ML063240233

Final - RO & SRO Written Examination with Answer Key (401-5 Format) (Folder 3)

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 I Answer Kev c Choice Correct:

Incorrect A

B 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.

Incorrect C While this will occur, the Reactor power rise will be slight and gradual. This is not the reason for the Scram.

-t Incorrect D While this level transient will occur, it is not part of the basis for the scram I Psychometrics Time Allowance PRA RO SRO (minutes) 10CFR55.41 10CFR55.43 Low 2.5 2 Y (b) (5) N/A Source Documentation Source: New Exam Item Previous NRC Exam Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(sk LGS UFSAR, Chapter 15.2, LGS Tech Specs, LSSS Learning LLOTI575.03 0bjective:

Knowledge/Ability 295005 Importance: RO / SRO WA AK3.01 3.8 I 3.8 (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 (610) 718-4085 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 X s ) 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 Answer Key I Choice I Basis or Justification Correct: The full in and full out lights on the Full Core Display continue to function with PMS and RDCS inoperable.

Incorrect Two Xs on the Four Rod Display indicate that control rod indication is unknown, due to more than one reed switch being made up.

Incorrect C A - - indication on the Four Rod Display indicates an odd numbered reed switch is made up.

D The blue SCRAM light on the Full Core Display indicates that the scram valves are open, and does not indicate control rod position.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 LOW 2.0 3 N (b) (10) (b) (5)

Source Documentation Source: New Exam Item 0Previous NRC Exam 0 Modified Bank Item 0Other Exam Bank 0 ILT Exam Bank Reference(s): ARC 108 Reactor, E-4 Learning LLOTOO80.02 0bjective:

Knowledge/Ability 295006 Importance: RO / SRO KIA AA2.02 4.3 / 4.4 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

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. Energized Energized Page 6 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination r- ~ Answer Key Correct: 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.

Incorrect A Both busses will be energized as described above.

Incorrect Incorrect IBl 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 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.

~

Psychometrics Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 -

HIGH 3.5 3 Y (b) (10) (b) (5)

Source: [XI New Exam Item Previous NRC Exam 0Modified Bank Item 0Other Exam Bank I7 ILT Exam Bank Reference(s): E10/20, Steps 2.1 and 2.3.1 Learning LLOT0640.08 0bjective:

Knowledge/Ability 295003 Importance: RO / SRO WA AA2.04 3.5 13.7 Required Materials :

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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 (1F003)

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 SRQ Basis or Justification Correct: C A HPCl isolation signal is present due to high turbine exhaust rupture diaphragm pressure. The 1F003 valve isolates, however, the 1F002 valve does not isolate due to NO control power to the isolation logic.

Incorrect A The 1FOO2 valve does not isolate due to NO control power to the isolation logic Incorrect B The IF002 valve does not isolate due to NO control power to the isolation logic Incorrect D The 1F003 valve isolates Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43 HIGH 3.0 3 Y (b) (7) N/A Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank 0 ILT Exam Bank Reference(s): GP-8.1, Rev.11, Pg. 31; GE Elemental Dwgs. M-1-E41-1030-F-004, Shts. 1 & 2 M-1-E41-1030-F-005, Shts 1 & 2 Learning LLOT0340.14 Objective:

Knowledge/Ability 295004 I Importance: RO / SRO WA I AA1.02 3.8 / 4.1 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

5. Unit 1 plant conditions are as follows:

0 Drywell Temperature is 140°F 0 Drywell Pressure is 1.0 psig and rising slowly 0 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 3R-0 Choice Basis or Justification Correct:

I D Per OT-I01 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.

Incorrect I A 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.

Incorrect Incorrect II Bc The Drywell chill water isolation may be bypassed after entry into and meeting the Drywell temperature requirementsof 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.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minUtes) 10CFR55.41 10CFR55.43 LOW 2.5 2 N (b) (5) N/A Source Documentation Source: [xi New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s ): OT-I01, Bases Step 2.1 Learning LLOTI540.05 0bjective:

Knowledge/Ability 295010 Importance: RO / SRO WA AK3.02 3.4 I 3.4 Required Materials:

Notes and Comments:

Prepared By:

Rick Rhode (610) 718-4085 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 Answer Key I

Choice Basis or Justification Correct: C Although allowed by Tech. Specs., Exelon has decided to continue to direct that a manual scram be inserted with the plant in natural circulation.

Incorrect:

lA/ A scram is required, however, not to avoid THI. See basis for answer C.

Incorrect IBl By procedure, Limerick does not allow restarting a Recirc. Pump in natural circulation with the Reactor critical.

Incorrect I D / This is not an allowed action in natural circulation.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 10CFR55.43 LOW 2.0 2 N (b) (8) to (IO) NIA Source: [XI New Exam Item 0 Previous NRC Exam Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): OT-I f 2 Bases, step 2.1 Learning LLOTI540.05 Objective:

KnowledgelAbility 295001 Importance: RO / SRO KIA AKI .01 3.5 13.6 Required Materials:

Notes and Comments:

Prepared By:

Rick Rhode (610) 718-4085 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

Limerick Generating Station ILTO5-I NRC Initial Licensing Examination Answer Key

~

Incorrect D This is incorrect as load limit does not runback, also bypass valves will open Psychometrics Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 5 High 3.0 4 Y b)7 N Source Documentation Source: New Exam Item c]Previous NRC Exam 0Modified Bank Item 0Other Exam Bank c]ILT Exam Bank Reference(s): ON-I 14, Step 2.10 Learning LLOT0590.03 0bjective:

Knowledge/Ability 295007 Importance: RO / SRO WA AA1.05 3.7 / 3.8 (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 + I O 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 I Choice Basis or Justification I Correct: B 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)

Incorrect A This would mean exceeding the maximum cooldown rate 1 Incorrect C This does not identify the minimum amount of time before SDC can be placed in service.

I-----Incorrect D This does not identify the minimum amount of time before SDC can be placed in service.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 HIGH 3.5 5 Y (b) (IO) (b) (5)

Source: New Exam Item [7 Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): SEI, Attachments 2 & 3 Learning LLOT0735.04 0bjective:

Knowledge/Ability 295016 Importance: RO / SRO WA 2.1.25 2.8 t 3.1 Required Materials:

SE-1 Notes and Comments:

Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station lLTO5-1 NRC Initial Licensing Examination

9. Both units are at 100% power:

0 A loss of the 220 KV switchyard occurs followed immediately by a lockout of the 4A Auto Transformer 0 The D12 and D14 Diesel Generators fail to start 0 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 Procedural Direction A. ESW E-l0/20, Loss Of Offsite Power B. ESW E-I, Station Blackout C. RECW E-l0/20, Loss Of Offsite Power D. RECW E-I, Station Blackout Page 18 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key I Choice I Basis or Justification Correct: ESW can be used to backup normal Service Water for TECW and RECW

/A( by performing manual local valve manipulations per E-I 0/20.

Incorrect The correct procedure is E-10/20. Since six of the Diesel Generators start, this is not a Station Blackout.

Incorrect RECW is not hard piped to backup TECW.

(c/ RECW is not hard piped to backup TECW. The correct procedure is E-Incorrect D 10/20. Since six of the Diesel Generators start, this is not a Station Blackout.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.5 4 Y (7) N/A Source Documentation Source: 0New Exam item 0Previous NRC Exam Modified Bank item 0Other Exam Bank ILT Exam Bank Reference(s): E-I 0/20, Attachment 5 Learning LLOT0430.07 Objective:

Knowledge/Ability 295018 Importance: RO / SRO KIA AA1.01 3.6 13.5 (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 (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination IO. 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 1B 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 Answer Key Question ID# 010 Both RC ERej Choice Basis or Justification Correct: A 1B 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.

Incorrect: I B 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..

Incorrect Service Air Compressor would only supply IA if both the 1A & 1B IA header pressures were low.

See B and C above Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 4.0 6 Y Y (b) ( 5 ) N Source: [E3 New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank

[7 ILT Exam Bank Reference(s): M-I 5 Learning LLOT0730.02, 04,07, I O 0bjective:

Knowledge/Ability 295019 Importance: RO / SRO WA AK3.01 3.3 13.4 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 1I. 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 2Kand 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 Answer Key Choice I Basis or Justification Correct D 50# DIP is required across the SRVs in order to open and establish alternate heat removal.

Incorrect A While 1 0 0 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.

Incorrect B Level is high enough to fill the MSLs and no additional Level is required.

Incorrect 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 SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 4.0 5 Y Y (b) (7) N Source: [XI New Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): ON-121, Step 2.1.7, Attachment 6 S41.7.B, Step 4.2 Learning LLOT-5010.01 0bjective:

Knowledge/Ability KIA 1 295021 AA1.04 (Description of K&A, from catalog)

Importance: RO / SRO 3.7 13.7 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 (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination

12. Unit Iplant conditions are as follows:

0 Reactor level is 20 0 Reactor Pressure is 350 psig 0 Drywell Pressure is 25 psig 0 1B RHR Pump is operating at 8200 gpm with the following valve indications:

HV-51-1F016B, OUTBOARD SPRAY, green light lit HV-51-1F017B, LPCl INJECTION, red, green and white lights lit HV-51-1F021B, 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-51-1FO21B, then open HV-51-1F016B, then reopen HV-51-1F021B.

C. Close HV-51-1F017B and open HV-51-1F016B.

D. Close HV-51-1F024B and open HV-51-1FOI 6B.

Page 24 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key Question ID# 012 Both RC Choice Basis or Justification Correct IC 17B valve must be closed in order to open 16B - all other conditions for opening 16B are already .

r lA Incorrect LOCA Signal already present. PB not required. Also 178 must be closed.

Incorrect This valve manipulation only required if LOCA signal not present. 17B must also be closed..

~~ ~ ~~ ~~

Incorrect 24B dose not need to be closed Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 4 Y Y (b) (7) N Source Documentation Source: I New Exam Item Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference@): T-225, Step 4.5 Learning Objective: I LL0T0370.09 WA 1 Knowledge/Ability 295024 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 I 0 0 0 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 Answer Key Choice Basis or Justification 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.

Incorrect A SP level is high but 3.5feet 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 9OOB 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.

Incorrect D SP temp is still 20°F away from HCTL and rising slowly. T-I12 is not warranted at this point Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.5 4 Y Y (b) ( I O ) Y (b) (5)

Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank T-102 sh.1 Learning LLOTI560.04 0bjective:

KnowledgelAbility 295026 Importance: RO / SRO EA2.03 3.9 / 4.0 (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 (610) 718-4085 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 One B. One Fan per Cooler Two C. Two Fans per Cooler One D. Two Fans per Cooler Two Page 28 of 200

Limerick Generating Station ILT05-I NRC Initial Licensing Examination Answer Key I Choice I Basis or Justification I Correct: B 1 Meets the criteria specified in T-102 Bases, for step DW/T-5 r Incorrect:

Incorrect A

C Does not meet the criteria specified in T-I 02 Bases, step DW/T-5. Only has one DWCW pp cunning vs. two 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.

Incorrect D Does not represent the minimum number. 2 DW fans in-service - DW fans are 100% capacity and in parallel.

I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.5 3 Y (b) (7) N Source Documentation Source: New Exam Item 17Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): T-102 Bases, DW/T-5 Learning LOT-1560.06 0bjective:

Knowledge/Ability 295028 Importance: RO J SRO WA EK2.04 3.6 J 3.6 Required Materials:

T-I 02 Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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 Suppression Pool level is 20 and lowering 0 RClC is being used for RPV level control 0 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 pp ression Pool.

Page 30 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key Incorrect IBl NPSH limit for HPCl would be at 15.42 ft, where it is already secured at 18 for the reason above Incorrect RClC Turbine exhaust pressure is insufficient to cause pressurizationof the Suppression Pool in excess of PCPL.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.5 3 Y Y (b) (5) N/A Source Documentation Source: [XI New Exam Item 0Previous NRC Exam 0Modified Bank Item c]Other Exam Bank 0ILT Exam Bank Reference(s): T-102, sh. 1 Learning LLOTI560.05 0bjective:

Knowledge/Ability 295030 Importance: RO / SRO WA EK3.02 3.5 / 3.7 (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 (610) 718-4085 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 1B 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. -185 800 psig 1B CRD pump C. -1 95 910 psig None D. -205 890 psig 1B CRD pump Page 32 of 200

Limerick Generatina Station ILT05-I NRC Initial Licensing Examination

~~

Answer Key Question ID# 016 Both-R( SRd Choice Basis or Justification Correct: A 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-IIILR-14. Even though pressure is <I OO# below recorded value, this supply calls for a new pressure load.

1 ~ Incorrect B 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.

Incorrect C 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.

Incorrect D 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.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.5 5 Y (b) (8-10) NIA Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 1 0Other Exam Bank ILT Exam Bank Reference(s): T-I 11 BASES, LR-12 through LR-17 Learning LOT-1560.03 Objective:

Knowledge/Ability WA 295031 Importance: RO / SRO WA EKI .01 4.6 14.7 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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 Correct:

is reached Incorrect A This would only be appropriate in the event of criticality.

I Incorrect C FH-105 requires suspension of component movement when one doubling is reached Incorrect D 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.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minUtes) 10CFR55.41 10CFR55.43 Low 2.0 3 Y (b) (8-10) N/A Source: New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): FH-105, STEP 3.7 Learning LLOT0760.12 Objective:

Knowledge/Ability 295023 Importance: RO / SRO KIA 2.2.28 3.5 / 3.3 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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 Ihour 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 Answer Key Choice Basis or Justification Correct: C Reactor Coolant System Pressure Safety Limit has been violated. Tech Spec action must satisfy 2.1 and 6.7.1 Incorrect A 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 Incorrect B Meets 3.3.1 for RPS Instrumentation but is not conservative enough to meet 2.1 and does not meet 6.7.1 Incorrect D 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 Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 10CFR55.43 High 3.5 5 N (b) (8-10) NIA Source: New Exam Item Previous NRC Exam Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): LGS Tech Specs Learning LLOTI540.05 0bjective:

KnowledgelAbility 295025 Importance: RO I SRO KIA EKI .05 4.41 4.7 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 Reactor mode switch is in STARTUP

'W IRM is failed upscale &Q, \@(ob

" ID" 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 Cylose power, Reactor 1/2 Scram ONLY.

Page 38 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination I Answer Kev I Question ID# 0'19 Both RC

~ ~

Basis or Justification Correct: A 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)

Incorrect: B ONLY IRM Channels A, and C, loss power is incorrect as E & G channels also lose power, Full Reactor Scram is correct Incorrect: C IRM Channels A, C, E, and G loss power is correct, Reactor 1/2 Scram is r---

incorrect as full reactor scram will occur Incorrect: D 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 Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 N (b) 7 N Source Documentation Source: New Exam Item 0Previous NRC Exam Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): E-1AY160, Step 1.2 and 1.22, AND GP-2, Caution before step 3.4.7 Learning LLOT0250.07 Objective:

Knowledge/Ability 215003 Importance: RO / SRO WA K2.01 2.5 / 2.7 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 1 A and ID IRMs are on range 1 0 All other IRMs are on range 2 1 A 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 Answer Key Choice Basis or Justification Correct: B 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 Incorrect A No rod blocks are enforced, is not correct. It would be correct if all IRMs were above range 2 Incorrect C 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 Incorrect D 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 RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.5 4 N (b) ( 5 ) N Source: Ix] New Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): GP-2Appendix 1, step 3.3.7 and NOTE Learning LLOT0240.06:

0bjective:

Knowledge/Ability 215004 Importance: RO / SRO WA K5.03 2.8 12.8 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination

21. Unit 2 is at 100% power.

1. 2 APRM output fails to 2%.

WHICH ONE of the following completes the statement below?

91 The 2B Rod Block Monitor channel A. initiates a rod block B. automatically goes to Bypass mode C. automatically swaps to reference #3 APRM D. automatically swaps to reference ##4APRM Page 42 of 200

Limerick Generating Station ILT05-I NRC Initial Licensing Examination I Answer Key I Choice I Basis or Justification Correct: B The RBM sees less than 30% power from its reference APRM and Auto Bypasses 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 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.

Incorrect D ##4APRM is the correct alternate, however, the reference APRM would only swap if the primary APRM channel were INOP or Bypassed.

I I I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 4 N (b) (2) N Source: New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): ARC 108, A-5 .

Learning LLOT0280.09a 0bjective:

KnowledgelAbility 215005 Importance: RO I SRO WA K1.03 3.4 13.5 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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 1E 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 IE SRV is still open 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. -100 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 Answer Key I Choice I Basis or Justification Correct: D Conditions are set for level lowering to below TAF. The bases for this level lowering is reduction of natural circulation driving head Incorrect A This is the appropriate level band and reasons for the first level lowering.

This is N/A once SP temp is II O " and SRV is open Incorrect B This level condition is not appropriate, the reason is associated with the

-161 to -186 level band Incorrect C This level band is correct, the reason is associated with the higher level band Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 5 Y (b) (5) N Source Documentation I Source: New Exam Item 0Previous NRC Exam LReference s :

Modified Bank Item 17 ILT Exam Bank T-I 17, T-I 17 Bases, LQ-6 through LQ-11 and LQ-16.

Other Exam Bank ILearning Objective:

LLOTI 560.05 Knowledge/Ability 295037 EK.2.09 (Description of K&A, from catalog)

Importance: RO / SRO 4.0 / 4.2 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 (610) 718-4085 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 Iis 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 Iand 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 48 .

Page 46 of 200

Limerick Generating Station lLTO5-I NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43 High 3.0 4 Y (b) (IO) (b) (5)

Source: New Exam Item Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): T-I 01, note 14, Tech Specs definition of Shutdown Margin Learning LLOTI560.03 0bjective:

KnowledgeIAbility 295037 Importance: RO I SRO WA EA 2.05 4.2 I 4.3 Required Materials:

Notes and Comments 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 Basis or Justification Correct: B Possible source, ST must be performed and LGS Emergency Plan annex, Table 3-1 must be consulted Incorrect A Possible source but alarm alone is not sufficient reason to enter and execute T-I 04

_ _ _ ~

Incorrect C Not a possible source based on the given conditions, although the action is plausible given this source Incorrect 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 SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.5 4 N (b) (7) N Source Documentation Source: [XI New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank 0 ILT Exam Bank Reference(s): ARC-MCR-003-EII ST-6-104-880-0, T-I 04 Learning LLOT0720.03 0bjective:

KnowledgelAbility 295038 Importance: RO I SRO KIA EK2.03 3.6 13.8 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

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 EMERGENCY 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 Answer Key Question ID# 025 Both RC $Fa Choice Basis or Justification Correct: C 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.

Incorrect A RClC manual control is available, but HPCl will cycle in AUTO as long as it has not been disabled.

Incorrect B HPCl manual control is not available from the RSP. It can either be allowed to cycle in AUTO, or completely disabled from the RSP.

_ _ ~_ _ ~ __ ~~

Incorrect D HPCl will cycle in AUTO as long as it has not been disabled. RClC must be started up and shutdown manually.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.5 3 Y (b) (5) N Source: New Exam Item 0Previous NRC Exam c]Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): SE-1 step4.3 Learning LLOT0735.02, .03 Objective:

Knowledge/Ability 295016 Importance: RO I SRO WA AK2.01 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 (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination

26. Unit 2 Plant conditions are as follows:

0 Main Condenser vacuum is 20 and dropping 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 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 Answer Key Question ID# 026 Both R( gij" Choice Basis or Justification Correct: D With no sealing steam pressure, main condenser vacuum will draw cold air across the seals and the hot turbine rotor Incorrect A Preventing windage damage is the reason why vacuum should not be broken greater than 1200 RPM Incorrect B Preventing Turbine exhaust hood over-pressurization is the reason for tripping the Main Turbine at 21.5" VAC Incorrect C Uneven rotor heating is a problem if sealing steam is applied to a stationary turbine rotor Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.5 4 Y (b) (7) N Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s) : OT-I 16 BASES, step 3.3 Learning LLOTI 540.05 Objective:

Knowledge/Ability 295002 Importance: RO / SRO WA AK2.11 2.6 12.7 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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 Answer Key Choice Basis or Justification Correct: A 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 Incorrect B T-213 is not directed in T-I00 Incorrect C As Reactor power is below 4% entry into T-I 00 (vice T-I 01) is appropriate Incorrect I D 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 Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 I

3.0 3 N N 1 Source Documentation Source: I [E3 New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank ILT Exam Bank Reference@): T-100 Bases step RC/Q-3 Learning LLOTI 540.02 0bjective:

Knowledge/Ability 295015 Importance: RO / SRO WA AA2.01 4.1 / 4.3 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

28. Unit Iplant 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 Answer Key I Question ID# 028 Both RC $*W Basis or Justification Correct: D An inadvertent VlllA isolation would result in both DWCW and Recirc Pump cooling water isolating Incorrect A Both will isolate I------

1 Incorrect Incorrect B

C DWCW will also isolate Recirc Pump cooling water will also isolate Difficulty Time Allowance PRA RO SRO (minutes) IOCFR55.41 10CFR55.43 Low 2.5 2 N (b) (8, 9, 10) N Source: New Exam Item Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): GP-8.1 for Group VlllA Learning LLOT0180.05 0bjective:

Knowledge/Ability 295020 Importance: RO / SRO WA AKI .05 3.3 13.6 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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 MAIN STEAM LINE DIV 1 RAD MONITOR HVDOWNSCALE (109 F I )

0 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 I Answer Key Choice I ~~

Basis or Justification Correct: C 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 Incorrect A 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 Incorrect B 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 Incorrect D 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 Difficulty Time Allowance PRA RO SRO (minutes) 10CFR55.41 10CFR55.43 High 4.0 5 Y Y (b)(10) y (b)(2)

Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item [7 Other Exam Bank ILT Exam Bank Reference(s): ARC-MCR-109-F1, ARC-MCR-109-F2, ARC-MCR-107-11, ON-I 02 Step 1.2, T-I 03 Learning LLOTI560.02, LLOT1550.01 Objective:

KnowledgelAbility 295033 Importance: RO I SRO WA (32.4.4 4.0 14.3 (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 (610) 718-4085 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 Answer Key Question ID# 030 Both RC I Choice Basis or Justification I Correct: Applying the containment H2and 0 2 levels to the tables, PC/G-1 and PC/G-A 2 in T-102, sh. 2, results in the use of flowpaths DW/G-3 and SP/G-1 1 Incorrect B Neither of these flowpaths are correct per PC/G-1 and PC/G-2, T-102, sh. 2 Incorrect C The drywell flowpath is correct; the suppression pool flowpath is not, per PC/G-1 and PC/G-2, T-102, sh. 2.

I Incorrect D The suppression pool flowpath is correct; the drywell flowpath is not, per PC/G-1 and PUG-2, T-102, sh. 2.

Difficulty Time Allowance PRA RO SRO (minutes) 10CFR55.41 10CFR55.43 High 3.5 4 Y Y (b)(lO) Y (b)(5)

Source: New Exam Item Previous NRC Exam Modified Bank Item 0Other Exam Bank - Modified LOR ILT Exam Bank Exam bank item Reference(s): T-102, sheet 2 and T-102 Bases Step PC/G-5 Learning LLOTI560.06 Objective:

Knowledge/Ability 500000 Importance: RO / SRO K/A EA 2.03 3.3 / 3.8 Required Materials:

T-I02 sht. 2 Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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. IManual Initiation Pushbutton.

B. Start the 2 A 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 Answer Key Question ID# 031 Both RC I Choice Basis or Justification I Correct: A Div 1 Manual Initiation Pushbutton will provide a Div 1 LOCA Signal, Start the 1 A pump and open the injection valves as long as the Reactor low pressure permissive is met.

Incorrect B The HV-52-2F005 will not open unless there is a LOCA signal present I incorrect C Div 3 Manual Initiation Pushbutton will start the I C Core Spray Pump, but it will not make up the open logic for the injection valves. Only the Div l(2)

L I Incorrect D Pushbuttons will do that The HV-51-2F017C will not open automatically unless there is a LOCA signal present.

Difficulty Time Allowance PRA RO SRO (minutes) IOCFR55.41 10CFR55.43 High 3.5 4 Y Y (b)(7) N Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 17Other Exam Bank 0ILT Exam Bank Reference(s): S52.7A, note above step 4,4 Learning LLOT0350.I O Objective:

Knowledge/Ability 209001 Importance: RO/ SRO K/A PWG 2.1.30 3.9 13.4 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 1 2 5 V f + % W D C is inoperable due to maintenance on the battery charger e&& 43(ob An inadvertent Group Iisolation causes a reactor scram.

Unit 2 RClC starts on low reactor level A steam leak develops in the RClC room. RClC room temperature reaches 210°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 Isolation to CLOSE.

Page 64 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 032 Both RC Choice Basis or Justification Correct: C With a loss of Div 3 DC, the 2F007 will fail to isolate on High RClC room temperature (205OF)and must be closed Incorrect A The RClC Turbine will trip on a Div 1 NS4 isolation signal on High RClC Room temperature Incorrect l B Manual isolation will not close 2F007 valve due to loss of Div 3 DC 0

~ ~

Incorrect The 2F008 will close on a Div INS4 Isolation signal on High RClC Room temperature Difficulty Time Allowance PRA RO SRO (minutes) 10CFR55.41 10CFR55.43 High 3.0 4 Y Y (b)(5) N Source: [xi New Exam Item c]Previous NRC Exam 0Modified Bank Item c]Other Exam Bank ILT Exam Bank Reference(s): E-2FC, GE DWG M-1-E51-1040-E-028, Sht.1 Learning LLOT0380.05, LLOT0380.12 0bjective:

1 Knowledge/Ability 217000 I Importance: RO / SRO WA I A205 3.3 13.3 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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 1B 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 1B RHR Loop if Reactor Water level lowers to -140?

A. I B RHR loop will realign to the LPCl mode.

B. I B 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 LicensinQExamination Answer Kev

?BE?

Choice Basis or Justification Correct: 1 c 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 Incorrect: A F024 and F017B will not reposition due to loss of Div 2 DC Incorrect:

IB RHR pump will not load shed during a LOCA Incorrect: I D Min flow valve will not open Difficulty Time Allowance PRA RO SRO (minutes) 10CFR55.41 10CFR55.43 High 3.0 4 Y Y (b)(7) N Source: 0New Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): E-IFB U/1, GE DWG. M-1-Ell-1040-E-039 SH.l Learning LLOT0370.3e 0bjective:

Knowledge/Ability 203000 Importance: RO / SRO KIA K6.02 2.8 / 3.0 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 I A 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-51-1F006A HV-51-1FOO9 Shutdown Cooling Shutdown Cooling 1 A RHR Pump Suction Valve Isolation valve A. Running Open Open B. Running Open Closed C. Tripped Closed Open D. Tripped Open Closed Page 68 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination I Answer Key I Basis or Justification Correct: D 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 A Incorrect as FOO9 will close with level below +125 and pump will trip Incorrect Incorrect as pump will trip when level drops below 12.5 due to FOO9 closure I Incorrect C Incorrect as F006A will not automatically close and FOO9 y level drops below +I 25 Ji close when Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 Y y W(7) N Source Documentation Source: New Exam Item Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 17 ILT Exam Bank Reference(s): S51.8.8, step 3.2 Learning LLOT0370.14~

Objective:

KnowledgelAbility 205000 Importance: RO / SRO WA K6.04 3.6 13.6 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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 IC-M 1- 1R600)

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 SBtI I Choice Basis or Justification 1 Correct: A SCRAM profile will swap controller to three element even if operator selected single element.

I1 Incorrect Incorrect B

C 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%

1ncorrect D 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).

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 Y y (b)(7) N Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): S.06.1 .D Unit 1, Attachment 1 Learning LLOT0550.08 Objective: '

Knowledge/Ability 259002 Importance: RO I SRO WA K5.01 3.1 13.1 REQUIRED MATERIALS:

Notes and Comments:

This question relates to the LGS plant specific FW controllers.

Prepared By:

Rick Rhode (610) 718-4085 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-55-1F008 HPCI, Test Loop Shutoff is throttled to maintain pump discharge pressure 150 psig over Reactor pressure.

0 The RO throttles HV-55-1F008 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 Generating Station ILT05-I NRC Initial Licensinq Examination Answer Key Choice

~

I Basis or Justification Correct: 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 Incorrect A Flow Controller is in Auto, maintaining system flow constant Incorrect

/c/ To maintain constant flow w/F008 throttled closed, speed goes up.

Incorrect D Flow Controller is in Auto, maintainingsystem flow constant.

I Psvchometrics I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 2.5 3 N y (W(7) N Source Documentation Source: New Exam Item c]Previous NRC Exam Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s ): S55.1.D, note Step 4.4.3 Learning LLOT0340.12 0bjective:

KnowledgetAbility 206000 HPCl Importance: RO I SRO WA A I .09 3.4 t 3.5 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

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 IADS 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 Basis or Justification Correct: C 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.

r Incorrect: A DIV Iwill not initiate without correct pumps running DIV 3 will initiate as described above Incorrect B DIV 1 ADS will not initiate without correct pumps running DIV 3 will initiate as described above D 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.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43 High 3.5 4 Y Y (b)(7) N Source Documentation Source: New Exam Item Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): B21-1060 (ADS) Sh. 3 Learning LLOT0350.04~

0bjective:

Knowledge/Ability 209001 Importance: RO / SRO K/A K3.02 3.8 i 3.9 (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 (610) 718-4085 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 cond itions?

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 Answer Key Choice I Basis or Justification Correct: 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 Incorrect B Is incorrect as SLC tank low-low level would not be alarming at this point.

Incorrect C Squib valve continuity lights lit is wrong as SLC will have initiated Incorrect D Squib valve continuity lights lit is wrong as SLC will have initiated I I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 Y Y (b)(5) N Source: N N e w Exam Item Previous NRC Exam 2001 0Modified Bank Item c]Other Exam Bank 0ILT Exam Bank Reference(s): S48.1.B, section 4.0, ANN 113, B5 Learning LLOT0310.06 Objective:

Knowledge/Ability 211000 Importance: RO / SRO WA A1.10 3.7 / 3.7 REQUIRED MATERIALS:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILTO5-1 NRC Initial Licensinn Examination

39. Unit 2 plant conditions are as follows:

0 Turbine shell warming is in progress 0 Turbine first stage pressure rises to 200 psig 0 PIS-001-652A and D are lit on panels 10609 and lOC61 Iin 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 I Basis or Justification I Correct:

Incorrect B Turbine control valve closure scram is wrong as turbine control valves are open to support shell warming Incorrect I Cpp This answer is wrong as a complete SCRAM will occur Incorrect D This answer is wrong as a complete SCRAM will occur Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 4.5 3 Y y (b)(7) N Source Documentation Source: [xi New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): GP-2 Appendix 3, step 3.2.8 caution ANN 107,A2 Learning LLOT0300.04 0bjective:

Knowledge/Ability 212000 RPS Importance: RO / SRO KIA K4.12 3.9 / 4.1 (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. Feedwater Master Level Controller will swap to single element, Reactor level will go up.

B. Feedwater Master Level Controller will swap to single element, Reactor level will remain at 35.

C. Feedwater Master Level Controller will remain in three element, Reactor level will remain at 35.

D. 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 Answer Key Question ID# 040 Both RC swicj Choice Basis or Justification Correct: C 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 Incorrect: A 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 Incorrect: B This is incorrect as FW will not swap to single element on level transmitter failures (1/2 hour apart)

Incorrect: D 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 Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.5 3 Y Y (b)(7) N Source: 0New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): S06.1.H U/1, Attachment 1 Learning LLOT0550.1OC Objective:

Knowledge/Ability 259001 Importance: RO / SRO WA K6.07 3.8 / 3.8 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 1B 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 Answer Key Choice Basis or Justification Correct: D RRCS manual initiation requires depressing both pushbuttons in the SAME Division, the noted action (one pushbutton in separate divisions) will not initiate RRCS Incorrect A 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 Incorrect Icl SLC will not initiate as RRCS is not initiated, and conditions for automatic initiation are not met I Psvchometrics I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 Y Y (b)(7) N Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): GP-18 Attachment 4, ANN 004 F-5 Learning LLOT0315.05 Objective:

Knowledge/Ability 212000 Importance: RO I SRO KIA A4.16 4.4 14.4 REQUIRED MATERIALS:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generatinq Station ILT05-I NRC Initial Licensinq Examination

42. Unit Iplant 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-42-1N681A and LIS-42-1N681B, 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 OASGTS Fan running.

C. Only OBSGTS Fan running.

D. Both SGTS Fans off.

Page 84 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key Question-ID# 042 Both RC Choice Basis or Justification Correct: I B A Reactor enclosure isolation and A SGTS start will occur on LIS-42-IN681A and B downscale failure Incorrect: A Incorrect as B Fan will not start

- _ _ _ _ ~ ~

Incorrect C Incorrect as B Fan will not start

~~~

Incorrect: D Incorrect as A Fan will start Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 IOCFR55.43 Source Documentation Source: New Exam Item Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): ANN 004 E-I Learning LLOT0200.1OB Objective:

Knowledge/Ability 261000 Importance: RO / SRO WA K6.08 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 (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination

43. Unit Iplant 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. I A RFP is tripped, IB and I C RFPs are running.

B. 1C RFP is tripped, 1 A and 1B RFPs are running.

C. I Aand 1 B RFPs are tripped, 1C RFP is running.

D. All RFPs are tripped.

Page 86 of 200

Limerick Generating Station ILTO5-1 NRC Initial Licensinq Examination Answer Key Choice Basis or Justification Correct: B 1C RFP will trip on Low suction after 5 seconds pressure due to suction pressure less than 233 psi for 5 Incorrect A 1 A RFP will not trip as C RFP trips first followed by 1B at 10 seconds and 1 A at 15 seconds Incorrect 7 1B and 1 A tripped is wrong as 1C RFP will trip first Incorrect D 1 All RFPs tripped is wrong as suction pressure stabilized prior to trip of all 3 RFPs Psychometrics Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Source Documentation Source: New Exam Item 0Previous NRC Exam

[7 Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): ANN 104 Cond E-2 ANNS 102 Feed AI, BI, C1 Learning LLOT0520.08 Objective:

Knowledge/Ability 256000 Importance: RO / SRO KIA K1.02 3.3 f 3.3 (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) 718-4085 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:

RPV water level has recovered to +35 and is steady 0 Drywell pressure is 2.5 psig and steady 0 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 pushbutton.

Close the RClC trip throttle valve (HV-50-112).

B. Depress the RClC turbine manual isolation pushbutton.

Close the RClC steam supply valve (HV-50-1F045).

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-50-1F045).

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 Answer Key Choice Basis or Justification Correct: C 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 Incorrect A Once the initiation signal is reset, the manual isolation will not work Incorrect B These steps will shutdown RCIC, but the isolation must be reset in order to be ready for auto injection Incorrect D These steps will shutdown RCIC if the initiation signal were still present.

RClC will not be ready to auto inject Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 2.5 3 Y y (bN7) N Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): S49.2A section 4.1, S49.1C section 4.3 Learning LOT0380.08 0bjective:

I Knowledge/Ability 217000 1 Importance: RO / SRO KIA (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 (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station . ILT05-1 NRC Initial Licensing Examination

45. WHICH ONE of the following identifies SRV indications during an ADS automatic blowdown?

Amber White Has Lifted Light Solenoid Energized Light A. Lit Not Lit B. Lit Lit C. Not Lit Lit D. Not Lit Not Lit Page 90 of 200

. Limerick Generatinq Station Question I.D# 045 Both RC Choice Correct:

Incorrect Incorrect Incorrect Level of A

C D

Difficulty initiation Answer Kev ILT05-I NRC Initial Licensinq Examination 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 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 Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.0 2 Y Y (b)(7) N Source Documentation Source: New Exam Item 0Previous NRC Exam (7 Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): OT-114, ARC 110 B-2 Learning LLOT0330.07a 0bjective:

Knowledge/Ability 218000 Importance: RO / SRO WA A3.01 4.21 4.3 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

46. Unit Iis 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 Answer Key Choice I Basis or Justification Correct:

lD1 NZSupply valve closes and vent valve opens on a Lo-Lo Reactor level signal (VIIIB)

~~

Incorrect: 1 A 1 This is incorrect as instrument gas block valves isolate at Lo-Lo-Lo Level Incorrect This is incorrect as recirc vent valves do not automatically open on an isolation Incorrect C This is incorrect as main steam line vent valves do not automatically open Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.5 3 Y Y (b)(5) N Source Documentation Source: 0New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): GP-8.1, Reactor Level 2-L0w, Low section Learning LLOTOI80.08d Objective:

KnowledgeIAbility 223002 Importance: RO I SRO KIA A2.05 3.31 3.6 (Description of K&A, from catalog)

Ability to predict the impact of Nuclear Boiler Instrumentationfailure 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 (610) 718-4085 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 Iimits?

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 Basis or Justification Correct: D Reducing VARS to less than 1500 restores W A R S to less than 75% KW, which corresponds to a Power Factor of 0.8 Incorrect: A Raising KW would also restore the ratio of KVAR to KW, but KW would have to be raised to 2133 KW.

Incorrect: B Lowering KW would make the D/G further from its operating limit.

Incorrect:

Icl Raising KVAR would also make the D/G further from its operating limit.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 2.5 3 Y y (W7) N

~ ~ ~~

Source Documentation Source: New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): S92.1.O, caution above step 4.5.5 Learning LLOTO670.02 Objective:

KnowledgelAbility 264000 Importance: RO / SRO WA A4.01 3.3 I 3.4 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

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. 1 A 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. 1 A CRD pump trips.

Can only be restarted from 4 KV switchgear.

Page 96 of 200

Limerick Generating Station ILT05-I NRC Initial Licensina Examination Answer Key Question Id# 048 Both R(

Basis or Justification Correct: A A CRD will trip due to Div Ill LOCA signal and LOCA load shed it can be restarted from the MCR Incorrect B This is incorrect as a CRD pump will trip due to Div Ill LOCA load shed Incorrect C This is incorrect as a CRD can be restarted Incorrect D This is incorrect as CRD can be restarted from the MCR Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 2.5 3 Y y (b)(5) N Source: ONew Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): SE-10, step 4.6 Learning LLOT0660.05b 0bjective:

KnowledgeIAbility 262001 Importance: RO I SRO WA 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 (610) 718-4085 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?

A. 1B SRV from the MCR.

B. 1C SRV from the RSP.

C. 1J SRV from the AER.

D. 1S SRV from the AER.

Page 98 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 049 Both RC I Choice Basis or Justification Correct:

I D 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.

Incorrect Incorrect iA I B 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 Incorrect I C While J SRV is one of the preferred SRVs for use with high level, control is not availabre in the AER Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 Y Y (b)(7) N Source: New Exam Item 0 Previous NRC Exam 0801#221 Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): OT-I 10 Step 3.1.4 Learning LLOTOI20.12a 0bjective:

Knowledge/Ability 239002 Importance: RO i SRO WA K4.05 3.6 i 3.7 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

~ - ~~

Limerick Generat ing Stat ion ILT05-1 NRC Initial Licensing Examination

50. Unit Iplant conditions are as follows:

0 Reactor power is 100%

0 1 A 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

Limerick Ge ne ratinq Station ILT05-I NRC Initial Licensing Examination Answer Key I Choice I Basis or Justification Correct: 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 Incorrect: A On high seal cavity temperature ON-I 13 directs reducing speed to maintain temperature this occurs at a cavity temperature of 175OF not ZOOOF Incorrect: Pump motor temperature is unaffected by a LOSS of RECW (DWCW supplies motor cooler)

Incorrect: D Pump motor temperature is unaffected by a LOSS of RECW (DWCW supplies motor cooler)

I I I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 2.5 3 Y Y (b)(5) N Source Documentation Source: Ix] New Exam Item Previous NRC Exam 0Modified Bank Item 0Other Exam Bank c]ILT Exam Bank Reference(s): ON-I 13 step 2.1, S43.0.D Learning LLOT0030.07b:

0bjective:

KnowledgelAbility 202001 Importance: RO / SRO KIA A2.17 3.1 13.2 (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) 718-4085 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 Answer Key Choice I Basis or Justification Correct: A When their respective safeguard MCCs re-energized both RECW pumps auto start on low heat exchange outlet pressure Incorrect 2A portion of this distractor is correct, 28 portion is incorrect, for the reason stated above Incorrect C 2A portion of this distractor is incorrect, 2B portion is correct for the reason stated above Incorrect D Both the 2A and 2B portions of this distractor are incorrect as stated above.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 Y y (W(7) N Source Documentation Source: New Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank ILT Exam Bank E-565 Learning LLOT0460.07 Objective:

Knowledge/Ability 400000 Importance: RO I SRO K/A K4.01 3.4 / 3.9 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 to a malfunction of RMCS Incorrect A RBM upscale will not result in a rod block as Reactor power is less than 30%

Incorrect B RBM downscale will not result in a block as Reactor power is less than 30%

Incorrect 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 SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 Y Y (b)(7) N Source: [XI New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): S73.O.B, step 4.2 & note above step, ANN 108 D-4 Learning LLOT0080.06 =

0bjective:

WA I KnowledgelAbility 201002 K3.02 (Description of K&A, from catalog)

Importance: RO ISRO 2.9 13.2 Knowledge of the effect that a loss or malfunction of RMCS will have on RBM Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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 Answer Key Incorrect A Rod cannot be withdrawn as RWM will enforce a withdraw block Incorrect C Rod does not need to be bypassed to allow insertion Incorrect 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 SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 N Y (b)(7) N Source Documentation Source: New Exam Item 0Previous NRC Exam I 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): ON-I23 step 2.12 Learning LLOT0093f 0bjective:

Knowledge/Ability 201006 Importance: RO / SRO WA K4.06 3.2 / 3.4 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

% Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination

54. Unit 1 plant conditions are as follows:

0 Reactor was scrammed due to a condensate line rupture.

0 Reactor level is -35 and lowering 0 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 1 A and I C SLC injection pumps are started and verified to be injecting WHICH ONE of the following describes the RWCU system response?

A. HV-44-1F004 RWCU Outboard Suction Valve closes.

B. HV-44-1FOOI RWCU Inboard Suction Valve closes.

C. HV-44-1F004 RWCU Outboard Suction Valve and HV-44-1FOOI RWCU Inboard Suction Valve close.

D. HV-44-1F040 RWCU Inlet Suction Valve closes.

Page 108 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Kev sm

~

QuestionID# 054 Both RC Choice Basis or Justification Aor C SLC pump start close Fool valve as B was not started (D124 is power supply for the 73 pump) F004 did not close Incorrect A F004 does not close as B SLC pump did not start Incorrect Incorrect IC D 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 Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 N Y (b)(7) N Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank - LORT 0ILT Exam Bank Reference(s): GP-8.1, Signal Y Learning LLOTOI10.05 Objective:

KnowledgelAbility 204000 Importance: RO I SRO KIA A3.03 3.6 13.6 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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 110 of 200

Limerick Generatinq Station ILTO5-1 NRC Initial Licensinn Examination Answer Key Question ID# 055 Both RC SR!

Choice Basis or Justification Correct: A Due to Loss of 1AY160 and PMG (Turbine speed 300 RPM) bypass will not operate Incorrect B Bypass jack will not operate due to loss of 1AY160 Incorrect C Pressure set will not operate due to the loss of 1AY160 Incorrect D Raising max combine flow (115%) will not open bypass valves (CVs are closed)

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 -

Low 3.0 3 Y Y (b)(7) N Source Documentation Source: I New Exam Item Previous NRC Exam 0ILT Exam Bank Reference(s): E-1AY160 Attachment #1 Learning LLOT0560.01Ok 0bjective:

KnowledgelAbility 262002 Importance: RO I SRO KIA K3.15 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.

1A and 1B 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 Correct: D 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 I Incorrect A This is incorrect as inboard MSlVs also close. Also non ADS SRVs cannot be opened from handswitches due to loss of PClG Incorrect B This is incorrect as outboard MSlVs also close Incorrect C This is incorrect as non-ADS SRVs cannot be opened from handswitches due to loss of PClG Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 4.0 3 Y Y (b)(9) N Source Documentation Source: [XI New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): ON-I 19 Attachment 1 Learning LLOT0730.08 0bjective:

Knowledge/Ability 300000 Importance: RO / SRO WA K1.03 2.8 / 2.9 (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 118 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 Answer Kev Incorrect Ici Reactor pressure 1096 is incorrect (1096 is the Reactor Scram setpoint) additionally 30 seconds is the Feedwater runback length once initiated Incorrect iDi Reactor pressure 1096 is incorrect additionally 9 seconds is incorrect (9 seconds is the RRCS Recirc pump RPT Breaker time delay)

Level of Difficulty Time Allowance PFW RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 HIGH 3.0 3 Y NIA NIA Source: New Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): GE Elementary Drawing G31-I020 ARC 004, B-4 Learning LLOT0315.04 Objective:

KnowledgelAbility 216000 Importance: RO / SRO WA 2.4.50 3.3 13.3 Required Materials:

Notes and Comments:

Rick Rhode (610) 718-4085 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 116 of 200

Limerick Generating Station ILTO5-1 NRC Initial Licensing Examination Answer Key Question ID# 058 Both RC Choice Basis or Justification Correct:

Incorrect:

ID A All 4 loads are Now Safeguard DC Refuel Floor HVAC isolation logic and Primary RPS/UPS Inverter Power are Safeguard DC loads

--- Incorrect:

Incorrect: C Primary RPS/UPS inverter Power is a Safeguard DC load Reactor Enclosure HVAC Isolation logic and 4KV Breaker Control Power are Safeguard DC loads Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43 Low 3.0 3 Y (b) (7) N Source Documentation Source: New Exam Item 0Previous NRC Exam Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): E-33, Sh 1-3 E-619, Sh 1-3 Learning LLOT0690.04 0bjective:

Knowledge/Ability 263000 Importance: RO / SRO KIA K2.01 3.1 / 3.4 (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 (610) 718-4085 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 118 of 200

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Answer Key Choice I Basis or Justification Correct: Vacuum Breakers Relief's will open on Drywell Pressure lower than Suppression Pool Pressure Incorrect B Vacuum Breaker Operate on to ensure Drywell is not drawn negative Incorrect C While some equalization will occur when Vacuum Breaker opens it is not the reason they open Incorrect The exact opposite is true, as Vacuum Breakers relieve the higher Suppression Pool pressure to the Drywell.

Level of Difficulty Time Allowance PRA . RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 Y Y (b)(5) N Source Documentation Source: New Exam Item Previous NRC Exam 0999#119 0Modified Bank Item 0Other Exam Bank

[XI ILT Exam Bank Reference(s): ANN 114 G-I Learning LLOTOI30.02f 0bjective:

Knowledge/Ability 223001 Importance: RO / SRO WA K5.01 3.1 / 3.3 (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 (610) 718-4085 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 Bside 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: 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 Incorrect: A ADS is supplied by Div 1 and Div 3 DC r Incorrect:

Incorrect:

B D

I While B RPS will swap to its AC power source, it is still operable RClC is supplied by Div 1 and Div 3 DC Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.5 3 Y Y (b) (IO) N Source Documentation Source: New Exam Item [7 Previous NRC Exam Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): ARC-MCR-122 G2, ARC MCR-117 A I Learning LLOT0690.02 Objective:

Knowledge/Ability 263000 Importance: RO ISRO WA 2.4.31 3.3 13.4 (Description of K&A, from catalog)

DC Electrical Distribution: Knowledge of annunciators alarms and indicationslanduse of the response instructions Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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 4.0KV 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 Answer Key Question ID# 061 Both RC SQ>Q Basis or Justification Correct: B 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 Incorrect A Voltage meets the requirement, Frequency does not Incorrect C Frequency meets the requirement, voltage does NOT Incorrect ID Frequency meets the requirement, voltage does not Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 HIGH 3.5 4 Y Y (b) (7) N Source Documentation Source: New Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): E-I64 Learning LLOT0670.02. LLOT0660.04 0bjective:

KnowledgeJAbility 264000 Importance: RO / SRO WA A3.03 3.4 J3.4 (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 (610) 718-4085 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 I A 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 I A LPCl injection valve remains closed.

Page 124 of 200

Limer/ck Generating Station ILTO5-I NRC Initial Licensing Examination Answer Key Question ID# 062 Both RC Choice Basis or Justification Correct: C 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 Incorrect A This is incorrect as spray does not isolate (LOCA) signal received previously) additionally, it cannot be re-established until LPCl injection valve is closed Incorrect B This is incorrect as spray does not isolate (LOCA signal received previously)

~

Incorrect D This is incorrect as LPCl injection valve will open (Delta P ANN)

I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43

+

Low 4.0 3 Y y (b)(7)

Source Documentation Source: New Exam Item c]Previous NRC Exam L 0Modified Bank Item 0ILT Exam Bank ARC-MCR-113 F4, T-225 step 4.2.2 0Other Exam Bank LLOT0370.09b Objective:

230000 Importance: RO / SRO A4.02 3.8/ 3.6 (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 (610) 718-4085 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 IMain Generator conditions are as follows:

1175MWe 0 230 MVAR's (lagging)

Subsequently, IGEN 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 I125 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 Answer Key Choice Basis or Justification Correct: B Reduction in real load to less than 1125 MWe will restore the MW /MWe output to a value consistent with the 60 psig H2heating curve.

Incorrect: A H2Pressure would have to be restored to 75 psig in order to restore the MW/MWe output to within the armature heating curve.

Incorrect: C Reducing MVAR will not reduce the MW/MWe output to within the armature heating curve.

Incorrect: D A GP-4 Shutdown and trip of the Main Turbine would only be required if Hydrogen Pressure could not be maintained above 55 psig.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 10CFR55.43 High 3.5 4 N Y (b)(5) N Source: New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): ON-126, Attachment 1 Learning LLOT0600.10 0bjective:

Knowledge/Ability 245000 Importance: RO / SRO WA AI.Ol 2.7 / 2.7 Required Materials:

ON-126 Notes and Comments Prepared By:

Rick Rhode (61 0) 718-4085 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 1BY 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 Answer Key Question ID# 064 Both RC Choice Basis or Justification Correct: B APRMs power supply is auctioneered, therefore, APRMs are still indicating on a loss of IBY185. Loss of 1BY185 also results in a K SCRAM due to loss of power to 2 PRNMS voter units.

Incorrect A While APRMs would be indicating, this is incorrect because a full scram would not occur.

~~

Incorrect C This is incorrect because it requires a loss of both I A Y I85 and 1BY185 for the APRMs to fail downscale. In addition, a full scram would not occur.

Incorrect D 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.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.5 3 N Y (b)(7) N Source Documentation New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank ILT Exam Bank ANN 123 F-5, ANN 108 D-4, ANN 108 A-I LLOT0275.I3c Objective:

I Knowledge/Ability 215002 K2.03 (Description of K&A, from catalog)

~~~~ ~~ ~

Importance: RO I SRO 2.8 12.9 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. OA No C. OB Yes D. OB No Page 130 of 200

Limerick Generatinq Station ILTO5-I NRC Initial Licensina Examination Answer Key Question ID# 065 Both RC rFRq Choice Basis or Justification Correct:

I D 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)

Incorrect:

IA 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

~~~

Incorrect:

Incorrect:

lB C OA Fan will not start on a D RAD signal Same text as A distractor Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 I

Source Documentation Source: [XI New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank ILT Exam Bank P&ID M-26 sht 5 detail D, M-78 sht 1 LLOT0450.7a 0bjective:

Knowledge/Ability 290003 Importance: RO / SRO KIA K4.01 3.1 / 3.2 (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 (610) 718-4085 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 1B Reactor Recirc Pumps?

I A Recirc Pump 1B 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 Basis or Justification Correct: D 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 r

therefore, both pumps will be deenergized.

Incorrect: A Neither pump will be running due to RPT breakers for both pumps tripping Incorrect: B The I B will be tripped, however the 1 A will also be tripped.

Incorrect: C The 1 A will be tripped, however the 1B will also be tripped.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 HIGH 3.5 4 Y N Y (b)(5)

Source Documentation Source: HNew Exam Item Previous NRC Exam OModified Bank Item 0Other Exam Bank (LOR) 0ILT Exam Bank Reference(s): E-I FB, ARC MCR 11IC-5, ARC MCR 112 D-3, GP-18, step 1.O Learning LLOT0315.06 Objective:

Knowledge/Ability 2.4.21 I Importance: RO / SRO KIA 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 (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination

67. Unit Iplant 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 1BC208 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 Answer Key I Choice I Basis or Justification 1 Correct: C 1BC208 panel trouble and HPCl room temp are consistent Incorrect: Drywell pressure value is below Alarm setpoint I Incorrect:

B l Reactor pressure valve is below the ALARM setpoint L

I Incorrect: D SDV level is below the ALARM setpoint Psvc hometrics I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.5 3 N N Y (b)(5)

Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Modified Reference@): ANNS 004 A3 Learning LLOTI560.02 Objective:

Knowledge/Ability 2.4.46 Importance: RO / SRO WA 3.5 13.6 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

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 I Choice I Basis or Justification Correct:

IDl Liquid Radwaste discharge to Cooling Tower Blowdown Line isolates on Hi Hi Rad.

Incorrect Equipment Drain Sample Tank to CST isolates on EDST Level only (Pump off, discharge valve closes)

Incorrect B Waste Sludge Tank to external processing isolates on Low Waste Sludge Tank level only (Pump off, discharge valve closes)

Incorrect C 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.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 N N N Source: New Exam Item Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference@): ARC-MCR-003 RAD-A-5, ARC-BOP-OAC304-C-1 Learning 0bjective: I LL0T-0705-04 Knowledge/Ability 2.3.1 1 Importance: RO / SRO WA 2.7 13.2 Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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 Answer Key auestion ID# 069 ROISRC Choice Basis or Justification Correct: B 3 Rem = 3000 mRem 3000 mRem X .75= 2250 mRem 2250 mRem + 1760 mRem = 4010 mRem 4010 mRem exceeds 2000 mRem TEDE Admin Dose Control Level Incorrect A Admin Dose Control Level is exceeded Incorrect C 4010 mRem <NRC Limit of 5000 mRem Incorrect D 4010 mRem <NRC Limit of 5000 mRem 4010 mRem <Emergency Exposure Limit of 10,000 mRem for protecting station property Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 4 Y N Y (b)(4)

Source: 0New Exam Item Previous NRC Exam 2002 Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): RP-AA-203 sects 4.1 .I, 4.2,4.5 Learning LLOTI760.04,.05 Objective:

KnowledgelAbility 2.3.4 Importance: RO / SRO WA 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 (610) 718-4085 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 Iand Group 2 control rods are fully withdrawn.

SRM count rate data since the startup began is as follows:

0 Channel Y A has gone from 240 cps to 975 cps 0 Channel 1B has gone from 225 cps to 915 cps 0 Channel I C has gone from 220 cps to 890 cps 0 Channel I D 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 78 C. Between 18 and 30 D. Between 30 and 48 Page 140 of 200

Li merick Generat ing Station lLTO5-1 NRC Initial Licensing Examination 1 Answer Key Question ID# 070 Both RC I Choice Basis or Justification Correct: A 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.

Incorrect B 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.

Incorrect C Due to the reasons stated above, the 00 to 12 requirement still applies. I 8 to 30 falls outside that band.

Incorrect D Due to the reasons stated above, the 00 to 12 requirement still applies. 30 to 48 falls outside that band.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 N N N Source Documentation Source: 0New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): GP-2, Appendix I,Caution after step 3.2.7 Learning LLOTI530.02 0bjective:

KnowledgelAbility 2.2.1 Importance: RO I SRO WA 3.7 13.6 Required Materials:

GP-2, Appendix 1 Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generatinq Station ILT05-I NRC Initial Licensing Examination

71. Unit 1 PRO is performing ST-6-051-231-1, I A RHR Pump, Valve, and Flow Test.

At step 4.3.6, the PRO discovers that HV-51-1F021A is incorrectly identified as HV-51-1F022A.

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 Answer Key Question ID# 071 Both RC Choice Basis or Justification Correct: B The test must stop. An equipment number error requires a Temporary Change I.A.W. AD-LG-101-1002, before the test can continue.

Incorrect: A The status of the test is correct, but the procedure process cited is not correct.

Incorrect: C The procedure process cited is correct, however the test cannot continue.

~ ~

Incorrect: D Both the status of the test and the procedure process cited are incorrect.

Psychometrics I Level of Knowledge Low Difficulty 2.5 Time Allowance (minutes) 3 I pRA N

1 RO 10CFR55.41 Y (b)(lO)

I 10CFR55.43 SRo Y (b)(3)

I ISource: New Exam Item Source Documentation Modified Bank Item 0Previous NRC Exam 0Other Exam Bank 0ILT Exam Bank AD-LG-I 01-1002 Learning LLOTI570.01 Objective:

1 Importance:

LKnowledge/Ability 2.2.1 1 (Descriptionof K&A, from catalog)

Knowledge of the process for controlling temporary changes.

RO / SRO 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

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-109-1OI?

.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 Answer Key Question ID# 072 Both RC 9FtQ Choice Basis or Justification Correct: B When 2-valve protection is required but not available then the clearance shall be designated as Exceptional.

Incorrect: A A technical review is required only when there are questions about a systems response to the proposed isolation technique (such as logic

~

system response)

Incorrect: C A walkdown is suggested in circumstances where clearance informationor documentation is missing or in question Incorrect: D 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 Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 2.5 3 N Y (b)(lO) N Source Documentation Source: New Exam Item Previous NRC Exam Modified Bank Item [XI Other Exam Bank (CAT) 0ILT Exam Bank Reference@): OP-MA-109-101, attachment 4 Learning OP-MA-109-101 DB16 objective #2 0bjective:

Knowledge/Ability 2.2.13 Importance: RO / SRO WA 3.6 13.8 (Description of K&A, from catalog)

Knowledge of Clearance and Tagging procedures 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

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.

B. MFLPD and MAPRAT ONLY.

C. MFLPD, MAPRAT, and FLLLP.

D. All values are acceptable; no action is required.

Page 146 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key Question'ID# 073 Both RC ggg I Choice ~~

Basis or Justification Correct: B MFLPD (>I .O) and MAPRAT (20.99) require entry into GP-14

~

Incorrect: A MFLPD does require action (see above) but this choice omits MAPRAT, which also requires action

~

Incorrect: C FLLLP does not require action r Incorrect: D MFLPD and MAPRAT require action Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43 HIGH 2.5 3 N N N Source Documentation Source: 0New Exam Item Previous NRC Exam 0Modified NRC Bank Item Other Exam Bank (LOR-modified)

ILT Exam Bank Reference(s): GP-5, Sect 3.1.I Learning LLOT0741.04 Objective:

KnowledgeIAbility 2.1 . I 9 I Importance: RO / SRO KIA 3.0 13.0 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

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 I Answer Key Ic Question ID# 074 Both RC geq I Choice Basis or Justification Correct: C 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.

Incorrect: A There will be a % scram on B RPS, in addition to the Rod Withdraw Block.

Incorrect: B There will be a K scram on B, not A,RPS 1 Incorrect: 1 D There will be a K scram on only BRPS I~ Psychometrics I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 10CFR55.43 High 3 3 Y Y (b)(lO) Y (b)(3)

I Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): Tech Specs 2.2.1 and 3.3.6 Learning LLOT0250.08,09 Objective:

Knowledge/Ability 2.1.28 Importance: RO / SRO WA 4.0 / 3.5 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

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 3rdRO 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 Answer Key Choice Basis or Justification Correct: D 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 Incorrect: A 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.

Incorrect: B Duration is correct, turnover criteria described applies to full turnover, not short duration Incorrect: -I+ Turnover criteria is correct, short turnover duration is 60 minutes, not 30 Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 10CFR55.43 Low 2.5 3 N Y (b)(lO) N Source: New Exam Item Previous NRC Exam Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): OP-AA-112-101, Sect 4.1.7 Learning LLOTI 574.24 0bjective:

KnowledgelAbility 2.1.3 Importance: RO / SRO KIA 3.0 13.4 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILTO5-1 NRC Initial Licensing Examination

76. Unit 1 Plant conditions are as follows:

0 Reactor power is 100%

0 Reactor level is 35and 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-M1-1 RGOIA(B,C) A(B,C) RFPT Speed Controllers, and the procedure entered to address initial plant response?

Effect on Procedure FIC-M1-I RGOIA(B,C) Entered A. Swaps to Manual OT-I 00 B. Swaps to Manual OT-I I0 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 Answer Key CQuestion ID# 076 SRO Or i I Choice Basis or Justification Correct: B 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 Incorrect: A This is incorrect as OT-100 REACTOR LOW LEVEL, is for low reactor level, Reactor level will go up Incorrect C 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 Incorrect D This is incorrect as individual RFP M/A stations will swap to manual.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43 High 3.0 4 Y y (b)(5) y (b)(5)

Source: [XI New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): S06.1 .HU/1, Alarm Identity IXX-FW302.1TFFE S06.1 .D U/1 Appendix 1 Learning LLOT0550.1Od 0bjective:

Knowledge/Ability 259002 Importance: RO / SRO WA A2.03 3.6 I3.7 (Descriptionof 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) 718-4085 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 12OoFand 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 Station lLTO5-1 NRC Initial Licensinq Examination Correct: D 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 I 1 0 degrees Incorrect: A Injecting immediately is incorrect as Blowdown has already started. -60 to

-100 is incorrect as Supp pool temp is greater than 110 degrees Incorrect B Injecting immediately is incorrect as Blowdown has already started.

Incorrect -60 to -1 00 is incorrect as Supp pool temp is greater than 110 degrees I Psvchometrics I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43 High 4.0 4 Y Y (b)(lO) Y (b)(5)

Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): T-I 17 BASES, Step LQ-21 Learning LLOTI560.05 Objective:

KnowledgelAbility 295037 Importance: RO ISRO, KIA 2.12 0 4.3 14.2 T-I 17 Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station lLTO5-1 NRC Initial Licensinq Examination ATTACHMENT: SAMP-I Sheet 1 Provided I

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 Answer Key Question ID# 078 SRO Or /

Choice Basis or Justification Correct: D 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).

Incorrect: A 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.

Incorrect B Sheet 5 is incorrect as RPV injection is unsafe on MDRIR as plotted (20 minutes, Rx press 800 psig, injection rate 600 gpm)

Incorrect C Sheet 6 is incorrect as conditions are unsafe as plotted on PSP curve (pool level 22, and pressure 20 psig)

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 10CFR55.43 High 4.0 4 Y Y (b)(l 0) Y (b)(5)

Source: New Exam Item 0Previous NRC Exam Modified Bank Item Other Exam Bank (LOR)

ILT Exam Bank Reference(s): SAMP 1, Sheet 1 Learning LLOTI 562.6 Objective:

Knowledge/Ability 295031 Importance: RO I SRO WA 2.4.6 3.1 14.0 Required Materials:

SAMPI Sht 1 Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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-042-1R613 indicates core plate differential pressure is 1.3 psid 0 XR-042-1R613 indicates core flow is 42 x 1O6 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 Answer Key Choice ~

I Basis or Justification Correct: D 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.

Incorrect: A Immediately scram the reactor is not correct because the operating point is not in the Exclusion Region, therefore, a reactor scram is not required.

Incorrect B Restart 1B Recirc Pump and raise core flow with 1B recirc pump is wrong as restarting a pump to raise flow is not allowed in OT-I I 2 Incorrect C 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.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 10CFR55.43 High 3.0 5 N Y (b)(lO) Y (b)(5)

Source: New Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): OT-I 12, Step 3.7 Learning LLOT0040.07g Objective:

Knowledge/Ability 295001 Importance: RO / SRO WA 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. Level 1 Radiation Protection Manager B. Level 1 Plant Manager C. Level 2 Radiation Protection Manager D. Level 2 Plant Manager Page 160 of 200

Limerick Generating Station ILT05-I NRC Initial Licensina Examination Answer Key Question ID# 080 SRO Or Y

~~

Basis or Justification Correct: The area is a Level 1 LHRA ( 2 1000 hr/hr and < I 5 Whr) per RP-LG-460-1010. This requires authorizationfrom the RP Manager for issuing the key per RP-LG-460-1016.

Incorrect: B The level is correct, but the Plant Managers authorization is not required.

incorrect C 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.

Incorrect ID Level 2 LHRA would be an area with dose rate 2 15 Whr. The Plant Manager may authorization for this entry.

I I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 4.0 4 N N (b) (4)

Source: 0New Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): RP-LG-460-1010, RP-LG-460-1016.

Learning LLOTI760.01 Objective:

Knowledge/Ability 295016 Importance: RO / SRO KIA 2.3.1 2.6 13.0 Notes and Comments:

Prepared By:

Rick Rhode (610) 718-4085 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 2B loop of SDC is in service 0 Reactor coolant temperature is 3OO0F 0 RPV pressure is 54 psig 0 ?A RHR Heat Exchanger is being drained for maintenance 0 A Group IIsolation signal is in for I&C testing 0 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 Answer Key Choice

~~

I Basis or Justification Correct: 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.

Incorrect: A Dedicated LPCl Pumps will not work because SDC is isolated.

Incorrect IBl RHR Alternate SDC lineup will not work because current plant conditions will not support it.

Incorrect ici Although this choice correctly identifies that RPV pressure must be reduced, MSL drains will not work because the condenser is not available.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 10CFR55.43 High 4.0 4 Y Y (b)(lO) y (b) ( 5 )

Source Documentation Source: New Exam Item Previous NRC Exam Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): ON-121, Attachment 5 Learning LLOT0370.13 0bjective:

Knowledge/Ability 295021 Importance: RO / SRO K/A AA2.06 3.2 / 3.3 (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 (610) 718-4085.

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 I B LP Turbine Back Pressure is 6.6 in Hg Abs 0 I C 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 Answer Key Question ID# 082 SRO 01 i Choice Basis or Justification Correct:

I C 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 Incorrect:

l A If turbine backpressure could not be restored, then a GP-4 Shutdown is directed. Tripping the turbine at this time is not directed.

Incorrect Incorrect IB D 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 Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43 High 3.0 3 Y Y (b) (IO) Y (b) (5)

Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s ): GP-5 Attachment 7 Learning LLOT0500.06a Objective:

1

~

Knowledge/Ability 295002 Importance: RO / SRO WA AA2.01 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 (610) 718-4085 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 Answer Key CQuestion ID# 083 SRO Or I Choice Basis or Justification I Correct: I B 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 (110 degrees F) once T-I 02 or T-117 is entered.

Incorrect Incorrect ic D 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.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.0 3 N N Y (b)(2)

Source: New Exam Item Previous NRC Exam Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): Tech Spec basis 3.6.2.1 Learning LLOTOI30.04f Objective:

Knowledge/Ability 295013 Importance: RO / SRO WA 2.2.25 4.0 / 4.0 Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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-10/20 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 I

I Basis or Justification Correct: D 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.

Incorrect: A The procedure reference is not correct. PAMS is not available.

incorrect B The procedure reference is correct. PAMS is not available.

r--- Incorrect C The procedure reference is not correct. The instrument is correct.

Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 3 Y Y (b)(lO) Y (b)(5)

Source: [XI New Exam item 0Previous NRC Exam 0Modified Bank Item c]Other Exam Bank 0ILT Exam Bank Reference(s ): E-I, E-I0/20 Learning LLOT0275.13 0bjective:

Knowiedge/Ability 295003 Importance: RO / SRO WA AA2.02 4.2 / 4.3 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 Iplant 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?

RPV Water Level Procedures Instrument Entered A. Wide Range Recorder T-290, T-291 ONLY XR42-I R623A on 1OC601 B. Wide Range Recorder T-290, T-291, T-250 XR42-I R623A on 1OC601 C. Upset Range Recorder T-290, T-291 ONLY LR-42-1 R608 on IOC603

d. Upset Range Recorder T-290, T-291, T-250 LR-42-1R608 on 1OC603 Page 170 of 200

Limerick Generating Station ILT05-I NRC Initial Licensinq Examination Answer Key 1 Question ID# 085 SRO Or i I Choice Basis or Justification 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.

XR42-1R623A on IOC601 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 incorrect: A XR42-1R623A on 1OC601 is correct, but, as noted above T-250 should be performed per step SCCTT-5 incorrect C LR-42-1R608 on 1OC601 is a not a PAM and cannot be used Incorrect D LR-42-1R608 on 1OC601 is a not a PAM and cannot be used I Psvchometrics I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 Y Y (b)(lO) Y (b)(5)

Source: New Exam Item Previous NRC Exam 17 Modified Bank Item 0Other Exam Bank 17 ILT Exam Bank Reference(s): T-291 Attachment 2 Learning 0bjective: II Knowledge/Ability 295032 LL0T1561.03 I Importance: RO ISRO WA I EA2.02 3.3 13.5 (Description of K&A, from catalog) Ability to determine and/or interpret equipment operability as it applies to high secondary containment area temperature

?quiredMaterials:

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 Drywell pressure is 24 psig and rising slowly 0 Drywell temperature is 32OoF and rising slowly 0 RPV pressure is 350 psig and dropping slowly 0 Suppression Pool pressure is 19 psig and rising slowly 0 Suppression Pool temperature is 96OF and rising slowly 0 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?

BAS IS A. Spray the Drywell Reduce containment pressure while per T-225 preventing excessive negative pressure In the Drywell B. Perform an Emergency Transfer RPV energy to the Suppression Blowdown per T-I12 Pool due to steam in the pool airspace preventing containment function C. Spray the Drywell Reduce containment temperature in order to per T-225 prevent exceeding the Drywell ternperature limit D. Perform an Emergency Transfer RPV energy to the Suppression Blowdown per T-I 12 Pool before conditions threaten the integrity of the SRV tailpipes Page 172 of 200

Limerick Generating Station ILT05-I NRC Initial Licensinq Examination Answer Key Question ID# 086 SRO Or I

~~~

Basis or Justification Correct: 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.

1 Incorrect: I A This is a legitimate reason for spraying the drywell if conditions supported this action. Current conditions are unsafe to spray.

Incorrect C This is a legitimate reason for spraying the drywell if conditions supported this action. Current conditions are unsafe to spray.

u Incorrect Level of Difficulty 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.

Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43 High 3.0 3 Y y (b)(lO) Y (b)(5)

Source Documentation Source: New Exam Item 0Previous NRC Exam Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): T-102, T-102 Bases Learning LLOTI560.06 0bjective:

Knowledge/Ability 295024 I Importance: RO / SRO WA EA2.04 3.9 / 3.9 (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 (610) 718-4085 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 I C Main Steam ine (R

, SL) High Flow Transrr ters PDT-41-1N088B 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 Answer Key Question ID# 087 SR-0 Or I I Choice Basis or Justification Correct: D 88C is Div 1. 88B is Div 2. therefore there is only one Div 1 and Div 2 instrument operable for the 1C 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 />.

Incorrect: A 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.

Incorrect B 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 I

having to place it in the tripped condition I Incorrect C 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 Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 5 N Y (b)(5) y (bP)

Source Documentation Source: [XI New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): Unit 1 Tech Specs, LCO 3.3.2 Learning LLOTOI80.1OC 0bjective:

KnowledgeiAbility 223002 Importance: RO i SRO WA A2.08 2.7 i 3.1 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

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 Answer Key 4-Question ID# 088 SRO 01 Choice Basis or Justification Correct: A 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.

Incorrect:

I B Work on a CRDM hydraulic line does not qualify as an Operation with Potentialfor Draining the Vessel.

Incorrect 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.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 4.0 4 Y N Y (b)(2)

Source Documentation Source: New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): Tech Spec 3.8.1.2, GP-6.2 Learning LLOT0670.13 0bjective:

KnowledgelAbility 264000 Importance: RO / SRO WA 2.2.22 4.0 14.0 (Description of K&A, from catalog)

Knowledge of limiting conditions for operational and safety limits.

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

89. Unit 2 conditions are as follows:

0 An inadvertent Group Iisolation 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?

0perator Action Procedure A. Throttle closed HV-49-2F013, S49.7.A, Transfer of RClC From RClC Pump Discharge to Pressure Control Mode to Injection Feedwater Mode and Back B. Raise output of the RClC flow OP-LG-I 08-101-1001, Simple Quick Controller Actsnransient Acts C. Throttle open HV-49-2F013, S49.7.A, Transfer of RClC From RClC Pump Discharge to Pressure Control Mode to Injection Feedwater Mode and Back D. Lower output of the RClC flow OP-LG-108-101-1001, Simple Quick Controller Actsnransient Acts Page 178 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key Choice I Basis or Justification Correct: D 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.

I ncorrect: A 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.

Incorrect B 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.

Incorrect C 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.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 Y y (b)(5) y W(5)

Source: New Exam Item 0Previous NRC Exam Modified Bank Item Other Exam Bank c]ILT Exam Bank Reference(s): S49.7.A Learning LLOT0380.08 0bjective:

Knowledge/Ability 217000 Importance: RO / SRO WA A2.10 3.1 / 3.1

!QUIRED MATERIALS:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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 required proceduraI act ions?

Initial EHC Response Procedural Action A. BPV(s) remain closed, reactor Reduce reactor power to less pressure rises to Scram setpoint than 90% per OT-I02 without operator action B. BPV(s) remain closed, reactor Reduce reactor power until pressure rises to Scram setpoint pressure is less than 1053 psig without operator action per OT-I 04 C. BPV(s) open, reactor pressure Reduce reactor power to less rises and stabilizes without than 90% per OT-I02 operator action D. BPV(s) open, reactor pressure Reduce reactor power until rises and stabilizes without pressure is less than I053 psig operator action per OT-I 04 Page 180 of 200

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 090 SRO-Or I Choice Basis or Justification Correct: C 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.

Incorrect: A This is incorrect as Reactor pressure will not reach the scram setpoint.

Electricalfailure of the solenoid for the control valve does not affect bypass valve response. The procedural action is correct.

Incorrect B This is incorrect as Reactor pressure will not reach the scram setpoint.

Electricalfailure of the solenoid for the control valve does not affect bypass valve response. While power may rise slightly, if OT-104 were entered, it

---t Incorrect D 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.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High '3.0 4 N y (b)(5) y Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item c]Other Exam Bank 0ILT Exam Bank Reference(s): OT-102,step 3.5 T.S. 3.2.3.b Learning LLOT0590.02a 0bjective:

Knowledge/Ability 241000 Importance: RO / SRO WA A2.04 3.7 / 3.8 Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-I NRC Initial Licensing Examination

91. Unit Iplant conditions are as follows:

0 95%power 0 IC 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 1Idays 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 1C 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.

a4 r,/3(ob 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 Answer Key jr Choice Basis or Justification Correct: C 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 /> Incorrect: A This is a Tech Spec 3.0.3 action applicable only when LCOs cannot be met Incorrect B This would be the correct action if HPCI were operable.

Incorrect D This would be correct if IC RHR were operable with HPCl INOP Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 4 Y N Y (b)(2)(5)

Source: U N e w Exam Item 0Previous NRC Exam Modified Bank Item Other Exam Bank (LOR modified)

ILT Exam Bank Reference(s): T. S. 3.5.1.b and 3.5.1.c.2 Learning LLOT0340.16 Objective:

Knowledge/Ability 206000 Importance: RO ISRO KIA 2.1.12 2.9 14.0 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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 18OoFand 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 Yes B. T-I03 ONLY 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 Answer Key Question ID# 092 SRO Or /

I Choice Basis or Justification Correct: D 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.

Incorrect: A T-I04 entry is required and T-I 12 is not for the reasons given above.

I ncorrect B T-104 entry is required for the reason given above.

Incorrect C T-I 12 is not required for the reason given above Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 N Y (b) 10 y (b)(5)

Source: 0New Exam Item [XI Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): Emergency Action Level Matrix (Table 3-I), T-103, T-I04 Learning LLOTl560.02,06 0bjective:

KnowledgelAbility 2.4.1 Importance: RO I SRO WA 2.3 14.1 Required Materials:

EAL Matrix Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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 HZis 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 Answer Key

~~ ~~ ~~

Basis or Justification 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)

Allowed but not preferred per the note in section 4.3 and Table 1 of T-228 Does not apply to the given conditions Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): T-228 section 4.3, 4.5 and 4.6 Learning LLOTI561-03 0bjective:

Knowledge/Ability 2.3.9 Importance: RO I SRO K/A 2.5 13.4 Required Materials:

T-228 Assessment Table, and section first pages Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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 Aand B for Rod 30-31 are taken to TEST and then immediately back to NORMAL 13:00:08 - Control rod 30-31 is at Position 1.88 05 a

WHICH ONE of the following describes the required action?

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 Answer Key

?a Question ID# 094 SRO Or Choice Basis or Justification C 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 .

Incorrect: A 30-31 is not OPERABLE, therefore it cannot just be regored to position 12.

B The rod is INOP, Incorrect ID While 30-31 must have insertion capability demonstrated, its original position is 12, not 48.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 N Y (b)(10) y (b)(2)

Source Documentation Source: New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): TS 3.1.3.2 AND 3.1.3.1 Learning LLOT0060.12 0bjective:

Knowledge/Ability 201002 2.1.32 Importance: RO ISRO WA 3.4 13.8 (Description of K&A, from catalog)

Ability to explain and apply system limits and precautions.

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

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 Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key Question ID# 095 SRO Or I Choice Basis or Justification 1 Correct: B 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 1IOOF, SLC injection is required per T-101.

I Incorrect: A While T-217 and T-218 are required, T-I01 requires SLC injection.

Incorrect C 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.

Incorrect D 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.

Psychometrics Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 5 High 3.5 4 Y b 10 Y b 5 Source Documentation 1 Source: 0New Exam Item Previous NRC Exam I

Modified Bank Item Other Exam Bank 0ILT Exam Bank T-I 01 Learning LLOTI560.06 0bjective:

I Knowledge/Ability 2.4.6 WA (Description of K&A, from catalog)

Importance: RO / SRO 3.1 /4.0 Knowledge of symptom based EOP mitigation strategies.

~~ ~~

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

96. WHICH ONE of the following identifies Work Execution Centerwork Control Center Supervisor (WCS) staffing requirements per OP-AA-I 01-11Iand 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 Generatinq Station ILT05-1 NRC Initial Licensing Examination

~~

Answer Key Question ID# 096 SRO Or i I Choice Basis or Justification 1

~ ~~ ~

Correct: C If WCS is STA then IA function is not required (OP-AA-101-1I1, 4.5.2) 1 Incorrect: A

~

WCS cannot be both STA and IA (OP-LG-I 01-111, Attachment 3)

I

~~

I Incorrect B WCS cannot be both IA and NRC Communicator (OP-LG-101-11I, Attachment 3)

I Incorrect D If WCS is the IA, they support the STA function, the STA is stili required Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.0 3 N N Y (b)(2)

Source Documentation Source: New Exam item 0Previous NRC Exam 0Modified Bank item 0Other Exam Bank 0ILT Exam Bank Reference(s): OP-AA-101-11 I,page 5, step 4.5 OP-LG-101-111, page 11 #3 Learning LLOTI 574.01a 0bjective:

Knowledge/Abiiity 2.1.4 importance: RO / SRO KIA 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 (610) 718-4085 Limerick Regulatory Exam Author

- __ - ~~

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination

97. The AChlorine 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?

ACREFAS 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 Answer Key Question ID# 097 SRO Or I I Choice Basis or Justification 1 Correct: A 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.

Incorrect: B The procedure reference is correct, however the A CREFAS is running.

~~~

Incorrect C The fan status is correct, however manual isolation is not required and only verification of the existing isolation.

Incorrect D The A CREFAS is running and manual isolation is not required and only verification of the existing isolation.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 4 N N Y (b)(5)

Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): E-IFC, SE-2 Learning LLOT0450.03,07 0bjective:

Knowledge/Ability 290003 Importance: RO / SRO WA A2.01 3.1 13.2 (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 (610) 718-4085 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 Answer Key i

Choice Basis or Justification Correct:

Incorrect:

II DA Changes to activities in a procedure requires a SQR review Changes to reference are excluded from requiring SQR review Incorrect IB Editorial change are excluded from requiring SQR review Incorrect IC Addition of clarifying information is excluded from requiring SQR review Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.5 4 N N Y (b)(3)

Source Documentation Source: 0New Exam Item c]Previous NRC Exam Modified NRC Bank Item 0Other Exam Bank extensively modified ILT exam bank item c]ILT Exam Bank Reference(s): AD-AA-101, Page 3, step 4.3.5 Learning LLOTI570.013 0bjective:

Knowledge/Ability 2.2.6 I Importance: RO / SRO WA 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 (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generat ing Station ILT05-1 NRC Initial Licensing Examination

99. Fuel is being loaded into the core on Unit 1 with the following conditions:

0 I A SRM count rate is 3.5 cps and has a signal-to-noise ratio of 2.0 0 1B 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 I D 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 Answer Key Question ID# 099 SRO Or Choice Basis or Justification Correct: C B and CSRMs are inoperable (ICdue to inadequate signalhoise ratio, per T.S. fig 3.3.6-1) Therefore, Fuel movement is only permitted in quadrants Aand D per T.S. 3.9.2 Incorrect: A See above Incorrect B See above Incorrect D Fuel cannot be loaded into quadrant C because its SRM is inoperable.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 4 N N (b) (7)

Source Documentation ~

Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): T.S. 3.9.2 and Figure 3.3.6-1 Learning LLOT0240.10 0bjective:

Knowledge/Ability 2.2.28 Importance: RO / SRO WA 2.6 / 3.5 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 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~+ pb 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 Answer Kev -

I Choice Basis or Justification Correct: A 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 Incorrect: B This action would be correct if hot well conductivity were rising, which is not indicated

~~~

Incorrect C This action would be appropriate if GP-12 action level 3 (>5 ymhokm) were reached Incorrect D This action would be appropriate if the plant was in any OPCON other than 1,2or3 Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 4 N Y (b)(lO) Y (b)(5)

Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): GP-12, Sect 3.3, ON-I 16, T&RM 3.4.4 Learning LLOTI030.12 0bjective:

Knowledge/Ability 2.1.34 Importance: RO / SRO K/A 2.3 12.9 (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 (610) 718-4085 Limerick Regulatory Exam Author