ML20268A163
| ML20268A163 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 07/06/2020 |
| From: | Bryan Bergeon Entergy Nuclear Operations |
| To: | NRC/RGN-III/DRS/OLB |
| Bergeon B | |
| Shared Package | |
| ML19213A183 | List: |
| References | |
| Download: ML20268A163 (100) | |
Text
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 1 of 100 30 June 2020 1
ID: 852830 Points: 1.00 (Reference Provided)
After a trip from 100% power, EOP-1.0, Standard Post Trip Actions, is complete.
The crew has entered EOP-8.0, Loss of Offsite Power / Forced Circulation Recovery.
The Safety Function Status Checks (SFSCs) are being performed and the following are the current conditions:
NO PCPs are running PZR Level is 50% with Charging and Letdown in service PZR Pressure is 1620 psia ALL RVLMS lights are green AFW is maintaining BOTH S/Gs at 65% level Tcolds are 540°F Thots are 560°F Tave indicates 550°F Average of Qualified CETs (KCETA) is 584°F ASDVs are throttled and lowering PCS temperatures Given these conditions, complete the following statements:
The Safety Function Status Check for:
PCS Heat Removal ___(1)___ satisfied.
Core Heat Removal ___(2)___ satisfied.
(1)
(2)
A.
is is B.
is is NOT C.
is NOT is D.
is NOT is NOT
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 2 of 100 30 June 2020 2
ID: 847350 Points: 1.00 (Reference Provided)
PCS Heatup is in progress in accordance with SOP-1C, "Primary Coolant System - Heatup".
A bubble has been formed in the Pressurizer.
At time 1000:00, PCS is at 400°F Pressurizer Pressure is at 450 psia 3 PCPs are operating within the required parameters of the procedures The LTOP Switches are in 'ENABLE' BOTH PZR PORV Block valves are OPEN At time 1005:00, PT-0104B, Pressurizer Pressure input to LTOP Controller PY-0105B fails to 1500 psia Complete the following:
At 1005:00, the number of OPEN Pressurizer PORVs is ___(1)___.
At 1006:00, if TS-0115, PCS Temperature input to LTOP Controller PY-0105A fails to 450°F, then
___(2)___ PZR PORV can provide automatic programmed LTOP protection throughout the heatup.
(1)
(2)
A.
ONLY ONE ONLY ONE B.
ONLY ONE NEITHER C.
NONE NEITHER D.
NONE ONLY ONE
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 3 of 100 30 June 2020 3
ID: 847669 Points: 1.00 Given the following:
At time 1000:00 The Plant has been tripped from 100% power due to a small break LOCA 2400V Bus 1C is de-energized (faulted)
Levels in BOTH Steam Generators are 55% and lowering at 10% per minute At time 1004:00 Auxiliary Feedwater flow will ___(1)___ automatically initiated.
At time 1005:00 Highest S/G pressure is 900 psia The actions of EOP-1.0, Standard Post Trip Actions, have been completed The CRS has given the direction to commence a PCS cooldown and depressurization When AFW flow is established, AFW flow will be from ___(2)___.
(1)
(2)
A.
have P-8A B.
have P-8C C.
have NOT P-8A D.
have NOT P-8C
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 4 of 100 30 June 2020 4
ID: 848570 Points: 1.00 The Plant is at 100% power, with ALL systems normally aligned.
A seismic event occurs, and the operators note that PCS pressure rapidly lowers to containment pressure.
While performing EOP-1.0, Standard Post Trip Actions, The operators will stop ___(1)___ PCPs.
The reason for the above action is to ___(2)___.
(1)
(2)
A.
ONLY two provide protection against cavitation B.
ONLY two prevent unwanted additional loss of mass from PCS C.
ALL four provide protection against cavitation D.
ALL four prevent unwanted additional loss of mass from PCS
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 5 of 100 30 June 2020 5
ID: 847690 Points: 1.00 Note to Examinee: There is a color image provided as a handout for this question The plant is in MODE 3 at normal operating temperature and pressure PCS Flow on Panel C-12 is shown below:
Then, EK-0902, PRI COOLANT PUMP P-50B TRIP annunciates.
Given these conditions, complete the following statements:
PCS Flow indication on ___(1)___ Flow Indicator(s) lower(s).
The automatic start of a Lift Oil Pump is indicated by the illumination of a(n) ___(2)___ light on Panel C-02.
(1)
(2)
A.
ONLY one Amber B.
ONLY one Red C.
ALL four Amber D.
ALL four Red
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 6 of 100 30 June 2020 6
ID: 853530 Points: 1.00 The plant is at 100% power, with all systems in automatic control Single Charging is aligned in accordance with SOP-2A, Chemical and Volume Control System P-55A, Charging Pump, trips.
NO other charging pump starts.
All other equipment functions as designed.
Given these conditions and with NO operator action, complete the following statements:
Letdown isolates ___(1)___ EK-0763, Pressurizer Level CH A LO-LO, or EK-0764, Pressurizer Level CH B LO-LO annunciates.
In 15 minutes, Pressurizer Level ___(2)___.
(1)
(2)
A.
before B.
before C.
after D.
after stabilizes continues to lower stabilizes continues to lower
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 7 of 100 30 June 2020 7
ID: 853534 Points: 1.00 The plant has just been shutdown from a 100 day run at full power.
Component Cooling Water Temperature is 95°F E-60A, Shutdown Cooling (SDC) Heat Exchanger is unavailable Given these conditions, complete the following statements:
The SDC system ___(1)___ meet its design basis.
With SDC in service and a loss of air to CV-3212, CV-3213, CV-3223, and CV-3224, SDC HX Isolation valves occurs, PCS flow through the SDC HXs ___(2)___.
(1)
(2)
A.
can stops B.
can continues C.
can NOT stops D.
can NOT continues
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 8 of 100 30 June 2020 8
ID: 847954 Points: 1.00 The plant is in MODE 1, Component Cooling Water flow has degraded The following PCP Temperatures are ALL noted to be rising at a rate of 1°F per minute:
P-50A Upper Guide Bearing 170°F P-50B Upper Thrust Bearing 171°F P-50C Lower Seal 172°F P-50D Vapor Seal 173°F In accordance with AOP-29, PCP Abnormal Conditions, which PCP temperature will FIRST require an immediate reactor trip?
A.
Upper Guide Bearing B.
Upper Thrust Bearing C.
Lower Seal D.
Vapor Seal
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 9 of 100 30 June 2020 9
ID: 848571 Points: 1.00 The Plant is at 100% power.
Which of the following would cause the Primary Coolant System to get closer to saturated conditions?
A.
Steam Generator ADV inadvertently opens B.
Pressurizer Spray valve CV-1057 loses Instrument Air C.
In service Pressurizer Pressure Controller output fails low D.
In service Pressurizer Pressure Controller output fails high
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 10 of 100 30 June 2020 10 ID: 852014 Points: 1.00 The plant is at power, when a transient occurs causing PCS Pressure to reach 2385 psia.
Reactor Power has NOT changed For these conditions...
A.
NO Trip is required.
B.
ONLY RPS Trip circuits have failed.
C.
ONLY ATWS Trip circuits have failed.
D.
BOTH RPS and ATWS Trip circuits have failed.
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 11 of 100 30 June 2020 11 ID: 847990 Points: 1.00 A SGTR occurred while the plant was in MODE 1 EOP-5.0, Steam Generator Tube Rupture Recovery, is in progress.
Given these conditions, complete the following statements:
The requirement to maintain PCP NPSH for any running PCP ___(1)___ take precedence over the equalization of primary and secondary pressure.
The reason for lowering PCS pressure to the affected S/G pressure is to ___(2)___.
(1)
(2)
A.
does raise injection flow from the SIS pumps B.
does minimize the potential for overfilling the affected S/G C.
does NOT raise injection flow from the SIS pumps D.
does NOT minimize the potential for overfilling the affect S/G
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 12 of 100 30 June 2020 12 ID: 852250 Points: 1.00 (Reference Provided)
Given the following Plant conditions during an Excess Steam Demand Event (ESDE):
Containment temperature is 250°F
'B' steam generator pressure is 300 psia
'B' steam generator level indicated by LI-0752A is 67%
PCS Pressure is 900 psia Which of the following describes the actual level in 'B' steam generator?
A.
56%
B.
59%
C.
62%
D.
66%
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 13 of 100 30 June 2020 13 ID: 847995 Points: 1.00 A Station Blackout occurred 30 minutes ago.
The crew is evaluating indications to verify Natural Circulation is occurring:
Pressurizer Pressure is 1700 psia Average Qualified CETs is 548°F Pressurizer level is 36%
Auxiliary Feedwater is keeping each SG level at 40%
Given these conditions, complete the following statements:
If PCS temperatures are slowly lowering, then Natural Circulation is occurring if the PCS Loop Tcolds are between ___(1)___,
AND the PCS Loop Thots are between ___(2)___.
(1) Tcolds (2) Thots A.
485°F and 495°F 520°F and 530°F B.
485°F and 495°F 535°F and 545°F C.
500°F and 510°F 520°F and 530°F D.
500°F and 510°F 535°F and 545°F
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 14 of 100 30 June 2020 14 ID: 847996 Points: 1.00 (Reference Provided)
A Loss of Offsite Power has occurred.
EOP-8.0 Loss of Offsite Power/ Forced Circulation Recovery is in progress at step 13b, which states:
Corrected PZR level is greater than 20% (40% for degraded Containment) and controlled.
The following indications are noted:
Containment Ambient Temperature is 250°F Pressurizer Pressure is 1000 psia LIC-0101A and 0101B indicate 60% PZR Level Actual pressurizer level is closest to....
A.
37%
B.
46%
C.
51%
D.
59%
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 15 of 100 30 June 2020 15 ID: 847830 Points: 1.00 Given the following conditions with the plant at 65% power during Power Escalation:
Preferred AC Bus Y-20 de-energizes With NO operator action, then over the next 30 seconds the response of level in the Steam Generators is...
A.
A rises, and B lowers B.
B rises, and A lowers C.
BOTH rise D.
BOTH lower
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 16 of 100 30 June 2020 16 ID: 848010 Points: 1.00 The Plant was at 100% power with the following alignments:
ED-17, Station Battery Charger No 3, is in service supplying the No 1 DC Bus ED-18, Station Battery Charger No 4, is in service supplying the No 2 DC Bus FIVE minutes ago, the Plant experienced a Loss of Offsite Power ALL systems and equipment responded as designed EXCEPT:
2400V bus 1C faulted and remains de-energized AC Supply Breaker (52-285) for ED-17, Station Battery Charger No 3, tripped and can NOT be reclosed Given these conditions, complete the following statements:
Assuming NO operator actions, DC Bus No 1 is currently powered from ___(1)___.
DC Bus No 2 is currently powered from ___(2)___.
A.
(1) ONLY Station Battery No 1 (2) ONLY Station Battery No 2 B.
(1) ED-15, Station Battery Charger No 1, and Battery No 1 (2) ONLY Station Battery No 2 C.
(1) ONLY Station Battery No 1 (2) ED-18, Station Battery Charger No 4, and Station Battery No 2 D.
(1) ED-15, Station Battery Charger No 1, and Station Battery No 1 (2) ED-18, Station Battery Charger No 4, and Station Battery No 2
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 17 of 100 30 June 2020 17 ID: 848599 Points: 1.00 While at 100% power, entry conditions for AOP-35, Loss of Service Water, were met:
Service Water Header Pressure is 43 psig Below is an excerpt from AOP-35, Loss of Service Water, Section 5.0 IMMEDIATE ACTIONS:
© 1. VERIFY EK-1165, "NON CRITICAL SERV WATER LO PRESS" is clear.
1.1 IF any of the following annunciators are in alarm, THEN TRIP the Reactor, if reset. Refer to EOP-1.0, "Standard Post-Trip Actions."
EK-0259, "EXCITER COOLER HI TEMP" (50C)
PPC Urgent Alarm, "EXC Field Cold Air RTD-31" (48°C)
PPC Urgent Alarm, " EXC Diode Cold Air RTD-32" (48°C) 1.2. IF the following occur, THEN PERFORM, "Break Condenser Vacuum":
Non-Critical Service Water has been isolated or lost Exciter Cold Air Temperature is greater than 80C or rising as indicated on REC-C11A-01, Generator Temperature Recorder The reason for tripping the reactor per step 1.1 is because ___(1)___.
The reason for breaking condenser vacuum per step 1.2 is to ___(2)___.
A.
(1) exciter damage occurs within 10 seconds (2) protect the condenser from overpressure B.
(1) exciter damage occurs within 10 seconds (2) minimize the amount of time the exciter is subjected to overheating conditions C.
(1) the heat load in containment needs to be reduced to raise available cooling to other service water loads (2) minimize the amount of time the exciter is subjected to overheating conditions D.
(1) the heat load in containment needs to be reduced to raise available cooling to other service water loads (2) protect the condenser from overpressure
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 18 of 100 30 June 2020 18 ID: 848572 Points: 1.00 The Plant is at 825 MWe:
Generator Hydrogen pressure is 75 psig A grid disturbance occurred due to severe weather in the area resulting in:
Generator reactive load is 225 MVAR OUT The following annunciators are LIT o
EK-0303, VOLTAGE REGULATOR LIMITER OPERATION o
EK-0310, GENERATOR VOLTAGE REG TRIP Initial attempts to clear the alarms per the ARPs are unsuccessful.
Given these conditions, complete the following statements:
When using the DC Adjuster under these conditions:
the Automatic Regulator Limits ___(1)___ function.
390CS, Voltage Regulator Control Switch should be in the ___(2)___ position.
(1)
(2)
A.
will AUTO or ON B.
will OFF or TEST C.
will NOT AUTO or ON D.
will NOT OFF or TEST
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 19 of 100 30 June 2020 19 ID: 853531 Points: 1.00 The plant is at 70% power, with the controlling group of Regulating Rods at 120 inches withdrawn.
One of the rods in this controlling group drops to the bottom of the core.
The reactor remains critical.
Given these conditions, complete the following statements:
If NO operator action is taken, the average indicated Reactor Power (NI-5, 6, 7, 8) will stabilize at a level ___(1)___ the power level prior to the dropped rod.
In accordance with AOP-5, Control Rod Drop, the operators must ___(2)___ to maintain Tave-Tref mismatch within the prescribed band.
(1)
(2)
A.
equal to dilute the PCS B.
equal to lower turbine load C.
lower than lower turbine load D.
lower than dilute the PCS
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 20 of 100 30 June 2020 20 ID: 852018 Points: 1.00 A reactor start up is in progress.
Initial readings were taken at 1000:00 Then rods were withdrawn, and rod motion stopped At 1015:00, 1/M plot was performed The following Nuclear Instrument readings are obtained:
Nuclear Instrument Initial Reading 1/M Plot Reading NI-1A, Source Range 3.0 cps 290 cps NI-2A, Source Range 3.3 cps 360 cps NI-3A, Wide Range 1.2 x 10E-7% power 9.5 x 10E-5% power NI-4A, Wide Range 1.3 X 10E-7% power 9.5 x 10E-6% power The overlap response of the Nuclear Instrument that is outside of procedural requirements is:
A.
NI-1A, Source Range B.
NI-2A, Source Range C.
NI-3A, Wide Range D.
NI-4A, Wide Range
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 21 of 100 30 June 2020 21 ID: 848052 Points: 1.00 The Plant was at 100% power, AOP-6, Loss of Condenser Vacuum, has been entered, due to P-39A, Cooling Tower Pump trip
- , Cooling Tower Pump Trip actions, are in progress Given these conditions and in accordance with AOP-6, Attachment 1...
ENSURE ___(1)___ MV-AE111, 'A' Secondary Air Ejector Steam Supply ENSURE ___(2)___ MV-AE117, 'A' Secondary Air Ejector Suction (1)
(2)
A.
OPEN CLOSED B.
CLOSED OPEN C.
OPEN OPEN D.
CLOSED CLOSED
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 22 of 100 30 June 2020 22 ID: 848584 Points: 1.00 T-101A, Waste Gas Decay Tank, develops a leak on its manway.
The Radiation Monitor that will indicate this release FIRST is...
A.
RIA-1113, Waste Gas B.
RIA-2326, Stack Gas Effluent C.
RIA-1809, Radwaste Ventilation D.
RIA-1810, East Safeguards Equipment Room
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 23 of 100 30 June 2020 23 ID: 848600 Points: 1.00 The plant was just tripped from 100% power, Conditions in the Main Control Room degrade to the point where Evacuation is required.
After leaving the Main Control Room, Breaker 152-105, the normal feed breaker to Bus 1C trips on OVERCURRENT / LOCKOUT.
NO Emergency Diesel Generators automatically start due to UV relay failures.
Given these conditions, complete the following statements:
EDG 1-1 ___(1)___ be started from the local control panel in the Emergency Diesel Generator Room.
Starting EDG 1-1 ___(2)___ cause Breaker 152-107, EDG output breaker, to AUTOMATICALLY close.
(1)
(2)
A.
can will B.
can will NOT C.
can NOT will D.
can NOT will NOT
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 24 of 100 30 June 2020 24 ID: 848590 Points: 1.00 Conditions have arisen that may require entry and performance of AOP-32, Loss of Containment Integrity.
The following are excerpts from steps 3 and 8 of the procedure:
ACTIONS\\EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. DETERMINE AND PERFORM required procedure steps Inoperable containment isolation valve(s) in a path with two containment isolation valves (Steps 4 through 5)
- Inoperable containment isolation valve in a path with one containment isolation valve and a closed system (Step 6)
- Failed containment air lock (Steps 7 through 9)
An INOPERABLE Main Steam Isolation Valve (MSIV) ___(1)___ addressed by the actions of this procedure.
ACTIONS\\EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8.
VERIFY the interlock mechanism is OPERABLE in each Containment Air Lock.
8.1 ENSURE an OPERABLE door is closed on the affected air lock within...
8.2 CAUTION TAG the outer door handwheel of the affected air lock...
When the interlock mechanism of a Containment Air Lock is NOT OPERABLE, the reason for hanging a CAUTION Tag on the outer door handwheel of the affected air lock in Step 8.2 is to ensure ___(2)___.
A.
(1) is NOT (2) ONLY one door on the affected air lock is opened at a time B.
(1) is NOT (2) an OPERABLE door is verified locked closed C.
(1) is (2) ONLY one door on the affected air lock is opened at a time D.
(1) is (2) an OPERABLE door is verified locked closed
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 25 of 100 30 June 2020 25 ID: 848614 Points: 1.00 The plant has been tripped from 100% power due to a LOCA.
An Inadequate Core Cooling condition exists and the operators have implemented Once Through Cooling in accordance with EOP-9.0 Functional Recovery.
BOTH HPSI pumps (P-66A and P-66B) are available and operating ALL Charging Pumps (P-55A, P-55B, and P-55C) are operating ALL PCPs are stopped Given these conditions, complete the following statements:
The position of the PZR PORV BLOCK valves for these conditions is ___(1)___ OPEN.
If P-66B were to trip, the operator will ___(2)___.
(1)
(2)
A.
BOTH maintain any open PORV OPEN B.
BOTH CLOSE at least one PORV C.
ONLY ONE maintain any open PORV OPEN D.
ONLY ONE CLOSE at least one PORV
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 26 of 100 30 June 2020 26 ID: 848645 Points: 1.00 Given the following conditions:
The Plant is at 100% power Tave is stable at 560°F PCS pressure is stable at 2060 psia NO dilution or boration activities are in progress The following data has been collected:
Parameter 1000:00 1012:00 PZR Level 57.9%
58.5%
VCT Level 71.0%
68.5%
RIA-0631, Off Gas monitor 20 cpm 25 cpm RIA-0707, S/G BD monitor 360 cpm 350 cpm Containment Sump Level Stable Rising Given these conditions, complete the following statements:
The estimated PCS leak rate is ___(1)___ gpm.
The NCO-T should recommend entering ___(2)___.
(1)
(2)
A.
> 4 AOP-24, Steam Generator Tube Leak B.
> 4 AOP-23, Primary Coolant Leak C.
< 4 AOP-23, Primary Coolant Leak D.
< 4 AOP-24, Steam Generator Tube Leak
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 27 of 100 30 June 2020 27 ID: 851771 Points: 1.00 A transient has occurred resulting in the implementation of EOP-9.0, Functional Recovery Procedure.
The following procedure step is in progress:
Safety Function: Maintenance of Vital DC Power Success Path: Battery Chargers/Station Batteries Resource Tree: B
- 4. VERIFY the following on ED-10L/ED-10R DC Bus:
4.1 PUSH 72-01, Isolation Breaker To DC Battery NO. 1 ED-01 (Shunt Trip Breaker.)
LOCATION: ED-11A behind 1C Bus Any faults are isolated Voltage greater than 105 volts 4.2 REFER TO AOP-41, "Alternate Safe Shutdown Procedure."
If ED-10L/ED-10R DC Bus is 100 volts, complete the following statements:
After a local operator completes step 4.1 DG 1-1, Emergency Diesel Generator, ___(1)___ able to be manually started.
DG 1-1, ___(2)___ able to field flash.
(1)
(2)
A.
is is B.
is is NOT C.
is NOT is D.
is NOT is NOT
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 28 of 100 30 June 2020 28 ID: 848820 Points: 1.00 Control rod drop testing is being performed.
ZERO Power Mode Bypass is in operation 4 PCPs are operating Consider each of the following situations separately:
Situation 1:
P-50A, Loop 1A PCP trips. A reactor trip ___(1)___ occur.
Situation 2:
P-50A, Loop 1A PCP trips AND ONE of the Wide Range Nuclear Instruments drifts over ten minutes to an output of 0.01% power. The reactor ___(2)___ trip.
(1)
(2)
A.
does does B.
does does NOT C.
does NOT does D.
does NOT does NOT
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 29 of 100 30 June 2020 29 ID: 848710 Points: 1.00 The plant is at 100% power with normal single charging and letdown in service.
Consider each of the following situations independently.
Situation 1:
Opening MO-3064, HPSI Train 2 Loop Injection valve, results in TICA-0201, Regen Heat Exchanger Temperature Indicator ___(1)___.
Situation 2:
Opening CV-2117, PZR Aux Spray valve, results in ___(2)___ flow being returned to the PCS Cold leg.
(1)
(2)
A.
remaining stable less B.
remaining stable more C.
rising less D.
rising more
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 30 of 100 30 June 2020 30 ID: 848810 Points: 1.00 The plant is at 100% power with double charging aligned using P-55A, and P-55C Charging pumps.
CV-2003, Letdown Orifice Stop valve is OPEN with its handswitch in AUTO CV-2004, Letdown Orifice Stop valve is OPEN with its handswitch in OPEN PIC-0202, Intermediate Letdown Pressure Controller is failed 'AS IS' Which of the following operations will result in exceeding the maximum design letdown flow through the demineralizers as indicated on FIC-0202, Letdown Flow, while operating at 100% power?
A.
Opening CV-2005, Letdown Orifice Stop valve B.
Opening CV-2002, and CV-2202, Letdown Orifice Bypass valves C.
RV-2006, Letdown Relief valve fails open D.
RV-2013, Low Pressure Letdown line Safety Relief valve, fails open
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 31 of 100 30 June 2020 31 ID: 847827 Points: 1.00 The Plant is in a solid condition on Shutdown Cooling:
CV-3006, SDC HX Bypass Valve, is throttled as needed.
The air line to CV-3006 becomes damaged such that NO operating air is supplied.
Given these conditions, complete the following statements:
With NO operator action, CV-3006 ___(1)___.
ONE minute after the air line was damaged, PCS pressure has ___(2)___.
(1)
(2)
A.
OPENS risen B.
OPENS lowered C.
CLOSES risen D.
CLOSES lowered
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 32 of 100 30 June 2020 32 ID: 849650 Points: 1.00 The plant has been tripped from 100% power due to a LOCA.
EOP-4.0, LOCA, is in progress and the crew is trying to determine if SI Throttling Criteria are met.
The Pressurizer Level, S/G Heat Removal, and RVLMS requirements are ALL met.
They note the following:
TWO PCPs running Pressurizer Pressure 1200 psia Average Qualified CETs 539°F TI-0112HC, Loop 1 Th 536°F TI-0112HD, Loop 1 Th 535°F TI-0112CC, Loop 1 Tc 531°F TI-0112CD, Loop 1 Tc 531°F SMM-0114, Subcooled Margin Monitor is indicating the following margins:
20°F 242 psi Given these conditions, complete the following statements:
HPSI flow ___(1)___ be throttled.
The indication on SMM-0114 is ___(2)___.
(1)
(2)
A.
can accurate B.
can too low C.
can NOT too low D.
can NOT accurate
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 33 of 100 30 June 2020 33 ID: 847829 Points: 1.00 The plant was tripped from 100% power due to a LOCA.
The Safety Injection Tanks (SIT) are expected to start injecting at a PCS Pressure of ___(1)___
psia.
If while implementing EOP-4.0, Loss of Coolant Accident Recovery, Pressurizer Pressure is controlled and a controlled PCS cooldown is in progress, the SITs should be isolated or vented when PZR Pressure FIRST reaches ___(2)___ psia.
(1)
(2)
A.
320 250-200 B.
320 350-300 C.
250 250-200 D.
250 350-300
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 34 of 100 30 June 2020 34 ID: 846870 Points: 1.00 At time 1000:00, with the Plant operating at 100% power, LIA-0116, T-73 Quench Tank level is 72%
PIA-0116, T-73 Quench Tank Pressure is 3 psig and rising at 3 psi / minute SS-0116, Pressurizer Quench Tank PI Range Selector is in NARROW position Given these conditions complete the following statements:
At 1002:00, EK-0732, QUENCH TANK HI PRESS, ___(1)___ in alarm.
It will take ___(2)___ 25 minutes until the quench tank rupture disc blows.
(1)
(2)
A.
is less than B.
is NOT less than C.
is NOT more than D.
is more than
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 35 of 100 30 June 2020 35 ID: 846871 Points: 1.00 The plant is at 100% power Breaker 152-107, Diesel Generator (DG) 1-1 to Bus 1C is racked to disconnect for cleaning and repair At time 1000:00 A differential current actuation condition at the Safeguards Transformer causes breaker 152-401, Safeguards Transformer 1-1 Incoming Breaker, to open Breaker 152-202, Startup Transformer 1-2 to Bus 1D, fails to close Given these conditions, with NO other operator actions, which of the following, if any, is energizing P-52A, Component Cooling Pump?
A.
Diesel Generator 1-2 B.
Startup Transformer 1-2 C.
Station Power Transformer 1-2 D.
P-52A is de-energized
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 36 of 100 30 June 2020 36 ID: 846918 Points: 1.00 During a power escalation a transient occurs which causes Pressurizer pressure to change to 2075 psia.
If all equipment is functioning properly, the expected indications for the in service Pressurizer Pressure Controller are:
Process Indication is ___(1)___ Setpoint Indication Output Signal is ___(2)___ 66%
(1)
(2)
A.
less than less than B.
less than greater than C.
greater than less than D.
greater than greater than
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 37 of 100 30 June 2020 37 ID: 847153 Points: 1.00 The Plant is at 60% power, EY-10, Preferred AC Bus #1, develops a problem and de-energizes AOP-12, Loss of Preferred Bus EY-10, is entered Given these conditions, complete the following statements:
BEFORE any operator action, the MINIMUM number of additional RPS channels that must reach a trip setpoint on RPS to cause a Reactor Trip is ___(1)___.
AFTER the affected RPS Channel is addressed per the AOP, the MINIMUM number of RPS channels that must reach a RPS trip setpoint to cause a Reactor Trip is ___(2)___.
(1)
(2)
A.
one one B.
one two C.
two one D.
two two
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 38 of 100 30 June 2020 38 ID: 847154 Points: 1.00 (Reference provided)
The plant is at 30% power, The white high power rate pre-trip bistable unit light on the RPS panel for channel 'A' has illuminated.
Given these conditions complete the following statements:
A cause for the bistable trip unit light to illuminate at this power level is a(n) ___(1)___.
After the condition clears, the bistable light is reset by ___(2)___.
(1)
(2)
A.
Start-up rate = 1.5 DPM bypassing the channel with the keyswitch B.
Start-up rate = 1.5 DPM depressing the two lamp pushbutton C.
ASI = -0.56 depressing the two lamp pushbutton D.
ASI = -0.56 bypassing the channel with the keyswitch
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 39 of 100 30 June 2020 39 ID: 847828 Points: 1.00 While the plant was at 100% power, PT-0102A, Pressure Transmitter that provides input to RPS and ESF for Pressurizer Pressure Channel A failed.
RPS Channel 'A' has been bypassed Now, the Plant is being cooled down and depressurized in preparation for a refueling outage:
The Actuation Logic Channels for Safety Injection Signal (SIS) have been manually BLOCKED per GOP-9, MODE 3 > 525°F to MODE 4 or MODE 5 CHECKLIST.
A failure of the Pressurizer pressure controller causes PCS pressure to rise from 1550 psia to the following:
A Channel - Failed Low B Channel - 1685 psia C Channel - 1685 psia D Channel - 1700 psia Assuming NO accidents, as the PCS cool down and depressurization continues and pressure is intentionally lowered to 100 psia, Safety Injection...
A.
can NOT be actuated manually.
B.
will automatically actuate on BOTH trains.
C.
will automatically actuate on ONLY one train.
D.
will NOT automatically actuate on EITHER train.
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 40 of 100 30 June 2020 40 ID: 849651 Points: 1.00 Which of the following Engineered Safeguards Features (ESF) Instrument Channels has a built-in bypass capability that uses a key operated switch (similar to the RPS Trip Channel Bypasses)?
A.
Containment High Pressure (CHP)
B.
Containment High Radiation (CHR)
C.
Main Steam Isolation Signal (MSIS)
D.
Auxiliary Feedwater Actuation Signal (AFAS)
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 41 of 100 30 June 2020 41 ID: 847311 Points: 1.00 Plant is at 100% power in mid-summer.
Outside air temperature is 98°F Service Water Pumps P-7A and P-7B are in service Service Water Pump P-7C is in Standby EK-1132, SERVICE WATER PUMP P-7A BASKET STR HI dP, has annunciated B' Critical Service Water header pressure is 49 psig A Critical Service Water Header is 50 psig Containment Cooling system components are in normal operating alignment with ALL components OPERABLE and available What action(s) should be taken?
A.
Start the third Service Water Pump, P-7C B.
Close CAC VHX-4 outlet Bypass, CV-0843 C.
Open CAC VHX-4 outlet control valve, CV-0867 D.
Start Containment Cooling Fans V-4A and V-4B
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 42 of 100 30 June 2020 42 ID: 847174 Points: 1.00 The plant is at 100% power, when a transient occurred resulting in an SIAS and a Loss of Offsite Power.
At time 1000:00, ONLY the DBA Sequencer from the SIS RIGHT channel starts operating Containment Pressure is 10 psig With NO operator action, which Containment Spray (CS) Pump(s) is / are operating at 1006:00?
A.
CS pump P-54A ONLY B.
CS pumps P-54B and P-54C ONLY C.
CS pumps P-54A and P-54C ONLY D.
CS pumps P-54A, P-54B and P-54C
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 43 of 100 30 June 2020 43 ID: 847312 Points: 1.00 The Plant is at 100% power.
A failure of the input to PIC-0511, Turbine Bypass Valve controller, CV-0511, Turbine Bypass Valve (TBV), has occurred CV-0511 has been closed by placing PIC-0511 in MANUAL with a zero output signal HIC-0780A, Steam Dump controller is in AUTO The TBV is NOT isolated If a Reactor Trip were to occur now, the quick open feature would cause ___(1)___ to open.
A.
ONLY the TBV B.
ONLY the ADVs C.
BOTH the ADVs and the TBV D.
NEITHER the ADVs NOR the TBV
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 44 of 100 30 June 2020 44 ID: 847313 Points: 1.00 Given the following:
The Plant is at 100% power A steam line break occurs OUTSIDE the Containment Building UPSTREAM of CV-0510, 'A' S/G MSIV
'A' S/G Pressure indicates 475 psia
'B' S/G Pressure indicates 850 psia Which of the following describes the expected response of the MSIVs and Feed Regulating Valves (FRVs) to this event?
A.
BOTH 'A' and 'B' S/G MSIVs close.
BOTH 'A' and 'B' S/G FRVs close.
B.
BOTH 'A' and 'B' S/G MSIVs close.
ONLY 'A' S/G FRV closes.
C.
ONLY 'A' S/G MSIV closes.
BOTH 'A' and 'B' S/G FRVs close.
D.
ONLY 'A' S/G MSIV closes.
ONLY 'A' S/G FRV closes.
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 45 of 100 30 June 2020 45 ID: 847310 Points: 1.00 A plant power escalation is in progress, with the following alignments:
LIC-0701/LIC-0703, S/G Level Indicating Controllers are in AUTO BOTH MFW pumps are at 3900 RPM each HIC-0525, Feedwater Control Mode Selector, is in MANUAL HIC-0526/HIC-0529, MFW Pump Speed Controllers are in MANUAL (Controller Span 0-6000 RPM)
The red pointers and the blue pointers on the HIC-0526 and HIC-0529 are matched SG levels are stable at program value Feedwater pump discharge pressure is 160 psi greater than Steam Generator (S/G) pressure On an Individual Speed Controller, should the Programmed Function (PF) light be flashing? If NOT, what action is necessary to cause it to start flashing?
A.
YES; The PF light should be flashing.
B.
NO; LOWER Main Feed Pump Speed C.
NO; RAISE Main Feed Pump Speed D.
NO; RAISE FW/SG Delta Pressure
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 46 of 100 30 June 2020 46 ID: 847236 Points: 1.00 Given the following conditions:
EOP-7.0, 'Loss of All Feedwater', actions are in progress E-50A, 'A' S/G level is -130% and lowering at 2% / minute E-50B, 'B' S/G level is -78% and lowering at 2% / minute Feedwater flow has just become available, but due to valve control issues, is available ONLY at flow rates of 350 gpm or more.
Complete the following statements:
Feeding at flow rates of 350 gpm should be commenced to S/G ___(1)___.
The risk of feeding the OTHER S/G at 350 gpm is ___(2)___.
(1)
(2)
A.
A causing significant tube bundle damage B.
B causing significant tube bundle damage C.
A challenging the PCS cooldown limits D.
B challenging the PCS cooldown limits
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 47 of 100 30 June 2020 47 ID: 847257 Points: 1.00 The Plant is in MODE 1.
The Technical Specification volume requirement of LCO 3.7.6 Condensate Storage and Supply is met if there is a minimum of at least ___(1)___ gallons of useable volume in the designated tank(s).
A volume measured at 85% in EACH tank (T-2, CST and T-81, PMST) ___(2)___ meet the MINIMUM volume required by SHO-1.
(1)
(2)
A.
100,000 does B.
100,000 does NOT C.
250,000 does D.
250,000 does NOT
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 48 of 100 30 June 2020 48 ID: 848150 Points: 1.00 The plant is at 90% power.
Preferred AC Bus EY-30 is to be placed on the Bypass Regulator in accordance with SOP-30, Station Power.
For this evolution, complete the following statements:
In accordance with this procedure Emergency Diesel Generator ___(1)___is to be considered INOPERABLE.
Although NO power interruption to EY-30 is expected to occur, if EY-30 did momentarily lose power then RPS Breaker 42-2 ___(2)___ trip.
(1)
(2)
A.
1-1 would NOT B.
1-1 would C.
1-2 would NOT D.
1-2 would
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 49 of 100 30 June 2020 49 ID: 851907 Points: 1.00 The Plant has just been synchronized to the grid with power at 10% when the following occurs:
EK-0547, 125V DC Bus Ground annunciates The 250 amp fuses supplying ED-21-2, 125 VDC Distribution Panel, blow and de-energize ED-21-2.
Given these conditions, complete the following statements:
___(1)___ CLOSES.
The required action(s) is/are to ___(2)___.
A.
(1)
CV-1359, Non-critical Service Water Isolation (2)
Trip the Reactor B.
(1)
CV-1359, Non-critical Service Water Isolation (2)
Trip the Turbine ONLY C.
(1)
CV-2099, PCP Controlled Bleedoff Containment Isolation (2)
Trip the Reactor and all Primary Coolant Pumps D.
(1)
CV-2099, PCP Controlled Bleedoff Containment Isolation (2)
Verify Controlled Bleedoff pressure is < 140 psig
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 50 of 100 30 June 2020 50 ID: 848151 Points: 1.00 The Plant is at full power:
Fuel Oil Transfer Pump P-18B is tagged out for maintenance Due to Chemistry sampling, D/G 1-2 Fuel Oil Day Tank T-25B level has lowered Fuel Oil Transfer Pump P-18A has automatically started and is pumping fuel oil to T-25B While this fuel oil transfer is in progress the following occurs:
A Loss of All Offsite Power occurs D/G 1-1 FAILS to automatically start and will NOT start manually D/G 1-2 starts and loads per design Given these conditions, complete the following statement:
Fuel oil transfer to T-25B A.
occurs ONLY after manually re-energizing MCC-2.
B.
occurs ONLY after manually re-energizing MCC-8.
C.
automatically occurs as part of the D/G 1-2 loading sequence.
D.
is occurring by gravity feed from T-10A, Fuel Oil Storage Tank, ONLY.
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 51 of 100 30 June 2020 51 ID: 850890 Points: 1.00 Emergency Diesel Generator (EDG) 1-1, is operating in PARALLEL with its bus for the monthly surveillance.
ALL switches are appropriately aligned in accordance with the governing procedure(s) MO-7A-1, Emergency Diesel Generator 1-1.
One of the loads on the bus trips Given these conditions, complete the following statements:
Immediately after the load trips, the Speed of EDG 1-1 __(1)___.
the Voltage of EDG 1-1 ___(2)___.
(1) Speed (2) Voltage A.
rises rises B.
rises lowers C.
lowers rises D.
lowers lowers
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 52 of 100 30 June 2020 52 ID: 848152 Points: 1.00 Digital Rate meters in the Process Liquid Monitor and Gaseous Process Monitoring Systems ___(1)___
have a CHECK SOURCE Function.
When the HIGH Pushbutton on the operating Analog Linear Rate Meter, RIA-1809, Waste Gas Plenum Radiation Monitor, is illuminated it means ___(2)___.
(1)
(2)
A.
do depressing this button RESETS the High alarm B.
do NOT depressing this button RESETS the High Alarm C.
do the monitor reading is (or was) above the HIGH Setpoint D.
do NOT the monitor reading is (or was) above the HIGH Setpoint
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 53 of 100 30 June 2020 53 ID: 848153 Points: 1.00 The plant is at 100% power.
P-7A, Service Water System (SWS) pump trips on an overcurrent condition Given these conditions, complete the following statements:
The Service Water System Train associated with the Right Safeguards Electrical Distribution Train includes the SWS pump ___(1)___.
With P-7A tripped as described, entering LCO 3.7.8 Service Water System, ___(2)___ required.
(1)
(2)
A.
7C is B.
7B is C.
7C is NOT D.
7B is NOT
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 54 of 100 30 June 2020 54 ID: 848156 Points: 1.00 The plant is at 100% power A loss of instrument air has occurred, and the following annunciators are in alarm:
EK-1101, CONTAIMENT INSTR AIR LO PRESS EK-1102, INSTRUMENT AIR LO PRESS EK-1103, SERVICE AIR LO PRESS AOP-37, Loss of Instrument Air has been entered All Instrument Air Compressors are running, Air header pressure is 30 psig and lowering Given these conditions, Pressurizer Pressure will be maintained by __(1)___.
Pressurizer level will be maintained by intermittent automatic operation of ___(2)___.
(1)
(2)
A.
Manual control of heaters ONLY P-55A, Charging Pump B.
Manual control of heaters ONLY P-55B or P-55C, Charging Pump C.
Aux Spray and manual control of heaters P-55A, Charging Pump D.
Aux Spray and manual control of heaters P-55B or P-55C, Charging Pump
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 55 of 100 30 June 2020 55 ID: 848163 Points: 1.00 The plant was shutdown for refueling 10 days ago.
The plant is in MODE 6 CORE ALTERATIONS are in progress Irradiated Fuel is being moved in the Spent Fuel Pool Equipment Hatch is closed and held in place by four bolts ONLY ONE door of the personnel air lock is closed ALL other Containment Penetrations meet the requirements of LCO 3.9.3, Containment Penetrations The ONLY running Fuel Handling Area Fan has just tripped.
Given these conditions, complete the following statements:
Tech Spec LCO 3.9.3, Containment Penetrations ___(1)___ met.
Irradiated fuel movements in the Spent Fuel Pool ___(2)___.
(1)
(2)
A.
is can continue B.
is must be suspended C.
is NOT must be suspended D.
is NOT can continue
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 56 of 100 30 June 2020 56 ID: 851790 Points: 1.00 The plant is at 100% power.
The following alarm annunciates:
EK-0954, Rod Drive Seal Leak Off HI Temp The indication on TRA-150 for CRD-23 shows 201°F.
Given these conditions, complete the following statement:
When a CRDM has excessive leak off, ___(1)___ is leaking into the ___(2)___.
(1)
(2)
A.
CCW Quench Tank B.
PCS Quench Tank
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 57 of 100 30 June 2020 57 ID: 848171 Points: 1.00 The reactor has been tripped from 60% power.
A loss of Bus 1D occurs at the time of the trip During performance of EOP 1.0, Standard Post Trip Actions, the Reactor Operator notes the following:
At time 1000:00, PCS pressure is 1850 psia and is rising at 10 psia per minute.
Pressurizer Level is 30% and rising at 1% per minute Given these conditions, and assume NO manipulation of any PZR Controllers, complete the following statements:
At time 1003:00, There are ___(1)___ PZR Heater Groups ON / Energized.
At time 1015:00, There are a MAXIMUM of ___(2)___ PZR Heater Groups ON / Energized.
(1) 1003:00 (2) 1015:00 A.
NO 3
B.
NO 6
C.
SOME 3
D.
SOME 6
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 58 of 100 30 June 2020 58 ID: 852019 Points: 1.00 On ALL Power Range NIs (NI-5, 6, 7, and 8), Reactor power is STABLE at 6%.
The Main Turbine is TRIPPED WR NI-1/3 starts drifting high at 1% per minute from 6%
In 10 minutes, with NO operator action, the Loss of Load Reactor Trip ___(1)___ BYPASSED.
the Reactor ___(2)___ automatically TRIPPED.
(1)
(2)
A.
is has B.
is has NOT C.
is NOT has D.
is NOT has NOT
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 59 of 100 30 June 2020 59 ID: 848173 Points: 1.00 The plant is at 100% power:
ALL control switches for the CRHVAC system on panel C-11A are in the AUTO position with the exception of V-95, Air Handling Unit Fan, which is in the ON position Containment Pressure is 1.0 psig Containment Radiation level is 1 R/hr At time 1000:00, an event occurs inside containment Containment Pressure is rising at 0.15 psig per minute Containment Radiation is rising by 0.7 R/hr every minute Given these conditions, and assuming equipment operates as designed, complete the following statements:
At time 1015:00, Charcoal Filter Unit 26A ___(1)___ in service.
CRHVAC Compressor VC-11 ___(2)___ running.
(1)
(2)
A.
IS IS B.
IS IS NOT C.
IS NOT IS D.
IS NOT IS NOT
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 60 of 100 30 June 2020 60 ID: 851872 Points: 1.00 Given the following conditions:
A loss of coolant accident occurs inside containment EOP-4.0, "Loss of Coolant Accident Recovery" is being implemented ALL PCPs have been tripped CETs temperatures are 550°F and rising on TRI-0101A1, A2, and TRI-0101B1, B2 PCS Thots are 560°F PCS Tcolds are 518°F PCS Tave is 539°F PZR level is at 45% and rising PCS pressure is at 1100 psia and lowering BOTH channels of Reactor Vessel Level Monitoring System (RVLMS) have five red lights LIT These conditions indicate that the fluid in the vessel is...
A.
superheated.
B.
more than 1°F, but less than 10°F subcooled.
C.
more than 10°F, but less than 25°F subcooled.
D.
more than 25°F subcooled.
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 61 of 100 30 June 2020 61 ID: 848193 Points: 1.00 In accordance with SOP-27, Fuel Pool System:
When filling the Spent Fuel Pool from the SIRWT, the MAXIMUM level should be NO higher than
___(1)___ the Southeast Skimmer.
The reason the MAXIMUM level should NOT be exceeded is to ___(2)___.
A.
- 1) at the level of
- 2) prevent unwanted SFP liner leakage B.
- 1) 5 inches below
- 2) prevent unwanted SFP liner leakage C.
- 1) 5 inches below
- 2) allow fuel movement D.
- 1) at the level of
- 2) allow fuel movement
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 62 of 100 30 June 2020 62 ID: 848195 Points: 1.00 The plant was at 100% power, when a total loss of Instrument Air occurs The reactor was manually tripped 386AST, Turbine Trip Relay, does NOT actuate when the turbine trips Instrument Air header pressure to the ASDVs and TBV is near zero psig Tave is 542°F and STABLE HIC-0780A, Steam Dump Controller demand is Steady at 2-3%
ALL other equipment functions as designed Given these conditions, complete the following statements:
CV-0511, Turbine Bypass Valve, (TBV) ___(1)___ open and controlling Tave.
To bring Tave to the requirements of EOP-1.0, Standard Post Trip Actions, (525°F-540°F) the
___(2)___ must be opened in MANUAL.
(1)
(2)
A.
is TBV B.
is ASDVs C.
is NOT TBV D.
is NOT ASDVs
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 63 of 100 30 June 2020 63 ID: N/A Points: 0.00 Question 63 deleted from examination per revised answer key.
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 64 of 100 30 June 2020 64 ID: 851770 Points: 1.00 Note to examinee: There is a color image provided as a handout With the Plant at 100% power, the following alarm is received in the Control Room during a Waste Gas Decay Tank batch release:
EK-1364, GASEOUS WASTE MONITORING HI RADIATION The Control Room Operator checks RIA-1113, Waste Gas Discharge Monitor, and sees the following:
Based on the above indication or image provided, RIA-1113 indication is (1) and CV-1123, Waste Gas Decay Tank Discharge Valve, will (2).
A.
(1) high out of range (2) remain open B.
(1) high out of range (2) automatically close C.
(1) low out of range (2) remain open D.
(1) low out of range (2) automatically close
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 65 of 100 30 June 2020 65 ID: 848219 Points: 1.00 Placing the cutout switches for the RIA-2316 and RIA-2317, Fuel Handling Area Radiation Monitors, to the "IN" position will:
A.
Enable automatic closure of specific Containment Isolation valves.
B.
Trip the Fuel Handling Area Supply Fan, V-7, on one out of two logic.
C.
Enable automatic closure of Fuel Handling Area exhaust dampers.
D.
Trip the Penetration and Fan Room Fans, V-78 and V-79, on high radiation.
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 66 of 100 30 June 2020 66 ID: 847460 Points: 1.00 Admin Procedure 4.00, Conduct of Operations requires:
After completing a formal turnover of the 'At-The-Controls' responsibilities, the NCO ___(1)___
notify the Control Room Supervisor (CRS) when this transfer takes place.
The operator designated as the At-The-Controls Operator (ATC) needs to discuss a procedure step with the Control Room Supervisor (CRS). If this discussion takes place at the PPC on the CRS' island, a turnover of the ATC position ___(2)___ occur first.
(1)
(2)
A.
must must B.
must does NOT have to C.
do NOT have to must D.
do NOT have to does NOT have to
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 67 of 100 30 June 2020 67 ID: 847657 Points: 1.00 A work group who has been granted access to the surveillance area and the At-The-Controls (ATC) area needs to go behind the control room panels and then return to the surveillance area.
Upon return, the work group ___(1)___ required to ask permission to enter the surveillance area.
If the work group needs to enter the At-The-Controls (ATC) area, permission must be granted
___(2)___.
(1)
(2)
A.
is ONLY once B.
is each time of entry C.
is NOT ONLY once D.
is NOT each time of entry
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 68 of 100 30 June 2020 68 ID: 847462 Points: 1.00 EOP-1.0, Standard Post Trip Actions, is in progress.
E-50A, 'A' Steam Generator level is 6% and rising slowly E-50B, 'B' Steam Generator level is -5% and lowering slowly P-8A, 'A' AFW pump is providing 165 gpm to each Steam Generator During the Verbal Verifications, the CRS has asked:
Do we have at least one Steam Generator with level between 5 and 70% with feedwater available?
In accordance with the Operations Standards Clarifications, the MINIMUM acceptable response to this direction is...
A.
YES.
B.
YES, we have feedwater available at 165 gpm to each Steam Generator.
C.
YES, 'B' Steam Generator level is -5% and lowering slowly, being fed by P-8A Aux Feedwater Pump at 165 gpm to each Steam Generator.
D.
YES; 'A' Steam Generator level is 6% and rising slowly, 'B' Steam Generator is -5% and lowering slowly, being fed by P-8A Aux Feedwater Pump at 165 gpm to each Steam Generator.
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 69 of 100 30 June 2020 69 ID: 847501 Points: 1.00 What part of the procedure change process in Administrative Procedure 10.41, Site Procedure Processes, ensures the usability of the revised procedure by the least experienced qualified worker?
A.
Technical Review B.
Validation Review C.
Cross-Discipline Review D.
On-Site Safety Review Committee
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 70 of 100 30 June 2020 70 ID: 847470 Points: 1.00 The following is an excerpt from Admin Procedure 4.02, Control of Equipment', Attachment 4:
When performing this checklist for the component listed as MO-1043A Indication, you observe the indication as 'OPEN'.
Given these conditions, complete the following statements:
Without any further instruction, the 'INITIAL' block for MO-1043A Indication, should be ___(1)___.
This Checklist is to be completed ___(2)___.
(1)
(2)
A.
left blank at any time during each shift B.
left blank within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the beginning of shift C.
initialed with comments added within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the beginning of shift D.
initialed with comments added at any time during each shift
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 71 of 100 30 June 2020 71 ID: 850975 Points: 1.00 Note to examinee: RWP 2020-12345 is provided as a handout Complete the following statements based on the information provided in RWP No. 2020-12345.
You are the operator tasked with performing the manipulations of Valves 'A' and 'B'.
You are signed onto RWP No. 2020-12345 and are now at the location of the valves.
After unlocking and closing valve 'A', some liquid is observed to be dripping from the stem of valve 'A',
which is absorbed by the absorbent material in the bag.
After this manipulation, you notice a tear in the outer glove of your right hand.
You reopen and backseat valve 'A' and the liquid flow stops.
You unlock and close valve 'B'.
The manipulations you performed ___(1)___ covered by this RWP.
A re-survey of the valve ___(2)___ required.
(1)
(2)
A.
ARE IS B.
ARE NOT IS C.
ARE IS NOT D.
ARE NOT IS NOT
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 72 of 100 30 June 2020 72 ID: 850972 Points: 1.00 The Plant is at 50% power.
A Containment Entry needs to be made.
Placing one additional Letdown orifice on line, raises power by 9 MWth.
The limit on the change in Heat Balance Power during a Containment Entry is ___(1)___%
power.
Raising letdown flow by placing an additional letdown orifice in service ___(2)___ violate the constant power requirements of the Containment Entry procedure.
(1)
(2)
A.
0.5 does B.
2.0 does C.
0.5 does NOT D.
2.0 does NOT
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 73 of 100 30 June 2020 73 ID: 847851 Points: 1.00 EOP-1.0, Standard Post Trip Actions, are in progress due to a LOCA Immediate Actions are complete During the performance of the first Operator Action, the NCO-R recognizes the need to trip all Primary Coolant Pumps (PCPs)
To meet the EOP Performance Standards in Attachment 15 of Admin Procedure 4.06, Emergency Operating Procedure Development and Implementation, the NCO-R will...
A.
immediately trip all four PCPs, and then report the action taken.
B.
announce Pressurizer pressure value, then wait for CRS to direct the action.
C.
announce the action to be taken, provide opportunity for intervention from the crew, and then trip all four PCPs.
D.
advocate the need to trip all four PCPs, obtain permission from the CRS, and then perform the action once permission is given.
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 74 of 100 30 June 2020 74 ID: 852017 Points: 1.00 Question 74 withheld from public disclosure due to security-related content.
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 75 of 100 30 June 2020 75 ID: 850991 Points: 1.00 At time 1000:00, An event has occurred while you are assigned to the Main Control Room.
At time 1005:00 The event has been initially classified as an Unusual Event, with no release in progress and you are to perform the duties of the communicator for the initial notifications of the Offsite Response Organizations (OROs).
If ALL the InForm machines are NOT in service, the FIRST Agency to contact is...
A.
Allegan County B.
Berrien County C.
Van Buren County D.
State of Michigan
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 76 of 100 30 June 2020 76 ID: 848220 Points: 1.00 SRO ONLY With the Plant at full power, a reactor trip occurs due to a loss of off-site power.
During the actions of EOP-1.0, "Standard Post Trip Actions," a fire develops in the cable spreading room causing ALL Preferred AC Buses to DEENERGIZE.
Given these conditions, complete the following statements:
The location for controlling the plant is at ___(1)___.
The appropriate procedure to mitigate this event is ___(2)___.
(1)
(2)
A.
Panel C-150/C-150A EOP-3.0, "Station Blackout Recovery" B.
Panel C-33 EOP-3.0, "Station Blackout Recovery" C.
Panel C-33 EOP-9.0, "Functional Recovery Procedure" D.
Panel C-150/C-150A EOP-9.0, "Functional Recovery Procedure"
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 77 of 100 30 June 2020 77 ID: 848251 Points: 1.00 SRO ONLY The plant is at 100% power.
At time 1000:00, Component Cooling Water (CCW) Surge tank level starts lowering CCW discharge pressure starts lowering AOP-36, Loss of Component Cooling Water is entered At time 1005:00 AOP-29, Primary Coolant Pump (PCP) Abnormal Conditions is entered due to low CCW flow and rising PCP temperatures causing alarms on P-50A, PCP At time 1010:00, CCW to P-50A seal cooling has degraded to the point where imminent PCP Failure indications are present for P-50A P-50A Lower Guide bearing temperature is 184°F and rising P-50A vibrations are 35 mils and oscillating Given these conditions, complete the following statements:
P-50A should be manually tripped ONLY after the reactor has been tripped and the ___(1)___
Safety Function is satisfied.
After tripping ONLY P-50A, CV-2083, CV-2099, and CV-2191, Controlled Bleedoff valves should be ___(2)___.
(1)
(2)
A.
Reactivity CLOSED B.
Reactivity left OPEN C.
Core Heat Removal CLOSED D.
Core Heat Removal left OPEN
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 78 of 100 30 June 2020 78 ID: 848270 Points: 1.00 SRO ONLY The plant has just established Shutdown Cooling (SDC) when the LPSI pumps were found to be steam bound.
AOP-30, Loss of Shutdown Cooling, has been entered Highest PCS temperature has risen to 315°F BOTH Containment Spray (CS) pumps are available SIRWT is at 80%
Containment is accessible Given these conditions, complete the following statements:
When performing the step to ENSURE PCS Level is restored as high as possible, it ___(1)___
permissible to exceed Technical Specification Cooldown Limits.
Using a Containment Spray (CS) pump to remove steam from a steam bound LPSI pump
___(2)___ make the CS pump inoperable.
(1)
(2)
A.
is NOT would B.
is NOT would NOT C.
is would D.
is would NOT
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 79 of 100 30 June 2020 79 ID: 848285 Points: 1.00 SRO ONLY:
A Steam Generator Tube Rupture has occurred on the 'A' Steam Generator. The appropriate EOP(s) are being performed:
A S/G has been isolated A S/G pressure is 840 psia B S/G pressure is 560 psia Pressurizer pressure is 960 psia Pressurizer level is 42%
PCS temperature is 508°F
'A' S/G Level is 80% and rising For these conditions, which of the following actions, regarding Pressurizer pressure, will the CRS direct?
A.
Raise Pressurizer pressure to 980 psia to re-establish adequate subcooling margin B.
Raise Pressurizer pressure to 970 psia to prevent backflow dilution of the PCS C.
Lower Pressurizer pressure to 755 psia to initiate backflow into the PCS D.
Lower Pressurizer pressure to 935 psia to ensure Main Steam Safety Valves remain closed
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 80 of 100 30 June 2020 80 ID: 848302 Points: 1.00 (Reference Provided)
SRO ONLY The plant is addressing a Loss Of All Feedwater per EOP-7.0.
At time 1000:00, ALL PCPs have been stopped
'A' S/G level is -75% and lowering at 5% per minute
'B' S/G level is -80% and lowering at 5% per minute BOTH S/G pressures are 300 psia and stable At time 1002:00, discharge pressure of the in service condensate pump is 550 psia.
Given these conditions, which Feedwater Regulating Valve Bypass Valve position will be selected for use?
A.
10%
B.
20%
C.
30%
D.
40%
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 81 of 100 30 June 2020 81 ID: 848311 Points: 1.00 SRO ONLY:
The plant was at 100% power, when Instrument Air (IA) Header Pressure began to lower At time 1000:00, Instrument Air (IA) header pressure was 79 psig The plant was tripped due to erratic response of equipment required for safe operations from lowering IA pressure Troubleshooting and repairs have begun At time 1030:00, A high energy line break inside containment causes containment pressure to reach 4.2 psig At time 1300:00, IA header pressure is 50 psig and still lowering Given these conditions, complete the following statements:
Closing manual valves MV-CC712, CCW Supply to Containment and MV-CC713, CCW Return from Containment by ___(1)___ at the LATEST, is required by Technical Specifications.
The closure of these manual valves is directed in ___(2)___.
(1)
(2)
A.
1400:00 AOP-37, Loss of Instrument Air B.
1400:00 AOP-36, Loss of Component Cooling Water C.
1700:00 AOP-37, Loss of Instrument Air D.
1700:00 AOP-36, Loss of Component Cooling Water
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 82 of 100 30 June 2020 82 ID: 851536 Points: 1.00 SRO ONLY:
The plant is holding at 24% power during a power escalation after a brief shutdown for maintenance.
Rods are being balanced The following two alarms come in simultaneously:
EK-0905, Shutdown Rod Position Abnormal EK-0906, Incore Alarm Given these conditions, complete the following statement.
Annunciator ___(1)___ requires the EARLIEST action to ___(2)___.
(1)
(2)
A.
EK-0905 withdraw the rod to above 124 inches B.
EK-0905 determine the LHR is within the COLR limits C.
EK-0906 withdraw the rod to above 124 inches D.
EK-0906 determine the LHR is within the COLR limits
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 83 of 100 30 June 2020 83 ID: 847672 Points: 1.00 SRO ONLY The Plant is at 50% power with the following conditions:
LIC-0101B, B Channel PZR Level Controller, is in service in CASCADE P-55A, Charging Pump, is operating with P-55B and P-55C secured in Automatic CV-2003, Letdown Orifice Stop Valve, is in Automatic and open CV-2004 and CV-2005, Letdown Orifice Stop Valves, are in AUTO and closed SS-TAVE, Avg Temp Display Select Switch, on Panel C-02 is in the LOOP 2 position Then, the following occurs:
EK-0761, PRESSURIZER LEVEL HI-LO, annunciates EK-0967, LOOP 1/LOOP 2 TAVE DEVIATION, annunciates EK-0969, LOOP 2 TAVE / TREF GROSS DEVIATION, annunciates The setpoint meter (blue pointer) on LIC-0101B indicates 42%
The process meter (red pointer) on LIC-0101B indicates 49%
TI-0110, TAVE Digital Temperature Indicator, on Panel C-02 indicates 515°F A valid POWER_PIP_DELTA_T reading on the PPC is 45%
Given these conditions, complete the following statements:
For PDIL monitoring, the POWER_PIP_DELTA_T is ___(1)___.
The procedure and action(s) to address these conditions are ___(2)___.
A.
(1) OPERABLE (2) alternate PZR Level Controller to LIC-0101A per AOP-22, Pressurizer Level Control Malfunctions B.
(1) OPERABLE (2) select valid Tave channel with SS-Tave Selector Switch per AOP-27, Tave/Tref Controller Failure C.
(1) INOPERABLE (2) alternate PZR Level Controller to LIC-0101A per AOP-22, Pressurizer Level Control Malfunctions D.
(1) INOPERABLE (2) select valid Tave channel with SS-Tave Selector Switch per AOP-27, Tave/Tref Controller Failure
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 84 of 100 30 June 2020 84 ID: 851530 Points: 1.00 SRO ONLY:
The Plant is in Mode 5 for a maintenance outage.
An UNPLANNED ENTRY into a Higher Risk Plant Operating States (HRPOS) is required.
Given these conditions, complete the following statements:
Any Hot Work in progress ___(1)___.
LCO 3.0.9, which addresses situations where required barriers are unable to perform their related support functions and provides instructions and conditions for meeting the supported system LCOs ___(2)___ applicable to Fire Barriers.
(1)
(2)
A.
must be stopped is B.
must be stopped is NOT C.
can continue is D.
can continue is NOT
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 85 of 100 30 June 2020 85 ID: 850970 Points: 1.00 SRO ONLY An event has occurred requiring a plant trip from 100% power Conditions are such that EOP-9.0, Functional Recovery Procedure, has been entered ALL PCPS are OFF Corrected PZR Level is 10%
MSIVs are closed E-50A, 'A' S/G is completely depressurized ALL feedwater to 'A' S/G has been stopped Following the current check of Safety Functions 15 minutes ago, it has been determined that the PCS cooldown rate has been exceeded, and the PCS is over subcooled.
PZR Pressure is 1800 psia PCS Temperature is 400°F What actions will the Control Room Supervisor direct the operators to perform to restore PCS to within the limits?
A.
Operate PZR PORVs to reduce PCS Pressure, and stop PCS cooldown for at least 45 minutes B.
Operate PZR PORVs to reduce PCS Pressure, and continue PCS cooldown at less than 100°F per hour C.
Control Charging and Letdown to reduce PCS Pressure, and stop PCS cooldown for at least 45 minutes D.
Control Charging and Letdown to reduce PCS Pressure, and continue cooldown at less than 100°F per hour
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 86 of 100 30 June 2020 86 ID: 851561 Points: 1.00 SRO ONLY:
The plant is at 100% power with P-52C, Component Cooling Pump, in service.
At time 1000:00, the following annunciator alarms:
EK-1167, Component Clg Pumps P-52A, P-52B, P-52C Trip Operators immediately determine P-52C tripped At 1001:00 P-52A auto-started At time 1005:00, the following annunciator alarms:
EK-1172, Component Clg Surge Tank T-3 Hi-Lo Level At time 1008:00 The CCW Surge Tank level issue results in isolating the CCW side of E-54B, CCW Heat Exchanger.
Given these conditions, complete the following statements:
Just prior to 1001:00, there ___(1)___ 2 trains of CCW OPERABLE.
Isolating the CCW side of E-54B, CCW Heat Exchanger, ___(2)___ directed by AOP-36, Loss of Component Cooling.
(1)
(2)
A.
are is B.
are is NOT C.
are NOT is D.
are NOT is NOT
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 87 of 100 30 June 2020 87 ID: 851111 Points: 1.00 SRO ONLY:
The plant is in MODE 3 after a trip from 100% power.
The PCS is at normal operating temperature and pressure.
2400 Volt AC Bus 1D develops a fault and is de-energized Given these conditions, complete the following statements:
LCO 3.6.6, Containment Cooling Systems ACTION C for Less than 100% of the required post accident Containment Cooling Capability ___(1)___ required to be entered.
The required support function of Containment Spray for the HPSI pumps ___(2)___ met.
(1)
(2)
A.
is NOT is NOT B.
is NOT is C.
is is NOT D.
is is
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 88 of 100 30 June 2020 88 ID: 850971 Points: 1.00 SRO ONLY:
A LOCA has occurred that has resulted in the actuation of the Containment Spray System.
The appropriate EOPs are being performed.
Given these conditions complete the following statements:
If the pH of the containment sump was NOT buffered by Sodium Tetraborate then the radiological contribution of iodine to a containment atmosphere leak will be ___(1)___.
If the SIRWT reaches 2% with an Active SIAS, and the CV-3030 and CV-3029, Containment Sump Isolation Valves fail to auto actuate, the procedure that addresses this alignment is EOP Supplement ___(2)___.
(1)
(2)
A.
higher 42, Pre and Post RAS Actions B.
higher 5, Checklist for Safeguards Equipment Following SIAS C.
unaffected 42, Pre and Post RAS Alignment D.
unaffected 5, Checklist for Safeguards Equipment Following SIAS
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 89 of 100 30 June 2020 89 ID: 851480 Points: 1.00 SRO ONLY:
The plant is in MODE 1, with the instrumentation issues listed below:
Instrument Issue LI-0702, 'A' SG Narrow Range Level failed low LI-0757B, 'A' SG Wide Range Level failed high FI-0727A Aux Feedwater Flow to 'B' SG failed high LI-0752D, 'B' SG Safety Channel failed low Given these conditions:
The number of INOPERABLE Post Accident Monitoring (PAM) Instrument(s) is ___(1)___.
A.
one B.
two C.
three D.
four
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 90 of 100 30 June 2020 90 ID: 851810 Points: 1.00 SRO ONLY:
The plant is in MODE 3 after a trip from 100% power.
The PCS is at normal operating temperature and pressure.
2400 Volt AC Bus 1C develops a fault and is de-energized EK-0532, Bus 1C or 1D Overcurrent Lockout, is in alarm Critical Service Water Header Pressure lowers to 42 psig Given these conditions complete the following statements:
The Tech Spec ACTION for the Condition where Less than 100% of the required post accident SWS Cooling Capability ___(1)___ required to be entered.
Emergency Diesel Generator (DG) 1-1 should be ___(2)___.
(1)
(2)
A.
is tripped B.
is left running C.
is NOT tripped D.
is NOT left running
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 91 of 100 30 June 2020 91 ID: 851072 Points: 1.00 (Reference Provided)
SRO ONLY:
The plant is at 98% power, and GOP-5, Power Escalation is in progress Control Rods are fully withdrawn EK-0917, Rod Withdrawal Prohibit, annunciates There are NO Variable High Power Pre Trips active Investigation reveals a failure in the Rod Control System (DW10-K22, Rod Withdrawal Block Relay failed)
The Rod Mode Select Switch is placed in 'EM OFF' Repairs are estimated to be completed in 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> Given these conditions complete the following statements:
The LCO to enter for this is ___(1)___.
If the repairs are completed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from now, the General Operating Procedure (GOP) in progress is ___(2)____.
A.
(1) LCO 3.1.1, Shutdown Margin (2) GOP-5 Power Escalation B.
(1) LCO 3.1.1, Shutdown Margin (2) GOP-8 Power Reduction to Mode 2 or Mode 3 > 525°F C.
(1) LCO 3.1.4, Control Rod Alignment (2) GOP-5 Power Escalation D.
(1) LCO 3.1.4, Control Rod Alignment (2) GOP-8 Power Reduction to Mode 2 or Mode 3 > 525°F
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 92 of 100 30 June 2020 92 ID: 851070 Points: 1.00 SRO ONLY:
Irradiated Sources are being transferred in accordance with SOP-28, Fuel Handling System.
After lowering the source lifting tool directly over the source to be removed, as the SRO you will direct ___(1)___ SFP Overhead Crane prior to closing the jaws of the lifting tool.
The reason for this action is to prevent ___(2)___.
A.
(1) de-energizing (2) re-opening of the source lifting tool jaws B.
(1) energizing (2) unintended lifting of neutron sources C.
(1) energizing (2) re-opening of the source lifting tool jaws D.
(1) de-energizing (2) unintended lifting of neutron sources
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 93 of 100 30 June 2020 93 ID: 851052 Points: 1.00 SRO ONLY:
At time 1000:00, With the plant at 100% power, it is noted that LCO 3.7.6, Condensate Storage and Supply, is NOT met because of volume.
Below is an excerpt from the ACTIONS portion of this Technical Specification:
Given these conditions, complete the following statements:
The LATEST the OPERABILITY of the backup water supplies must be verified is ___(1)___;
For subsequent performances of the Operability Verification of Backup Water Supplies, a 25%
time extension ___(2)___ allowed.
(1)
(2)
A.
1400 is NOT B.
1400 is C.
1500 is NOT D.
1500 is
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 94 of 100 30 June 2020 94 ID: 847872 Points: 1.00 (Reference Provided)
SRO ONLY The MAXIMUM allowable Linear Heat Rate (LHR) at the top of the peak powered fuel rod is ______
kW/ft.
A.
6.11 B.
9.16 C.
14.21 D.
15.28
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 95 of 100 30 June 2020 95 ID: 847882 Points: 1.00 SRO ONLY It is day 15 of a refueling outage CORE ALTERATIONS are about to begin Equipment Hatch is open The Fuel Handling Ventilation system is aligned as follows:
V-7, Fuel Handling Area Supply Fan is OFF V-8A, Fuel Handling Exhaust Fan is ON V-8B, Fuel Handling Exhaust Fan is ON V-69, Fuel Handling Area Supply Fan is OFF V-70A, Fuel Handling Area Exhaust Fan is OFF V-70B, Fuel Handling Area Exhaust Fan is ON In order to meet Technical Specification requirements before CORE ALTERATIONS can begin,
___(1)___ fans have to be started or stopped.
The basis for the required fan alignment is to ___(2)___.
(1)
(2)
A.
2 allow Fuel Handling Building atmosphere flow to bypass the HEPA filter B.
2 ensure all fuel handling areas exhaust to the HEPA filter C.
3 ensure all fuel handling areas exhaust to the HEPA filter D.
3 allow Fuel Handling Building atmosphere flow to bypass the HEPA filter
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 96 of 100 30 June 2020 96 ID: 847891 Points: 1.00 SRO ONLY The Plant is in MODE 3 The PCS Safety Limit has been violated PCS Pressure peaked at 3000 psia The ACTIONS for this Safety Limit violation...
A.
require a MODE reduction to MODE 4 in order to perform the necessary engineering evaluation of PCS Integrity.
B.
require a MODE reduction to MODE 6, and when the first Reactor Vessel head bolt is less than fully tensioned, this safety limit no longer applies.
C.
do NOT require a MODE reduction because the PCS was hydro tested to 125% of design pressure (3125 psia) and that pressure was NOT reached.
D.
do NOT require a MODE reduction because reducing MODES would add further thermal gradient stress due to the cooldown to the existing pressure stress.
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 97 of 100 30 June 2020 97 ID: 847926 Points: 1.00 SRO ONLY For 100% power conditions, which of the following conditions affecting the ability to makeup to the Primary Coolant System requires notification to the Nuclear Regulatory Commission?
A.
P-67A, LPSI pump, is INOPERABLE and will be restored in 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />.
B.
P-55B, Charging Pump, is INOPERABLE and will be restored in 4 days.
C.
T-82A, Safety Injection Tank, pressure is 180 psig and lowering. It will be restored to normal in 4 days.
D.
P-56A, Boric Acid Pump, spuriously started and was manually stopped. Repairs will require 68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br />.
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 98 of 100 30 June 2020 98 ID: 851010 Points: 1.00 SRO ONLY A waste gas release is being planned for Waste Gas Decay Tanks, T-101A, T-101B and T-68C.
Samples have been completed and analyzed per CH 6.22, Sampling Waste Gas Decay Tank, and CH 6.23, Evaluation and Release of Waste Gas Decay Tank."
There are NO Operational or Maintenance needs driving the release of any Waste Gas Decay Tank The following information is contained on the batch release forms for T-101A, T-101B and T-68C:
T-101A T-101B T-68C Isolation date 52 days ago 50 days ago 18 days ago Isolation pressure 90 psig 91 psig 93 psig Current pressure 93 psig 97 psig 95 psig Which tank(s), if any, should be approved for release?
A.
ONLY T-101A B.
ONLY T-68C C.
ONLY T-101A and T-101B D.
T-101A, T-101B, and T-68C
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 99 of 100 30 June 2020 99 ID: 850994 Points: 1.00 SRO ONLY:
The plant is tripped, after an accident in which the General Emergency Thresholds are exceeded.
A General Emergency has just been declared.
The State Emergency Operations Center is NOT yet activated.
The INITIAL Protective Action Recommendation (PAR) to be made to the State and Local authorities must be approved by the ___(1)___, and personally communicated to Van Buren county by ___(2)___.
(1)
(2)
A.
Shift Manager the Shift Manager B.
Shift Manager a qualified ENS Communicator C.
Operations Manager the Shift Manager D.
Operations Manager a qualified ENS Communicator
EXAMINATION LOI-20 NRC Licensing Exam PLP - 2018 NRC EXAM Page: 100 of 100 30 June 2020 100 ID: 850993 Points: 1.00 (Reference Provided)
SRO ONLY The Plant was operating at full power when an event occurs.
The Shift Manager determines that the Primary Coolant System barrier is lost and the Containment barrier is potentially lost.
Which of the following describes the Emergency Classification that would apply for these conditions?
A.
Unusual Event B.
Alert C.
Site Area Emergency D.
General Emergency