ML063240233
| ML063240233 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 10/10/2006 |
| From: | Exelon Generation Co |
| To: | Todd Fish Operations Branch I |
| Sykes, Marvin D. | |
| References | |
| Download: ML063240233 (200) | |
Text
Limerick Generating Station ILT05-I NRC Initial Licensinq Examination
- 1. WHICH ONE of the following describes the reason for a reactor scram that occurs as a result of a Main Turbine trip?
A. Limits positive reactivity due to a reduced void concentration when turbine stop valves close.
B. Minimizes level transient that occurs when feed pumps swap to high pressure steam.
C. Limits positive reactivity due to increased feedwater su b-cooling when extraction steam is lost.
D. Minimizes level transient that occurs when voids collapse due to turbine control valves closing.
Page 2 of 200
Limerick Generatinq Station lLTO5-1 NRC Initial Licensinq Examination Time Allowance (minutes) 2 I
Answer Kev PRA RO SRO 1 OCFR55.41 1 OCFR55.43 Y
(b) (5)
N/A Choice c Correct:
Low Incorrect 2.5 Incorrect 295005 AK3.01 t------
Incorrect Importance: RO / SRO 3.8 I 3.8 A
B C
D Basis or Justification Void concentration will rapidly decrease on closing of the turbine steam admission valves resulting in a large positive reactivity addition.
While the reactor feed pumps do swap from cross-around (LP) steam to main steam (HP) and this does contribute to the post-scram level transient that will occur, it is not part of the basis for the scram.
While this will occur, the Reactor power rise will be slight and gradual. This is not the reason for the Scram.
While this level transient will occur, it is not part of the basis for the scram I
Psychometrics Source:
Reference(sk Learning 0 bjective:
Knowledge/Ability WA Source Documentation New Exam Item Modified Bank Item ILT Exam Bank Previous NRC Exam 0
Other Exam Bank LGS UFSAR, Chapter 15.2, LGS Tech Specs, LSSS LLOTI 575.03 (Description of K&A, from catalog)
Knowledge of the reasons for the following responses as they apply to MAIN TURBINE GENERATOR TRIP:
Reactor scram Required Materials:
Notes and Comments:
Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-I NRC Initial Licensinq Examination
- 2.
Unit 2 plant conditions are as follows:
0 Reactor power is 100%
0 Plant Monitoring System (PMS) is inoperable Five minutes later control rod 30-31 inadvertently scrams.
WHICH ONE of the following can be used to confirm that control rod 30-31 is fully inserted?
A. XX (two Xs) on the Four Rod Display.
B. Green IN light is lit on the Full Core Display.
C. - -I (two dashed lines) on the Four Rod Display.
D. Blue SCRAM light is lit on the Full Core Display.
Page 4 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination C
D Answer Key A - - indication on the Four Rod Display indicates an odd numbered reed switch is made up.
The blue SCRAM light on the Full Core Display indicates that the scram valves are open, and does not indicate control rod position.
I Choice Level of Knowledge LOW I
Basis or Justification Difficulty Time Allowance PRA RO SRO 2.0 3
N (b) (10)
(b) (5)
(minutes) 1 OCFR55.41 1 OCFR55.43 Correct:
Knowledge/Ability KIA Incorrect 295006 Importance:
RO / SRO AA2.02 4.3 / 4.4 Incorrect The full in and full out lights on the Full Core Display continue to function with PMS and RDCS inoperable.
Two Xs on the Four Rod Display indicate that control rod indication is unknown, due to more than one reed switch being made up.
Source:
Reference(s):
Source Documentation New Exam Item 0
Modified Bank Item 0
ILT Exam Bank ARC 108 Reactor, E-4 0
Previous NRC Exam 0
Other Exam Bank Learning 0 bjective:
LLOTOO80.02 Required Materials:
Notes and Comments:
Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-I NRC Initial Licensing Examination
- 3.
LGS site conditions are as follows:
Both units are at 100% power 0
Both units Auxiliary transformers are supplying their respective Unit Auxiliary busses 0
The 10 Station Auxiliary Bus is de-energized for maintenance 0
All other station electrical busses are energized Subsequently, the 20 Station Auxiliary Bus supply breaker (205) trips open.
WHICH ONE of the following identifies the status of the 22 Auxiliary Bus and the D22 Safeguard Bus twenty (20) seconds later?
22 Auxiliarv Bus D22 Safeguard Bus A.
De-energized De-energized B.
Energized De-energized C.
De-energized Energized D.
En erg ized Energized Page 6 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Correct:
Incorrect r-
~
Answer Key D
The 22 Aux Bus will continue to be supplied by the Unit 2 Main Generator D22 Diesel Generators will start and supply the D22 Safeguard Bus in approximately I O seconds.
Both busses will be energized as described above.
A
~
Psychometrics Level of Difficulty Time Allowance PRA RO SRO HIGH 3.5 3
Y (b) (10)
(b) (5) 1 OCFR55.41 1 OCFR55.43 Knowledge (minutes)
While this choice is correct for the 22 Aux Bus, it is incorrect for D22 Safeguard Bus, which will be energized by the D22 D/G within 10 seconds I B l Incorrect Source:
Reference(s):
Learning 0 bjective:
Knowledge/Ability WA While this choice is correct for the D22 Safeguard Bus, it is incorrect for the 22 Aux Bus, which will remain energized from the Unit 2 Main Generator.
Incorrect
[XI New Exam Item 0
Modified Bank Item I7 ILT Exam Bank E10/20, Steps 2.1 and 2.3.1 LLOT0640.08 Previous NRC Exam 0
Other Exam Bank 295003 Importance:
RO / SRO AA2.04 3.5 13.7 Required Materials :
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station lLTO5-I NRC Initial Licensing Examination
- 4.
Unit I plant conditions are as follows:
0 Reactor Power is 100%
0 Division 4 DC (125 VDC Bus D) is de-energized The following events then occur:
0 Drywell Pressure rises to 2.0 psig Both HPCl Exhaust Diaphragms rupture on pump start 0
HPCl room temperature rises and stabilizes at 198°F 0
No operator action is taken WHICH ONE of the following describes the status of HPCl steam line containment isolation valves after the events above?
INBOARD ISOL (I F002)
OUTBOARD ISOL (1 F003)
A.
Closed Open B.
Closed Closed C.
Open Closed D.
Open Open Page 8 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key Correct:
Incorrect C
A Incorrect B
SRQ Basis or Justification Incorrect A HPCl isolation signal is present due to high turbine exhaust rupture diaphragm pressure. The 1 F003 valve isolates, however, the 1 F002 valve does not isolate due to NO control power to the isolation logic.
The 1 FOO2 valve does not isolate due to NO control power to the isolation logic D
The I F002 valve does not isolate due to NO control power to the isolation logic Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 HIGH 3.0 3
Y (b) (7)
The 1 F003 valve isolates SRO I
OCFR55.43 N/A WA I AA1.02 Source:
3.8 / 4.1 Reference(s):
Learning Objective:
Knowledge/Ability Source Documentation New Exam Item 0
Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam Other Exam Bank GP-8.1, Rev.11, Pg. 31; GE Elemental Dwgs. M-1-E41-1030-F-004, Shts. 1 & 2 LLOT0340.14 M-1-E41-1030-F-005, Shts 1 & 2 295004 I Importance:
Notes and Comments:
Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-I NRC Initial Licensing Examination
- 5.
Unit 1 plant conditions are as follows:
0 Drywell Temperature is 140°F 0
0 Drywell Pressure is 1.0 psig and rising slowly OT-101, HIGH DRYWELL PRESSURE, is being executed WHICH ONE of the following is a reason why Drywell cooling is maximized?
A. Ensure continued operation of the Reactor Recirculation Pump motors.
B. Slow the rate of pressure rise to allow time to bypass the potential Drywell Chilled Water system isolation.
C. Protect the integrity of the ADS valve solenoids.
D. Slow the rate of pressure rise to allow Drywell venting.
Page 10 of 200
Limerick Generating Station ILT05-1 NRC initial Licensing Examination Answer Key Level of Difficulty Time Allowance PRA RO Knowledge (min Utes) 1 OCFR55.41 LOW 2.5 2
N (b) (5)
Choice SRO 1 OCFR55.43 N/A I
D Correct:
Knowledge/Ability WA Incorrect I
A 29501 0 Importance: RO / SRO AK3.02 3.4 I 3.4 I B Incorrect Incorrect I
c 3R-0 Basis or Justification Per OT-I 01 bases, the Drywell may be vented if pressure is less than 1.68 psig. Therefore, slowing the rate of Drywell pressure rise allows time to vent.
The reason for Maximizing Drywell cooling is to slow the rise or prevent reaching 1.68 psig in the Drywell. It is not to protect the Recirc pumps.
The Drywell chill water isolation may be bypassed after entry into and meeting the Drywell temperature requirements of T-I 02 The design Drywell temperature of 340°F is to protect the ADS solenoids.
This is beyond the bases for OT-I 01.
Source:
Reference( s) :
Learning 0 bjective:
Source Documentation
[xi New Exam Item 0
Modified Bank Item 0
ILT Exam Bank OT-I 01, Bases Step 2.1 LLOTI 540.05 0
Previous NRC Exam Other Exam Bank Required Materials:
Notes and Comments:
Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
- 6.
Unit 2 plant conditions are as follows:
0 The 2B Recirc. Pump has tripped 0
Reactor power is 68%
0 All feedwater heaters are in service 0
Four OPRM channels are operable The unit is in the Restricted Region of the Power to Flow map Subsequently, the 2A Recirc Pump inadvertently trips.
WHICH ONE of the following describes the required action and the basis for this action?
A. SCRAM to prevent the occurrence of thermal hydraulic instabilities.
B. Restart a Recirc Pump to prevent RPV thermal stratification.
C. SCRAM to avoid the reactivity effects of starting a Recirc Pump in natural circulation.
D. Insert control rods to exit the Restricted Region of the Power to Flow map.
Page 12 of 200
Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Choice Correct:
C Answer Key Basis or Justification Although allowed by Tech. Specs., Exelon has decided to continue to direct that a manual scram be inserted with the plant in natural circulation.
I Level of Difficulty Time Allowance PRA RO Knowledge (minutes)
I OCFR55.41 LOW 2.0 2
N (b) (8) to (IO)
SRO 1 OCFR55.43 NIA A scram is required, however, not to avoid THI. See basis for answer C.
l A
/
Incorrect:
Source:
Reference (s) :
Learning Objective:
KnowledgelAbility KIA By procedure, Limerick does not allow restarting a Recirc. Pump in natural circulation with the Reactor critical.
I B l Incorrect
[XI New Exam Item Modified Bank Item ILT Exam Bank OT-I f 2 Bases, step 2.1 LLOTI 540.05 0
Previous NRC Exam Other Exam Bank 295001 Importance: RO / SRO AKI.01 3.5 13.6 This is not an allowed action in natural circulation.
I D /
Incorrect Required Materials:
Notes and Comments:
Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station ILTO5-1 NRC Initial Licensinq Examination
- 7.
Unit 1 plant conditions are as follows:
0 Reactor power is 35%
0 GEN STATOR COOLANT TROUBLE (125 B4) Annunciator is alarming An EO verifies the Stator Cooling Water return temperature is 82OC and rising.
WHICH ONE of the following describes the automatic response of EHC due to the conditions above?
A. LOAD SET will reduce to 21.4%
Bypass valves will remain closed B. LOAD SET will reduce to 21.4%
Bypass valves will open C. LOAD LIMIT will reduce to 21.4%
Bypass valves will open D. LOAD LIMIT will reduce to 21.4%
Bypass valves remain closed Page 14 of 200
~
Incorrect Limerick Generating Station ILTO5-I NRC Initial Licensing Examination D
This is incorrect as load limit does not runback, also bypass valves will open Answer Key Psychometrics Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 1 OCFR55.41 1 OCFR55.43 5
High 3.0 4
Y b)7 N
295007 AA1.05 Importance:
Reference(s):
Learning 0 bjective:
Knowledge/Ability WA Source Documentation New Exam Item 0
Modified Bank Item c] ILT Exam Bank c]
Previous NRC Exam 0
Other Exam Bank ON-I 14, Step 2.10 LLOT0590.03 (Description of K&A, from catalog)
Ability to operate and/or monitor the following as they apply to HIGH REACTOR PRESSURE:
Reactorrrurbine Pressure Regulating System
!quired Materials:
Notes and Comments:
Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination ATTACHMENT: SE-1 Provided
- 8.
The Main Control Room has become uninhabitable and SE-1, Remote Shutdown, is in progress at the Remote Shutdown Panel with the following conditions:
0 All SE-1 immediate operator actions are complete 0
All Remote Shutdown Panel transfer switches are in EMERGENCY 0
Reactor Level is +IO 0
Reactor Pressure is 490 psig WHICH ONE of the following identifies the EARLIEST point from now where Shutdown Cooling can be placed in service?
A. 1.0 Hours B. 1.5 Hours C. 2.0 Hours D. 2.5 Hours Page 16 of 200
Limerick Generating Station ILTO5-I NRC Initial Licensinq Examination B
A C
I Choice Basis or Justification Using Attachment 2 and 3 to SE-1 and at the maximum cooldown rate, it would take at least 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to go from 470 degrees F (490 psig) to 320 degrees F (75 psig)
This would mean exceeding the maximum cooldown rate This does not identify the minimum amount of time before SDC can be placed in service.
I Correct:
D Incorrect This does not identify the minimum amount of time before SDC can be placed in service.
1 Incorrect Level of Difficulty Time Allowance PRA HIGH 3.5 5
Y Knowledge (minutes)
Incorrect I-----
RO SRO 1 OCFR55.41 1 OCFR55.43 (b) (IO)
(b) (5)
Source:
Reference(s):
Learning 0 bjective:
New Exam Item 0
Modified Bank Item 0
ILT Exam Bank SEI, Attachments 2 & 3 LLOT0735.04
[7 Previous NRC Exam 0
Other Exam Bank Knowledge/Ability WA 29501 6 Importance:
RO / SRO 2.1.25 2.8 t 3.1 Required Materials:
SE-1 Notes and Comments:
Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station lLTO5-1 NRC Initial Licensing Examination
- 9. Both units are at 100% power:
0 0
0 A loss of the 220 KV switchyard occurs followed immediately by a lockout of the 4A Auto Transformer The D12 and D14 Diesel Generators fail to start All other Diesel Generators start as designed WHICH ONE of the following systems can be used to provide alternate cooling to the TECW heat exchangers and the procedural direction for using this system?
Alternate Cooling Water for TECW Heat Exchanqers A.
ESW B.
ESW C.
RECW D.
RECW Procedural Direction E-l0/20, Loss Of Offsite Power E-I, Station Blackout E-l0/20, Loss Of Offsite Power E-I, Station Blackout Page 18 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Incorrect Answer Key D
RECW is not hard piped to backup TECW. The correct procedure is E-10/20. Since six of the Diesel Generators start, this is not a Station Blackout.
I Choice I
Basis or Justification Level of Knowledge High ESW can be used to backup normal Service Water for TECW and RECW by performing manual local valve manipulations per E-I 0/20.
/A(
Correct:
Difficulty Time Allowance PRA RO SRO 3.5 4
Y (7)
N/A 1 OCFR55.41 1 OCFR55.43 (minutes)
The correct procedure is E-10/20. Since six of the Diesel Generators start, this is not a Station Blackout.
Incorrect 29501 8 AA1.01 RECW is not hard piped to backup TECW.
(c/
Incorrect Importance:
Reference(s):
Learning Objective:
Knowledg e/Ability KIA Source Documentation 0
New Exam item Modified Bank item ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank E-I 0/20, Attachment 5 LLOT0430.07 (Description of K&A, from catalog)
Ability to operate andlor monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Backup systems Required Materials:
Notes and Comments:
Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination I O.
Unit 1 Reactor Power is 100% with Instrument Air and Service Air in a normal lineup, when the following annunciator alarms:
0 I A INSTRUMENT AIR HEADER LO PRESS ( I 18 B2)
The following indications are observed:
0 I A Instrument Air Header Pressure is 85 psig and dropping slowly.
0 1 B Instrument Air Header Pressure is 108 psig and steady 0
Service Air Header Pressure is 102 psig and rising slowly 0
Backup Service Air Receiver is 100 psig and steady 10 minutes later the following indications are observed:
0 I A Instrument Air Header Pressure is 69 psig and dropping slowly 0
1 B Instrument Air Header Pressure is 100 psig and dropping slowly 0
Service Air Header Pressure is 99 psig and dropping slowly 0
Backup Service Air Receiver is 102 psig and dropping slowly WHICH ONE of the following identifies the source of air for the Instrument Air LOADS and Service Air LOADS?
Source of Instrument Air Source of Service Air A. I B Instrument Air compressor Service Air Compressor B. 1 B Instrument Air Compressor Backup Service Air Compressor C. Service Air Compressor Service Air Compressor D. Service Air Compressor Backup Service Air Compressor.
Page 20 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Correct:
Answer Key A
Question ID# 010 Both RC Level of Difficulty Time Allowance PRA Knowledge (minutes)
High 4.0 6
Y Choice RO SRO 1 OCFR55.41 1 OCFR55.43 Y (b) (5)
N Source:
Reference (s):
Learning 0 bjective:
Knowledge/Ability WA Incorrect:
I B
[E3 New Exam Item 0
Modified Bank Item
[7 ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank M-I 5 LLOT0730.02, 04, 07, I O 29501 9 Importance: RO / SRO AK3.01 3.3 13.4 Incorrect ERej Basis or Justification 1 B Compressor will begin supplying the IA loads on higher pressure due to check valves at the individual load. Service Air Compressor remains in service for service air loads.
The Backup Service Air Compressor, which is normally lined up to Unit 1, will only supply Unit 1 Service Air, if service air header pressure drops below 92 psig..
Service Air Compressor would only supply IA if both the 1A & 1 B IA header pressures were low.
See B and C above Required Materials:
Notes and Comments:
Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination 1 I. Unit 2 has just entered Opcon 4 in preparation for a refueling outage.
A failure of HV-51-2F008 results in a loss of Shutdown Cooling and necessitates establishing Alternate Shutdown Cooling using SRVs and Suppression Pool Cooling.
Conditions have been established as follows:
Suppression Pool Cooling is in service with 2A RHR.
Suppression Pool pressure is 0 psig SRV handswitches for the 2K and 2M SRVs are in the OPEN position Injection to the RPV has been established with the 2D RHR pump via HV-51-2F017D RPV Level is 150 on Shutdown Range RPV pressure is 40 psig WHICH ONE of the following describes the action required in order to establish Alternate Decay Heat removal?
A. Reduce RPV injection until RPV Level is 5 100.
B. Increase RPV injection until RPV Level is 2 200.
C. Reduce RPV injection until RPV pressure is 5 25 psig.
D. Increase RPV injection until RPV pressure is 2 50 psig.
Page 22 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination D
Answer Key 50# DIP is required across the SRVs in order to open and establish alternate heat removal.
Choice I
Basis or Justification Incorrect Incorrect Incorrect Correct A
While 100 is an important milestone in OT-100 Reactor High Level, when trying to prevent filling MS lines, filling the MSLS is required for this procedure.
Level is high enough to fill the MSLs and no additional Level is required.
B C
In order to establish Alternate heat removal the SRVs must open which requires 50# D/P. Correct conditions require raising pressure, not lowering.
Level of Difficulty Time Allowance PRA RO 1 OCFR55.41 Knowledge (minutes)
High 4.0 5
Y Y (b) (7)
SRO 1 OCFR55.43 N
Source:
Reference( s) :
Learning 0 bjective :
[XI New Exam Item Modified Bank Item ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank ON-121, Step 2.1.7, Attachment 6 S41.7.B, Step 4.2 LLOT-5010.01 Knowledge/Abili ty 29502 1 KIA 1 AA1.04 Importance:
RO / SRO 3.7 13.7 (Description of K&A, from catalog)
Ability to operate and or monitor the following as they apply to LOSS OF SHUTDOWN COOLING:
Alternate Heat Removal Methods Required Materials Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
- 12.
Unit I plant conditions are as follows:
0 Reactor level is 20 0
Reactor Pressure is 350 psig 0
Drywell Pressure is 25 psig 0
1 B RHR Pump is operating at 8200 gpm with the following valve indications:
HV-51-1 F016B, OUTBOARD SPRAY, green light lit HV-51-1 F017B, LPCl INJECTION, red, green and white lights lit HV-51-1 F021 B, INBOARD SPRAY, red light lit HV-51-1F024B, FULL FLOW TEST, red, green and white lights lit The CRS has directed the PRO to place I B RHR in Drywell Spray.
WHICH ONE of the following actions must be performed to initiate Drywell Spray?
A. Arm and depress I B RHR manual LOCA initiation pushbutton and open HV-51-1F016B.
B. Close HV-51-1 FO21 B, then open HV-51-1 F016B, then reopen HV-51-1 F021 B.
C. Close HV-51-1F017B and open HV-51-1F016B.
D. Close HV-51-1 F024B and open HV-51-1 FOI 6B.
Page 24 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 Low 3.0 4
Y Y (b) (7)
Answer Key SRO 1 OCFR55.43 N
Question ID# 012 Both RC Reference@):
Choice 0
Modified Bank Item 0
ILT Exam Bank 0
Other Exam Bank T-225, Step 4.5 I C Correct l A Incorrect Incorrect r Incorrect Basis or Justification 17B valve must be closed in order to open 16B - all other conditions for opening 16B are already.
LOCA Signal already present. PB not required. Also 178 must be closed.
This valve manipulation only required if LOCA signal not present. 17B must also be closed..
~~
~
~~
~~
24B dose not need to be closed Source Documentation Source:
I New Exam Item Previous NRC Exam Learning Objective:
I LL0T0370.09 Knowledge/Ability 295024 WA 1 EA1.04 Importance: RO / SRO 4.1 13.9 (Description of K&A, from catalog)
Ability to operate and/or monitor the following as they apply to HIGH DRYWELL PRESSURE:
RHWLPCI Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-I NRC Initial Licensing Examination
- 13.
An ATWS is in progress on Unit 1.
RPV Level was intentionally lowered per T-I 17.
The following conditions currently exist:
Reactor power is 6%
RPV level is -1 95 and slowly rising MSIVs are closed 1 ADS SRV is open RPV pressure is I000 psig Suppression Pool temperature is 145°F and slowly rising 2 Loops of Suppression Pool Cooling are in service Suppression Pool pressure is 6 psig & slowly rising Suppression Pool level is 24.5 and stable WHICH ONE of the following describes the required action and the reason for taking the action?
A. Reduce RPV pressure to less than 900 psig, in order to maintain on the safe side of SP/L-1 SRV Tail Pipe Level Limit.
B. Perform Emergency Blowdown per T-I 12, due to unable to restore and maintain RPV Level above -1 86.
C. Reduce RPV pressure to less than 900 psig, in order to maintain on the safe side of SP/T-1 Heat Capacity Temperature Limit.
D. Perform Emergency Blowdown per T-I 12, due to the safe side of SP/T-I, Heat Capacity Temperature Limit, cannot be maintained.
Page 26 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Incorrect Answer Key D
Choice Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 Incorrect SRO 1 OCFR55.43 A
High 3.5 4
Y Y (b) ( I O )
Y (b) (5)
Basis or Justification 295026 EA2.03 SP temp is 20°F from HCTL and rising slowly despite having 2 loops of SP Cooling in service. T-102 SPK-8 directs that if SP temp cannot be maintained on the safe side of HCTL, then maintain RPV pressure on the safe side of HCTL.
SP level is high but 3.5 feet away from SP/L-l limit and level is stable -
Reducing pressure for the purposes of maintaining this curve is not warranted.
While RPV Level is e-186, it is only 9 OOB and rising slowly. The criteria for T-l17LQ is level can be restored. With SRVs being used for pressure control, it is not unusual to go e-186 for short periods of time. T-I12 is not warranted under these conditions.
SP temp is still 20°F away from HCTL and rising slowly. T-I12 is not warranted at this point Importance:
Learning 0 bjective:
Source Documentation New Exam Item 0
Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank T-102 sh.1 LLOTI 560.04 KnowledgelAbility (Description of K&A, from catalog)
Ability to determine and/or interpret the following as it applies to Suppression Pool water temperature:
Reactor Pressure Required Materials:
T-102 Sht. I Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination
- 14.
A LOCA is in progress on Unit 2.
Drywell Temperature is 148°F.
The CRS directs the PRO to maximize drywell cooling.
Per T-I02 Bases, WHICH ONE of the following describes the minimum number of components that must be in service in order to maximize drywell cooling for the above conditions?
Drywell Fans DWCW Pumps A. One Fan per Cooler B. One Fan per Cooler C. Two Fans per Cooler D. Two Fans per Cooler One Two One Two Page 28 of 200
Limerick Generating Station ILT05-I NRC Initial Licensing Examination C
D Answer Key Does not meet the criteria wJrespect to the number of required DWCW pps.
In addition specifics 2 DW Fans per cooler. Fans are in parallel and are 100% capacity.
Does not represent the minimum number. 2 DW fans in-service - DW fans are 100% capacity and in parallel.
I Choice I
Basis or Justification Level of Difficulty Time Allowance PRA RO 1 OCFR55.41 Knowledge (m in u tes)
Low 2.5 3
Y (b) (7)
I Correct:
SRO 1 OCFR55.43 N
B 1 Meets the criteria specified in T-102 Bases, for step DW/T-5 Knowledge/Ability WA Incorrect:
r 295028 Importance:
RO J SRO EK2.04 3.6 J 3.6 Does not meet the criteria specified in T-I 02 Bases, step DW/T-5. Only has one DWCW pp cunning vs. two A
Incorrect Incorrect I
Source:
Reference(s):
Learning 0 bjective:
Source Documentation New Exam Item 0
Modified Bank Item 0
ILT Exam Bank T-102 Bases, DW/T-5 17 Previous NRC Exam 0
Other Exam Bank LOT-1560.06 Required Materials:
T-I 02 Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
- 15.
Unit 2 was manually scrammed due to a leak in the Suppression Pool.
0 0
0 Suppression Pool level is 20 and lowering RClC is being used for RPV level control HPCl is being used for RPV pressure control Suppression Pool level drops to 17.9.
WHICH ONE of the following describes the required action and the reason for it?
A. RClC must be secured due to insufficient net positive suction head.
B. HPCl must be secured due to insufficient net positive suction head.
C. RClC must be secured in order to prevent direct pressurization of the Suppression Pool.
D. HPCl must be secured in order to prevent direct pressurization of the Su p p ression Pool.
Page 30 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 Low 2.5 3
Y Y (b) (5)
Answer Key SRO 1 OCFR55.43 N/A NPSH limit for HPCl would be at 15.42 ft, where it is already secured at 18 I B l for the reason above Incorrect 295030 EK3.02 RClC Turbine exhaust pressure is insufficient to cause pressurization of the Suppression Pool in excess of PCPL.
Incorrect Importance:
Reference(s):
Learning 0 bjective:
Knowledge/Ability WA Source Documentation
[XI New Exam Item 0
Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam c]
Other Exam Bank T-102, sh. 1 LLOTI 560.05 (Description of K&A, from catalog) Knowledge of the reasons for the following responses as they apply to Low SP Water Level: HPCl Operation Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatinn Station lLTO5-1 NRC Initial Licensing Examination
- 16.
A loss of all high pressure injection has occurred on Unit 1 with conditions as follows:
0 All rods in 0
RPV Water Level is -170 and dropping 0
No low pressure ECCS pumps can be started 0
RPV pressure has been recorded at 900 psig and is being maintained with SRVs The crew is attempting to restore the 1 B CRD pump and line up per T-240.
WHICH ONE of the following describes steam cooling conditions under which adequate core cooling is assured?
RPV Level RPV Pressure lniection A.
-1 75 795 psig None B.
-1 85 800 psig 1 B CRD pump C.
-1 95 910 psig None D.
-205 890 psig 1 B CRD pump Page 32 of 200
Limerick Generatina Station ILT05-I NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 3.5 5
Y (b) (8-10)
~~
Answer Key SRO 1 OCFR55.43 NIA Question ID# 016 Both-R(
Source:
Reference(s):
Objective:
Knowledge/Ability WA Learning Choice New Exam Item 0
Modified Bank Item ILT Exam Bank 0
Previous NRC Exam 1 0 Other Exam Bank T-I 11 BASES, LR-12 through LR-17 LOT-1560.03 WA 295031 Importance:
RO / SRO EKI.01 4.6 14.7 Correct:
1
~
Incorrect Incorrect Incorrect A
B C
D SRd Basis or Justification Core Cooling is assured in steam cooling as long as level is between -161 and -201, with no injection and pressure less than the value recorded in T-I I I LR-14. Even though pressure is <I OO# below recorded value, this supply calls for a new pressure load.
Calculations for MZI RWL assures that there is no sub cooling at the core inlet. Since any injection would invalidate this assumption, adequate Core Cooling cant be assured if RPV level is <-I61 and water is being injected.
Once stabilized, if RPV pressure rises above the value recorded in CR-14, MZIRWL calculations are no longer valid and the core may not be adequately cooled.
The candidate would select this answer if he didnt recognize that the safe area of this curve is below the curve. This is a common error because this varies between curves. It is also incorrect because water is being injected.
Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILTO5-1 NRC Initial Licensing Examination
- 17.
Unit 1 conditions are as follows:
0 Core reload has just commenced during a refueling outage.
0 SRM count rate is 30 cps While lowering a fuel assembly not adjacent to an SRM, count rate increases to 65 cps and stabilizes.
WHICH ONE of the following describes the required action, if any?
A. Immediately evacuate the refuel floor.
B. Suspend component movement.
C. Continue lowering fuel assembly.
D. Raise the fuel assembly from the core so that it clears the upper grid.
Page 34 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination A
C D
Correct:
is reached This would only be appropriate in the event of criticality.
FH-105 requires suspension of component movement when one doubling is reached This action is not required if it is the 1 through 4'h fuel assembly adjacent to the detector at the start of a core reload.
Incorrect Level of Difficulty Time Allowance PRA RO Knowledge (min Utes) 1 OCFR55.41 Low 2.0 3
Y (b) (8-10)
I Incorrect SRO 1 OCFR55.43 N/A Incorrect Source:
Reference( s ):
Learning Objective:
Knowledge/Ability KIA New Exam Item 0
Modified Bank Item ILT Exam Bank Previous NRC Exam Other Exam Bank FH-105, STEP 3.7 LLOT0760.12 295023 Importance:
RO / SRO 2.2.28 3.5 / 3.3 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station lLTO5-1 NRC Initial Licensing Examination
- 18.
An ATWS is in progress on Unit 1.
Reactor Power is 100%.
A Group 1 NSSSS isolation occurs and SRVs open to lower RPV pressure.
The PRO is controlling RPV pressure 990 - 1096 psig with SRVs.
The highest recorded RPV steam dome pressure was 1340 psig.
WHICH ONE of the following describes actions that satisfy the MOST LIMITING Tech Spec requirements?
A. Notify the NRC and be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
B. Place RPS in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in HOT SHUTDOWN within I 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
C. Notify the NRC within I hour and be in HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
D. Be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Page 36 of 200
Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes)
I OCFR55.41 High 3.5 5
N (b) (8-1 0)
Answer Key SRO 1 OCFR55.43 NIA Choice Source:
Reference(s):
Learning 0 bjective:
KnowledgelAbility KIA Correct:
New Exam Item Modified Bank Item ILT Exam Bank Previous NRC Exam Other Exam Bank LGS Tech Specs LLOTI 540.05 295025 Importance:
RO I SRO EKI.05 4.41 4.7 Incorrect Incorrect Incorrect C
A B
D Basis or Justification Reactor Coolant System Pressure Safety Limit has been violated. Tech Spec action must satisfy 2.1 and 6.7.1 States the NRC must be notified and meets 3.0.3 for LCO not met and 3.3.4 for ATWS Instrumentation but is not conservative enough to meet 2.1 and 6.7.1 Meets 3.3.1 for RPS Instrumentation but is not conservative enough to meet 2.1 and does not meet 6.7.1 This meets 3.4.2 for SRV's and 3.4.6.2 for Reactor Steam Dome Pressure, but is not conservative enough to meet 2.1 and does not meet 6.7.1 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
~
Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination
- 19.
Unit 1 plant conditions are as follows:
0 Reactor Power is 8%
0
'W IRM is failed upscale
&Q,
\\@(ob Reactor mode switch is in STARTUP
" I D" An electrical fault results in the loss of 1AY160.
WHICH ONE of the following identifies the impact on IRMs and status of RPS?
A. IRM Channels A, C, E, and G lose power, Full Reactor Scram.
B. ONLY IRM Channels A, and C, lose power, Full Reactor Scram.
C. IRM Channels A, C, E, and G lose power, Reactor 1/2 Scram ONLY.
D. ONLY IRM Channels A, and Cy lose power, Reactor 1/2 Scram ONLY.
Page 38 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Knowledge High I
Answer Kev Difficulty Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 3.0 3
N (b) 7 N
I Question ID# 0'19 Both RC Source:
Reference(s):
Learning Objective:
Correct:
New Exam Item Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam Other Exam Bank E-1AY160, Step 1.2 and 1.22, AND GP-2, Caution before step 3.4.7 LLOT0250.07 Incorrect:
Knowledge/Ability WA Incorrect:
21 5003 Importance:
Incorrect:
A B
C D
Basis or Justification
~
~
IRM Channels A, C, E, and G loss power on a loss of 1AY160, Full Reactor Scram occurs due to mode switch in startup and RPS A side % scram loss of 1AY160 and RPS B side % scram (D IRM upscale)
ONLY IRM Channels A, and C, loss power is incorrect as E & G channels also lose power, Full Reactor Scram is correct IRM Channels A, C, E, and G loss power is correct, Reactor 1/2 Scram is incorrect as full reactor scram will occur ONLY IRM Channels A, and C is incorrect as E & G channels also lose power, Reactor 1/2 Scram is incorrect as full reactor scram will occur Source Documentation Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Limerick Generating Station lLT05-I NRC Initial Licensinq Examination
- 20.
Unit 1 Plant conditions are as follows:
0 Reactor Startup is in progress 0
1A and I D IRMs are on range 1 0
All other IRMs are on range 2 1A SRM is being withdrawn when the count rate drops to 90 CPS.
WHICH ONE of the following identifies the impact on the Reactor Manual Control System (RMCS)?
A. No rod blocks are enforced.
B. Only a rod withdraw block is enforced.
C. Only a rod insert block is enforced.
D. Both rod insert and withdrawal rod blocks are enforced.
Page 40 of 200
Limerick Generatinq Station ILT05-1 NRC initial Licensina Examination Choice Correct:
B Incorrect A
Incorrect C
D Incorrect Answer Key Basis or Justification Only a rod withdraw blocks is enforced, is correct as all IRMs are not above range 2 and SRM CPS are less than 100 with detector not full in No rod blocks are enforced, is not correct. It would be correct if all IRMs were above range 2 Only a rod insert block is enforced. This is not correct as SRM CPS less than 100 with detector not full in does not enforce an insert block Rod insert and withdrawal rod blocks are enforced SRM CPS are less than 100 with detector not full in Level of Difficulty Time Allowance PRA Low 3.5 4
N Knowledge (minutes)
RO SRO 1 OCFR55.41 1 OCFR55.43 (b) (5)
N Source:
Reference(s):
Learning 0 bjective:
Ix] New Exam Item Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank GP-2 Appendix 1, step 3.3.7 and NOTE LLOT0240.06:
Required Materials:
Knowledge/Ability WA Notes and Comments 21 5004 Importance:
RO / SRO K5.03 2.8 12.8 Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination
- 21. Unit 2 is at 100% power.
- 2 APRM output fails to 2%.
WHICH ONE of the following completes the statement below?
The 2B Rod Block Monitor channel 91 A. initiates a rod block B. automatically goes to Bypass mode C. automatically swaps to reference #3 APRM D. automatically swaps to reference ##4 APRM Page 42 of 200
Limerick Generating Station ILT05-I NRC Initial Licensing Examination Correct:
I Answer Key B
The RBM sees less than 30% power from its reference APRM and Auto Bypasses I
Choice I
Basis or Justification Incorrect A
Rod Block results an Upscale, Downscale, or hop condition. Failure of the reference APRM will NOT cause a RBM hop or Downscale.
Incorrect Incorrect C
The reference APRM would only swap if the primary APRM channel were INOP or Bypassed. This failure does not constitute these conditions. The alternate reference APRM for #2 is #4.
D I
I I
Level of Knowledge Low Difficulty Time Allowance PRA RO SRO (minutes) 10CFR55.41 10CFR55.43 3.0 4
N (b) (2)
N Source:
Reference(s):
Learning 0 bject ive:
KnowledgelAbility WA Required Materials:
New Exam Item 0
Modified Bank Item ILT Exam Bank Previous NRC Exam Other Exam Bank ARC 108, A-5 LLOT0280.09a 21 5005 Importance:
RO I SRO K1.03 3.4 13.5 Notes and Comments Prepared By:
Rick Rhode (610) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILTOS-I NRC Initial Licensing Examination
- 22.
The CRS has ordered a GP-4 shutdown as a result of the 1 E SRV being stuck open.
Following the performance of GP-4 actions plant conditions are as follows:
0 Reactor power is 28%
0 CRS has entered T-I 17 0
Suppression Pool temperature is 112°F and going up 0
T-270 is complete, injection has been terminated Reactor level is -100 when reactor power is noted to be below 4%.
WHICH ONE of the following describes the correct RPV water level band and the basis for this band?
A. -60 to -100 in order to lower power by reducing core inlet subcooling.
B. -60 to -100 in order to lower power by reducing natural circulation driving load and core flow.
C. -1 00 to -1 86 in order to lower power by reducing core inlet subcooling.
D. -1 00 to -186 in order to lower power by reducing natural circulation driving head and core flow.
Page 44 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination D
Answer Key Conditions are set for level lowering to below TAF. The bases for this level lowering is reduction of natural circulation driving head I
Choice I
Basis or Justification A
Correct:
This is the appropriate level band and reasons for the first level lowering.
This is N/A once SP temp is I I O " and SRV is open B
C Incorrect This level condition is not appropriate, the reason is associated with the
-161 to -186 level band This level band is correct, the reason is associated with the higher level band Level of Difficulty Time Allowance Knowledge (minutes)
High 3.0 5
Incorrect PRA RO SRO 1 OCFR55.41 1 OCFR55.43 Y
(b) (5)
N Incorrect 295037 EK.2.09 Importance:
RO / SRO 4.0 / 4.2 I Source: L Reference s :
Learning Objective: I; Knowledge/Ability Source Documentation New Exam Item Modified Bank Item 17 ILT Exam Bank 0
Previous NRC Exam Other Exam Bank T-I 17, T-I 17 Bases, LQ-6 through LQ-11 and LQ-16.
LLOTI 560.05 (Description of K&A, from catalog)
Knowledge of the interrelations between SCRAM Condition Present and Reactor Power above APRM down SCL or unknown & the following... Reactor Water Level Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
- 23.
Unit 2 is operating at 100% when a Turbine Trip occurs. Two minutes later the following conditions are noted:
Reactor Power is 0%
0 Rod 26-1 I is at position 48 0
Rod 50-31 is at position 48 0
Rod 22-51 is at position 48 0
All other control rods are at 00 SLC is not running Subsequently, the RO begins to insert rods.
WHICH ONE of the following describes control rod positions that meet the criteria for NO ATWS?
A. Rods 26-1 I, 50-31, and 22-51 are at position 04.
B. Rod 26-1 I and 50-31 are at position 02 and 22-51 is at position 04.
C. Rods 26-1 1 and 50-31 are at position 00 and 22-51 is at position 48.
D. Rod 26-1 1 is at position 00 and rods 50-31 and 22-51 are at position 4 8.
Page 46 of 200
Limerick Generating Station lLTO5-I NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 3.0 4
Y (b) (IO)
SRO I
OCFR55.43 (b) (5)
Source:
Reference (s):
Learning 0 bjective:
New Exam Item 0
Modified Bank Item 0
ILT Exam Bank Previous NRC Exam 0
Other Exam Bank T-I 01, note 14, Tech Specs definition of Shutdown Margin LLOTI 560.03 Required Materials:
KnowledgeIAbility WA Notes and Comments 295037 Importance:
RO I SRO EA 2.05 4.2 I 4.3 Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
~
Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination
- 24. A radiological accident has caused the following annunciators to alarm:
NORTH STACK HI-HI RADIATION (003 E l )
NORTH STACK HI RADIATION (003 E2)
WHICH ONE of the following areas is the location of the radiation release, and what is the required action to mitigate the release?
A. Standby Gas Treatment Exhaust Enter and execute T-I 04 Radiological Release.
B. Standby Gas Treatment Exhaust Perform ST-6-104-880-0, Gaseous Effluent Dose Rate Determination.
C. Reactor Enclosure Equipment Compartment Exhaust Evacuate all unnecessary personnel per SE-24, Plant Evacuations.
D. Reactor Enclosure Equipment Compartment Exhaust Enter and execute T-I 03, Secondary Containment Control.
Page 48 of 200
Limerick Generatinq Station ILT05-I NRC Initial Licensinq Examination Choice Correct:
B Incorrect A
Basis or Justification Possible source, ST must be performed and LGS Emergency Plan annex, Table 3-1 must be consulted Possible source but alarm alone is not sufficient reason to enter and execute T-I 04
_ _ _ ~
I n correct C
Not a possible source based on the given conditions, although the action is plausible given this source Incorrect Source Documentation D
Not a possible source based on the given conditions, although the action is plausible given this source Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 3.5 4
N (b) (7)
SRO 1 OCFR55.43 N
Required Materials:
Source:
Reference(s) :
Learning 0 bjective:
Notes and Comments
[XI New Exam Item 0
Modified Bank Item 0
ILT Exam Bank Previous NRC Exam Other Exam Bank ARC-MCR-003-EII ST-6-104-880-0, T-I 04 LLOT0720.03 Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author KnowledgelAbility KIA 295038 Importance: RO I SRO EK2.03 3.6 13.8
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
- 25.
Given the following plant conditions:
The Main Control Room has been abandoned due to a fire 0
Immediate actions of SE-I have been completed The Remote Shutdown Panel has been manned All Remote Shutdown Panel transfer switches have been placed in EM ERG EN CY Reactor pressure is 980 psig and rising slowly WHICH ONE of the following identifies the systems available for RPV level control?
A. RClC controlled manually, ONLY.
B. HPCl controlled manually, ONLY.
C. RClC controlled manually with HPCI cycling in AUTO.
D. HPCl controlled manually with RClC cycling in AUTO.
Page 50 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 Low 2.5 3
Y (b) (5)
Answer Key SRO 1 OCFR55.43 N
Question ID# 025 Both RC Source:
Reference( s):
Learning Objective:
Choice New Exam Item c]
Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam Other Exam Bank SE-1 step4.3 LLOT0735.02,.03 Correct:
Incorrect Incorrect Incorrect C
A B
D
$Fa Basis or Justification RClC is the primary means of level control from the Remote Shutdown Panel, but must be started up and shutdown manually. HPCl will cycle in AUTO as long as it has not been disabled.
RClC manual control is available, but HPCl will cycle in AUTO as long as it has not been disabled.
HPCl manual control is not available from the RSP. It can either be allowed to cycle in AUTO, or completely disabled from the RSP.
_ _ ~
_ _ ~
~~
HPCl will cycle in AUTO as long as it has not been disabled. RClC must be started up and shutdown manually.
Knowledge/Ability WA 29501 6 AK2.01 Importance:
RO I SRO 4.4 / 4.5 (Description of K&A, from catalog)
Knowledge of the interrelations between CONTROL ROOM ABANDONMENT and...Remote Shutdown Panel Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
- 26.
Unit 2 Plant conditions are as follows:
0 0
Reactor is scrammed 0
Main Turbine is tripped 0
Turbine speed is 100 RPM and slowly coasting down 0
Sealing Steam header pressure is 0 psig Main Condenser vacuum is 20 and dropping The CRS orders the PRO to break Main Condenser vacuum.
Per OT-I 16 Bases, WHICH ONE of the following describes the reason for this action?
A. Rapidly reduce turbine speed to prevent damage due to windage.
B. Reduce differential pressure across turbine seals to prevent turbine exhaust hood over-pressurization.
C. Rapidly reduce turbine speed to prevent damage due to uneven rotor heating.
D. Reduce differential pressure across turbine seals to prevent drawing cold air across the hot rotor.
Page 52 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 Low 3.5 4
Y (b) (7)
Answer Key SRO 1 OCFR55.43 N
Question ID# 026 Both R(
Source:
Reference( s) :
Learning Objective:
Choice New Exam Item 0
Modified Bank Item 0
ILT Exam Bank OT-I 16 BASES, step 3.3 LLOTI 540.05 0
Previous NRC Exam 0
Other Exam Bank Correct:
Knowledge/Ability WA Incorrect 295002 Importance:
RO / SRO AK2.11 2.6 12.7 Incorrect Incorrect D
A B
C gij" Basis or Justification With no sealing steam pressure, main condenser vacuum will draw cold air across the seals and the hot turbine rotor Preventing windage damage is the reason why vacuum should not be broken greater than 1200 RPM Preventing Turbine exhaust hood over-pressurization is the reason for tripping the Main Turbine at 21.5" VAC Uneven rotor heating is a problem if sealing steam is applied to a stationary turbine rotor Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILTO5-1 NRC Initial Licensing Examination
- 27.
A reactor startup is in progress on Unit 2.
Reactor Power is 3%.
0 A Reactor Scram is attempted 0
Ten control rods remain at position 04 to 48 WHICH ONE of the following describes the required operator action?
A. Enter T-100, bypass RWM and insert control rods with S73.0.D.
B. Enter T-100, insert control rods with T-213.
C. Enter T-101, bypass RWM and insert control rods with S73.0.D.
D. Enter T-I 01, insert control rods with T-213.
Page 54 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Difficulty Time Allowance PRA RO (minutes) 10CFR55.41 I
Answer Key SRO 1 OCFR55.43 Choice
3.0 Correct
3 N
N 1
A Reference@):
Learning 0 bjective:
Knowledge/Ability WA Incorrect 0
Modified Bank Item ILT Exam Bank T-100 Bases step RC/Q-3 LLOTI 540.02 Other Exam Bank 29501 5 Importance: RO / SRO AA2.01 4.1 / 4.3 B
Incorrect C
I D
Incorrect Basis or Justification As Reactor power is below 4% entry into T-I 00 is appropriate, Bypass RWM and Insert Control Rods with S73.0.D is directed T-213 is not directed in T-I00 As Reactor power is below 4% entry into T-I 00 (vice T-I 01) is appropriate As Reactor power is below 4% entry into T-I 00 (vice T-I 01) is appropriate and T-213 is not directed in T-I 00 Level of Knowledge Source Documentation Source:
I
[E3 New Exam Item 0
Previous NRC Exam Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station ILT05-I NRC Initial Licensing Examination
- 28.
Unit I plant conditions are as follows:
Reactor power is 100%
Drywell cooling is maximized An inadvertent Group VlllA isolation occurs.
WHICH ONE of the following describes the status of Drywell Chilled Water service to the Drywell and Recirc Pump cooling water one minute later?
Drywell Chilled Water Recirc Pump Coolinq Water A.
In Service In Service B.
In Service Isolated C.
Isolated In Service D.
Isolated Isolated Page 56 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Difficulty Time Allowance PRA RO (minutes)
I OCFR55.41 Answer Key SRO 10CFR55.43 I Question ID# 028 Both RC Low 2.5 2
N Correct:
Incorrect (b) (8, 9, 10)
N Incorrect I------
Source:
Reference(s):
Learning 0 bjective:
1 Incorrect New Exam Item 0
Modified Bank Item 0
ILT Exam Bank GP-8.1 for Group VlllA LLOT0180.05 Previous NRC Exam 0
Other Exam Bank D
Knowledge/Ability WA A
295020 Importance:
C
$*W Basis or Justification An inadvertent VlllA isolation would result in both DWCW and Recirc Pump cooling water isolating Both will isolate DWCW will also isolate Recirc Pump cooling water will also isolate Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
- 29.
Unit 1 plant conditions are as follows:
0 Reactor power is 100%
0 Hydrogen Water Chemistry is not in service The following annunciators are received:
0 0
MAIN STEAM LINE DIV 1 RAD MONITOR HVDOWNSCALE (109 FI)
MAIN STEAM LINE DIV 2 RAD MONITOR HVDOWNSCALE (I09 F2)
Subsequently the following annunciator is received:
MAIN STEAM LINE HIGH HIGH RADIATION (107 11)
WHICH ONE of the following describes the procedure(s), which must be entered for valid alarms, and the required operator action(s)?
A. Enter ON-I 02 ONLY; reduce reactor power in accordance with GP-5, Appendix 2.
B. Enter T-103 ONLY; perform a GP-3 Normal Plant Shutdown.
C. Enter ON-I02 and T-103; p.erform a rapid plant shutdown and close the MSIVs.
D. Enter ON-I02 and T-103; perform a rapid plant shutdown and Emergency Blowdown per T-I 12.
Page 58 of 200
Limerick Generating Station ILT05-I NRC Initial Licensing Examination C
A B
D I
Answer Key
~~
Main steam line high rad requires entry into ON-102 and 1-103. The high-high rad alarm indicates three times NFPB. Per T-I03 this requires a rapid plant shutdown and closure of the MSIVs While reducing power is an immediate action per ON-102, question conditions also require entry into T-103 and the actions described in C above ON-I02 entry is also required and a GP-3 shutdown would be appropriate per T-103 if 2 or more areas exceeded MSO rad level, but is not adequate for the stated conditions An emergency blow-down would be appropriate per T-I 03 if two or more areas exceeded MSO and a primary system was discharging into the Reactor Enclosure. but is not reauired for MSL Hiah-Hiah Rad onlv Choice Correct:
Difficulty Time Allowance PRA RO (minutes) 1 OCFR55.41 High 4.0 5
Y Y (b)(10)
Incorrect SRO 1 OCFR55.43 y (b)(2)
Incorrect 295033 (32.4.4 Incorrect Importance:
Basis or Justification Source:
Reference(s):
Learning Objective:
Source Documentation New Exam Item 0
Modified Bank Item ILT Exam Bank 0
Previous NRC Exam
[7 Other Exam Bank ARC-MCR-109-F1, ARC-MCR-109-F2, ARC-MCR-107-11, ON-I 02 Step 1.2, T-I 03 LLOTI 560.02, LLOT1550.01 KnowledgelAbility WA (Description of K&A, from catalog) High Secondary Containment Radiation Levels: Ability to recognize abnormal indications for system operating parameters which are entry level conditions for emergency and abnormal operating procedures.
Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination
- 30.
Plant conditions are as follows:
0 A LOCA is in progress 0
Drywell Hydrogen is 3%
0 Drywell Oxygen is 8%
0 Suppression Pool Hydrogen is 7%
Suppression Pool Oxygen is 4%
WHICH ONE of the following identifies the flowpath for combustible gas monitoring and control?
A. DW/G-3 and SP/G-I B. DW/G-2 and SP/G-2 C. DW/G-3 and SP/G-3 D. DW/G-2 and SPIG-1 Page 60 of 200
Limerick Generatinlq Station ILT05-1 NRC Initial Licensing Examination Difficulty Time Allowance PRA RO (minutes) 1 OCFR55.41 High 3.5 4
Y Y (b)(lO)
Answer Key SRO 1 OCFR55.43 Y (b)(5)
Question ID# 030 Both RC Source:
Reference(s):
Learning Objective:
I Choice New Exam Item Modified Bank Item ILT Exam Bank Previous NRC Exam 0
Other Exam Bank - Modified LOR Exam bank item T-102, sheet 2 and T-102 Bases Step PC/G-5 LLOTI 560.06 I
Correct:
Knowledge/Ability K/A 1
Incorrect 500000 Importance:
RO / SRO EA 2.03 3.3 / 3.8 Incorrect Incorrect I A
B C
D Basis or Justification Applying the containment H2 and 0 2 levels to the tables, PC/G-1 and PC/G-2 in T-102, sh. 2, results in the use of flowpaths DW/G-3 and SP/G-1 Neither of these flowpaths are correct per PC/G-1 and PC/G-2, T-102, sh. 2 The drywell flowpath is correct; the suppression pool flowpath is not, per PC/G-1 and PC/G-2, T-102, sh. 2.
The suppression pool flowpath is correct; the drywell flowpath is not, per PC/G-1 and PUG-2, T-102, sh. 2.
Required Materials:
T-I02 sht. 2 Notes and Comments Prepared By:
Rick Rhode (610) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
- 31.
A steam leak in the Unit 2 RCIC room resulted in a scram and Emergency Blowdown per T-I 12.
Conditions are as follows:
0 Reactor pressure is 90 psig and dropping 0
Reactor level is -30 and dropping 0
Drywell pressure is 1.2 psig and steady The PRO has been directed to maintain RPV level with low pressure ECCS.
WHICH ONE of the following actions will result in injecting to the RPV with low pressure ECCS? (No other operator actions are taken)
A. Arm and depress the Core Spray Div. I Manual Initiation Pushbutton.
B. Start the 2A Core Spray Pump and take the HV-52-2F005A, Inboard Injection Valve, to OPEN.
C. Arm and depress the Core Spray Div. 3 Manual Initiation Pushbutton.
D. Start the 2C RHR Pump, HV-51-2F017C LPCI, Injection Valve, will OPEN automatically.
Page 62 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Difficulty Time Allowance (minutes)
High 3.5 4
OCFR55.41 1 OCFR55.43 Y
Y (b)(7)
N Question ID# 031 Both RC Source:
Reference(s):
Learning Objective:
I Choice New Exam Item 0
Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam 17 Other Exam Bank S52.7A, note above step 4,4 LLOT0350.
I O Correct:
Knowledge/Ability K/A Incorrect 209001 Importance:
RO/ SRO PWG 2.1.30 3.9 13.4 I
incorrect L
I Incorrect A
B C
D Basis or Justification I
Div 1 Manual Initiation Pushbutton will provide a Div 1 LOCA Signal, Start the 1A pump and open the injection valves as long as the Reactor low pressure permissive is met.
The HV-52-2F005 will not open unless there is a LOCA signal present Div 3 Manual Initiation Pushbutton will start the IC Core Spray Pump, but it will not make up the open logic for the injection valves. Only the Div l(2)
Pushbuttons will do that The HV-51-2F017C will not open automatically unless there is a LOCA signal present.
Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
~~
Limerick Generating Station ILTO5-1 NRC Initial Licensinq Examination
- 32.
Unit 2 plant conditions are as follows:
0 Reactor power is 100%
0 Division 3 Safeguard 125Vf+%WDC is inoperable due to maintenance on the battery charger e&&
43(ob An inadvertent Group I isolation causes a reactor scram.
Unit 2 RClC starts on low reactor level A steam leak develops in the RClC room. RClC room temperature reaches 21 0°F WHICH ONE of the following operator actions places the RClC system in the configuration required by current plant conditions?
A. Trip the RClC Turbine.
B. Depress the RClC Manual Isolation Pushbutton.
C. Take the handswitch for the HV-49-2F007, RClC Steam Line Inboard Isolation to CLOSE.
D. Take the handswitch for the HV-49-2FOO8, RClC Steam Line Outboard I sol ation to CLOSE.
Page 64 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Correct:
Answer Key C
Question ID# 032 Both RC Incorrect Choice A
Difficulty Time Allowance PRA RO 1 OCFR55.41 (minutes)
High 3.0 4
Y Y (b)(5)
SRO 1 OCFR55.43 N
l B
Incorrect Source:
Reference(s):
Learning 0 bject ive :
Incorrect 0
[xi New Exam Item 0
Modified Bank Item ILT Exam Bank c]
Previous NRC Exam c]
Other Exam Bank E-2FC, GE DWG M-1-E51-1040-E-028, Sht.1 LLOT0380.05, LLOT0380.12 Basis or Justification With a loss of Div 3 DC, the 2F007 will fail to isolate on High RClC room temperature (205OF) and must be closed WA I A205 The RClC Turbine will trip on a Div 1 NS4 isolation signal on High RClC Room temperature Manual isolation will not close 2F007 valve due to loss of Div 3 DC 3.3 13.3
~
~
The 2F008 will close on a Div I NS4 Isolation signal on High RClC Room temperature Knowledge/Ability 1 217000 I Importance:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station lLTO5-1 NRC Initial Licensinq Examination
- 33.
Unit 1 plant conditions are as follows:
0 Reactor water level is 35 0
1 B RHR is in Suppression Pool cooling Div 2 Safeguard DC Bus is subsequently deenergized.
WHICH ONE of the following describes the effect, if any, on 1 B RHR Loop if Reactor Water level lowers to -140?
A. IB RHR loop will realign to the LPCl mode.
B. IB RHR pump will load shed and remain shutdown.
C. 1 B RHR loop will remain in Suppression Pool cooling.
D. 1 B RHR pump will continue to run; minimum flow valve will open.
Page 66 of 200
Limerick Generating Station ILT05-1 NRC Initial LicensinQ Examination Incorrect:
Answer Kev A
Choice High Correct:
1 c
Difficulty Time Allowance PRA RO SRO (minutes) 10CFR55.41 1 OCFR55.43 3.0 4
Y Y (b)(7)
N Source:
Reference( s):
Learning 0 bjective:
I B Incorrect:
0 New Exam Item Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank E-IFB U/1, GE DWG. M-1-Ell-1040-E-039 SH.l LLOT0370.3e Incorrect:
I D
Knowledge/Ability KIA
?BE?
Basis or Justification 203000 Importance: RO / SRO K6.02 2.8 / 3.0 RHR will remain in suppression pool cooling as F024 (SP cooling valve (and F017B (LPCI Inject valve) will not reposition during the LOCA due to the Loss of Div 2 DC F024 and F017B will not reposition due to loss of Div 2 DC RHR pump will not load shed during a LOCA Min flow valve will not open Required Materials:
Notes and Comments:
Existing bank question, Stem and Distractors Modified Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Limerick Generatina Station ILT05-1 NRC Initial Licensing Examination
- 34.
Unit 1 plant conditions are as follows:
0 OPCON4 0
IA RHR is in shutdown cooling Reactor water level drops from +70 to -1 0.
WHICH ONE of the following identifies current RHR pump and valve status?
HV-51-1 F006A HV-51-1 FOO9 Shutdown Cooling Shutdown Cooling 1 A RHR Pump Suction Valve Isolation valve A.
B.
C.
D.
Running Open Open Running Open Closed Closed Open Tripped Tripped Open Closed Page 68 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination C
I Answer Key Incorrect as F006A will not automatically close and FOO9 yiJ close when level drops below +I 25 Correct:
Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 3.0 3
Y y W(7)
Incorrect SRO 1 OCFR55.43 N
I Incorrect KnowledgelAbility WA I
Basis or Justification 205000 Importance:
When level decreases to below + I 2.5 Shutdown Cooling will isolate FOO9, which in turn trips the ARHR pump, F006 remains open as there is no auto closure Incorrect as FOO9 will close with level below +125 and pump will trip A
Incorrect as pump will trip when level drops below 12.5 due to FOO9 closure Source Documentation Source:
Reference(s):
Learning Objective:
New Exam Item 0
Modified Bank Item 17 ILT Exam Bank Previous NRC Exam 0
Other Exam Bank S51.8.8, step 3.2 LLOT0370.14~
Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination
- 35.
Unit 1 plant conditions are as follows:
0 Reactor power is 100%
0 The RO selects Single-Element control on the Feedwater Master Level Controller (L I C-M 1 - 1 R600)
WHICH ONE of the following describes the response, if any, of the Master Level Controller to a Reactor SCRAM?
A. Controller will swap to three-element when SCRAM Profile is activated.
B. Controller will swap to three-element when SCRAM Profile is reset.
C. Controller will swap to three-element when Reactor power is below 20%.
D. Controller will remain in single-element.
Page 70 of 200
Limerick Generating Station iLT05-I NRC initial Licensinq Examination Answer Key Level of Difficulty Time Allowance PRA RO 1 OCFR55.41 Knowledge (minutes)
High 3.0 3
Y y (b)(7)
I Choice SRO 1 OCFR55.43 N
Correct:
1 Source:
Reference(s):
Learning Objective:
Knowledge/Ability WA Incorrect I
New Exam Item 0
Modified Bank Item ILT Exam Bank 0
Previous NRC Exam Other Exam Bank S.06.1.D Unit 1, Attachment 1 LLOT0550.08 259002 Importance: RO I SRO K5.01 3.1 13.1 1
Incorrect 1 ncorrect A
B C
D SBtI Basis or Justification SCRAM profile will swap controller to three element even if operator selected single element.
This is incorrect as FW will swap to single element when SCRAM profile is reset This is incorrect as FW will swap to single element at -20%
This is incorrect a controller will not remain in single element if single is selected (IF FW flow failure had caused swap to single element this would be correct).
This is incorrect a controller will not remain in single element if single is selected (IF FW flow failure had caused swap to single element this would be correct).
REQUIRED MATERIALS :
Notes and Comments:
This question relates to the LGS plant specific FW controllers.
Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
- 36.
Unit 1 plant conditions are as follows:
0 HPCl is in service for RPV pressure control (CST to CST) 0 FIC-055-1 R600 HPCI FLOW CONTROL VALVE AUTO/MAN switch is in AUTO HV-55-1 F008 HPCI, Test Loop Shutoff is throttled to maintain pump discharge pressure 150 psig over Reactor pressure.
0 The RO throttles HV-55-1 F008 in the closed direction for one second WHICH ONE of the following describes HPCl turbine speed and flowrate one minute later?
HPCl Turbine Speed Flowrate A.
No change Higher B.
Higher No change C.
Lower No change D.
No change Lower Page 72 of 200
Limerick Gene rat in g Station ILT05-I NRC Initial Licensinq Examination
~
Correct:
Incorrect Answer Key B
With Flow Controller in AUTO, system flow is maintained constant. IF F008 is throttled closed HPCl speed will need to increase to maintain the same flow Flow Controller is in Auto, maintaining system flow constant A
Choice I
Basis or Justification Incorrect D
Flow Controller is in Auto, maintaining system flow constant.
To maintain constant flow w/F008 throttled closed, speed goes up.
/c/
Incorrect Level of Knowledge High Difficulty Time Allowance PRA RO SRO 10CFR55.41 1 OCFR55.43 (minutes) 2.5 3
N y (W(7)
N I
Psvchometrics I
Source:
Reference( s ):
Learning 0 bjective:
New Exam Item Modified Bank Item ILT Exam Bank S55.1.D, note Step 4.4.3 LLOT0340.12 c]
Previous NRC Exam Other Exam Bank Source Documentation KnowledgetAbility WA 206000 HPCl Importance:
RO I SRO A I.09 3.4 t 3.5 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
~~
Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination
- 37.
Unit 1 plant conditions are as follows:
ADS Auto Inhibit switches are in NORM 0
RPV water level is -1 0 and lowering 0
RPV pressure is 400 psig and steady 0
Drywell pressure is 1.8 psig 0
Core Spray pumps I B and I D are running 0
Core Spray pumps 1 A and IC are tripped and cannot be started 0
ALL RHR pumps are tripped and cannot be started Subsequently, RPV water level drops to -1 33.
WHICH ONE of the following identifies the response of DIV 1 and DIV 3 ADS subsystems? (Assume no operator actions)
DIV I ADS DIV 3 ADS A. initiates after 105 second TD Will not initiate B. Initiates after 525 second TD Will not initiate C. Will not initiate Initiates after 105 second TD D. Will not initiate Initiates after 525 second TD Page 74 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination B
Correct:
DIV 1 ADS will not initiate without correct pumps running DIV 3 will initiate as described above Incorrect:
r D
Incorrect DIV 1 will not initiate is correct but, DIV 3 initiating after 525 seconds is incorrect as -129 and 1.68# conditions bypass 420 sec timer.
C Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 3.5 4
Y Y (b)(7)
A SRO I
OCFR55.43 N
Basis or Justification DIV 1 ADS will not initiate as no Div 1 Core Spray or RHR pumps are running DIV 3 will initiate as B & D core spray pumps are running 105 sec is correct as -129 and HI DW pressure are met.
DIV I will not initiate without correct pumps running DIV 3 will initiate as described above 209001 K3.02 Importance:
Reference(s):
Learning 0 bjective:
Knowledge/Ability K/A Source Documentation New Exam Item 0
ILT Exam Bank Previous NRC Exam 0
Other Exam Bank Modified Bank Item B21-1060 (ADS) Sh. 3 LLOT0350.04~
(Description of K&A, from catalog)
Knowledge of the effect that a loss or malfunction of core spray will have on the following: ADS Logic REQUIRED MATERIALS:
Notes and Comments:
Existing Question, Stem and Distractors Modified Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination
- 38.
Unit 1 plant conditions are as follows:
0 An ATWS has occurred 0
No operator actions are taken 0
Reactor level is -40 and slowly lowering Reactor power is 30% and slowly lowering Three minutes later Reactor power is 27% and slowly lowering.
WHICH ONE of the following identifies lights and alarms for the given con d it ions?
A. Squib valve continuity lights NOT lit; CORE SPRAY LINE INTERNAL BREAK alarm annunciated.
B. Squib valve continuity lights NOT lit, STANDBY LIQUID TANK LO-LO LEVEL alarm annunciated.
C. Squib valve continuity lights lit, RWCU SYSTEM ISOLATED alarm annunciated.
D. Squib valve continuity lights lit, DIV 1/11 RRCS CHANNEL ACTIVATED alarm annunciated.
Page 76 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Correct:
Incorrect Answer Key A
Squib valve continuity Light not lit is correct as 3 minutes after -40 is reached with power above 4% SLC will have initiated. Additionally injection will result in core spray line internal break alarm Is incorrect as SLC tank low-low level would not be alarming at this point.
B Choice I
Basis or Justification Incorrect Incorrect C
Squib valve continuity lights lit is wrong as SLC will have initiated D
Squib valve continuity lights lit is wrong as SLC will have initiated Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 3.0 3
Y Y (b)(5)
I I
SRO 1 OCFR55.43 N
Source:
Reference(s):
Learning Objective:
Knowledge/Ability WA NNew Exam Item 0
Modified Bank Item 0
ILT Exam Bank Previous NRC Exam 2001 c]
Other Exam Bank S48.1.B, section 4.0, ANN 11 3, B5 LLOT0310.06 21 1000 Importance: RO / SRO A1.10 3.7 / 3.7 REQUIRED MATERIALS:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILTO5-1 NRC Initial Licensinn Examination
- 39. Unit 2 plant conditions are as follows:
0 0
0 Turbine shell warming is in progress Turbine first stage pressure rises to 200 psig PIS-001-652A and D are lit on panels 10609 and lOC61 I in the Aux Equipment Room respectively WHICH ONE of the following identifies the plant response?
A. Full Reactor SCRAM on Turbine Stop Valve closure.
B. Full Reactor SCRAM on Turbine Control Valve closure.
C. Half SCRAM ONLY on Turbine Stop Valve closure.
D. Half SCRAM ONLY on Turbine Control Valve closure.
Page 78 of 200
Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination B
Correct:
Turbine control valve closure scram is wrong as turbine control valves are open to support shell warming Incorrect Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 4.5 3
Y y (b)(7)
Incorrect Incorrect SRO 1 OCFR55.43 N
I Basis or Justification I
212000 RPS K4.12 Importance:
RO / SRO 3.9 / 4.1 Cpp I This answer is wrong as a complete SCRAM will occur D
This answer is wrong as a complete SCRAM will occur Source:
Reference( s):
Learning 0 bject ive :
Knowledge/Ability KIA Source Documentation
[xi New Exam Item 0
Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank GP-2 Appendix 3, step 3.2.8 caution ANN 107, A2 LLOT0300.04 (Description of K&A, from catalog)
Knowledge of RPS design feature andlor interlocks which provide for bypassing of selected SCRAM signals (manually and automatically):
REQUIRED MATERIALS:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
- 40.
Unit 1 plant conditions are as follows:
0 Reactor power 100%
0 Reactor level 35 LT-42-IN004A Feedwater Narrow Range Level Transmitter fails downscale Subsequently, LT-42-IN004C Feedwater Narrow Range Level Transmitter fails upscale.
WHICH ONE of the following describes the impact, if any, on feedwater level control and Reactor level?
A.
B.
C.
D.
Feedwater Master Level Controller will swap to single element, Reactor level will go up.
Feedwater Master Level Controller will swap to single element, Reactor level will remain at 35.
Feedwater Master Level Controller will remain in three element, Reactor level will remain at 35.
Individual Reactor Feed Pump speed controllers will swap to manual, Reactor level will go up.
Page 80 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Knowledge High Answer Key Difficulty Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 3.5 3
Y Y (b)(7)
N Question ID# 040 Both RC Source:
Reference(s):
Learning Objective:
Choice Correct:
Incorrect:
Incorrect:
0 New Exam Item 0
Modified Bank Item 0
ILT Exam Bank S06.1.H U/1, Attachment 1 LLOT0550.1 OC Previous NRC Exam Other Exam Bank Incorrect:
Knowledge/Ability WA C
259001 Importance:
B D
swicj Basis or Justification A failure of two level transmitter (1/2 hour apart) will not result in a FW failure, Master level controller will remain in 3 element, and Reactor level will remain unchanged This is incorrect as FW will not swap to single element on level transmitter failures (1/2 hour apart), additionally level will remain at 35 This is incorrect as FW will not swap to single element on level transmitter failures (1/2 hour apart)
A failure of two level transmitters (1/2 hour apart) will not result in speed controllers swapping to manual (two failure simultaneously, or three failures would), additionally reactor level will not go up REQUIRED MATERIALS:
Notes and Comments:
Modified Question from LOR bank Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILTO5-I NRC Initial Licensing Examination
- 41.
Unit 1 plant conditions are as follows:
An ATWS is in progress 0
Reactor power is 50% and steady 0
Reactor water level is 35 and steady e
Reactor pressure is 1045 psig and steady RRCS DIV 1 B AND DIV 2A Manual Initiation Pushbuttons are armed and depressed.
WHICH ONE of the following identifies RRCS response?
A. ARI will initiate immediately.
B. Recirc Pumps will trip in 9 seconds.
C. SLC will initiate if APRMs are not downscale in 1 18 seconds.
D. DIV I / II RRCS annunciators will illuminate, ARI solenoids remain deenergized.
Page 82 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Choice Correct:
D Incorrect A
Answer Key Basis or Justification RRCS manual initiation requires depressing both pushbuttons in the SAME Division, the noted action (one pushbutton in separate divisions) will not initiate RRCS ARI will not initiate as RRCS is not initiated, and conditions for automatic initiation are not met Incorrect B
Recirc pump trip does not initiate from manual RRCS initiation, and conditions for automatic initiation are not met SLC will not initiate as RRCS is not initiated, and conditions for automatic initiation are not met I c l Incorrect Level of Knowledge Low I
Psvchometrics I
Difficulty Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 3.0 3
Y Y (b)(7)
N Source:
Reference(s):
Learning Objective:
Source Documentation New Exam Item 0
Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank GP-18 Attachment 4, ANN 004 F-5 LLOT0315.05 Knowledge/Ability KIA 21 2000 Importance:
RO I SRO A4.16 4.4 14.4 REQUIRED MATERIALS:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station ILT05-I NRC Initial Licensinq Examination
- 42.
Unit I plant conditions are as follows:
Reactor power is 100%
0 Normal Reactor Enclosure ventilation is in service 0
Both Standby Gas Treatment System fans are in AUTO Reactor water level master trip units, LIS-42-1 N681A and LIS-42-1 N681 B, fail downscale.
WHICH ONE of the following identifies the status of Standby Gas Treatment System (SGTS) five minutes later?
A. O A SGTS Fan and OB SGTS Fan running.
B. Only OA SGTS Fan running.
C. Only OB SGTS Fan running.
D. Both SGTS Fans off.
Page 84 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes)
I OCFR55.41 Answer Key SRO I
OCFR55.43 Question-ID# 042 Both RC Choice Correct:
I B
Incorrect:
Incorrect A
C
~~~
Incorrect:
D Basis or Justification A Reactor enclosure isolation and A SGTS start will occur on LIS-42-IN681A and B downscale failure Incorrect as B Fan will not start
_ _ _ _ ~
~
Incorrect as B Fan will not start Incorrect as A Fan will start Source :
Reference(s):
Learning Objective:
Knowledge/Ability WA Source Documentation New Exam Item Modified Bank Item 0
ILT Exam Bank Previous NRC Exam 0
Other Exam Bank ANN 004 E-I LLOT0200.1 OB 261 000 K6.08 Importance:
RO / SRO 3.1 /3.1 (Description of K&A, from catalog)
Knowledge of the effect that a Loss or Malfunction of the following will have on the SGTS system:
Reactor vessel level Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
- 43. Unit I plant conditions are as follows:
0 Reactor power is 100%
0 Reactor level is 35 A Condensate min flow controller malfunction results in the following:
0 Reactor Feed Pump (RFP) suction pressure drops to 230 psi for 6 seconds and then goes up to 250 psig WHICH ONE of the following identifies the subsequent Feedwater system status?
A. IA RFP is tripped, IB and IC RFPs are running.
B. 1 C RFP is tripped, 1A and 1 B RFPs are running.
C. I A
and 1 B RFPs are tripped, 1 C RFP is running.
D. All RFPs are tripped.
Page 86 of 200
Limerick Generating Station ILTO5-1 NRC Initial Licensinq Examination B
Answer Key Basis or Justification 1 C RFP will trip on Low suction after 5 seconds pressure due to suction pressure less than 233 psi for 5 Choice A
Correct:
1A RFP will not trip as C RFP trips first followed by 1 B at 10 seconds and 1A at 15 seconds Incorrect Level of Knowledge Incorrect Difficulty Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 Incorrect 256000 K1.02 Importance:
RO / SRO 3.3 f 3.3 1 B and 1A tripped is wrong as 1 C RFP will trip first 7
D All RFPs tripped is wrong as suction pressure stabilized prior to trip of all 3 1 RFPs Psychometrics Source:
Reference(s):
Learning Objective:
Knowledge/Ability KIA Source Documentation New Exam Item
[7 Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam Other Exam Bank ANN 104 Cond E-2 ANNS 102 Feed AI, BI, C1 LLOT0520.08 (Description of K&A, from catalog)
Knowledge of the Physical connections and/or cause - effect relationship between condensate system and the following: Reactor Feedwater System REQUIRED MATERIALS:
Notes and Comments Prepared By:
Rick Rhode (610) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensinn Examination
- 44.
Unit 1 has been scrammed due to a LOCA.
RClC auto-initiated following the SCRAM. Conditions are as follows:
0 0
RPV water level has recovered to +35 and is steady Drywell pressure is 2.5 psig and steady The CRS has directed that RClC be secured WHICH ONE of the following will shutdown the RClC turbine and leave RClC ready for auto injection?
A. Reset the RClC initiation signal seal-in.
Depress the RClC turbine manual isolation push button.
Close the RClC trip throttle valve (HV-50-112).
B. Depress the RClC turbine manual isolation pushbutton.
Close the RClC steam supply valve (HV-50-1 F045).
Reset the RClC trip throttle valve (HV-50-112).
C. Reset the RClC initiation signal seal-in.
Depress the RClC turbine trip pushbutton.
Close the RClC steam supply valve (HV-50-1 F045).
Reset the RClC trip throttle valve (HV-50-112).
D. Depress the RClC turbine trip pushbutton.
Place the RClC pump discharge flow controller in MANUAL.
Set the RClC pump discharge flow controller to 0%.
Close the RClC trip throttle valve (HV-50-112).
Page 88 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 2.5 3
Y y (bN7)
Answer Key SRO 1 OCFR55.43 N
Choice Source:
Reference(s):
Learning 0 bjective:
Correct:
New Exam Item 0
Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank S49.2A section 4.1, S49.1 C section 4.3 LOT0380.08 Incorrect KIA Incorrect Incorrect C
A B
D Basis or Justification Since the initiation signal is no longer present the operator can reset it, Trip the turbine and close the steam supply. Resetting the Trip throttle valve leaves RClC ready for auto injection Once the initiation signal is reset, the manual isolation will not work These steps will shutdown RCIC, but the isolation must be reset in order to be ready for auto injection These steps will shutdown RCIC if the initiation signal were still present.
RClC will not be ready to auto inject I Knowledge/Ability 21 7000 1 Importance:
RO / SRO (Description of K&A, from catalog)
Ability to manually operate and/or monitor in the control room
--Manually initiated controls Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station.
ILT05-1 NRC Initial Licensing Examination
Amber White Has Lifted Light Solenoid Energized Light Lit Not Lit A.
B.
Lit Lit C.
Not Lit Lit D.
Not Lit Not Lit Page 90 of 200
Limerick Generatinq Station ILT05-I NRC Initial Licensinq Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 10CFR55.41 Low 2.0 2
Y Y (b)(7)
Answer Kev SRO 1 OCFR55.43 N
Question I.D# 045 Both RC Knowledge/Ability WA Choice Correct:.
21 8000 Importance: RO / SRO A3.01 4.21 4.3 Incorrect A
Incorrect C
Incorrect D
Basis or Justification
~
During an automatic blowdown both amber has lifted (Acoustic monitor) and white solenoid (ADS Div I
& 3) lights will light.
This is incorrect as white solenoid energized light will be lit on ADS auto initiation This is incorrect as Amber has lifted light will be lit This is incorrect as both lights will be lifted if there was no increased Drywell pressure this would be true Source Documentation Source:
Reference(s):
Learning 0 bjective:
New Exam Item (7 Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank OT-114, ARC 110 B-2 LLOT0330.07a Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
- 46.
Unit I is operating at 100%.
An instrument failure results in an inadvertent RPV low-low level signal
(-38).
WHICH ONE of the following describes the response of the Bypass Leakage Barrier Blocks and Vents?
A. Instrument Gas Block Valves are closed and the vents are open.
B. Recirc Pump Seal Purge Block Valves are closed and the vents are open.
C. Main Steam Line Drain Block Valves are closed and the vents are open.
D. N2 Supply Block Valves are closed and the vents are open.
Page 92 of 200
Limerick Generating Station iLT05-1 NRC initial Licensing Examination Incorrect Answer Key C
This is incorrect as main steam line vent valves do not automatically open Choice I
Basis or Justification Level of Difficulty Time Allowance PRA Low 3.5 3
Y Knowledge (minutes)
Correct:
RO SRO 1 OCFR55.41 1 OCFR55.43 Y (b)(5)
N NZ Supply valve closes and vent valve opens on a Lo-Lo Reactor level l
D 1
signal (VIIIB) 223002 A2.05
~~
Incorrect:
1 A
1 This is incorrect as instrument gas block valves isolate at Lo-Lo-Lo Level Importance:
RO I SRO 3.31 3.6 This is incorrect as recirc vent valves do not automatically open on an isolation Incorrect Source:
Reference(s):
Learning Objective:
KnowledgeIAbility KIA Source Documentation 0
New Exam Item 0
Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam Other Exam Bank GP-8.1, Reactor Level 2-L0w, Low section LLOTOI 80.08d (Description of K&A, from catalog)
Ability to predict the impact of Nuclear Boiler Instrumentation failure on the primary containment isolations systemhuclear steam supply shutoff and base on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations.
!quired Materials:
Notes and Comments:
Modified LOR Bank Question Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
- 47.
D11 Diesel Generator is operating in parallel with the 101 Safeguard Bus with the following indications:
60Hz 2000Kw 1600 KVAR WHICH ONE of the following actions will restore the diesel generator within operating I i m its?
A. Place Speed Governor in RAISE to adjust real load to 2100 KW.
B. Place Speed Governor in LOWER to adjust real load to 1900 KW.
C. Place Voltage Regulator in RAISE to adjust reactive load to 1700 KVAR.
D. Place Voltage Regulator in LOWER to adjust reactive load to 1500 KVAR.
Page 94 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Choice Correct:
D Incorrect:
A Incorrect:
B Basis or Justification Reducing VARS to less than 1500 restores WARS to less than 75% KW, which corresponds to a Power Factor of 0.8 Raising KW would also restore the ratio of KVAR to KW, but KW would have to be raised to 2133 KW.
Lowering KW would make the D/G further from its operating limit.
Raising KVAR would also make the D/G further from its operating limit.
I c l Incorrect:
Level of Difficulty Time Allowance PRA Knowledge (minutes)
High 2.5 3
Y RO SRO 1 OCFR55.41 1 OCFR55.43 y (W7)
N
~
~
~~
Source Documentation Source:
New Exam Item Previous NRC Exam 0
Modified Bank Item Other Exam Bank Reference( s):
Learning Objective:
0 ILT Exam Bank S92.1.O, caution above step 4.5.5 LLOTO670.02 Required Materials:
KnowledgelAbility WA Notes and Comments 264000 Importance: RO / SRO A4.01 3.3 I 3.4 Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-I NRC Initial Licensing Examination
- 48.
Unit 1 plant conditions are as follows:
a I A CRD pump is in service 0
Reactor power is 100%
0 Reactor level is 35 A failure of a level instrument line results in the following annunciators:
EXCESS FLOW CHECK VALVE OPERATED C218 (1 12 E5) 0 DIV 3 REACTOR LO-LO-LO Level (1 13 E3)
WHICH ONE of the following identifies the effect, if any, on the CRD system and the action required to restore CRD, if any?
A. I A CRD pump trips.
Can be restarted from the MCR.
B. 1A CRD pump remains running.
No action required.
C. I A CRD pump trips and cannot be restored.
1 B CRD pump must be placed in-service from the MCR.
D. 1A CRD pump trips.
Can only be restarted from 4 KV switchgear.
Page 96 of 200
Limerick Generating Station ILT05-I NRC Initial Licensina Examination Correct:
Incorrect Incorrect Answer Key A
B C
Question Id# 048 Both R(
Incorrect D
Level of Knowledge High Basis or Justification Difficulty Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 2.5 3
Y y (b)(5)
N A CRD will trip due to Div Ill LOCA signal and LOCA load shed it can be restarted from the MCR This is incorrect as a CRD pump will trip due to Div Ill LOCA load shed Source:
Reference(s):
Learning 0 bjective:
This is incorrect as a CRD can be restarted ONew Exam Item 0
ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank Modified Bank Item SE-10, step 4.6 LLOT0660.05b This is incorrect as CRD can be restarted from the MCR KnowledgeIAbility WA 262001 Importance:
RO I SRO A2.02 3.6 I 3.9 Required Materials:
Notes and Comments:
This question was extensively modified from Question 373224 (ILT LERT EXAM 2005)
Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-I NRC Initial Licensinq Examination
- 49.
Unit 1 Plant conditions are as follows:
0 Reactor is scrammed 0
Reactor pressure is 600 psig 0
Division I DC is lost 0
Reactor water level is +I 15 Which one of the following can be used to lower Reactor pressure?
C. 1 J SRV from the AER.
D. 1 S SRV from the AER.
Page 98 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 3.0 3
Y Y (b)(7)
Answer Key SRO 1 OCFR55.43 N
Question ID# 049 Both RC Source:
Reference(s):
Learning 0 bjective:
Knowledge/Ability WA I
Choice New Exam Item Modified Bank Item ILT Exam Bank 0
Previous NRC Exam 0801#221 0
Other Exam Bank OT-I 10 Step 3.1.4 LLOTOI 20.12a 239002 Importance:
D Correct:
i A
Incorrect Incorrect I
B I
C Incorrect Basis or Justification S SRV is an ADS SRV and has power in the AER. While it is not one of the preferred SRVs (B,J,C) for use in OT-I I O, as the preferred SRVs are not available a non-preferred SRV is directed.
While B SRV is one of the preferred SRVs for use with high level it cannot be operated from the MCR due to the Loss of Div I DC While C SRV is one of the preferred SRVs for use with high level it cannot be operated from the MCR due to the Loss of Div I DC While J SRV is one of the preferred SRVs for use with high level, control is not availabre in the AER Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
~
~~
Limerick Genera t ing Stat ion ILT05-1 NRC Initial Licensing Examination
- 50.
Unit I plant conditions are as follows:
0 Reactor power is 100%
0 1A RECW pump is blocked for bearing replacement 0
1B RECW pump trips and cannot be restarted WHICH ONE of the following identifies the effect on the Reactor Recirc Pumps and required operator action?
A. Seal cavity temperature rises.
Reduce pump speed to maintain cavity temperature below 200OF.
B. Seal cavity temperature rises.
Trip the RECIRC pumps within I O minutes.
C. Pump motor temperature rises.
Trip the RECIRC pumps if motor winding temperature exceeds 20OoF.
D. Pump motor temperature rises.
Trip the RECIRC pumps within 10 minutes.
Page 100 of 200
Li mer ic k G e n e rat inq Stat ion ILT05-I NRC Initial Licensing Examination A
Answer Key On high seal cavity temperature ON-I 13 directs reducing speed to maintain temperature this occurs at a cavity temperature of 175OF not ZOOOF I
Choice I
Basis or Justification Incorrect:
Correct:
D Pump motor temperature is unaffected by a LOSS of RECW (DWCW supplies motor cooler)
Loss of RECW will result in an increase in seal cavity temperature ON-I 13 directs tripping a RECIRC pump within 10 minutes of a loss of RECW Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 2.5 3
Y Y (b)(5)
Incorrect:
SRO 1 OCFR55.43 N
202001 A2.17 Incorrect:
Importance:
RO / SRO 3.1 13.2 Pump motor temperature is unaffected by a LOSS of RECW (DWCW supplies motor cooler)
I I
I Source:
Reference(s):
Learning 0 bjective:
KnowledgelAbility KIA Source Documentation Ix] New Exam Item 0
Modified Bank Item c] ILT Exam Bank ON-I 13 step 2.1, S43.0.D LLOT0030.07b:
Previous NRC Exam 0
Other Exam Bank (Description of K&A, from catalog)
Ability to predict the impact of a loss of seal cooling water on the RECIRC system; and based on those predictions use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations.
Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station lLTO5-1 NRC Initial Licensing Examination 51, Unit 2 plant conditions are as follows:
2A RECW pump is running with its handswitch in AUTO after START 0
2B RECW pump is off with its handswitch in AUTO after STOP A complete Loss Of Offsite Power (LOOP) occurs.
All 4 KV systems operate as designed with all buses re-energizing SIMULTANEOUSLY.
WHICH ONE of the following describes the response of the RECW pumps?
A. 2A RECW pump auto re-starts.
2B RECW pump auto starts in standby.
B. 2 A RECW pump auto re-starts.
2B RECW pump does NOT auto start in standby.
C. 2A RECW pump does NOT auto re-start.
2B RECW pump auto starts in standby.
D. 2 A RECW pump does NOT auto re-start.
2B RECW pump does NOT auto start in standby.
Page 102 of 200
Limerick Generating Station ILTOS-1 NRC Initial Licensinq Examination A
Answer Key When their respective safeguard MCCs re-energized both RECW pumps auto start on low heat exchange outlet pressure Choice Correct:
C Incorrect 2A portion of this distractor is incorrect, 2B portion is correct for the reason stated above In correct D
Incorrect Both the 2A and 2B portions of this distractor are incorrect as stated above.
I Basis or Justification Level of Difficulty Time Allowance PRA RO Knowledge (mi nu tes) 1 OCFR55.41 Low 3.0 3
Y y (W(7)
SRO 1 OCFR55.43 N
2A portion of this distractor is correct, 28 portion is incorrect, for the reason stated above Knowledge/Ability K/A 400000 Importance: RO I SRO K4.01 3.4 / 3.9 Source Documentation Source:
Learning Objective:
New Exam Item Modified Bank Item ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank E-565 LLOT0460.07 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-I NRC Initial Licensinq Examination
- 52.
Unit 1 plant conditions are as follows:
0 Reactor startup is in progress 0
Reactor power is 20%
Control rod withdrawal is in progress.
WHICH ONE of the following will result in a rod withdraw block?
A. RBM upscale B. RBM downscale C. Control rod withdrawn past its withdraw limit D. RDCS Activities Control Disagree condition Page 104 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Incorrect to a malfunction of RMCS A
RBM upscale will not result in a rod block as Reactor power is less than 30%
Incorrect Incorrect B
RBM downscale will not result in a block as Reactor power is less than 30%
C CR withdraw will not result in a Rod block as Reactor power is above RWM LPSP (18%)
Level of Difficulty Time Allowance PFW RO Knowledge (minutes) 10CFR55.41 Low 3.0 3
Y Y (b)(7)
SRO 1 OCFR55.43 N
KnowledgelAbility 201 002 WA I K3.02 Source:
Reference(s):
Learning 0 bject ive:
Importance:
[XI New Exam Item 0
Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam Other Exam Bank S73.O.B, step 4.2 & note above step, ANN 108 D-4 LLOT0080.06 =
(Description of K&A, from catalog)
Knowledge of the effect that a loss or malfunction of RMCS will have on RBM Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
~
_~
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
- 53.
Unit 1 plant conditions are as follows:
0 Reactor STARTUP is in progress 0
Reactor power is 12?h Insert limit for current RWM rod group is 00 0
Withdraw limit for the current RWM rod group is 12 0
Control rod 10-39 is selected Control rod 10-39, the first rod of the current group, is withdrawn to position 14 with no further operator action taken.
WHICH ONE of the following identifies the ability to move control rod 10-39?
A. Control rod can be withdrawn and inserted without additional actions.
B. Control rod can only be inserted without additional action.
C. Control rod insertion capability requires rod to be bypassed in the RWM.
D. Control rod insertion or withdraw capability requires a substitute position to be entered into RWM.
Page 106 of 200
Limerick Generating Station ILT05-I NRC Initial Licensinq Examination Source Documentation Source:
New Exam Item 0
Previous NRC Exam I
0 Modified Bank Item 0
ILT Exam Bank 0
Other Exam Bank Refere n ce(s):
Learning LLOT0093f 0 bjective:
ON-I 23 step 2.12 Answer Key Incorrect Incorrect Incorrect A
Rod cannot be withdrawn as RWM will enforce a withdraw block C
Rod does not need to be bypassed to allow insertion D
This is not correct as substitute rod position is only used if there is no position indication Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 Low 3.0 3
N Y (b)(7)
SRO 1 OCFR55.43 N
Knowledge/Ability WA Required Materials:
201 006 Importance: RO / SRO K4.06 3.2 / 3.4 Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination
- 54.
Unit 1 plant conditions are as follows:
0 0
0 Reactor was scrammed due to a condensate line rupture.
Reactor level is -35 and lowering D I 24 safeguard load center transformer breaker tripped on over current The RO is directed to start Standby Liquid Control to augment Reactor level.
0 1A and IC SLC injection pumps are started and verified to be injecting WHICH ONE of the following describes the RWCU system response?
A. HV-44-1 F004 RWCU Outboard Suction Valve closes.
B. HV-44-1 FOOI RWCU Inboard Suction Valve closes.
C. HV-44-1 F004 RWCU Outboard Suction Valve and HV-44-1 FOOI RWCU Inboard Suction Valve close.
D. HV-44-1 F040 RWCU Inlet Suction Valve closes.
Page 108 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Incorrect Answer Kev A
~
Question ID# 054 Both RC Incorrect Choice D
Level of Knowledge High I C Incorrect Difficulty Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 3.0 3
N Y (b)(7)
N Source:
Reference( s):
Learning Objective:
sm Basis or Justification New Exam Item 0
Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank - LORT GP-8.1, Signal Y LLOTOI 10.05 A
or C SLC pump start close Fool valve as B was not started (D124 is power supply for the 73 pump) F004 did not close KnowledgelAbility KIA F004 does not close as B SLC pump did not start 204000 Importance: RO I SRO A3.03 3.6 13.6 While Fool did close answer is incorrect as F004 did not close due to B SLC pump not started F040 does not receive and isolation signal on SLC start I
Psvchometrics I
Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination
- 55.
Unit 1 plant conditions are as follows:
0 Reactor Power is 100%
0 lAY160 trips due to a ground fault 30 minutes later a Reactor SCRAM and turbine trip occur.
0 Reactor pressure is 900 psig and steady 0
Turbine speed is 300 RPM and dropping WHICH ONE of the following identifies the ability to lower Reactor pressure using the bypass valves?
A. Bypass valves cannot be used to control Reactor pressure.
B. Bypass valves can be opened by raising the Bypass Jack.
C. Bypass valves can be opened by lowering Pressure Set.
D. Bypass valves can be opened by raising Maximum Combined Flow.
Page 11 0 of 200
Limerick Generatinq Station ILTO5-1 NRC Initial Licensinn Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 Low 3.0 3
Y Y (b)(7)
Answer Key SRO N
1 OCFR55.43 Question ID# 055 Both RC Reference(s):
Learning 0 bjective:
Choice 0
ILT Exam Bank E-1AY160 Attachment #1 LLOT0560.01 Ok Correct:
Incorrect Incorrect Incorrect A
B C
D SR!
Basis or Justification Due to Loss of 1AY160 and PMG (Turbine speed 300 RPM) bypass will not operate Bypass jack will not operate due to loss of 1 AY160 Pressure set will not operate due to the loss of 1AY160 Raising max combine flow (1 15%) will not open bypass valves (CVs are closed)
Source Documentation Source:
I New Exam Item Previous NRC Exam KnowledgelAbility KIA 262002 K3.15 Importance: RO I SRO 2.6 12.7 (Description of K&A, from catalog)
Knowledge of the effect that a loss or malfunction of UPS will have on Main Turbine Operation Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station ILT05-I NRC Initial Licensing Examination
- 56.
A loss of instrument air is in progress on Unit I.
1 A and 1 B Instrument Air Headers are at 20 psig and lowering.
WHICH ONE of the following describes the response of Main Steam system valves?
A. Only Outboard MSIVs close.
All SRVs can be opened.
B. Only Inboard MSlVs close.
Only ADS and RSP SRVs can be opened.
C. Inboard and Outboard MSlVs close.
All SRVs can be opened.
D. Inboard and Outboard MSlVs close.
Only ADS and RSP SRVs can be opened Page 112 of 200
Limerick Generating Station ILT05-I NRC Initial Licensinq Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 Low 4.0 3
Y Y (b)(9)
Correct:
SRO 1 OCFR55.43 N
Incorrect I
300000 K1.03 Incorrect Importance:
RO / SRO 2.8 / 2.9 Incorrect D
A B
C Outboard MSIVs close on loss of instrument air inboard MSlVs close on loss of PClG (PCIG is lost due to loss of Instrument Air Only ADS and RSP SRVs have accumulator and can be opened with Loss of PClG This is incorrect as inboard MSlVs also close. Also non ADS SRVs cannot be opened from handswitches due to loss of PClG This is incorrect as outboard MSlVs also close This is incorrect as non-ADS SRVs cannot be opened from handswitches due to loss of PClG Source:
Reference(s):
Learning 0 bjective:
Knowledge/Ability WA Source Documentation
[XI New Exam Item 0
Modified Bank Item 0
ILT Exam Bank ON-I 19 Attachment 1 L LOT0730.08 0
Previous NRC Exam Other Exam Bank (Description of K&A, from catalog)
Knowledge of the connections and/or cause effect relationships between instrument air and containment air Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Limerick Generating Station lLTO5-1 NRC Initial Licensinq Examination
- 57.
Unit 1 plant conditions are as follows:
0 An ATWS is in progress 0
Reactor power is 40% and steady 0
Reactor level is -60 and steady A turbine trip occurs; and Reactor power remains at 40%.
WHICH ONE of the following identifies conditions that will result in a RRCS feedwater runback, and when the runback will occur?
A. Reactor pressure 1160 psig.
Runback occurs in 11 8 seconds.
B. Reactor pressure 1160 psig.
Runback occurs in 25 seconds.
C. Reactor pressure 1096 psig.
Runback occurs in 30 seconds.
D. Reactor pressure 1096 psig.
Runback occurs in 9 seconds.
Page 114 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PFW RO Knowledge (mi nu tes) 10CFR55.41 HIGH 3.0 3
Y NIA Answer Kev SRO 1 OCFR55.43 NIA Reactor pressure 1096 is incorrect (1 096 is the Reactor Scram setpoint) additionally 30 seconds is the Feedwater runback length once initiated I c i Incorrect Source:
Reference(s):
Learning Objective:
Reactor pressure 1096 is incorrect additionally 9 seconds is incorrect (9 seconds is the RRCS Recirc pump RPT Breaker time delay) i D i Incorrect New Exam Item Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank GE Elementary Drawing G31-I 020 LLOT0315.04 ARC 004, B-4 KnowledgelAbility WA 21 6000 Importance:
RO / SRO 2.4.50 3.3 13.3 Required Materials:
Notes and Comments:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ~
ILT05-1 NRC Initial Licensing Examination
- 58.
WHICH ONE of the following lists contains ONLY Non-Safeguard DC System loads?
A. Turbine Enclosure Area Rad Monitors Refuel Floor HVAC Isolation logic Primary RPS/UPS Inverter Power Recirc MG Set Emergency Lube Oil Pumps B. 13.2 KV Breaker Control Power Main Control Room Annunciator Emergency Lighting Panels Primary RPS/UPS inverter Power C. Primary APRM Inverter Power Reactor Enclosure HVAC Isolation logic 4KV Breaker Control Power RFP Emergency Lube Oil Pumps D. Recirc MG Set Emergency Lube Oil Pumps Primary APRM Inverter Power Emergency Lighting Panels Main Control Room Annunciator Page 11 6 of 200
Limerick Generating Station ILTO5-1 NRC Initial Licensing Examination Incorrect:
Answer Key A
Question ID# 058 Both RC Incorrect:
Choice C
I D Correct:
Level of Difficulty Time Allowance Knowledge (minutes)
Low 3.0 3
OCFR55.43 Y
(b) (7)
N Incorrect: ---
263000 K2.01 Importance:
RO / SRO 3.1 / 3.4 Basis or Justification All 4 loads are Now Safeguard DC Refuel Floor HVAC isolation logic and Primary RPS/UPS Inverter Power are Safeguard DC loads Primary RPS/UPS inverter Power is a Safeguard DC load Reactor Enclosure HVAC Isolation logic and 4KV Breaker Control Power are Safeguard DC loads Source:
Reference(s):
Learning 0 bject ive:
Knowledge/Ability KIA Source Documentation New Exam Item Modified Bank Item ILT Exam Bank 0
Previous NRC Exam Other Exam Bank E-33, Sh 1-3 E-619, Sh 1-3 LLOT0690.04 (Description of K&A, from catalog)
Knowledge of electrical power supplies to the following: Major DC loads Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination
- 59.
WHICH ONE of the following describes the reason Drywell Vacuum Relief Valves open?
A. Prevent drawing excess negative pressure in the Drywell.
B. Prevent drawing excess negative pressure in the Suppression Pool.
C. Equalize pressure between the SRV Downcomer and the Suppression Pool.
D. Ensure the Suppression Pool pressure remains higher than Drywell pressure.
Page 11 8 of 200
Limerick Generatinq Station I LT05-1 NRC Initial Licensing Examination Incorrect Incorrect Answer Key B
Vacuum Breaker Operate on to ensure Drywell is not drawn negative C
While some equalization will occur when Vacuum Breaker opens it is not the reason they open Choice I
Basis or Justification Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 Low 3.0 3
Y Y (b)(5)
Vacuum Breakers Relief's will open on Drywell Pressure lower than Suppression Pool Pressure Correct:
SRO 1 OCFR55.43 N
223001 K5.01 The exact opposite is true, as Vacuum Breakers relieve the higher Suppression Pool pressure to the Drywell.
Incorrect Importance:
Reference( s):
Learning 0 bjective:
Knowledge/Ability WA Source Documentation New Exam Item 0
Modified Bank Item
[XI ILT Exam Bank Previous NRC Exam 0999#119 0
Other Exam Bank ANN 114 G-I LLOTOI 30.02f (Description of K&A, from catalog)
Knowledge of the Operational implications of Vacuum Breaker/relief operations as applies to Primary Containment system and auxiliaries Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
- 60.
Unit 1 is at 100% power when the following alarm is received:
IDB-1 250V DC MCC UNDERVOLTAGE (122 G-2)
WHICH ONE of the following identifies the system that is no longer operable, and the required action?
A. ADS, station an Equipment Operator in the AER for SRV operation.
B. RPS, stop all B side RPS testing.
C. HPCI, declare HPCI INOPERABLE per Technical Specification.
D. RCIC, perform T-249 for RCIC.
Page 120 of 200
Limerick Generating Station lLTO5-1 NRC Initial Licensinq Examination Correct:
Incorrect:
C HPCl is INOP due to loss of power to initiation logic and MOVs on a loss of Div 2 DC, HPCl should be declared INOP as a result of the loss of initiation logic ADS is supplied by Div 1 and Div 3 DC A
Incorrect: r B
While B RPS will swap to its AC power source, it is still operable I
Incorrect:
D RClC is supplied by Div 1 and Div 3 DC Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 10CFR55.41 Low 3.5 3
Y Y (b) (IO)
Source:
Reference(s):
Learning Objective:
Knowledge/Ability WA Source Documentation New Exam Item Modified Bank Item ILT Exam Bank
[7 Previous NRC Exam 0
Other Exam Bank ARC-MCR-122 G2, ARC MCR-117 AI LLOT0690.02 263000 2.4.31 Importance:
RO I SRO 3.3 13.4 (Description of K&A, from catalog)
DC Electrical Distribution: Knowledge of annunciators alarms and indicationsland use of the response instructions Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
- 61.
WHICH ONE of the following identifies values for both frequency and voltage that will satisfy the requirement for a diesel generator breaker to automatically close in on its associated bus?
Frequency Voltaqe A.
56.2 Hz 4.1 KV B.
57.4 Hz 4.0 KV C.
58.6 Hz 3.9 KV D.
59.8 Hz 3.8 KV Page 122 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Correct:
Incorrect Incorrect Answer Key B
A C
Question ID# 061 Both RC Level of Difficulty Time Allowance PRA HIGH 3.5 4
Y Knowledge (minutes)
RO SRO 1 OCFR55.41 1 OCFR55.43 Y (b) (7)
N I D Incorrect 264000 A3.03 SQ>Q Basis or Justification Importance:
RO / SRO 3.4 J3.4 Frequency and Voltage are required to be 95% of rated in order to energize the Diesel Ready to Load relay and close the output Breaker. These values would be 57 Hz and 3.952 KV Voltage meets the requirement, Frequency does not Frequency meets the requirement, voltage does NOT Frequency meets the requirement, voltage does not Source:
Reference(s):
Learning 0 bj ect ive :
Knowledg eJAbility WA Source Documentation New Exam Item Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank E-I 64 LLOT0670.02. LLOT0660.04 (Description of K&A, from catalog)
Ability to monitor automatic operations of the Emergency Generators including: Indicating lights, meters and recorders Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination
- 62.
Unit 1 conditions are as follows:
0 Reactor is shutdown 0
Drywell pressure is 12 psig and steady 0
Reactor pressure is 430 psig and steady 1 A RHR is placed in Suppression Pool Spray.
Reactor pressure drops to 280 psig DIV 1 LPCl INJECTION VALVE DELTA P PERMISSIVE
( I 13A F4) annunciator is in alarm WHICH ONE of the following identifies the response of IA RHR?
A. Suppression Pool Spray automatically isolates and can be immediately re-established.
B. Suppression Pool Spray automatically isolates and cannot be re-established until I A LPCl Injection Valve is closed.
C. Suppression Pool Spray remains in service and must be manually secured to prevent pump runout.
D. Suppression Pool Spray remains in service and IA LPCl injection valve remains closed.
Page 124 of 200
Limer/ck Generating Station ILTO5-I NRC Initial Licensing Examination Incorrect Answer Key A
Question ID# 062 Both RC Incorrect Incorrect Choice B
D Correct:
Level of Difficulty Time Allowance PRA RO Knowledge (mi nu tes) 10CFR55.41 Low 4.0 3
Y y (b)(7)
C SRO I
OCFR55.43 230000 A4.02 Importance: RO / SRO 3.8/ 3.6 I
Basis or Justification LPCl Injection valve opens (Delta P ANN) as Suppression Pool Spray was placed in service after LPCl initiation signal was present (LOCA signal) it will not automatically isolate and must be manually secured to prevent pump runout with LPCl Injection valve open This is incorrect as spray does not isolate (LOCA) signal received previously) additionally, it cannot be re-established until LPCl injection valve is closed This is incorrect as spray does not isolate (LOCA signal received previously)
~
This is incorrect as LPCl injection valve will open (Delta P ANN)
+
Source: L Objective:
Source Documentation New Exam Item 0
Modified Bank Item 0
ILT Exam Bank c]
Previous NRC Exam 0
Other Exam Bank ARC-MCR-113 F4, T-225 step 4.2.2 LLOT0370.09 b (Description of K&A, from catalog)
Ability to manually operate and/or monitor in the control Room. Spray valves Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination ATTACHMENT: ON-I 26 Provided
- 63.
Unit 1 generator load has been raised in support of a PJM Grid Emergency.
Unit I Main Generator conditions are as follows:
1175MWe 0
Subsequently, I GEN HYDROGEN AND SEAL OIL SYS TROUBLE ALARM annunciates at 125 GEN.
An EO is dispatched and reports that generator hydrogen pressure is 60 psig and steady.
WHICH ONE of the following describes the required action(s)?
A. Raise hydrogen pressure to 65 psig.
B. Reduce generator output below I 125 MWe.
C. Reduce reactive load to 200 MVAR's lagging.
D. Perform a GP-4 Shutdown, trip the Main Turbine.
Page 126 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes)
I OCFR55.41 High 3.5 4
N Y (b)(5)
Answer Key SRO 1 OCFR55.43 N
Choice Correct:
Source:
Reference(s):
Learning 0 bjective:
Knowledge/Ability WA Incorrect:
New Exam Item 0
Modified Bank Item 0
ILT Exam Bank ON-126, Attachment 1 LLOT0600.10 Previous NRC Exam Other Exam Bank 245000 Importance: RO / SRO AI.Ol 2.7 / 2.7 Incorrect:
Incorrect:
B A
C D
Basis or Justification Reduction in real load to less than 1125 MWe will restore the MW /MWe output to a value consistent with the 60 psig H2 heating curve.
H2 Pressure would have to be restored to 75 psig in order to restore the MW/MWe output to within the armature heating curve.
Reducing MVAR will not reduce the MW/MWe output to within the armature heating curve.
A GP-4 Shutdown and trip of the Main Turbine would only be required if Hydrogen Pressure could not be maintained above 55 psig.
Required Materials:
ON-126 Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
- 64.
Unit 1 plant conditions are as follows:
0 Reactor power is 100%
A failure of 1 BY 185 occurs.
WHICH ONE of the following identifies the status of APRM and RPS?
APRMS RPS A.
Indicating 0% Power Full Scram B.
Indicating 100% Power Half Scram ONLY C.
Failed Downscale Full Scram D.
Failed Downscale Half Scram ONLY Page 128 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Knowledge Answer Key Difficulty Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 Question ID# 064 Both RC High Choice Correct:
3.5 3
N Y (b)(7)
N Incorrect Incorrect Incorrect B
A C
D Basis or Justification APRMs power supply is auctioneered, therefore, APRMs are still indicating on a loss of I BY185. Loss of 1 BY1 85 also results in a K SCRAM due to loss of power to 2 PRNMS voter units.
While APRMs would be indicating, this is incorrect because a full scram would not occur.
~~
This is incorrect because it requires a loss of both IAYI 85 and 1 BY185 for the APRMs to fail downscale. In addition, a full scram would not occur.
While a half scram would occur, this is incorrect because it requires a loss of both 1AY185 and 1BY185 for the APRMs to fail downscale.
Objective:
Source Documentation New Exam Item 0
Modified Bank Item ILT Exam Bank 0
Previous NRC Exam Other Exam Bank ANN 123 F-5, ANN 108 D-4, ANN 108 A-I LLOT0275. I 3c Knowledge/Ability I
21 5002 K2.03 Importance: RO I SRO 2.8 12.9
~~~~
~~
~
(Description of K&A, from catalog)
Knowledge of electrical power supplies to the APRM channels Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
- 65.
Plant conditions are as follows:
0 Control Room Ventilation system is operating in the normal mode A control room intake high radiation isolation signal is received on the ID channel ONLY.
WHICH ONE of the following describes the subsequent Control Room Ventilation system status?
CREFAS FAN RUNNING OUTSIDE AIR ENTERING MCR A.
OA Yes B.
O A No C.
OB Yes D.
OB No Page 130 of 200
Limerick Generatinq Station ILTO5-I NRC Initial Licensina Examination
~~~
Incorrect:
Question ID# 065 Both RC C
Choice Level of Difficulty Time Allowance PRA RO 1 OCFR55.41 Knowledge (minutes)
I D Correct:
SRO 1 OCFR55.43 Answer Key rFRq Basis or Justification D RAD Signal will start the OB Fan and result in normal CR ventilation isolation. It will not lineup the correct dampers to supply outside air to the MCR (Additional channel isolations needed)
Outside air will not be lined up as correct dampers to supply outside air to MCR are not opened on a D only isolation signal also OA Fan will not start on a D RAD signal OA Fan will not start on a D RAD signal 290003 K4.01 I A Incorrect:
Importance:
RO / SRO 3.1 / 3.2 l B Incorrect:
Same text as A distractor Source: I 0 bjective:
Source Documentation
[XI New Exam Item 0
Modified Bank Item ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank P&ID M-26 sht 5 detail D, M-78 sht 1 LLOT0450.7a Knowledge/Ability KIA (Description of K&A, from catalog)
Knowledge of Control Room HVAC: design features and/or interlocks which provide for system initiationdreconfiguration Recirculation System Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
- 66.
Unit 1 plant conditions are as follows:
0 Div II DC is deenergized 0
A digital feedwater malfunction is causing RPV level control problems 0
A GP-4 shutdown is performed Following the scram, RPV level drops and is automatically restored by RCIC.
WHICH ONE of the following describes the status of the IA and 1 B Reactor Recirc Pumps?
IA Recirc Pump 1 B Recirc Pump A.
Running Running B.
Running Tripped C.
Tripped Running D.
Tripped Tripped Page 132 of 200
Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination Level of Difficulty Time Allowance PRA RO HIGH 3.5 4
Y N
Knowledge (minutes) 1 OCFR55.41 Correct:
SRO 1 OCFR55.43 Y (b)( 5)
Incorrect:
r Incorrect:
Incorrect:
D A
B C
Basis or Justification RPT breaker logic will normally trip both RPTs on -38. RClC auto start indicates this parameter is reached. The loss of Div II DC will prevent one RPT breaker per pump from tripping, but the other one will trip and therefore, both pumps will be deenergized.
Neither pump will be running due to RPT breakers for both pumps tripping The I B will be tripped, however the 1A will also be tripped.
The 1A will be tripped, however the 1 B will also be tripped.
Source:
Reference( s):
Learning Objective:
Knowledge/Ability KIA Source Documentation HNew Exam Item OModified Bank Item 0
ILT Exam Bank Previous NRC Exam 0
Other Exam Bank (LOR)
E-I FB, ARC MCR 11 I C-5, ARC MCR 11 2 D-3, GP-18, step 1.O LLOT0315.06 2.4.21 I Importance:
RO / SRO 3.7/ 4.3 (Description of K&A, from catalog)
Knowledge of the parameters and logic used to assess the status of safety functions iquired Materials:
Notes and Comments:
Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
- 67.
Unit I plant conditions are as follows:
Drywell pressure 0.5 psig and rising 0
Reactor pressure 1045 psig and steady 0
HPCl room temperature 175OF and rising 0
SDV level in AER is 10% and rising WHICH ONE of the following alarms is consistent with the noted conditions?
A. DIV 1 DRYWELL HI PRESS ( I 13 E4)
B. REACTOR HI PRESSURE TRIP (107 G I )
C. B REAC ENCL HVAC PCL 1 BC208 TROUBLE (004 A3)
D. SCRAM DISCHARGE VOLUME HI LEVEL TRIP (107 C l )
Page 134 of 200
Limerick Generatinq Station ILTO5-1 NRC Initial Licensinq Examination C
Answer Key 1 BC208 panel trouble and HPCl room temp are consistent I
Choice D
I Basis or Justification SDV level is below the ALARM setpoint 1
Correct:
Level of Knowledge Low Incorrect:
Difficulty Time Allowance PRA RO SRO 10CFR55.41 1 OCFR55.43 (minutes) 3.5 3
N N
Y (b)(5)
I Incorrect:
Source:
Reference@):
Learning Objective:
Knowledge/Ability WA Incorrect: L New Exam Item 0
Modified Bank Item 0
ILT Exam Bank Modified 0
Previous NRC Exam Other Exam Bank ANNS 004 A3 LLOTI 560.02 2.4.46 Importance: RO / SRO 3.5 13.6 Drywell pressure value is below Alarm setpoint Reactor pressure valve is below the ALARM setpoint B l I
Psvc hometrics I
Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-I NRC Initial Licensing Examination
- 68.
Both units are at 100% when the following alarms:
0 LIQUID RADWASTE DISCHARGE HI RADIATION (003 A5)
The Radwaste Operator contacts the MCR and,reports the following in alarm in the Radwaste Control Room:
LIQUID RADWASTE DISCHARGE RAD MONITOR HIHI/INOP (OA304, C-1)
WHICH ONE of the following flowpaths will automatically isolate based on these conditions?
A. Equipment Drain Sample Tank Discharge to CST B. Waste Sludge Tank Discharge to External Processing C. Reactor Enclosure Floor Drain Sump Discharge to Liquid Radwaste D. Floor Drain Sample Tank Discharge to Cooling Tower Blowdown Line Page 136 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key Incorrect Incorrect I
Choice I
Basis or Justification B
Waste Sludge Tank to external processing isolates on Low Waste Sludge Tank level only (Pump off, discharge valve closes)
The only control functions associated with RE Floor Drain Sump pumps are Low-Low Level and Primary Containment Isolation Hi Rad Lockout (Post LOCA Rad Monitor Hi-Hi) will deenergize the pumps.
C Liquid Radwaste discharge to Cooling Tower Blowdown Line isolates on Hi I D l Hi Rad.
Correct:
Level of Difficulty Time Allowance PRA RO Low 3.0 3
N N
Knowledge (minutes) 1 OCFR55.41 Equipment Drain Sample Tank to CST isolates on EDST Level only (Pump off, discharge valve closes)
Incorrect SRO 1 OCFR55.43 N
Source:
Reference@):
New Exam Item 0
Modified Bank Item 0
ILT Exam Bank Previous NRC Exam 0
Other Exam Bank ARC-MCR-003 RAD-A-5, ARC-BOP-OAC304-C-1 Learning 0 bjective:
Knowledge/Ability WA I LL0T-0705-04 2.3.1 1 Importance:
RO / SRO 2.7 13.2 Notes and Comments Prepared By:
Rick Rhode (610) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
- 69.
An Equipment Operator (EO) is required to enter an area in the Main Condenser with a general area radiation level of 3 Rem/hr in order to perform a surveillance test.
The EOS radiation history is as follows:
0 1760 mRem cumulative exposure for the current year (TEDE) 0 I 9 Rem lifetime exposure to this date (TEDE) 0 NRC form 4 completed and on file 0
No dose extensions have been obtained The surveillance test will take 45 minutes to complete.
WHICH ONE of the following radiation exposure limits, if any, would be exceeded if the EO performs the surveillance test?
A. No limits are exceeded.
B. Administrative Dose Control Level ONLY.
C. Administrative Dose control Level AND NRC Exposure Limit ONLY.
D. Administrative Dose Control Level, NRC Exposure Limit, AND Emergency Exposure Limit.
Page I38 of 200
Limerick Generating Station lLT05-1 NRC Initial Licensinq Examination Level of Difficulty Time Allowance PRA RO High 3.0 4
Y N
Knowledge (minutes) 1 OCFR55.41 Answer Key SRO 1 OCFR55.43 Y (b)(4) auestion ID# 069 ROISRC Source:
Reference(s):
Learning Objective:
Choice 0
New Exam Item Modified Bank Item ILT Exam Bank Previous NRC Exam 2002 0
Other Exam Bank RP-AA-203 sects 4.1.I, 4.2,4.5 LLOTI 760.04,.05 Correct:
Incorrect Incorrect Incorrect B
A C
D Basis or Justification 3 Rem = 3000 mRem 3000 mRem X.75 = 2250 mRem 2250 mRem + 1760 mRem = 401 0 mRem 4010 mRem exceeds 2000 mRem TEDE Admin Dose Control Level Admin Dose Control Level is exceeded 4010 mRem <NRC Limit of 5000 mRem 4010 mRem <NRC Limit of 5000 mRem 401 0 mRem <Emergency Exposure Limit of 10,000 mRem for protecting station property KnowledgelAbility WA
2.3.4 Importance
RO / SRO 2.5 13.1 (Description of K&A, from catalog)
Knowledge of radiation exposure limits and contamination controVincluding permissible levels in excess of those authorized..
Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-I NRC Initial Licensinq Examination ATTACHMENT: GP-2, Appendix 1 Provided
- 70.
A reactor startup is in progress on Unit 2.
All Group I and Group 2 control rods are fully withdrawn.
SRM count rate data since the startup began is as follows:
0 Channel YA has gone from 240 cps to 975 cps 0
Channel 1 B has gone from 225 cps to 91 5 cps 0
Channel IC has gone from 220 cps to 890 cps 0
Channel ID has gone from 235 cps to 940 cps WHICH ONE of the following identifies control rod notch positions where control rod withdraw shall be restricted to single notch movement?
A. Between 00 and 08 B. Between I 2 and 7 8 C. Between 18 and 30 D. Between 30 and 48 Page 140 of 200
Li me rick Genera t i n g Station lLTO5-1 NRC Initial Licensing Examination Correct:
1 Answer Key A
Question ID# 070 Both RC Incorrect Incorrect Incorrect I
Choice B
C D
Level of Difficulty Time Allowance Knowledge (minutes)
Low 3.0 3
PRA RO SRO 1 OCFR55.41 1 OCFR55.43 N
N N
Basis or Justification After 75% rod density (Group 1-2 fully withdrawn), control rod withdraw between notch positions 00 to 12 shall be restricted to single notch movements until criticality is achieved. 00 to 08 falls within this band.
Single notch is require between 04 to 30 applies once the SRM count rate reaches four doublings. SRM count rate is only doubled at this point, so the 00 to 12 requirement still applies. 12 to 18 falls outside that band.
Due to the reasons stated above, the 00 to 12 requirement still applies. I 8 to 30 falls outside that band.
KnowledgelAbility WA Due to the reasons stated above, the 00 to 12 requirement still applies. 30 to 48 falls outside that band.
2.2.1 Importance
Reference( s):
Learning 0 bjective:
Source Documentation 0
New Exam Item 0
Modified Bank Item ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank GP-2, Appendix I, Caution after step 3.2.7 LLOTI 530.02 Required Materials:
GP-2, Appendix 1 Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station ILT05-I NRC Initial Licensing Examination
- 71.
Unit 1 PRO is performing ST-6-051-231-1, IA RHR Pump, Valve, and Flow Test.
At step 4.3.6, the PRO discovers that HV-51-1 F021A is incorrectly identified as HV-51-1 F022A.
WHICH ONE of the following identifies the status of the Surveillance Test and the action required to correct the error?
A. Stop the test. Identify the component number error in an action item to revise the procedure per AD-LG-101-1004, Procedure Performance Improvement System (PPIs), prior to resuming the ST.
B. Stop the test. Initiate a Temporary Change to correct the component number error per AD-LG-101-1002, Temporary Changes to Approved Documents and Partial Procedure Use, prior to resuming the ST.
C. Continue the test. When it is complete, identify the component number error in an action item to revise the procedure per AD-LG-101-1004, Procedure Performance Improvement System (PPIs).
D. Continue the test. When it is complete, initiate a Temporary Change to correct the component number error per AD-LG-101-1002, Temporary Changes to Approved Documents and Partial Procedure Use.
Page 142 of 200
Limerick Generating Station lLTO5-I NRC Initial Licensing Examination Level of Knowledge Answer Key Difficulty Question ID# 071 Both RC Low Choice 2.5 3
N Y (b)(lO)
Y (b)(3)
Correct:
Incorrect:
Incorrect:
Incorrect:
B A
C D
Basis or Justification The test must stop. An equipment number error requires a Temporary Change I.A.W. AD-LG-101-1002, before the test can continue.
The status of the test is correct, but the procedure process cited is not correct.
The procedure process cited is correct, however the test cannot continue.
~
~
Both the status of the test and the procedure process cited are incorrect.
Psychometrics I
SRo I
Time Allowance RO (minutes)
I pRA 1
Source:
Learning Objective:
Knowledge/Ability L
Source Documentation New Exam Item Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank AD-LG-I 01-1 002 LLOTI 570.01 2.2.1 1 1 Importance:
RO / SRO (Description of K&A, from catalog)
Knowledge of the process for controlling temporary changes.
Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station lLTO5-1 NRC Initial Licensinq Examination
- 72.
YA Reactor Feed Pump impeller needs to be repaired at power.
0 Only one manual valve is available for isolation of the pump suction 0
Pump suction pressure is 450 psig 0
Pump suction temperature is 36OoF WHICH ONE of the following clearance requirements will allow this work to be performed per OP-MA-109-1 OI?
.A. A clearance Technical Evaluation shall be performed.
B. The work shall be performed under an Exceptional Clearance.
C. A component walkdown shall be performed prior to application.
D. The single isolation valve shall be restrained and locked in the closed position.
Page 144 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Difficulty Time Allowance PRA RO (minutes) 1 OCFR55.41 2.5 3
N Y (b)(lO)
Answer Key SRO 1 OCFR55.43 N
Question ID# 072 Both RC 2.2.13 Choice Correct:
Importance: RO / SRO 3.6 13.8 Incorrect:
~
In correct:
Incorrect:
B A
C D
9FtQ Basis or Justification When 2-valve protection is required but not available then the clearance shall be designated as Exceptional.
A technical review is required only when there are questions about a systems response to the proposed isolation technique (such as logic system response)
A walkdown is suggested in circumstances where clearance information or documentation is missing or in question A Blocking device (such as a lock, restraint, or gag) is only required for a component that can fail to a position other than the tagged position.
Level of Knowledge Source:
Reference@):
Learning 0 bjective:
Knowledge/Ability WA Source Documentation New Exam Item Modified Bank Item 0
ILT Exam Bank Previous NRC Exam
[XI Other Exam Bank (CAT)
OP-MA-109-101, attachment 4 OP-MA-109-101 DB16 objective #2 (Description of K&A, from catalog)
Knowledge of Clearance and Tagging procedures Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-I NRC Initial Licensinq Examination
- 73.
Given the following values from the most recent P-I :
0 MFLCPR 0.954 0
MFLPD 1.015 0
MAPRAT 0.991 0
FLLLP 0.967 WHICH ONE of the following identifies the thermal limit(s) that require action, if any?
A. MFLPD ONLY.
D. All values are acceptable; no action is required.
Page 146 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO HIGH 2.5 3
N N
Knowledge (minutes) 1 OCFR55.41 Answer Key SRO I
OCFR55.43 N
Question'ID# 073 Both RC KIA I
Choice 3.0 13.0 Correct:
Incorrect:
Incorrect:
In correct:
r B
A C
D ggg Basis or Justification
~~
MFLPD (>I
.O) and MAPRAT (20.99) require entry into GP-14
~
MFLPD does require action (see above) but this choice omits MAPRAT, which also requires action
~
FLLLP does not require action MFLPD and MAPRAT require action Source:
Reference(s):
Learning Objective:
Source Documentation 0
New Exam Item 0
Modified NRC Bank Item ILT Exam Bank Previous NRC Exam Other Exam Bank (LOR-modified)
GP-5, Sect 3.1.I LLOT0741.04 KnowledgeIAbility 2.1.I9 I Importance:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensina Examination
- 74.
Unit I is in OPCON 2 with reactor startup in progress.
All IRMs are on Range 6 and reading as follows:
A - 37/125ths B - 23/125ths tC - 31/125ths D - 38/125ths E - 28/125ths F - 39/125ths G - 33/125ths H - 26/125ths WHICH ONE of the following identifies the Rod Block and RPS status if all IRM Range Switches are positioned to Range 5?
A. Control Rod Withdraw Block ONLY B. Control Rod Withdraw Block AND A side /2 Scram ONLY C. Control Rod Withdraw Block AND B side % Scram ONLY D. Control Rod Withdraw Block AND full Scram Page 148 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Correct:
Incorrect:
Incorrect:
I Answer Key C
A B
I Question ID# 074 Both RC c
~
Level of Knowledge High I
Choice Difficulty Time Allowance PRA RO SRO (minutes)
I OCFR55.41 1 OCFR55.43 3
3 Y
Y (b)(lO)
Y (b)(3)
Knowledge/Ability WA 1
Incorrect:
1 D
2.1.28 Importance:
RO / SRO 4.0 / 3.5 geq Basis or Justification Ranging from 6 to 5 will multiply all readings by 3.16, which will result in exceeding 120/125ths on channel IF. This channel inputs to B RPS resulting in a % scram. Any channel over 85/125ths results in a Rod Withdraw Block.
There will be a % scram on B RPS, in addition to the Rod Withdraw Block.
There will be a K scram on B, not A, RPS There will be a K scram on only B RPS I
Psychometrics I
I Source Documentation Source:
Reference(s):
Learning Objective:
New Exam Item 0
Modified Bank Item 0
ILT Exam Bank Tech Specs 2.2.1 and 3.3.6 LLOT0250.08,09 0
Previous NRC Exam Other Exam Bank Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-I NRC initial Licensing Examination
- 75.
Given the following conditions:
Both units are operating at full power The entire shift attended the morning Shift Turnover Meeting given by the Control Room Supervisor (CRS) and Shift Manager (SM)
At 1100, the 3rd RO relieves the Unit 2 RO for lunch.
The Unit 2 RO will be eating lunch in the Main Control Room (MCR)
Lunchroom.
WHICH ONE of the following identifies the required MINIMUM TURNOVER ACTIVITY and MAXIMUM DURATION of the RO's mid-shift turnover for the given conditions?
A. Read the MCR logs through the last previous day on shift.
The relief duration shall be a MAXIMUM of 30 minutes.
B. Read the MCR logs through the last previous day on shift.
The relief duration shall be a MAXIMUM of 60 minutes.
C. Review the Shift Turnover Checklist and review updated plant status.
The relief duration shall be a MAXIMUM of 30 minutes.
D. Review the Shift Turnover Checklist and review updated plant status.
The relief duration shall be a MAXIMUM of 60 minutes
' Page 150 of 200
Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination D
A B
-I+
Answer Key Basis or Justification Mid-shift turnover of less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> consists of a review of the Shift Turnover checklist and update of plant status, provided the original watch stander remains in the Main Control Room area Reading the MCR logs through the last previous day on shift applies to a full shift turnover, short turnover duration is 60 minutes, not 30.
Duration is correct, turnover criteria described applies to full turnover, not short duration Turnover criteria is correct, short turnover duration is 60 minutes, not 30 Choice Level of Difficulty Time Allowance PRA RO Knowledge (minutes)
I OCFR55.41 Low 2.5 3
N Y (b)(lO)
Correct:
SRO 1 OCFR55.43 N
Incorrect:
Source:
Reference(s):
Learning 0 bjective:
Incorrect:
New Exam Item Modified Bank Item 0
ILT Exam Bank OP-AA-112-101, Sect 4.1.7 LLOTI 574.24 Previous NRC Exam Other Exam Bank Incorrect:
KnowledgelAbility KIA
2.1.3 Importance
RO / SRO 3.0 13.4 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Stat ion ILTO5-1 NRC Initial Licensing Examination
- 76.
Unit 1 Plant conditions are as follows:
0 Reactor power is 100%
0 Reactor level is 35 and steady Narrow Range RPV Level Transmitters LT-042-1 N004A, B, and C suffer hardware failures with outputs at 0 mA, resulting in the following:
0 FEEDWATER FAILURE (107 D4) annunciator is in alarm WHICH ONE of the following identifies the effect on individual Reactor Feed Pump M/A stations: FIC-M 1-1 RGOIA(B,C) A(B,C) RFPT Speed Controllers, and the procedure entered to address initial plant response?
Effect on FIC-M1-I RGOIA(B,C)
Procedure Entered A. Swaps to Manual OT-I 00 B. Swaps to Manual OT-I I 0
C. Remains in Auto OT-I 00 D. Remains in Auto OT-I 10 Page 152 of 200
Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA Knowledge (minutes)
High 3.0 4
Y Answer Key RO SRO 1 OCFR55.41 I
OCFR55.43 y (b)(5) y (b)(5)
CQuestion ID# 076 SRO Or Source:
Reference (s):
Learning 0 bjective:
I Choice
[XI New Exam Item 0
Modified Bank Item 0
ILT Exam Bank S06.1.H U/1, Alarm Identity IXX-FW302.1TFFE S06.1.D U/1 Appendix 1 LLOT0550.1 Od 0
Previous NRC Exam 0
Other Exam Bank Correct:
Knowledge/Ability WA In correct:
259002 Importance: RO / SRO A2.03 3.6 I3.7 Incorrect Incorrect B
A C
D i
Basis or Justification With 3 level transmitters failed downscale, individual RFP MIA stations will automatically swap to manual. Additionally due to the failure of the level signal, the recirc pumps will run back. This combination of RFPs in manual coincident with a Recirc pump run back, result in level going up requiring in entry into OT-I I O REACTOR HIGH LEVEL This is incorrect as OT-100 REACTOR LOW LEVEL, is for low reactor level, Reactor level will go up This is incorrect as individual RFP M/A stations will swap to manual, and OT-I00 REACTOR LOW LEVEL, is for low reactor level, Reactor level will go up This is incorrect as individual RFP M/A stations will swap to manual.
(Description of K&A, from catalog)
Ability to predict the impact of the following on Reactor water level control and based on those predictions use procedures to correct, control or mitigate the consequence of those abnormal conditions or operations: Loss of Reactor Water Level Input.
bquired Materials:
Notes and Comments:
Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
- 77.
Unit 1 plant conditions are as follows:
0 Reactor power is 10%
0 Reactor level is -200 and lowering 0
All MSlVs are closed 0
Suppression Pool temperature is 12OoF and rising 0
A blowdown is in progress with 3 SRVs open 0
Reactor pressure is 650 psig and lowering The Floor Supervisor reports T-251 is complete for Unit I WHICH ONE of the following identifies the required operator action?
A. Immediately inject with HPCI.
Restore level to -60 to -1 00.
B. Immediately inject with HPCI.
Restore level to -1 61 to -1 86.
C. Inject with HPCl when Reactor pressure is below 400 psig.
Restore level to -60 to -1 00.
D. Inject with HPCl when Reactor pressure is below 400 psig.
Restore level to -1 61 to -1 86.
Page 154 of 200
Limerick Generating Statio n lLTO5-1 NRC Initial Licensinq Examination D
A Correct:
As Blowdown is already in progress, injection cannot occur until MIN ALT FLOODING PRESSUE is met. With only 3 SRVs open that occurs at 400 psig. Level band is -161 to -186 as Supp pool temp is greater than I10 degrees Injecting immediately is incorrect as Blowdown has already started. -60 to
-100 is incorrect as Supp pool temp is greater than 110 degrees Incorrect:
Incorrect B
Injecting immediately is incorrect as Blowdown has already started.
Level of Knowledge High Incorrect
-60 to -1 00 is incorrect as Supp pool temp is greater than 1 10 degrees Difficulty Time Allowance PRA RO SRO (minutes) 10CFR55.41 I
OCFR55.43 4.0 4
Y Y (b)(lO)
Y (b)(5)
I Psvchometrics I
Source:
Reference (s):
Learning Objective:
New Exam Item 0
Modified Bank Item 0
ILT Exam Bank T-I 17 BASES, Step LQ-21 LLOTI 560.05 0
Previous NRC Exam Other Exam Bank Source Documentation KnowledgelAbility KIA 295037 Importance:
RO I
- SRO, 2.1 2 0 4.3 14.2 T-I 17 Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station lLTO5-1 NRC Initial Licensinq Examination ATTACHMENT: SAMP-I I Sheet 1 Provided
- 78.
Unit 1 plant conditions are as follows:
SAMP-I and SAMP-2 have been entered The Reactor was shutdown 20 minutes ago Reactor Level is -320 and dropping Reactor pressure is 800 psig and steady RClC is injecting at 600 GPM ALL other high pressure injection systems are unavailable Suppression pool level is 22 Suppression pool pressure is 20 psig WHICH ONE of the following SAMP-I sheets must be executed?
A. Sheet 4 B. Sheet5 C. Sheet6 D. Sheet7 Page 156 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Knowledge High Answer Key Difficulty Time Allowance PRA RO SRO (minutes)
I OCFR55.41 1 OCFR55.43 4.0 4
Y Y (b)(l 0)
Y (b)(5)
Question ID# 078 SRO Or Source:
Reference( s):
Learning Objective:
Choice New Exam Item Modified Bank Item ILT Exam Bank 0
Previous NRC Exam Other Exam Bank (LOR)
SAMP 1, Sheet 1 LLOTI 562.6 Correct:
Knowledge/Ability WA Incorrect:
295031 Importance: RO I SRO 2.4.6 3.1 14.0 Incorrect Incorrect D
A B
C
/
Basis or Justification Sheet 7, To determine correct answer the candidate must determine that level cannot be restored to -31 1 (insufficient injection source are available for the current reactor pressure, AND attempts to blowdown as directed prior to reaching current reactor level must have been unsuccessful precluding use of low pressure systems), injection is unsafe as plotted on the MDRIR curve (20 minutes, Rx press 800 psig, injection rate 600 gpm), AND that conditions are unsafe as plotted on PSP curve (pool level 22, and pressure 20 psig).
Sheet 4 is incorrect as level cannot be restored above -31 1. The candidate must determine that insufficient injection source are available for the current Reactor pressure, AND attempts to blowdown as directed prior to reaching current reactor level must have been unsuccessful precluding use of low pressure systems.
Sheet 5 is incorrect as RPV injection is unsafe on MDRIR as plotted (20 minutes, Rx press 800 psig, injection rate 600 gpm)
Sheet 6 is incorrect as conditions are unsafe as plotted on PSP curve (pool level 22, and pressure 20 psig)
Required Materials:
SAMPI Sht 1 Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-I NRC Initial Licensing Examination ATTACHMENT: OT-I 12, Partial Provided
- 79.
Unit 1 Reactor Power is 100%.
The following transient occurs with the indicated plant conditions:
0 1B Recirc Pump trips 0
I A Recirc Pump speed is 65%
0 ALL four OPRM Operator Display Assemblies indicate Reactor power is 58%
0 XR-042-1 R613 indicates core plate differential pressure is 1.3 psid 0
XR-042-1 R613 indicates core flow is 42 x 1 O6 Ibm/hr WHICH ONE of the following is the required operator action?
A. Immediately Scram the Reactor B. Restart I B Recirc Pump, and raise core flow with I B Recirc Pump.
C. Reduce Recirc Pump speed to less than 60% and manually scram the reactor.
D. Insert control rods until the Restricted Region of the Power/Flow Map is exited.
Page 158 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
~
D A
Answer Key Because the speed of the operating Recirc Pump is >60%, the Core Flow and Reactor power indications provided should be used to determine operating point. With the given information, the plant is in the Restricted Region, and the correct action is an immediate exit by the insertion of control rods or the raising of Recirculation flow.
Immediately scram the reactor is not correct because the operating point is not in the Exclusion Region, therefore, a reactor scram is not required.
Choice Correct:
B Incorrect:
Restart 1 B Recirc Pump and raise core flow with 1 B recirc pump is wrong as restarting a pump to raise flow is not allowed in OT-I I 2 Incorrect C
Incorrect Reduce Recirc pump speed to less than 60% and manually scram the reactor is not correct as reducing speed drive the reactor further into the restricted region.
I Basis or Justification Level of Difficulty Time Allowance Knowledge (minutes)
OCFR55.41 1 OCFR55.43 High 3.0 5
N Y (b)(lO)
Y (b)(5)
Source:
Reference(s):
Learning Objective:
Knowledge/Ability WA New Exam Item Modified Bank Item ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank OT-I 12, Step 3.7 LLOT0040.07g 295001 Importance: RO / SRO AA2.01 3.5 f 3.8 OT-112, Power to Flow Maps Attachment 1 & 2 only Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination
- 80.
The Main Control Room has been abandoned due to a fire.
Equipment Operators are going to enter a locked high radiation area in order to manually operate Primary Containment Isolation Valves.
The highest dose rate in the area is 1250 mRem/hr.
Per RP-LG-460-1010 and RP-LG-460-1016, WHICH ONE of the following describes the type of Locked High Radiation Area and the highest level authorization required for issuing the key?
Tvpe of LHRA Highest Authorization Required A.
B.
C.
D.
Level 1 Level 1 Level 2 Level 2 Radiation Protection Manager Plant Manager Radiation Protection Manager Plant Manager Page 160 of 200
Limerick Generating Stat ion ILT05-I NRC Initial Licensina Examination Incorrect:
Answer Key B
Question ID# 080 SRO Or incorrect Correct:
C Level of Difficulty Time Allowance PRA RO Low 4.0 4
N N
Knowledge (minutes) 1 OCFR55.41 SRO 1 OCFR55.43 (b) (4)
I D Incorrect Source:
Reference(s):
Learning Objective:
Knowledge/Ability KIA Y
Basis or Justification 0
New Exam Item ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank Modified Bank Item RP-LG-460-1010, RP-LG-460-1016.
LLOTI 760.01 29501 6 Importance:
~~
The area is a Level 1 LHRA ( 2 1000 hr/hr and < I 5 Whr) per RP-LG-460-101 0. This requires authorization from the RP Manager for issuing the key per RP-LG-460-1016.
The level is correct, but the Plant Managers authorization is not required.
Level 2 LHRA would be an area with dose rate 2 15 Whr. The RP Manager may not be the sole authorization for this entry.
Level 2 LHRA would be an area with dose rate 2 15 Whr. The Plant Manager may authorization for this entry.
I I
Notes and Comments:
Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-I NRC Initial Licensing Examination
- 81.
Unit 2 is in OPCON 3 preparing for a refueling outage with the following conditions:
0 RPV Level is 85 0
0 0
0 0
0 2B loop of SDC is in service Reactor coolant temperature is 3OO0F RPV pressure is 54 psig
?A RHR Heat Exchanger is being drained for maintenance A Group I Isolation signal is in for I&C testing Cooling Tower draining is in progress An electrical fault causes a loss of 044k 1>22 MY&& 11131~b Subsequently, Reactor coolant temperature is 325OF and RPV pressure is 85 psig.
WHICH ONE of the following describes the action required and the procedure used to perform the required action?
A. Use dedicated LPCl Pumps for Shutdown Cooling per S51.8.H.
B. Line up for RHR Alternate Decay Heat Removal per S51.8.L.
C. Reduce RPV pressure using Main Steam Line Drains per ON-121.
D. Reduce RPV pressure using ADS SRVs per ON-I 21.
Page 162 of 200
Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination
~~
Correct:
Incorrect:
Answer Key D
RPV pressure is sufficient to cause a SDC isolation. Pressure must be reduced before SDC can be restored. The cooling tower draining makes the Main Condenser unavailable per ON-I 21 bases and therefore, pressure must be reduced with SRVs.
Dedicated LPCl Pumps will not work because SDC is isolated.
A Choice I
Basis or Justification Level of Difficulty Time Allowance PRA RO Knowledge (minutes)
I OCFR55.41 SRO 1 OCFR55.43 RHR Alternate SDC lineup will not work because current plant conditions will not support it.
I B
l Incorrect High Although this choice correctly identifies that RPV pressure must be reduced, MSL drains will not work because the condenser is not available.
i c i Incorrect 4.0 4
Y Y (b)(lO) y (b) (5) 295021 AA2.06 Importance: RO / SRO 3.2 / 3.3 Source:
Reference(s):
Learning 0 bjective:
Knowledge/Ability K/A Source Documentation New Exam Item Modified Bank Item ILT Exam Bank ON-121, Attachment 5 LLOT0370.13 Previous NRC Exam 0
Other Exam Bank (Description of K&A, from catalog)
Ability to determine and/or interpret the following as they apply to a loss of shutdown cooling: Reactor Pressure Required Materials:
Notes and Comments:
Prepared By:
Rick Rhode (61 0) 71 8-4085.
Limerick Regulatory Exam Author
Limerick Generating Station ILT05-I NRC Initial Licensing Examination ATTACHMENT: TURBINE BACKPRESSURE OPERATION LIMIT GRAPH Provided
- 82.
Unit 1 conditions are as follows:
0 Reactor Power is 75%
0 BESSI System is not in operation The following annunciators are received:
TURBINE HIGH BACK PRESSURE (106 D2) 1A CONDENSOR LO VACUUM (104 E-5)
The following parameters are observed:
0 LP Turbine Inlet Pressure is 100 psig 0
I A LP Turbine Back Pressure is 7.2 in Hg Abs 0
IB LP Turbine Back Pressure is 6.6 in Hg Abs 0
IC LP Turbine Back Pressure is 6.0 in Hg Abs 0
Main Condenser vacuum has dropped from 26 in Hg Vac to 23 in Hg Vac Main Condenser vacuum is 23 in Hg Vac and steady.
WHICH ONE of the following identifies the required operator action and the procedure used to perform the required action?
A: Trip the Main Turbine per GP-5.
B. Trip the Main Turbine per OT-I 16.
C. Reduce reactor power per GP-5.
D. Reduce reactor power per OT-I 16.
Page 164 of 200
Limerick Generating Station ILT05-I NRC initial Licensinn Examination Incorrect Answer Key D
Question ID# 082 SRO 01 Level of Difficulty Time Allowance Knowledge (minutes)
High 3.0 3
Choice PRA RO SRO 1 OCFR55.41 I
OCFR55.43 Y
Y (b) (IO)
Y (b) (5)
I C
Correct:
Source:
Reference( s ):
Learning Objective:
l A
Incorrect:
New Exam Item 0
Modified Bank Item ILT Exam Bank 0
Previous NRC Exam Other Exam Bank GP-5 Attachment 7 LLOT0500.06a I B Incorrect i
Basis or Justification Student must plot values on Turbine Backpressure Operation Limit Graph to determine that turbine is operating in the limited region and power must be reduced IAW GP-5 to restore backpressure to the unlimited region If turbine backpressure could not be restored, then a GP-4 Shutdown is directed. Tripping the turbine at this time is not directed.
Tripping the turbine is directed by OT-I 16 if Main Condenser vacuum reaches 21.5 in Hg Vac Reducing reactor power is directed by OT-I 16 until condenser vacuum stops dropping. Since vacuum is steady, a power reduction is not directed by OT-I 16 Knowledge/Ability 295002 WA 1 AA2.01
~
Importance:
RO / SRO 2.9 13.1 (Description of K&A, from catalog)
Ability to determine and/or interpret condenser vacuurn/absolute pressure as it applies to a loss of main condenser vacuum
!quired Materials:
TURBINE BACKPRESSURE OPERATION LIMIT GRAPH Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station lLTO5-I NRC Initial Licensing Examination
- 83. Unit 1 conditions are as follows:
0 Reactor power is 100%
0 HPCl is running in Full Flow Test for required surveillance WHICH ONE of the following identifies the Technical Specification limit for Suppression Pool temperature and the bases for the limit?
A. 105OF Provides sufficient temperature margin to allow SBLC injection to shutdown the reactor during an ATWS without exceeding HCTL.
B. 105OF Maintain bulk water temperature such that there is adequate NPSH for ECCS pumps following a blowdown.
C. 95OF Provides sufficient temperature margin to allow SBLC injection to shutdown the reactor during an ATWS without exceeding HCTL.
D. 95OF Maintain bulk water temperature such that there is adequate NPSH for ECCS pumps following a blowdown.
Page 166 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Incorrect Answer Key D
CQuestion ID# 083 SRO Or Level of Difficulty Time Allowance PRA RO Low 2.0 3
N N
Knowledge (minutes) 1 OCFR55.41 I
Choice SRO 1 OCFR55.43 Y (b)(2)
I Correct:
I B
Source:
Reference(s):
Learning Objective:
Knowledge/Ability WA i c Incorrect New Exam Item Modified Bank Item ILT Exam Bank Tech Spec basis 3.6.2.1 LLOTOI 30.04f Previous NRC Exam Other Exam Bank 29501 3 Importance:
RO / SRO 2.2.25 4.0 / 4.0 Basis or Justification Tech Spec 3.6.2.1 limits suppression pool max temperature to 105OF with testing that adds heat to the suppression pool. The basis for the limit is to maintain water temperature and suppression chamber conditions such that there is adequate NPSH for ECCS pumps following a blowdown.
The temperature limit is correct, however the basis is incorrect. This is the Trip Procedure basis suppression pool limit (1 10 degrees F) once T-I 02 or T-1 17 is entered.
This is the temperature limit for NO testing in progress that adds heat to the suppression pool and the Trip Bases temperature limit described above.
The Tech Spec basis is correct, however, the temperature limit is for NO testing in progress that adds heat to the suppression pool.
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
- 84.
A grid disturbance has caused as loss of power to the I O Station Aux Transformer and the 20 Regulating Transformer.
Conditions are as follows:
0 Unit 2 Reactor has scrammed 0
D23 and D24 Diesel Generators have started and are supplying their respective busses 0
021 and D22 Diesel Generators did NOT start On Unit 2, WHICH ONE of the following identifies an instrument that can be used to determine reactor pressure and the procedure entered due to the given conditions?
Instrument Procedure A. Wide Range PAMS E-1 B. Wide Range PAMS E-1 0/20 C. HPCl Steam Line Pressure E-1 D. HPCl Steam Line Pressure E-I 0/20 Page 168 of 200
Limerick Generating Station ILT05-I NRC Initial Licensing Examination Time Allowance PRA RO (minutes) 1 OCFR55.41 3
Y Y (b)(lO)
I SRO 1 OCFR55.43 Y (b)(5)
Correct:
Incorrect:
Source:
Reference( s ) :
Learning 0 bjective:
Knowiedge/Ability WA incorrect
[XI New Exam item 0
Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam c]
Other Exam Bank E-I, E-I 0/20 LLOT0275.13 295003 Importance:
RO / SRO AA2.02 4.2 / 4.3 Incorrect r---
D A
B C
I Basis or Justification Unit 2 is in a Loss of Offsite Power (E-l0/20). Due to the loss of D21 and D22, PAMS is not available. HPCl Steam Line Pressure is available on both units.
The procedure reference is not correct. PAMS is not available.
The procedure reference is correct. PAMS is not available.
The procedure reference is not correct. The instrument is correct.
Knowledge Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensina Examination
- 85.
Unit I plant conditions are as follows:
0 Reactor Power is 100%
0 A steam leak occurs in HPCl room 0
DIV 2 STEAM LEAK DET SYS HI TEMPmROUBLE (107, G5) annunciator is alarming Based on the given conditions, WHICH ONE of the following identifies RPV water level instrumentation that can be used and the T-200 procedures that are entered?
A.
B.
C.
- d.
RPV Water Level Instrument Wide Range Recorder XR42-I R623A on 1OC601 Wide Range Recorder XR42-I R623A on 1 OC601 Upset Range Recorder LR-42-1 R608 on I OC603 Upset Range Recorder LR-42-1 R608 on 1 OC603 Procedures Entered T-290, T-291 ONLY T-290, T-291, T-250 T-290, T-291 ONLY T-290, T-291, T-250 Page 170 of 200
Limerick Generating Station ILT05-I NRC Initial Licensinq Examination incorrect:
Answer Key A
1 Question ID# 085 SRO Or incorrect I
Choice C
Incorrect D
Level of Knowledge High i
Basis or Justification Difficulty Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 3.0 3
Y Y (b)(lO)
Y (b)(5)
A DIV I I steam leak detection alarm requires entry into T-103, which directs us of PAMs FZ and EQ PMS instruments only for reading Reactor Level.
XR42-1 R623A on I OC601 is a PAM and can be used, 1-290, T-291, and T-250 should be performed. In the case of T-250 The candidate must realize that the Div II alarms indicates that a temperature is above MNO which meets the conditions of stop sign SCC/T-4, requiring T-250 be performed per step SCC/T-5 XR42-1 R623A on 1 OC601 is correct, but, as noted above T-250 should be performed per step SCCTT-5 Source:
Reference(s):
LR-42-1 R608 on 1 OC601 is a not a PAM and cannot be used New Exam Item 17 Modified Bank Item 17 ILT Exam Bank T-291 Attachment 2 Previous NRC Exam 0
Other Exam Bank LR-42-1 R608 on 1 OC601 is a not a PAM and cannot be used WA I EA2.02 I
Psvchometrics I
3.3 13.5 Learning 0 bjective :
I LL0T1561.03 Knowledge/Ability I 295032 I Importance:
RO I SRO (Description of K&A, from catalog) Ability to determine and/or interpret equipment operability as it applies to high secondary containment area temperature
?quired Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-I NRC Initial Licensing Examination
- 86.
A LOCA is in progress on Unit 1 with the following conditions:
0 0
0 0
0 0
Drywell pressure is 24 psig and rising slowly Drywell temperature is 32OoF and rising slowly RPV pressure is 350 psig and dropping slowly Suppression Pool pressure is 19 psig and rising slowly Suppression Pool temperature is 96OF and rising slowly Suppression Pool level is 22' and rising slowly WHICH ONE of the following describes the required operator action and the basis for the required action?
A. Spray the Drywell per T-225 B. Perform an Emergency Blowdown per T-I12 C. Spray the Drywell per T-225 D. Perform an Emergency Blowdown per T-I 12 BAS IS Reduce containment pressure while preventing excessive negative pressure In the Drywell Transfer RPV energy to the Suppression Pool due to steam in the pool airspace preventing containment function Reduce containment temperature in order to prevent exceeding the Drywell tern pe ratu re limit Transfer RPV energy to the Suppression Pool before conditions threaten the integrity of the SRV tailpipes Page 172 of 200
Limerick Generating Station ILT05-I NRC Initial Licensinq Examination Incorrect Answer Key C
Question ID# 086 SRO Or Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 3.0 3
Y y (b)(lO)
Correct:
SRO I
OCFR55.43 Y (b)(5) 1 Incorrect:
I A
EA2.04 3.9 / 3.9 Incorrect u I
Basis or Justification
~~~
Suppression Pool Water level and pressure are in the UNSAFE region of the PSP Curve. T-I 02 directs a T-I 12 blowdown based on steam in the suppression pool airspace preventing pressure suppression function if conditions further degrade.
This is a legitimate reason for spraying the drywell if conditions supported this action. Current conditions are unsafe to spray.
This is a legitimate reason for spraying the drywell if conditions supported this action. Current conditions are unsafe to spray.
While the action is correct, the basis is not. At the given RPV pressure, Suppression Pool level would have to be 38.7 ft, in order to threaten the integrity of the SRV tailpipes.
Source:
Reference(s):
Learning 0 bj ect ive:
Knowledge/Ability WA Source Documentation New Exam Item ILT Exam Bank T-102, T-102 Bases LLOTI 560.06 0
Previous NRC Exam Other Exam Bank Modified Bank Item 295024 I Importance:
RO / SRO (Description of K&A, from catalog) Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE...Suppression Chamber Pressure REQUIRED MATERIALS:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
~~
~
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
- 87.
Unit 1 Plant conditions are as follows:
Reactor Power is 100%
0 I&C reports that IC Main Steam ine (R, SL) High Flow Transrr ters PDT-41-1 N088B and PDT-41-IN088C have failed their Surveillance Test 0
All other MSL Flow Transmitters are OPERABLE WHICH ONE of the following describes the status of the MSIV isolation logic and the required action?
A. Div 4 MSlV isolation logic is INOPERABLE.
Place ONE Channel in the tripped condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B. IC MSL MSlV isolation logic is INOPERABLE.
Place ONE Channel tripped condition within I 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
C. Div 1 and 2 MSlV isolation logic are INOPERABLE.
Place ONE Channel in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
D. Div 1 and 2 MSlV isolation logic are INOPERABLE.
Place ONE Channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Page 174 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Knowledge High Answer Key Difficulty Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 3.0 5
N Y (b)(5) y ( b P )
Question ID# 087 SR-0 Or Source:
Reference(s):
Learning 0 bjective:
I Choice
[XI New Exam Item 0
Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank Unit 1 Tech Specs, LCO 3.3.2 LLOTOI 80.1 OC Correct:
KnowledgeiAbility WA Incorrect:
Incorrect 223002 Importance: RO i SRO A2.08 2.7 i 3.1 I
I Incorrect D
A B
C I
Basis or Justification 88C is Div 1. 88B is Div 2. therefore there is only one Div 1 and Div 2 instrument operable for the 1 C MSL. Less than required number for 2 trip systems place one in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
If only one trip system is affected for instrumentation not common to RPS, and placing it in the tripped condition would not cause an isolation; you have 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> until having to place it in the tripped condition. If only one trip system were affected, this would be a correct answer.
A common misconception is that a streamline is a trip system. If only one trip system is affected for instrumentation common to RPS, and placing it in the tripped condition would not cause an isolation, you have 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> until having to place it in the tripped condition The number of affected systems per line is correct however the time to place in the tripped condition is wrong. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is for one trip system where placing it in the tripped condition will cause an isolation.
I Psvchometrics I
Source Documentation REQUIRED MATERIALS:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
- 88.
Unit 2 is in OPCON 5. Plant status is as follows:
Fuel Shuffle Part 2 is 80% complete in Quadrant IV The 201 Safeguards Transformer has been de-energized The 101 Safeguards Transformer is supplying all 4KV busses D21 and D23 Diesel Generators are INOPERABLE for planned maintenance Surveillance testing has just been completed on D24 Diesel Generator Control rod stroke timing is in progress in Quadrant II The C traversing in-core probe is being inserted into the RPV for a TIP Drive PMT Seal repair is in progress on a CRDM hydraulic line in the undervessel area The inside EO reports that the D24 Diesel Generator Fuel Oil Storage Tank indicates 32,500 gallons.
WHICH ONE of the following describes the action required by Tech Specs?
A. Stop control rod stroke timing.
B. Suspend all undervessel work.
C. Suspend operation of the overhead crane over the RPV.
D. Stop the traversing in-core probe PMT and withdraw probe from core.
Page 176 of 200
Limerick Generatina Station ILTO5-1 NRC Initial Licensing Examination Correct:
Answer Key 4-A Question ID# 088 SRO 01 Level of Difficulty Low 4.0 Knowledge Choice Time Allowance PRA RO SRO 1 OCFR55.41 1 OCFR55.43 (minutes) 4 Y
N Y (b)(2) 264000 2.2.22 I
B Incorrect:
Importance: RO / SRO 4.0 14.0 Incorrect Basis or Justification Tech Spec 3.8.1.2 requires suspension of Core Alterations with the AC electrical power sources inoperable in OPCON 5. Control rod movement with fuel in the vessel must be stopped.
Work on a CRDM hydraulic line does not qualify as an Operation with Potential for Draining the Vessel.
Operation of the Overhead Crane must be suspended over the Spent Fuel Pool but not over the Reactor Cavity.
Inserting a TIP is not considered a Core Alteration.
Source:
Reference(s):
Learning 0 bjective:
KnowledgelAbility WA Source Documentation New Exam Item 0
Modified Bank Item 0
ILT Exam Bank Tech Spec 3.8.1.2, GP-6.2 LLOT0670.13 Previous NRC Exam Other Exam Bank (Description of K&A, from catalog)
Knowledge of limiting conditions for operational and safety limits.
REQUIRED MATERIALS:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station ILT05-I NRC Initial Licensing Examination
- 89.
Unit 2 conditions are as follows:
0 An inadvertent Group I isolation resulted in MSlV closure and Scram 0
RClC is being used for pressure and level control 0
RClC is currently in injection mode and maintaining RPV level at 35 in Auto 0
RPV pressure is 900 psig and lowering slowly 0
ST-6-107-640-2, Rx Vessel Temperature And Pressure Monitoring, is in progress Subsequently, the RClC Flow Controller fails in AUTO.
The RClC Flow Controller is switched to MANUAL and adjusted so that level is
+35 and steady.
WHICH ONE of the following describes the operator action required to maintain RPV level over the next 30 minutes and the procedure used to perform the required action?
0 pe ra tor Action A. Throttle closed HV-49-2F013, RClC Pump Discharge to Feedwater B. Raise output of the RClC flow Controller C. Throttle open HV-49-2F013, RClC Pump Discharge to Feedwater D. Lower output of the RClC flow Controller Procedure S49.7.A, Transfer of RClC From Pressure Control Mode to Injection Mode and Back OP-LG-I 08-1 01-1 001, Simple Quick Actsnransient Acts S49.7.A, Transfer of RClC From Pressure Control Mode to Injection Mode and Back OP-LG-108-101-1001, Simple Quick Actsnransient Acts Page 178 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination D
A B
C Answer Key With the RClC flow controller in MANUAL, it is maintaining constant speed.
With the turbine at constant speed, as, RPV pressure goes down, injection will rise and RPV level will rise. The controller output must be lowered to reduce turbine speed. This is a simple quick act per OP-LG-108-101-1001.
This valve would be closed to transfer to pressure control mode. Given the conditions, pressure is going down with just the steam used to drive RCIC, therefore, level will go up. Transfer to pressure control would not be appropriate. The procedure would be appropriate if this were the correct action.
Raising RClC controller output would only exacerbate the level trend that will result from the given conditions. The procedure would be appropriate if this were the correct action.
This valve would be opened to transfer from level control to pressure to pressure control mode. The procedure would be appropriate if this were the correct action.
Choice Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 3.0 3
Y y (b)(5)
I Basis or Justification SRO 1 OCFR55.43 y W(5)
Correct:
Source:
Reference( s):
Learning 0 bjective:
I n correct:
New Exam Item Modified Bank Item c] ILT Exam Bank 0
Previous NRC Exam Other Exam Bank S49.7.A LLOT0380.08 Incorrect Knowledge/Ability WA Incorrect 21 7000 Importance:
!QUIRED MATERIALS:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination
- 90.
Unit 1 Plant conditions are as follows:
0 Reactor Power is 100%
0 An electrical fault on a turbine control valve solenoid results in the closure of the #2 Turbine Control Valve WHICH ONE of the following identifies the initial EHC response and the requ i red p roced u ra I act ions?
Initial EHC Response Procedural Action A. BPV(s) remain closed, reactor Reduce reactor power to less than 90% per OT-I02 pressure rises to Scram setpoint without operator action B. BPV(s) remain closed, reactor Reduce reactor power until pressure is less than 1053 psig per OT-I 04 pressure rises to Scram setpoint without operator action C. BPV(s) open, reactor pressure rises and stabilizes without operator action Reduce reactor power to less than 90% per OT-I02 D. BPV(s) open, reactor pressure rises and stabilizes without operator action per OT-I 04 Reduce reactor power until pressure is less than I053 psig Page 180 of 200
Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Knowledge High
'3.0 Answer Key Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 4
N y (b)(5) y Question ID# 090 SRO-Or Knowledge/Ability WA Choice Correct:
241 000 Importance: RO / SRO A2.04 3.7 / 3.8 Incorrect:
Incorrect t---
Incorrect C
A B
D I
Basis or Justification Reactor pressure will increase slightly requiring entry into OT-I 02. OT-I02 requires power to be lowered to below 90% on a control valve closure.
This is incorrect as Reactor pressure will not reach the scram setpoint.
Electrical failure of the solenoid for the control valve does not affect bypass valve response. The procedural action is correct.
This is incorrect as Reactor pressure will not reach the scram setpoint.
Electrical failure of the solenoid for the control valve does not affect bypass valve response. While power may rise slightly, if OT-104 were entered, it does NOT reference pressure.
The pressure response is correct, however the procedural action is not.
While power may rise slightly, if OT-I04 were entered, it does NOT reference pressure.
Source :
Reference(s):
Learning 0 bjective:
Source Documentation New Exam Item 0
Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam c]
Other Exam Bank OT-102, step 3.5 T.S. 3.2.3.b LLOT0590.02a Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-I NRC Initial Licensing Examination
- 91.
Unit I plant conditions are as follows:
0 95%power 0 I C RHR pump has been INOP for 19 days HPCl Full Flow Test is being performed. Maximum flow flow achieved is 5150 gpm.
WHICH ONE of the following describes the required Tech Spec actions?
A. Be in STARTUP in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, HOT SHUTDOWN in the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN in the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B. Restore the IC RHR Pump to operable within the next 1 I days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN in the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
C. Restore the 1 C RHR pump or the HPCl system to operable within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in HOT SHUTDOWN in the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN in the next +%hours.
r,/3(ob a4 D. Restore the HPCl system to operable within 14 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and reduce reactor steam dome pressure to 5 200 psig within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Page 182 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO Low 3.0 4
Y N
Knowledge (minutes) 1 OCFR55.41 Answer Key SRO 1 OCFR55.43 Y (b)(2)(5)
Choice Source:
Reference(s):
Learning Objective:
Correct:
UNew Exam Item Modified Bank Item ILT Exam Bank T. S. 3.5.1.b and 3.5.1.c.2 LLOT0340.16 0
Previous NRC Exam Other Exam Bank (LOR modified)
Incorrect:
Knowledge/Ability KIA Incorrect 206000 Importance: RO I SRO 2.1.12 2.9 14.0 Incorrect C
A B
D jr Basis or Justification Tech Spec 3.5.1 -with HPCl system INOP and one ECCS Subsystem INOP - Restore one of them to OPERABLE within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> This is a Tech Spec 3.0.3 action applicable only when LCOs cannot be met This would be the correct action if HPCI were operable.
This would be correct if IC RHR were operable with HPCl INOP Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station lLTO5-1 NRC Initial Licensing Examination ATTACHMENT: EAL Matrix Provided
- 92.
Units 2 plant conditions are as follows:
A steam leak is in progress in the Outboard MSlV Room 0
Outboard MSlV room temperature is 18OoF and steady No other areas are exceeding Maximum Safe Operating temperatures Security reports the blowout panel from the steam chase to the North Stack has actuated The reactor is manually scrammed All efforts to isolate the leak have failed Field Team Monitoring reports that the dose rate has been 200 mRem/hr TEDE at the Site Boundary for the last hour, WHICH ONE of the following identifies the TRIP procedure(s) that require(s) entry and if an Emergency Blowdown is required per T-I 12?
TRIP Procedure Entry T-I 12 Emerqency Required Blowdown Required A.
T-I03 ONLY B.
T-I03 ONLY Yes No C.
T-I 03 AND T-I 04 Yes D.
T-I 03 AND T-I 04 No Page 184 of 200
Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 3.0 3
N Y (b) 10 Answer Key SRO 1 OCFR55.43 y (b)(5)
Question ID# 092 SRO Or Source:
Reference(s):
Learning 0 bjective:
I Choice 0
New Exam Item Modified Bank Item 0
ILT Exam Bank
[XI Previous NRC Exam 0
Other Exam Bank Emergency Action Level Matrix (Table 3-I), T-103, T-I04 LLOTl560.02,06 Correct:
KnowledgelAbility WA Incorrect:
I n cor re ct
2.4.1 Importance
RO I SRO 2.3 14.1 I n correct D
A B
C
/
Basis or Justification Site boundary release is at Site Area Emergency level, therefore entry into T-104 is required per EAL Matrix. Release is not at or approaching General Emergency level and 2 areas are not exceeding MSO, therefore T-112 is not required.
T-I04 entry is required and T-I 12 is not for the reasons given above.
T-104 entry is required for the reason given above.
T-I 12 is not required for the reason given above Required Materials:
EAL Matrix Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick GeneratinQ Station ILT05-I NRC Initial Licensinq Examination ATTACHMENT: T-228, Partial Provided
- 93.
Unit 1 plant conditions are as follows:
0 A LOCA occurred 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago 0 T-I 01 and T-I 02 have been implemented T-I02 has directed inerting/purging the Drywell Suppression Pool level is 24 Feet 0 Drywell pressure is 2 psig The following containment parameters exists:
0 DW Ha is 5% and increasing 0 DW 0 2 is 4% and increasing SP HZ is 3% and increasing 0 SP 0 2 is 2% and increasing WHICH ONE of the following identifies the preferred method of Drywell inerting/purging, if any?
A. Drywell purge with air.
B. Drywell inerting with nitrogen (Low Flow Mode).
C. Drywell inerting with nitrogen (High Flow Mode).
D. Drywell purging is not required until Drywell 0 2 exceeds 5%.
Page 186 of 200
Limerick Generatinq Station ILT05-I NRC Initial Licensing Examination Level of Difficulty Time Allowance Knowledge (minutes)
Answer Key PRA RO SRO 1 OCFR55.41 1 OCFR55.43 Basis or Justification Source:
Reference(s):
Learning 0 bjective:
~~
~~
~~
Per T-228, Drywell inerting with Low Flow and High Flow are allowed given the conditions. Low Flow is the preferred flowpath per the note in section 4.3 and Table 1. per T-228 Not allowed due to high drywell pressure (>.75 psig)
New Exam Item 0
Modified Bank Item ILT Exam Bank 0
Previous NRC Exam Other Exam Bank T-228 section 4.3, 4.5 and 4.6 LLOTI 561 -03 Allowed but not preferred per the note in section 4.3 and Table 1 of T-228 Knowledge/Ability K/A Does not apply to the given conditions
2.3.9 Importance
RO I SRO 2.5 13.4 Required Materials:
T-228 Assessment Table, and section first pages Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatina Station ILT05-I NRC Initial Licensinq Examination
- 94.
Unit 1 plant conditions are as follows:
0 35%power 0
Control rod scram time testing is in progress per ST-6-107-790-1 0
All Unit 1 control rods are OPERABLE 0
Control rod 30-31 is withdrawn from position 12 to position 48 to support scram time testing The following sequence of events occur:
13:OO:OO - Control rod HCU toggle switches A and B for Rod 30-31 are 13:00:08 - Control rod 30-31 is at Position 1.88 05 WHICH ONE of the following describes the required action?
taken to TEST and then immediately back to NORMAL a
A. Restore Control Rod 30-31 to position 12.
B. Disarm HCU 30-31 Directional Control Valves.
C. Demonstrate insertion capability and restore Control Rod 30-31 to position 12.
D. Demonstrate insertion capability and restore Control Rod 30-31 to position 48.
Page 188 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA Low 3.0 3
N Knowledge (minutes)
Answer Key
?a RO SRO 10CFR55.41 1 OCFR55.43 Y (b)(10) y (b)(2)
Question ID# 094 SRO Or 201 002 2.1.32 Choice Importance:
I nco rrect :
A B
I D Incorrect Basis or Justification T.S 3.1.3.2 determines that 30-31 is INOP due to Scram time exceeding 7 seconds. T.S. 3.1.3.1 Action b.1.
J 30-31 is not OPERABLE, therefore it cannot just be regored to position 12.
The rod is INOP, While 30-31 must have insertion capability demonstrated, its original position is 12, not 48.
Source:
Reference(s):
Learning 0 bjective:
Knowledge/Ability WA Source Documentation New Exam Item 0
Modified Bank Item ILT Exam Bank TS 3.1.3.2 AND 3.1.3.1 LLOT0060.12 Previous NRC Exam Other Exam Bank (Description of K&A, from catalog)
Ability to explain and apply system limits and precautions.
Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
- 95.
The CRS directed a manual scram on Unit 2 from 100% power due to a stuck open SRV.
The scram was unsuccessful and RRCS was manually initiated.
Immediately after RRCS initiation, reactor power dropped to I
.2% on all APRMs.
Currently, Unit 2 plant conditions are as follows:
0 All APRMs indicate 1.2%
0 All IRMs are on Range 6 and stable 0
All SRM count rates are 55,000 cps and stable 0
ALL blue SCRAM lights are lit on the Full Core Display 0
Suppression Pool temperature is 108F and rising WHICH ONE of the following describes the correct mitigation strategy for control rod insertion and SLC?
Control Rods SLC A. Perform T-217 and T-218 Do NOT inject SLC B. Perform T-217 and T-218 Manually inject SLC C. Perform T-213, T-215, T-216, Do NOT inject SLC and T-219 D. Perform T-213, T-215, T-216, Manually inject SLC and T-219 Page 190 of 200
Limerick Gene rating Station ILT05-1 NRC Initial Licensinq Examination Psychometrics Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 1 OCFR55.41 1 OCFR55.43 5
High 3.5 4
Y b 10 Y b 5 Answer Key 2.4.6 Question ID# 095 SRO Or Importance:
Choice 1
Correct:
I Incorrect:
Incorrect Incorrect B
A C
D Basis or Justification The Blue scram lights lit indicate that Scram solenoid valves are open, which requires 1-217 and T-218. The given conditions indicate that the reactor is not shutdown, therefore, before Suppression Pool Temperature reaches 1 IOOF, SLC injection is required per T-1 01.
While T-217 and T-218 are required, T-I01 requires SLC injection.
T-213, T-215, T-216, and T-219 are not required because the scram valves are open. In addition, T-101 requires SLC injection.
While SLC injection is required per T-101; T-213, T-215, T-216, and T-219 are not required because the scram valves are open.
1 Source: I Learning 0 bjective:
Knowledge/Ability I WA Source Documentation 0
New Exam Item 0
ILT Exam Bank Previous NRC Exam Other Exam Bank Modified Bank Item T-I 01 LLOTI 560.06 (Description of K&A, from catalog)
Knowledge of symptom based EOP mitigation strategies.
~~
~~
Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
- 96.
WHICH ONE of the following identifies Work Execution Centerwork Control Center Supervisor (WCS) staffing requirements per OP-AA-I 01-1 1 I and OP-LG-101-111?
A. WCS may be credited as Shift Technical Advisor and Incident Assessor simultaneously.
B. WCS may be credited as Incident Assessor and NRC Communicator simultaneously.
C. If the WCS is credited as Shift Technical Advisor then Incident Assessor function is NOT required.
D. If the WCS is credited as Incident Assessor then Shift Technical Advisor function is NOT required.
Page 192 of 200
Limerick Gen erati nq Station ILT05-1 NRC Initial Licensing Examination I
~~
Answer Key Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 Question ID# 096 SRO Or SRO 1 OCFR55.43 I
Choice Low 1
Correct:
2.0 3
N N
Y (b)(2) 1 Incorrect:
I Incorrect I
Incorrect C
A B
D i
Basis or Justification
~
~
~~
If WCS is STA then IA function is not required (OP-AA-101-1 I 1, 4.5.2)
~
WCS cannot be both STA and IA (OP-LG-I 01-1 11, Attachment 3)
~~
WCS cannot be both IA and NRC Communicator (OP-LG-101-1 1 I, )
If WCS is the IA, they support the STA function, the STA is stili required Source:
Reference(s):
Learning 0 bjective:
Knowledge/Abiiity KIA Source Documentation New Exam item 0
Modified Bank item 0
ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank OP-AA-101-11 I, page 5, step 4.5 OP-LG-101-111, page 11 #3 LLOTI 574.01 a
2.1.4 importance
RO / SRO 2.3 f 3.4 (Description of K&A, from catalog)
Knowledge of Shift Staffing requirements Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
~~
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
- 97.
The A Chlorine detector fails upscale.
Subsequently, a loss of Div 3 DC power occurs.
WHICH ONE of the following describes the status of the A CREFAS Fan and the procedure entered?
A CREFAS Fan Procedure A.
Running S78.0.B Verification of MCR HVAC Isolation Signal B.
Not Running S78.0.B Verification of MCR HVAC Isolation Signal C.
Running S78.8.A Manual Initiation of MCR HVAC Isolation D.
Not Running S78.8.A Manual Initiation of MCR HVAC Isolation Page 194 of 200
Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO High 3.0 4
N N
Knowledge (minutes) 1 OCFR55.41 Answer Key SRO 1 OCFR55.43 Y (b)(5)
Question ID# 097 SRO Or 290003 A2.01 I
Choice Importance:
Correct:
I nco rrect :
Incorrect Incorrect A
B C
D I
Basis or Justification The A Chlorine detector causes a partial chlorine isolation. The Loss of Div 3 DC completes the isolation and causes the A CREFAS Fan to start due to de-energizing the trip logic. Therefore, a manual isolation is not required and only verification of the existing isolation.
The procedure reference is correct, however the A CREFAS is running.
~~~
The fan status is correct, however manual isolation is not required and only verification of the existing isolation.
The A CREFAS is running and manual isolation is not required and only verification of the existing isolation.
Source:
Reference(s):
Learning 0 bjective:
Knowledge/Ability WA Source Documentation New Exam Item 0
Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank E-IFC, SE-2 LLOT0450.03,07 (Description of K&A, from catalog)
Ability to predict the impact of the following on the Control Room HVAC, and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Initiationheconfiguration Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination
- 98.
WHICH ONE of the following procedure revisions requires a Station Qualified Reviewer (SQR) review per AD-AA-101 and AD-AA-102?
A. Changes to references in a Surveillance Test.
B. Editorial changes to an Operation's T&RM.
C. Addition of clarifying information in the form of a list of required tools in a systems procedure.
D. Changes to activities in an Off-Normal Procedure.
Page 196 of 200
Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA Low 2.5 4
N Knowledge (mi nu tes)
Answer Key RO SRO 1 OCFR55.41 1 OCFR55.43 N
Y (b)(3)
Choice I D Correct:
Incorrect:
I A
I B Incorrect I C Incorrect i
Basis or Justification Changes to activities in a procedure requires a SQR review Changes to reference are excluded from requiring SQR review Editorial change are excluded from requiring SQR review Addition of clarifying information is excluded from requiring SQR review Source:
Reference( s):
Learning 0 bjective:
Knowledge/Ability WA Source Documentation 0
New Exam Item Modified NRC Bank Item c] ILT Exam Bank c] Previous NRC Exam 0
Other Exam Bank extensively modified ILT exam bank item AD-AA-101, Page 3, step 4.3.5 LLOTI 570.01 3 2.2.6 I Importance:
RO / SRO 2.3 13.3 (Description of K&A, from catalog)
Knowledge of the process for making changes in procedures as described in the safety analysis report.
Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick G enerat i ng Station ILT05-1 NRC Initial Licensing Examination
- 99.
Fuel is being loaded into the core on Unit 1 with the following conditions:
0 IA SRM count rate is 3.5 cps and has a signal-to-noise ratio of 2.0 0
1 B SRM was declared inoperable last shift due to spiking 0
IC SRM count rate is 2.0 cps and has a signal-to-noise ratio of I
.5 0
ID SRM count rate is 2.5 cps and has a signal-to-noise ratio of 2.0 WHICH ONE of the following describes the limitations, if any, regarding loading fuel into the core?
A. Fuel may be loaded into any quadrant.
B. All fuel loading must be suspended immediately.
C. Fuel may be loaded into A or D core quadrants ONLY.
D. Fuel may be loaded into A, C or ID core quadrants ONLY.
Page 198 of 200
Limerick Generating Station ILTO5-I NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO Knowledge (mi nu tes) 10CFR55.41 Answer Key SRO 1 OCFR55.43 Question ID# 099 SRO Or High Choice 3.0 4
N N
(b) (7)
Correct:
Knowledge/Ability WA In correct:
2.2.28 Importance:
RO / SRO 2.6 / 3.5 Incorrect Incorrect C
A B
D Basis or Justification B and C SRMs are inoperable (IC due to inadequate signalhoise ratio, per T.S. fig 3.3.6-1) Therefore, Fuel movement is only permitted in quadrants A and D per T.S. 3.9.2 See above See above Fuel cannot be loaded into quadrant C because its SRM is inoperable.
Source:
Reference(s):
Learning 0 bjective:
Source Documentation
~
New Exam Item 0
Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank T.S. 3.9.2 and Figure 3.3.6-1 LLOT0240.10 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station ILTO!%I NRC Initial Licensing Examination ATTACHMENT: GP-I2 Provided 100. Unit 1 is at 100% power when the following occurs:
At 0100, Chemistry reports the following results of a Reactor water sample:
Conductivity is 2.5 pmho/cm pH is 5.4 Chloride concentration is 0.1 +y~+ b p
0 Hotwell conductivity is -c 0.1 pmho/cm and steady The RO reports a rising trend in Main Steam Line radiation.
WHICH ONE of the following describes the required action(s)?
A. Check RWCU and Condensate Deep Bed Demin effluent conductivity to identify the source.
B. Reduce power per GP-5, Appendix 2 and sequentially remove Circulating Water system loops from service to identify the source.
C. Begin a GP-3 shutdown by 0200 and place reactor in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D. Perform an engineering evaluation to determine the effects of any out-of-limit conditions on the structural integrity of the Reactor Coolant system.
Page 200 of 200
Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination A
B Answer Kev Basis or Justification ON-I 16 directs that with Conductivity > I.O pmho/cm AND Main Steam line radiation high AND ph low, to determine if RWCU or Condensate Deep Beds are passing resin This action would be correct if hot well conductivity were rising, which is not indicated I
C Choice
~~~
This action would be appropriate if GP-12 action level 3 (>5 ymhokm) were reached Correct:
D Incorrect:
This action would be appropriate if the plant was in any OPCON other than 1,2or3 Incorrect Level of Knowledge High Incorrect Difficulty Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 3.0 4
N Y (b)(lO)
Y (b)(5) 2.1.34 Importance:
Reference (s ):
Learning 0 bjective :
Knowledge/Ability K/A Source Documentation New Exam Item 0
Modified Bank Item 0
ILT Exam Bank 0
Previous NRC Exam 0
Other Exam Bank GP-12, Sect 3.3, ON-I 16, T&RM 3.4.4 LLOTI 030.12 (Description of K&A, from catalog)
Ability to maintain primary and secondary plant chemistry within allowable limits.
Required Materials:
GP-12 Notes and Comments Prepared By:
Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author