Exam NRC Written Exam The correct correct answer answer is is A.
A.
The strategy The strategy of of FRP-C.1 FRP-C.1 isis to to depressurize depressurize the SIGs to the S/Gs to 140 140 PSIG PSIG to to allow allow the the SI SI Accumulators Accumulators to discharge to discharge into into the RCS. Once the RCS. Once the the SI SI Accumulators Accumulators have have discharged, discharged, they they are are isolated isolated to to prevent the prevent the additional additional nitrogen nitrogen from from being being discharged discharged into into the the RCS.
RCS. Once Once the the SI SI Accumulators Accumulators have been have been isolated, isolated, the S/Gs S/Gs are are depressurized depressurized to to atmospheric pressure pressure to allow allow low low head head SISI injection injection to be be provided the core.
to the core.
A: Correct A: Correct - - Conditions have Conditions have been been met met to to isolate the the SISI Accumulators.
Accumulators. IfIf the the RCS RCS temperature has NOT decreased to 365 0 365°F, F, the procedure will place place you in a procedure loop to ensure that secondary heat sink is is available to allow the S/Gs to continue to be used for cooling.
B: Incorrect - 140 PSIG is correct but the RCS temperature is 365 S: -
0 F. 350 365°F. 0 F is the MODE 4 350°F transition temerature.
C: Incorrect - S/Gs are depressurized to atmospheric pressure after the SI Accumulators have been isolated. 365365°F0 F is the required RCS Hot Legs temperature for SI Accumulator isolation.
D: Incorrect - S/Gs are depressurized to atmospheric pressure after the SI Accumulators have 0: -
been isolated. 350350°F0 F is NOT the required RCS Hot Legs temperature for SI Accumulator isolation.
Exam Question Number: 85
Reference:
FRP-C.1, Pages 10, 12; FRP-C.1 SO, BD, Pages 14, 16, 17.
KA Statement: Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
History: New - Written for HLC-08 NRC exam.
SRO - Requires knowledge of Procedure (FRP-C.1) beyond entry condition. The strategy involved involved (maximum cooldown using intact SIGs) cooldown rate using S/Gs) and details of target temperatures for step actions such as SI Accumulator Isolation Isolation are are specific procedure details.
FINAL 124 124
HLC-08 NRC Written Exam Exam
- 86. 003 A2.03 86.003 A2.03 OOIIREAC 001/REAC COOL PUMP/2/1/2.7/3.1/SROIHIGHI43.5INEW - 2008/RCS-008 COOL PUMP/2/1/2.7/3.lISROIHIGHJ43.5INEW - 2008/RCS-008 Given the following; Given
- The plant is
- is operating at 100% RTP.
100% RTP.
- CCW temperature has increased to 102
- 102 of
°F due to CCW Heat Exchanger "A" A being out of service for scheduled maintenance.
- RCP "c"
- C thrust bearing temperature has reached 220 of °F and stabilized.
- APP-001-B5, RCP HIGH VIB and APP-001-F3, RCP C BEARING HI TEMP are illuminated.
- RCP "c"
- 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" C because the ...
A. Thrust bearing has exceeded the bearing temperature limit, close CVC-303C, SEAL RETURN ISOLATION Valve, within 3-5 minutes.
By 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.
125 125
HLC-08 NRC Written Exam The correct answer is B.
Incorrect - RCP thrust bearing has A: Incorrect - has exceeded its maximum limit limit of 200 o F. Valve CVC-303C 200°F.
is ONLY closed when a seal failure occurs on an RCP,RCP, NOT for a bearing failure.
B: Correct -- RCP thrust bearing has exceeded its maximum limit of 200 o F. After the RCP 200°F.
has been tripped, the affected PZR Spray valve is closed for the non-operating RCP.
C: Incorrect - RCP pump bearing temperature limit is 225 0 F and has NOT been exceeded.
225°F Action to close the PZR Spray valve for the non-oiperating RCP is correct.
D: Incorrect - RCP pump bearing temperature limit is 225 0: -
0 F and has NOT been exceeded.
225°F Valve CVC-303C is ONLY closed when a seal failure occurs on an RCP, NOT for a bearing failure.
Exam Question Number: 86
Reference:
APP-001-B5; APP-001-F3; AOP-018, Section B.
KA Statement: Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Problems associated with RCP motors, including faulty motors and current, and winding and bearing temperature problems.
History: New - Written for HLC-08 NRC exam.
SRO - Requires evaluation of plant conditions and selection of the applicable actions to mitigate the event.
FINAL 126 126
HLC-08 NRC Written Exam
- 87. G2. 1.7 001IESFAS/2/1/4.4/4.7/SROIHIGHl43.S/NEW 013 G2.1.7 00 1/ESFAS/2/1/4.4/4.7/SRO/H10H143 .5/NEW - 20081ESF-006
- 2008/ESF-006 Given the following:
- The plant is operating at 100%
- 100% RTP.
- MST-023, Train "B"
- B SAFEGUARDS testing is in progress.
l&C reports a condition that would prevent Train "B"
- I&C
- B ESFAS from actuating.
What ONE (1) of the following describes the effect on the plant?
A'I A Containment Isolation Phase A and Phase B will actuate if required.
LCD 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 />.
Enter LCO B. Containment Isolation Phase A and Phase B will actuate if required.
B Safeguards LCO Train "B" LCD 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 "A"A 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.
B Safeguards LCO Train "B" LCD 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 "A"A Safeguards is OPERABLE.
The correct answer is A.
A: Correct - - Containment Isolation Phase A and Phase B will be actuated from Train "A" A B Safeguards surveillance was in progress when the failure Safeguards. Train "B" was discovered. During surveillance testing, the LCO LCD can be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided that the other train is operable. When a failure occurs or is LCD must immediately be declared and the action statement discovered, the LCO applied.
B: Incorrect - The LCO
- LCD must be declared immediately once a failure has occurred or has been discovered.
C: Incorrect - BOTH Phase A and Phase B
- B will occur from Train A "A"
D: Incorrect - BOTH Phase A and Phase B
- B will occur from Train "A".
A. LCO LCD must be declared immediately when a failure occurs or is discovered.
127 127
HLC-08 NRC Written Exam Exam Question Number:
Exam Number: 87
Reference:
OMM-022, Page
Reference:
Page 35.
KA Statement: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrumentation interpretation.
History: New - Written for HLC-08 NRC exam.
SRO - The SRO must determine plant status, exercise operational judgement, and determine the correct actions during changing plant conditions.
FINAL 128 128
HHLC-08 NRC Written Exam LC-08 NRC Exam 88.
- 88. 061 061 G2.1.27 00 1IAFWI2I1/3 .914.OISRO/LOW/43. 1/NEW - 2008/AFW-002 02.1.27 001lAFWI2I1/3.9/4.0/SROILOW/43.1INEW - 2008/AFW-002 What is is the the basis basis for the Condensate Condensate Storage Storage Tank Tank minimum minimum volume required required by by LCO LCO 3.7.5, 3.7.5, CONDENSATE STORAGE CONDENSATE STORAGE TANK?
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 B:t Safety Valves.
C. Ability to maintain at least 11 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.
The correct answer is B.
For anticipated operational occurrences and accidents that do NOT affect the OPERABILITY of the Steam Generators, the analysis assumption is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at MODE 3, steaming through the MSSVs.
A: Incorrect - Condenser steam dumps are a valid path but the basis document assumes flow path is through the Main Steam Safety Valves.
B: Correct - - The analysis assumption is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at MODE 3, steaming through the MSSVs.
C: Incorrect - 8% level is a minimum level required to satisfy other Heat Sink requirements but the basis for CST level is NOT tied to S/G level.
D: Incorrect - Steam Line PORVs are a valid path but the basis document assumes flow path is through the Main Steam Safety Valves Exam Question Number: 88
Reference:
LCO 3.7.5 Basis Document.
KA Statement: Knowledge of system purpose and/or function.
History: New - Written for HLC-08 NRC Exam.
SRO - Understanding bases associated with conditions and limitations of the facility license.
FINAL 129 129
HLC-08 NRC Written Exam
- 89. OlO 010 A2.03 OOIJPZR 00 1/PZR PRESSURE CONTROLl211J4.1J4.2/SROIHIGHJ43.5INEW CONTROL/2/1/4. 1/4.2/SRO/HIGH/43 .5/NEW - 200S/FRP-H.I-003
- 2008/FRP-H. 1-003 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 11 PORV is NOT an adequate bleed path, OPEN ALL RCS and PZR vent valves.
A":I B. 11 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.
The correct answer is A.
A: Correct -- 1 PORV does NOT provide an adequate bleed path to ensure SI flow will cool 1
the core. FRP-H.1 directs opening ALL RCS and PZR vents to provide sufficient vent path if BOTH PORVs are NOT available.
B: Incorrect - 1
- 1 PORV is NOT an adequate vent path, but the action to depressurize ALL S/Gs will NOT mitigate the failure of the PORV to OPEN. Depressurizing ONE S/G is an action following lineup of the bleed path to assist in cooldown and allow low pressure water to be added to the S/G.
C: Incorrect - Assuming that 1
- 1 PORV is an adequate bleed path is incorrect and a candidate could make that choice if they assumed that ALL that was needed was a reduction in RCS pressure. Depressurizing ONE S/G is an action following lineup of the bleed path to assist in cooldown and allow low pressure water to be added to the S/G.
D: Incorrect - Assuming that 11 PORV is an adequate bleed path is incorrect and a candidate could make that choice if they assumed that ALL that was needed was a reduction in RCS pressure. Verifying that SI flow is adequate is an action after the bleed path is established and it is determined to be adequate.
130 130
HLC-08 NRC Written Exam Number: 89 Exam Question Number:
Reference:
FRP-H.1, Page 19; 19; FRP-H.1 SO, BD, Page 57.
KA Statement: Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
PORV Failures.
History: New - Written for HLC-08 NRC Exam.
SRO - Requires evaluation of plant conditions, selection of appropriate actions and sequence of actions lAW station procedures.
FINAL 131 131
HLC-08 HLC-08 NRC NRC Written Written Exam Exam 90.
- 90. 103 G2.4.30 001lCONTAINMENT/2I1/2.7/4.lISROILOW/43.S/NEW 103 G2.4.30 00 1/CONTAINMENT/2/1/2.7/4. 1/SROJLOW/43 .5/NEW - 2008/0MM-007-002
- 2008/OMM-007-002 Given the Given the following:
following:
The plant
- The
- plant isis operating operating at at 50%
50% RTP.
RTP.
Power ascension
- Power
- ascension inin progress progress lAW lAW GP-005, GP-005, POWER POWER OPERATION, OPERATION, following following aa refueling refueling outage.
During paperwork reviews, Maintenance
- During
- Maintenance Supervision Supervision has has discovered discovered that the blind flange on the on the Refueling Refueling Transfer Transfer Tube Tube was installed installed but but has has NOT NOT been been properly properly torqued.
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 />.
MODE hours.
Based on current plant conditions, notification to the NRC Operations Center will be required ...
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.
BY' 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.
The correct answer is B.
A: Incorrect - No 10 CFR 50.54(x) condition exists. The candidate may misunderstand the definition and use of 50.54(x).
B: Correct - - A TS shutdown is required, and lAW AP-030, REPORTING REQUIREMENTS, a notification to the NRC Operations Center is required.
C: Incorrect - This requirement is for aa notification when an actual failure to perform a required safety function has occurred, NOT for a condition where a barrier is degraded.
D: Incorrect Incorrect - This notification is for a notification of aa safeguard
- safeguard system as itit relates to allowance of unauthorized or undetected undetected access to a protected area. No No access issues are involved with the stated condition.
132 132
HLC-08 NRC HLC-08 Written Exam NRC Written Exam Exam Question Exam Question Number:
Number: 9090
Reference:
AP-030,
Reference:
AP-030, Pages Pages 11 11 and 12.
and 12.
KA Statement: Knowledge KA Statement: Knowledge of of events events related to system related to operation/status that system operation/status that must must be reported to be reported internal organizations internal organizations oror external external agencies, agencies, such such as as the the State, State, the the NRC, NRC, or or the the transmission system transmission system operator.
operator.
History: New History: - Written for New - Written for HLC-08 HLC-08 NRC NRC exam.
exam.
Notification to NRC SRO - Notification
- NRC or other outside agencies is SRO agencies is SRO responsibility, responsibility, per per AP-030.
FINAL 133 133
HLC-08 NRC Written Exam Exam 91.
- 91. 02.2.40 OOllREACTOR 002 G2.2.40 002 001/REACTOR COOLANT/2/2/3.4/4.7/SRO/HIGH/43.2/43.S/NEW COOLANT/2/2/3.4/4.7/SRO/HIGHJ43.2143.5/NEW - 2008IRCS-OIS
- 20081RCS-015 Given the following:
Given Plant is
- The Plant
- is in MODE 3 at 547 F following a reactor trip from 100%
0 547 of 100% RTP.
indicates DOSE EQUIVALENT 1-131
- RCS chemistry sample indicates 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 B~ °F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, to ensure RCS saturation pressure is below the AVG to < 500 of TAVG 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 °F 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 AVG to < 500 of TAVG AND PZR PORV Block valves can be closed.
The correct answer is B.
A: Incorrect - This is the partial LCO applicable to 1-131 greater than 0.25, and less than 60 Micro-Curies/gm, except LCO requires MODE 3 with T < 500 of AVG <
TAVG °F B: Correct -- ITS for 1-131 is applicable in MODE 3 with T AVG > 500 of.
TAVG> °F. Saturation pressure
°F is 665 PSIG which is below the S/G Safety Valve setpoint.
for 500 of C: Incorrect - No MODE 4 requirements. Basis is for conditions below S/G Safety Valve setpoint.
D: Incorrect - S/G Safety Valves, NOT MSIVs, are the bases for the requirement. MSIVs may be CLOSED any time following the trip, but will remain OPEN to allow controlled cooldown/depressurization of S/Gs. PZR PORV Block valves may be CLOSED below MODE 3, but are NOT the bases for the requirement.
134 134
HLC-08 NRC HLC-08 NRC Written Written Exam Exam Exam Question Exam Question Number:
Number: 91 91
Reference:
Reference:
ITS 3.4.16; 3.4.16; ITS ITS 3.4.16 3.4.16 BD.
BD.
KA Statement:
KA Statement: Ability toto apply apply Technical Technical Specifications Specifications for for aa system.
system.
History: New History: New - Written
- Written for HLC-08 HLC-08 NRC NRC exam.
exam.
SRO - Knowledge SRO - Knowledge of of ITS ITS beyond beyond 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> hour action action statements.
statements.
FINAL 135 135
HLC-08 NRC Written Exam
- 92. 011 G2.4.50 02.4.50 OOllPZR 001/PZR LVL CONTROLl2/2/4.2/4.0/SRO/HIGH/43.5/NEW CONTROL/2/2/4.2/4.0/SRO/HIGHJ4I5/NEW - 20081PZR-008
- 2008IPZR-008 Given the following:
100% RTP.
- The plant is operating at 100%
- RTP.
APP-003-E8, PZR CONTROL HIILO
- APP-003-ES,
- HI/LO LVL is illuminated.
APP-003.F4, CHG PMP HI SPEED is illuminated.
- APP-003-F4,
- RCS Pressure is 2215 PSIG and decreasing.
- T AVG is equal to T TAVG TREF.
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 D~ AOP-016, EXCESSIVE PRIMARY LEAKAGE.
Control Charging and Letdown to stabilize PZR level.
The correct answer is D.
APP-003-E8 lists possible causes as a Load Rejection (refer to AOP-015),
APP-003-ES AOP-01 5), excessive RCS AOP-01 6), a PZR level controller failure (AOP-025) and if a PZR level control leakage (refer to AOP-016),
problem exists then Manually adjust Charging Pump speed and Letdown to maintain PZR level.
A: Incorrect - AOP-01
- AOP-019 9 basis document states that this procedure is NOT intended to combat an RCS pressure decrease due to a loss of RCS inventory.
B: Incorrect - AOP-01
- AOP-019 9 basis document states that this procedure is NOT intended to combat an RCS pressure decrease due to a loss of RCS inventory.
C: Incorrect - AOP-016 is the proper procedure to restore stable conditions in the RCS. With the given conditions, restoring PZR Pressure to its normal band will NOT provide the necessary corrective actions for this situation.
D: Correct -- Controlling charging and letdown flow rates will enable the operators to restore conditions to stabilize the plant.
136 136
HLC-08 NRC HLC-08 NRC Written Written Exam Exam Exam Question Exam Number: 92 Question Number: 92
Reference:
Reference:
AOP-019, Pages Pages 5,5, 6; 6; AOP-016, Pages 6, AOP-016, Pages 7.
6, 7.
KA Statement:
KA Statement: Ability to to verify system alarm setpoints system alarm setpoints and and operate operate controls controls identified identified in in the alarm response response manual.
manual.
History: New History: New - Written
- WrItten for for HLC-08 HLC-08 NRC NRC exam.
exam.
SRO - Assessment of facility conditions and selection of appropriate procedures during abnormal situations.
FINAL 137 137
HLC-08 NRC Written Exam
- 93. 071 G2.2.25 001IWASTE 93.071 001/WASTE GAS DISPOSAL/2/2/3.2/4.2/SROILOW/43.2INEW DISPOSAL!2/2/3.2/4.2/SRO/LOW/43 .2/NEW - 200SIWD-00S
- 2008/WD-008 Which ONE (1) (1) of the following describes the TRM limitation on the quantity of radioactivity permitted in permitted in the Waste Gas Decay Tank(s) AND the basis for that limit?
The quantity contained in _J..jj_ ill shall be::s.
be < 1.9 1.9 X 10 4
i0 4 Curies (Xe-133 (Xe-i 33 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 DY' (2) NOT result in exceeding the annual total body exposure to offsite personnel The correct answer is D.
From TRM 3.21 Basis "...in .. .in the event of an uncontrolled release of the tank's tanks contents, the resulting total body exposure to a member of the public at the nearest site boundary will not exceed 0.5 rem in an event of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> duration."duration.
A: Incorrect - The limit is applied to EACH Waste Gas Decay Tank.
B: Incorrect - Applicability is correct to EACH tank, but basis is incorrect. Plausible if candidate assumes Accident Analysis addresses personnel likely to receive MOST exposure (onsite personnel) on a release, however analysis for TRM basis only addresses exposure at the site boundary.
C: Incorrect - The limit is applied to EACH tank and basis is incorrect. Plausible if candidate assumes Accident Analysis addresses personnel likely to receive MOST exposure (onsite personnel) on a release, however analysis for TRM basis only addresses exposure at the site boundary.
D: Correct - - The limit is applied to EACH Waste Gas Decay Tank, and ensures a member of the public will not receive a dose in excess of 0.5 Rem in event of an uncontrolled release of a single tanks tank's contents in an event of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> duration.
138 138
HLC-08 NRC HLC-08 NRC Written Written Exam Exam Exam Question Exam Number: 93 Question Number: 93
Reference:
Reference:
TRM 3.21; 321; TRM TRM 3.21 3.21 BD.
BD.
KA Statement:
KA Statement: Knowledge Knowledge of of the the bases in Technical bases in Technical Specifications Specifications for limiting limiting conditions conditions for operations and and safety limits.
limits.
History: New History: New - Written
- Wriffen for HLC-08 NRC for HLC-08 Exam.
NRC Exam.
SRO - Knowledge of Tech Spec Bases that
- that is required to analyze TS required actions and terminology.
FINAL 139 139
HLC-08 NRC Written Exam
- 94. G2.1.41 G2. 1.41 ~Ol/CONDUCT 001/CONDUCT OF OPERATION/3J2.8/3.7/SROILOW/43.6/NEW OPERATION/3/2.8/3 .7/SRO/LOW/43 .6/NEW - 2008/AOP-020-004 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 B:I its original location.
C. Upender.
D. core, in any location that is bordered by 2 other assemblies.
The correct answer is B.
A: Incorrect - RCC Change fixture does have a basket that is available to receive the fuel assembly, but placing the assembly in the RCC Change fixture while losing Refueling Cavity level could result in the fuel assembly being uncovered and cause excessive radiation exposure.
B: Correct - - Place the fuel assembly back in a location where subcritical configuration was known.
C: Incorrect - The Transfer Cart is en route to the SFP and contains the assembly basket and an irradiated fuel assembly. There is NO basket available in which to place the fuel assembly.
D: Incorrect - Placing a fuel assembly in an unanalyzed core position could result in a loss or reduction of the required shutdown margin.
Exam Question Number: 94
Reference:
AOP-020, Section B.
KA Statement: Knowledge of the refueling process.
History: New - Written for HLC-08 NRC Exam.
SRO - Knowledge of Refueling Procedures and processes.
140 140
HLC-08 NRC Written Exam FINAL 141 141
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 95. G2.2.1S
- 95. G2.2. 1800 1/EQUIPMENT CONTROLl3/2.6/3.9ISROIHIGHl43.5IRNP OOllEQUIPMENT CONTROL/3/2.6/3 .9/SRO/HIGH/43 .5IRNP AUDIT AUDIT - 200l/0MM-OOI-ll-002
- 200 1/OMM-00 1-11-002 Given the Given the following:
following:
- RC
- personnel need RC personnel need to to use Demin Water use Demin Water for for decon decon activities activities for for aa spent spent fuel fuel cask.
cask.
They will
- They
- need to will need operate one to operate one valve for about valve for about an hour AND will finish before an hour before shift shift turnover.
turnover.
manipulation is
- The valve manipulation
- is NOT NOT covered by by an an approved procedure.
procedure.
Which ONE Which ONE (1) (1) of of the following describes the following how this describes how this manipulation manipulation will will be tracked and be tracked and controlled controlled OMM-OO1-11, LOGKEEPING?
lAW OMM-001-11, procedure must be A. A temporary procedure be approved prior to manipulation manipulation of the valve.
B The valve manipulation must be entered in the Start/Stop Log B:I 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.
The correct answer is B.
A: Incorrect - A temporary procedure is NOT appropriate for single valve operation unless water is to be introduced into a system or within a clearance boundary.
B: Correct - - The WCC SRO or the CRSS determines which method of control is used. They will then direct an Autolog entry to provide the necessary tracking to ensure proper alignment of the valve lAW OMM-OO1 OMM-001-11.-11.
C: Incorrect - Use caution tags would be required if the alignment would be in effect past the end of the shift.
D: Incorrect - Portion of system component requires caution tags if out of position past the end of the shift.
Exam Question Number: 95
Reference:
OMM-OO1 OMM-001-11, -11, Pages 23-25.
KA Statement: Knowledge of the process for managing managing maintenance activities during shutdown operations, operations, such as risk assessments, work prioritization, etc.
History: Bank question.
History: Bank question.
SRO - Assessing SRO - Assessing plantplant conditions and then conditions and then applying appropriate appropriate procedural requirements for maintaining maintaining configuration control.
FINAL FINAL 142 142
HHLC-08 LC-08 NRC Written Exam
- 96. G2.2. 1500 G2.2.15 1/EQUIPMENT CONTROLl3/3.9/4.3/SROILOW/43.3INEW OOllEQUIPMENT CONTROL/3/3 .914.3ISRO/L0W143 .3/NEW - 2008/0MM-OOl-8-002
- 2008/OMM-00 1-8-002 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-S, OMM-OO1-8, 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 01' Operating Procedure.
The correct answer is D.
OMM-OO1 -8, Section S.5.6 A: Incorrect - OMM-001-S,
- 8.5.6 specifies that "if if there is reason to believe the valve was deliberately mispositioned or tampered with...
with ... " it is treated as a Deliberate Mispositioning. This is NOT the default assumption. Additional information or suspicion may invoke this set of actions, but NO evidence is established in the question stem.
B: Incorrect - If the cause of the mispositioning can be clearly identified, a single valve lineup is allowed. The question stem does NOT clearly identify the cause. There are other valves within close proximity to the mispositioned valve.
C: Incorrect - A full valve lineup is to be performed if the cause of the mispositioning is unknown and CANNOT be quickly determined. A full valve lineup is NOT required because the valve is within the Clearance boundary.
D: Correct - - OMM-001-S specifies that a valve lineup of valves within the Clearance OMM-OO1-8 boundary is to be performed if maintenance activities were performed on valves within the Clearance boundary, and it is believed that those maintenance activities caused the mispositioning.
143 143
HLC-08 NRC HLC-08 NRC Written Written Exam Exam Exam Question Exam Question Number:
Number: 96 96
Reference:
OMM-001-8,
Reference:
OMM-OO1-8, Page 17.
Page 17.
KA Statement:
KA Statement: Ability to determine the expected plant the expected plant configuration configuration using using design design and and configuration control configuration control documentation, documentation, such such as drawings, line-ups, as drawings, line-ups, tag-outs, tag-outs, etc.
etc.
History: New History: New - Written
- Written for for HLC-08 HLC-08 NRC Exam.
NRC Exam.
SRO - Requires analysis of plant events and administrative processes and determination of SRO -
required actions to maintain configuration control.
FINAL FINAL 144 144
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 97. G2.2.36
- 97. G2.2.36 OOllEQUIPMENT 00 1/EQUWMENT CONTROL/3/3.1/4.2/SROILOW/43.2/SALEM CONTROL/3/3. 1/4.2ISROILOWI43 .2/SALEM - 2001lITS
- 2001/ITS INTRO-OOS INTRO-005 Given the Given the following:
following:
The plant
- The plant is is operating operating at at 100%
100% RTP.
RTP.
SI Pump
- SI
- Pump "A" is INOPERABLE A is INOPERABLE due to failed motor motor bearings.
bearings.
- While aligning SI Pump
- B to replace Pump "B" replace SI Pump Pump "A",
A, the E-1 E-1 supply breaker breaker 52-22B breaker racking breaker racking mechanism mechanism was was found found broken, preventing the broken, preventing the breaker breaker from from being being racked racked in and in and closed.
closed.
surveillance procedures has determined the last quarterly
- An audit of surveillance surveillance on SI Pump "c" missed.
C was missed.
Which ONE (1) of the following describes the appropriate action?
A. Operability Determination is required for SI Pump "c" C lAW OPS-NGGC-1305, OPS-NGGC-1 305, OPERABILITY DETERMINATIONS.
B. Perform a Safety Function Determination for SI Pump "c" C lAW OMM-007, EQUIPMENT INOPERABLE RECORD.
C Demonstrate the operability of SI Pump "c" C':" 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 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.
D. Demonstrate the operability of SI Pump "c" 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 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
The correct answer is C.
A: Incorrect - Inappropriate application of operability determination procedure OPS-NGGC-1 OPS-NGGC-1305. 305.
B: Incorrect - Inappropriate application of TS 5.5.15, Safety Function Determination Program.
C: Correct - - Since SI Pumps A "A" is INOPERABLE INOPERABLE and B "B" CANNOT be placed in service, the plant isis in aa 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> hour LCO. The missed surveillance has placed the plant in aa condition where the surveillance must be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the plant plant must be placed in MODE 4 within 13 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.
D:
D: Incorrect - Represents
- Represents inappropriate inappropriate application application of TS 3.5.2, 3.5.2, Condition Condition AA for for aa single train of SI inoperable.
of SI inoperable. For or more For 11 or more trains trains inoperable inoperable with with 100%
100% flow to to aa single single operable train operable train available.
available.
145 145
HLC-08 HLC-08 NRCNRC Written Written Exam Exam Exam Question Exam Number: 97 Question Number: 97
Reference:
Reference:
ITS 3.0.3; 3.0.3; SR SR 3.0.3; ITS 5.5.15; 3.0.3; ITS 5.5.15; ITS ITS 3.5.2; 3.5.2; OMM-007, OMM-007, Pages Pages 25, 25, 26; 26; OPS-NGGC-1305, Pages OPS-NGGC-1305, Pages 77 and and 8.8.
KA Statement: Ability to analyze the effect KA effect of of maintenance maintenance activities, activities, such as as degraded power power sources, on the sources, the status of limiting limiting conditions for operations.
operations.
History: Bank History: Bank question.
question.
SRO - Requires a 'from
- from memory' memory application of Tech Specs in a situation where TS 3.0.3 and SR 3.0.3 may SR may apply. The SRO SRO has has to determine the appropriate course of action.
FINAL 146 146
HLC-08 NRC Written Exam HLC-OS
- 98. 02.4.6 9S. G2.4.6 OOllEMERO 00 1/EMERG PROCIPLAN/3/3.7/4.7/SRO/HIGH/43.5/NEW PROC/PLAN/3/3 .7/4.7/SRO/HIGHJ43 .5/NEW - 200SIEPP-16-003
- 2008/EPP- 16-003 Given the following:
Given Reactor has
- The Reactor
- has tripped from 100%
100% RTP.
RTP.
- RCS temperature is 430 of.
- °F.
SIG "A"
- S/G
- A pressure is 100 PSIG.
SIG "B"
- S/G
- B pressure is 50 PSIG.
SIG "c"
- S/G
- C 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" B and "C",
C, continue to feed S/G SIG "A" A lAW Foldout A.
C. Isolate Feedwater to S/Gs "B" B and "C",
C, continue to feed S/G SIG "A" A lAW EPP-16, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS.
D~
D Throttle Throffle Feedwater to ALL S/Gs to 80 to 90 GPM lAW EPP-16, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS.
The correct answer is D.
A: Incorrect - Correct mitigative strategy, but Foldout A requires 11 intact S/G. Stem conditions EPP-1 6 will be used.
indicate that ALL S/Gs are faulted and EPP-16 B: Incorrect - Correct mitigative strategy and correct procedure for 2 faulted S/Gs. Stem conditions indicate that ALL S/Gs are faulted and EPP-16 EPP-1 6 will be used.
EPP-1 6 is the correct procedure to enter, however, the mitigative strategy is C: Incorrect - EPP-16 incorrect, Feedwater would NOT be isolated to ALL S/Gs.
D: Correct - - Stem conditions indicate that ALL S/Gs are faulted and EPP-16 EPP-1 6 will be used.
EPP-16 throttles flow to ALL S/Gs to 80 to 90 GPM. This ensures S/G internals are kept wet.
147 147
HLC-08 NRC HLC-08 NRC Written Written Exam Exam Exam Question Exam Question Number:
Number: 98 98
Reference:
EPP-16,
Reference:
EPP-16, Pages and 8; Pages 33 and EPP-16 SO, 8; EPP-16 BD, Page Page 18; 18; Foldout Foldout A, A, Pages Pages 3-8.
3-8.
KA Statement: Knowledge KA Knowledge of of EOP EOP mitigation mitigation strategies.
strategies.
History: New History: New - Written for HLC-08
- HLC-08 NRC NRC exam.
exam.
SRO - Detailed SRO - Detailed knowledge knowledge and and implementation implementation of of the the EOP EOP network network mitigation mitigation strategy strategy past past Immediate Actions.
the Immediate FINAL 148 148
HLC-08 HLC-08 NRC NRC Written Written Exam Exam
- 99. G2.4.8 OOllEMERO
- 99. 02.4.S 00 1/EMERG PROCIPLAN/3/3.S/4.S/SROIHIOH/43.S/NEW PROC/PLAN/3/3 .8/4.5/SRO/HIGHI43 .5/NEW - 200S/0MM-022-009
- 2008/OMM-022-009 Given the Given the following:
following:
The plant
- The
- plant was was operating operating at 100% RTP at 100% RTP
- AA major
- major rupture rupture occurs occurs inin the the CCW CCW Common Common Discharge Discharge Header.
The crew
- The
- crew has has implemented implemented AOP-014, AOP-014, COMPONENT COMPONENT COOLINGCOOLING WATERWATER SYSTEM SYSTEM MALFUNCTION.
MALFUNCTION.
The Reactor
- The
- Reactor Operator Operator reports reports that that CCW CCW Surge Surge Tank Tank Level Level is is 5%
5% and and lowering.
lowering.
Which ONE Which ONE (1)(1) of of the following describes, describes, in in order, order, the actions actions required required in in response response to this event?
event?
A. 1)1) Reactor is Verify the Reactor is tripped
- 2) Perform the Immediate Immediate Actions of PATH-1 PATH-i
- 3) Trip the the RCPs.
- 4) Lockout the CCW Pumps B
B~ 1) Verify the Reactor is tripped
- 2) Trip the RCPs
- 3) Perform the Immediate Actions of PATH-1 PATH-i
- 2) Verify the Reactor is tripped
- 3) Perform the Immediate Actions of PATH-1 PATH-i
- 2) Verify the Reactor is tripped
- 4) Perform the Immediate Actions of PATH-i PATH-1 149 149
HLC-08 NRC HLC-08 Written Exam NRC Written Exam The correct The correct answer answer isis B.
B.
From AOP-014:
From AOP-014: 2. 2. Check Check Reactor Reactor - CRITICAL
- CRITICAL (YES)
(YES)
- 3. Verify
- 3. Verify Reactor Reactor - TRIPPED
- TRIPPED
- 4. Stop
- 5. Go
- 5. Go To PATH-i While Continuing To PATH-1 Continuing With This This Procedure Procedure Incorrect - Actions are A: Incorrect - are all correct however, however, AOP-014 and and OMM-022 OMM-022 specifically address this case this that the case that the RCPs RCPs will be be tripped tripped lAW lAW the the AOP AOP before before performing performing Immediate Actions of Immediate PATH-i.
of PATH-1.
B: Correct - - Order is correct lAWlAW AOP-014 and OMM-022.
Incorrect - Locking C: Incorrect - Locking out the CCWCOW pumps pumps would be required for these conditions, cond[tions, but but AOP-0i4 does NOT direct protecting the CCW AOP-014 COW pumps pumps until after the Reactor is tripped. OMM-022 states that other actions should NOT be performed until after Immediate Actions are complete.
D: Incorrect - Incorrect order of actions, but plausible if candidate believes protecting CCW COW pumps on lowering Surge Tank level is the priority and that Immediate Actions must be performed prior to tripping RCPs.ROPs.
Exam Question Number: 99
Reference:
OMM-022, Page 3S. 38.
KA Statement: Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
History: New - Wriffen
- Written for HLC-OS HLC-08 NRC exam.
SRO - Assessment of plant conditions and determination of procedural actions required for mitigating those events.
FINAL 150 150
HLC-08 NRC HLC-08 NRC Written Written Exam Exam 100. G2.4.18 100. G2.4. 1800 1/EMERG PROCIPLAN/3/3.3/4.0ISROILOW/43.1INEW OOllEMERG PROC/PLANI3I3.314 .0/SRO/L0W143. 1/NEW - 2008/FRP-H.I-003
- 2008/FRP-H. 1-003 Which ONE Which ONE (1) (1) of of the the following following isis the the strategy strategy andand basis basis for for Reactor Reactor Coolant Coolant Pump Pump (RCP)
(RCP) operation in operation in FRP-H.1, FRP-H.1, RESPONSE RESPONSE TO TO LOSS LOSS OF OF SECONDARY SECONDARY HEAT HEAT SINK?
SINK?
A. Verify ONLY A. Verify ONLY ONE ONE RCPRCP isis operating prior to operating prior to initiating initiating bleed bleed and and feed feed to to ensure ensure maximum maximum bleed flow through bleed through thethe PZR PZR PORVs.
B:I Stop ALL RCPs to eliminate the heat input B Stop input from the RCPsRCPs extending the time available to to restore feed flow restore flow before before bleed bleed and and feed feed criteria criteria isis met.
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 D. RCPs to establish Natural Natural Circulation cooling in preparation for bleed bleed and feed.
The correct answer is B.
A: Incorrect - Several FRPs do direct operation of only one pump and an RCP operating will increase bleed flow, but this procedure is for loss of S/G inventory and it is NOT desired during FRP-H.1.
B: Correct - - Elimination of the RCPs as a heat source extends the time available before bleed and feed criteria is met by as much as 9 minutes.
C: Incorrect - Elimination of ALL of the RCPs as a heat source extends the time available before bleed and feed criteria is met by as much as 9 minutes.
D: Incorrect - Stopping the RCPs eliminates the heat input to the RCS. Once bleed and feed 0: -
is established, sufficient SI flow will be provided through the core to meet the heat removal needs.
Exam Question Number: 100 100
Reference:
FRP-H.1 BD, Pages 15, 15, 16 16 and 48.
KA Statement: Knowledge of the specific bases for EOPs.
History: New New - Written for HLC-08 NRC exam.
SRO - Knowledge of strategy or action in
- in emergency procedures beyond beyond immediate immediate actions.
FINAL 151 151