ML062930254

Oct. 2006 Exam - Draft - RO & SRO Written Exam (Folder 2)

ML062930254
Person / Time
Site:	Limerick
Issue date:	09/11/2006
From:	Todd Fish Operations Branch I
To:	Exelon Generation Co
Sykes, Marvin D.
References
Download: ML062930254 (200)

Text

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NRC Question Data Sheet

1. Unit 1 is at 100% power when the failure of a Main Generator Lockout Relay causes a Unit 1 Main Generator Lockout resulting in:

0 Main Turbine Trip 0 A Reactor Scram occurs to limit the power excursion WHICH ONE of the following describes the reason a power excursion occurs as a result of a turbine trip?

A. A rise in feedwater subcooling when extraction steam is lost.

B. A rise in void concentration when turbine steam admission valves close.

C. A reduction in feedwater subcooling when extraction steam is lost.

D. A reduction in void concentration when turbine steam admission valves close.

Page 2 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Kev Question ID# 001 Both RC I Choice Basis or Justification Correct: D Void concentration will rapidly deplete on closing of the turbine steam admission valves resulting in a large positive reactivity addition.

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

Incorrect B This is incorrect since void concentration will deplete, not go up.

Incorrect This is incorrect since feedwater subcooling will go up, not go down.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 HIGH 2.5 2 Y (b) (5) N/A Source: New Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): LGS UFSAR, Chapter 15.2.3.3.3.1 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

NRC Question Data Sheet

2. Unit 2 plant conditions are as follows:

0 Reactor Power is 100% power 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. X X (two Xs) on the Four Rod Display.

B. Green IN light is lit on the Full Core Display.

C. - -I (two dashed lines) on the Four Rod Display.

D. Blue SCRAM light is lit on the Full Core Display.

Page 4 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Two Xs on the Four Rod Display indicate that control rod indication is unknown, due to more than one reed switch being made up.

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

Incorrect 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) IOCFR55.41 10CFR55.43 LOW 2.0 3 N (b) (10) (b) (5)

Source: [XI New Exam Item Previous NRC Exam

[7 Modified Bank Item Other Exam Bank 0 ILT Exam Bank Reference(s): ARC 108 Reactor, E-4

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Learning Objective: 1 LLoT0080.02 Knowledge/Ability 295006 Importance: RO / SRO WA AA2.02 4.3 / 4.4 Required Materials:

Notes and Comments:

Prepared By:

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

NRC Question Data Sheet

3. LGS Site conditions are as follows:

0 Both Units are at 100% power.

0 Both Units Auxiliary transformers are supplying their respective Unit Auxiliary busses.

The 10 Station Auxiliary Bus is de-energized for maintenance.

All other station electrical busses are energized.

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 B u s twenty (20) seconds later?

22 Auxiliary Bus D22 Safequard Bus A. de-e nergized de-ene rgized B. energized de-energized C. de-energized energized D. energized energized Page 6 of 200

LIMERICK October 2006 Initial License Operator NRC Examination I Choice Basis or Justification I 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 B 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 L Incorrect 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.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 HIGH 3.5 3 Y (b) (10) (b) (5)

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

I Knowledge/Ability 295003 I Importance: RO / SRO I WA I AA2.04 3.5 / 3.7 Required Materials :

Notes and Comments Prepared By:

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

NRC Question Data Sheet

4. Unit 1 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.

0 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 (I F003)

A. Closed Open B. Closed Closed C. Open Closed D. Open Open Page 8 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Choice I 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 1F002 valve does not isolate due to NO control power to the isolation logic Incorrect B The 1F002 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 Know1edge (minutes) 10CFR55.41 10CFR55.43 HIGH 3.0 3 Y (b) (7) N/A Source Documentation Source: [XI New Exam Item 0Previous NRC Exam Modified Bank Item Other Exam Bank 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 0bjective:

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

Notes and Comments:

Prepared By:

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

NRC Question Data Sheet

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

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LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 005 Both RC I Choice Basis or Justification Correct:

ID Per OT-I 01 bases, the Drywell may be vented if pressure is less than 1.68 psig. Therefore, slowing the rate of Drywell pressure rise allows time to vent.

Incorrect 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 B The Drywell chill water isolation may be bypassed after entry into and meeting the Drywell temperature requirements of T-I 02 Incorrect C 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 I Source Documentation Source: New Exam item Previous NRC Exam Modified Bank Item 0Other Exam Bank c]ILT Exam Bank Reference@): OT-101, Bases Step 2.1 Learning LLOTI540.05 0bjective:

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

Notes and Comments:

Prepared By:

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

NRC Question Data Sheet

6. Unit 2 plant conditions are as follows:

0 The 2BRecirc. Pump has tripped.

0 Reactor power is 68%.

0 All feedwater heaters are in service.

0 Four OPRM channels are operable.

0 The unit is in the Restricted Region of the Power to Flow map.

Subsequently, the 2ARecirc. 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 October 2006 Initial License Operator NRC Examination Answer Key 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: A A scram is required, however, not to avoid THI. See basis for answer C.

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

Incorrect D r--

This is not an allowed action in natural circulation.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 LOW 2.0 2 N (b) (8) to (IO) NIA Source Documentation Source: New Exam Item 0 Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): OT-I 12 Bases, step 2.1 Learning LLOTI540.05 Objective:

KnowledgelAbility 295001 Importance: RO I SRO KIA AKI .01 3.5 13.6 (Description of K&A, from catalog)

Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: Natural circulation Required Materials:

Notes and Comments:

Prepared By:

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

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NRC Question Data Sheet

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 October 2006 Initial License Operator NRC Examination Answer Key Question ID# 007 Both RC WQ Choice Basis or Justification Correct:

IB A STATOR WATER COOLING RUNBACK has occurred which lowers load set to 21.4 %, this closes control valves which raises Reactor pressure opening bypass valves Incorrect: A This is incorrect as bypass valves will open Incorrect C This is incorrect as load limit does not runback Incorrect D This is incorrect as load limit does not runback, also bypass valves will open Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 4 N y W(7) N Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): ON-1 14, Step 2.10 Learning LLOT0590.03 Objective:

Knowledge/Ability 295007 Importance: RO / SRO WA MI.05 3.7 i 3.8 Notes and Comments:

Prepared By:

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

NRC Question Data Sheet 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 co nditions:

0 All SE-1 immediate operator actions are complete 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 October 2006 Initial License Operator NRC Examination Choice Basis or Justification 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 Incorrect C This does not identify the minimum amount of time before SDC can be placed in service.

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

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

Source Documentation Source: New Exam Item Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s1: SEI, Attachments 2 & 3 Learning LLOT0735.04 0bjective:

Knowledge/Ability 295016 Importance: RO / SRO K/A 2.1.25 2.8 13.1 (Description of K&A, from catalog)

Ability to obtain and interpret station reference materials such as graphs / monographs / and tables which contain performance data Required Materials:

SE-I Notes and Comments:

Prepared By:

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

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NRC Question Data Sheet t

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 Procedural Direction TECW Heat Exchangers A. ESW E-l0/20, Loss Of Offsite Power B. ESW E - I , Station Blackout C. RECW E-I 0/20, Loss Of Offsite Power D. RECW E - I , Station Blackout Page 18 of 200

LIMERICK October 2006 Initial License Operator NRC Examination iAi

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Correct: ESW can be used to backup normal Service Water for TECW and RECW by performing manual local valve manipulations per E-I 0/20.

Incorrect IBl The correct procedure is E-I0120. Since six of the Diesel Generators start, this is not a Station Blackout.

Incorrect RECW is not hard piped to backup TECW.

Incorrect

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

I Psvchometrics I 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: 1 0New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank

[XI ILT Exam Bank '

Reference(s): E-10/20, Attachment 5 Learning LLOT0430.07 0bjective:

Knowledge/Ability 295018 Importance: RO / SRO WA AA1.01 3.6 / 3.5 Required Materials:

Notes and Comments:

Prepared By:

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

NRC Question Data Sheet 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 1 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 1AYInstrument Air Header Pressure is 69 psig and dropping slowly 0 1B 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 is102 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. 1B Instrument Air compressor Service Air Compressor B. I 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 October 2006 Initial License Operator NRC Examination Answer Key Choice I Basis or Justification Correct: A 1B Compressor will begin supplying the I A loads on higher pressure due to check valves at the individual load. Service Air Compressor remains in service for service air loads.

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

Incorrect IDl 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 Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): M-I 5 Learning LLOT0730.02, 04, 07, 10 0bjective:

KnowledgelAbility 295019 Importance: RO I SRO KIA AK3.01 3.3 13.4 Required Materials:

Notes and Comments:

Prepared By:

Rick Rhode (61 0) 718-4085 Limerick Regulatory Exam Author

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NRC Question Data Sheet II. 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 necessitated establishing Alternate Shutdown cooling using SRVs and Suppression Pool Cooling.

Conditions have been established as follows:

e Suppression Pool Cooling is in service with 2A RHR.

Suppression Pool pressure is 0 psig SRV handswitches for the 2K and 2M SRVs are in the OPEN position Injection to the RPV has been established with the 2D RHR pump via HV-51-2F017D RPV Level is 150 on Shutdown Range RPV pressure is 20 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

8. Increase RPV injection until RPV Level is 2 200 C. Reduce RPV injection until RPV pressure is 5 25 psig D. Increase RPV injection untilRPV pressure is 2 50 psig Page 22 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Kev

$RCj Basis or Justification Correct D 50# DIP is required across the SRVs in order to open and establish alternate heat removal.

Incorrect I A While 1 0 0 is an important milestone in OT-I00 Reactor High Level, when trying to prevent filling MS lines, filling the MSLS is required for this procedure.

Incorrect 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.

- Psychometrics I

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 IOCFR55.43 High 4.0 5 Y Y (b) (7) N Source Documentation Source: [XI New Exam Item c]Previous NRC Exam c]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 295021 Importance: RO I SRO WA AA1.04 3.7 13.7 (Description of K&A, from catalog)

Ability to operate and or monitor the following as they apply to LOSS OF SHUTDOWN COOLING:

Alternate Heat Removal Methods Required Materials Notes and Comments Prepared By:

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

NRC Question Data Sheet

12. Unit 1 plant 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-5I-lF017B, LPCl INJECTION, red, green and white lights lit HV-51-1FO21B, INBOARD SPRAY, red light lit HV-51-1F024I3, FULL FLOW TEST, red, green and white lights lit The CRS has directed the PRO to place 1B RHR in Drywell Spray.

WHICH ONE of the following actions must be performed to initiate Drywell Spray?

A. Arm and depress 1B RHR manual LOCA initiation pushbutton and open HV-51-1 FOI 6B B. Close HV-51-1F021B, then open HV-51-1F016B, then reopen HV-51-1 F021B.

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

D. Close HV-51-1F024B and open HV-51-1F016B.

Page 24 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key This valve manipulation only required if LOCA signal not present. 17B must also be closed..

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Incorrect D 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: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): 1-225, Step 4.5 Learning LLOT0370.09 Objective:

Knowledge/Ability 295024 Importance: RO / SRO WA EA1.04 4.1 13.9 (Descriptionof K&A, from catalog)

Ability to operate and/or monitor the following as they apply to HIGH DRYWELL PRESSURE:

RHR/LPCI Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

13. An EHC piping rupture on Unit 1 has resulted in a Turbine Trip and closure of Turbine Bypass Valves.

Unit 1 Reactor failed to SCRAM and RPV Level was intentionally lowered per T-I 17.

The following conditions currently exist:

0 Reactor power is 6%

0 RPV level is -195 and slowly rising 0 1 ADS SRV is open 0 RPV pressure is I 0 0 0 psig 0 Suppression Pool temperature is 145°F and slowly rising 2 Loops of suppression Pool cooling are in Service 0 Suppression Pool pressure is 6 psig & slowly rising 0 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 SPIL-I 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-I Heat Capacity Temperature Limit D. Perform Emergency Blowdown per T - I 12, due to the safe side of SP-T-1, Heat Capacity Temperature Limit cannot be maintained Page 26 of 200

LIMERICK October 2006 Initial License Operator NRC Examination

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Answer Key Question ID# 013 Both RC FRj I Choice Basis or Justification I Correct 1 c SP temp is 20°F from HCTL and rising slowly despite having 2 loops of SP Cooling in service. T-102 SP/T-8 directs that of SP temp cannot be maintained on the safe side of HCTL, then maintain RPV pressure on the safe side of HCTL.

SP level is high but 3.5feet away from SP/L-1 limit and level is stable -

Reducing pressure for the purposes of maintaining this curve is not i

warranted.

Incorrect While RPV Level is <-I 86, it is only 9 OOB and rising slowly. The criteria for T-I 17LQ is level can be restored. With SRVs being used for pressure control, it is not unusual to go <-I 86 for short periods of time. T-I 12 is not warranted under these conditions.

Incorrect ID SP temp is still 20°F away from HCTL and rising slowly. T-I 12 is not warranted at this point Psychometrics Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 4 High 3.5 4 Y b 10 y b) 5)

Source: [XI New Exam item Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): T-I 02 sh. 1 Learning LLOT1560.04 Objective:

Knowledge/Ability 295026 Importance: RO / SRO WA EA2.03 3.9 14.0 Required Materials:

T-I02 Sht. 1 Notes and Comments Prepared By:

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

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NRC Question Data Sheet

14. A LOCA is in progress on Unit 2 Drywell Temperature is 148°F The CRS directs the PRO to maximize drywell cooling 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?

D w e l l 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 October 2006 Initial License Operator NRC Examination I Choice Basis or Justification Correct: B Meets the criteria specified in T-102 Bases, for step DW/T-5 i Incorrect: A Does not meet the criteria specified in T-I02 Bases, step DWR-5. Only has one DWCW pp cunning vs. two Incorrect C Does not meet the criteria wlrespect 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.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank I ILT Exam Bank Reference(s): T-I02 Bases, DWR-5 Learning LOT-I560.06 0bjective:

Knowledge/Ability 295028 Importance: RO / SRO WA EK2.04 3.6 13.6 Required Materials:

T-I 02 Notes and Comments Prepared By:

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

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NRC Question Data Sheet

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 present direct pressurization of the Suppression Pool Page 30 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 015 Both RC SRQ I Choice Basis or Justification Correct: D HPCI Exhaust line is uncovered at 18. Operation of HPCI, with its relatively high exhaust pressure could result in direct pressurization of the Sumression Pool sufficient to exceed PCPC.

Incorrect A NPSH limit for RCIC would be at 12.3 (13.5 for T-I02 sh 1)

Incorrect B NPSH limit for HPCl would be at 15.42 ft, where it is already secured at 18 for the reason above C RClC Turbine exhaust pressure is insufficient to cause pressurization of the Suppression Pool in excess of PCPL.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 2.5 3 Y Y (b) ( 5 ) NIA Source: [XI New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): T-102, sh. 1 Learning LLOTI 560.05 Objective:

KnowledgeIAbility 295030 Importance: RO / SRO KIA EK3.02 3.5 13.7 Required Materials:

Notes and Comments Prepared By:

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

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NRC Question Data Sheet

16. A Loss of all High Pressure Injection has occurred on Unit 1 with conditions as follows:

0 All Rods in 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 Iniection A. -175 795 psig None B. -1 85 800 psig I B CRD pump C. -195 910 psig None D. -205 890 psig 1BCRD pump Page 32 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 016 Both RC pFQ I 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 <loo# below recorded value, this supply calls for a new pressure load.

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.

I 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 I

adequately cooled.

I 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 PF?A RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.5 5 Y (b) (8-10) N/A Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0 ILT Exam Bank Reference(s): T-I 11 BASES, LR-12 through LR-17 Learning LOT-I560.03 0bjective:

I I Importance:

~~ ~

Knowledge/Ability WA 295031 RO / SRO WA I EK1.O1 4.6 14.7 Required Materials:

Notes and Comments Prepared By:

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

__

NRC Question Data Sheet

17. Core reload has just commenced on Unit 1 during a refueling outage.

While lowering a fuel assembly not adjacent to an SRM count rate increases from 30 cps to 60 cps.

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 October 2006 Initial License Operator NRC Examination Answer Key Question ID# 017 Both RC SRbj Choice Basis or Justification Correct: B FH-105 requires suspension of component movement when one doubling is reached Incorrect A This would only be appropriate in the event of criticality.

Incorrect C FH-105 requires suspension of component movement when one doubling is reached Incorrect D This would be correct for the SRM count rate rise if it were poJ the third assembly adjacent to the detector.

Level of Difficulty Time Allowance PRA RO SRO Know1edge (minutes) 10CFR55.41 10CFR55.43 High 2.0 3 Y (b) (8-10) NIA Source Documentation Source: New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): FH-105, STEP 3.7 Learning LLOT0760.12 Objective:

KnowIedgelAbility 295023 Importance: RO I SRO K/A 2.2.28 3.5 I 3.3 Required Materials:

Notes and Comments Prepared By:

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

-

NRC Question Data Sheet

18. Unit IPlant is operating at 100% power when the following occurs:

0 The "IC" Inboard MSlV fails closed 0 REACTOR HI PRESS (107 G2) Annunciator is alarming and will not clear 0 Reactor Pressure is 1080 psig and steady The RO reduces reactor power with recirc flow in order to clear the High Pressure alarm WHICH ONE of the following describes the limits and the basis for this power reduction?

A. Reactor Steam Dome Pressure LCO, which is based on Safety Relief Valve sizing B. Reactor Steam Dome Pressure LCO, which is based on Turbine Bypass Valve sizing.

C. Reactor Coolant System Pressure safety limit, which is based on I10%

of Recirc Suction piping design pressure D. Reactor Coolant System Pressure safety limit, which is based on 110%

of Recirc Discharge piping design pressure.

Page 36 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Choice Basis or Justification Correct: A Immediate operator action per OT-102 Reactor High pressure is to reduce reactor power to maintain pressure less than 1053, which is the alarm setpoint. The basis for 1053 is the reactor steam done pressure LCO which is based on SRV sizing Incorrect B Steam done pressure LCO is correct however it is based on SRV, not BPV, sizing.

Incorrect C Reactor coolant system pressure safety limit is not correct, while the basis for the safety limit is the Recirc suction piping

~

Incorrect D Neither the reactor coolant system pressure safety limit nor the stated basis is correct I

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.5 5 N (b) (8-10) N/A Source Documentation Source: New Exam Item Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0 ILT Exam Bank Reference(s): OT-102 BASES, step 2.1 Learning LLOTI540.05 0bjective:

Knowledge/Ability 295025 Importance: RO I SRO WA EKI .05 4.4 I 4.7 (Description of K&A, from catalog)

Knowledge of the operational implication of the following concept as they apply to HIGH Reactor Pressure Exceeding Safety Limits..

Required MateriaIs:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

19. Unit 1 Plant conditions are as follows:

0 Reactor Power is 8%

0 Reactor Mode switch is in Startup 0 2D IRM is failed upscale An electrical fault results if the loss of 1AY160 WHICH ONE of the following identified the impact in IRMs and status of RPS?

A. IRM Channels A, C, E, and G loss power, Full Reactor Scram B. IRM Channels A, C, E, and G loss power, Reactor 1/2 Scram C. ONLY IRM Channels A, and C, loss power, Reactor 1/2 Scram D. ONLY IRM Channels A, and C, loss power, Full Reactor Scram Page 38 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key SFp 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)

B IRM Channels A, C, E, and G loss power is correct, Reactor 1/2 Scram is incorrect as full reactor scram will occur Incorrect: C 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 Incorrect: D ONLY IRM Channels A, and C, loss power is incorrect as E & G channels also lose power, Full Reactor Scram is correct 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 0Modified Bank Item [7 Other Exam Bank 0ILT Exam Bank Reference(s): 1 Learning LLOT0250.07 Objective:

~

Knowledge/Ability 215003 Importance: RO / SRO WA K2.01 2.5 / 2.7 (Description of K&A, from catalog)

Knowledge of electrical power supplies to the IRM channels/detectors Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

20. Unit 1 Plant conditions are as follows:

Reactor Startup is in progress 0 IA and ID lRMs are on range 1 0 All other IRMs are on range 2 I A SRM is being withdrawn when the count rate drops to 90 CPS WHICH ONE of the following identified 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 October 2006 Initial License Operator NRC Examination Answer Key Question ID# 020 Both RC 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 IC Only a rod insert block is enforced. This is not correct as SRM CPS less than 100 with detector not full in does not enforce an insert block Rod insert and withdrawal rod blocks are enforced SRM CPS are less Incorrect ID than I00 with detector not full in Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.5 4 N (b) ( 5 ) N I Source Documentation I Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s ): GP-2 Appendix 1, step 3.3.7 and NOTE Learning LLOT0240.06:

Objective:

KnowledgelAbility 215004 Importance: RO I SRO KIA K5.03 2.8 12.8 Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

21. WHICH ONE of the following describes the Rod Block Monitor (RBM) response to a APRM/LPRM failure?

A. RBM auto bypasses an LPRM if the detector output falls below 10%

B. RBM channel INOP occurs if unbypassed LPRMS are less than 70% of total used to calculate flux average C. Rod block occurs if there are less than 20 LPRM inputs to an APRM channel D. Rod block occurs if there are less than 5 LPRMS input signals per axial level to an APRM channel Page 42 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key I Choice Basis or Justification Correct: C Less than 20 LPRMS input to an APRM channel results in a Rod Block 1 l A m

Incorrect This is incorrect as RBM auto by passes detector if output fails below 3%

Incorrect Incorrect as channel INPO occurs if unbypassed LPRMS are less than 50%

of total Incorrect ID Incorrect as Rod Block occurs if there are less than 3 LPRMs inputs signals per axial level 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 0Previous NRC Exam Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): ARC 108, A-5 Learning LLOT0275.07B 0bjective:

Knowledge/Ability 215005 Importance: RO / SRO WA K1.03 3.4 / 3.5 Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

22. The CRS has ordered a GP-4 shutdown as a result of the IE SRV being stuck open.

Following the performance of GP-4 actions plant conditions are as follows:

0 Reactor power is 28%

0 IE SRV is still open 0 Suppression Pool temp is 112°F and going up 0 T-270 is complete, injection has been terminated 0 Reactor Level is -25 and going down WHICH ONE of the following describes an appropriate RPV water Level band and the reason for this band?.

A. -60 to -100 in order to lower power by reducing core inlet subcooling B. -60 to -1 00 in order to lower power by reducing natural circulation driving load and core flow C. -161 to -186 in order to lower power by reducing core inlet subcooling D. -161 to -186 in order to lower power by reducing natural circulation driving head and core flow Page 44 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Incorrect A This is the appropriate level band and reasons for the first level lowering.

This is N/A once SP temp is 110" and SRV is open Incorrect B This level condition is not appropriate, the reason is associated with the -

161 -, -186 level band L

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 Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): T-I 17, T-I 17 Bases, LQ-6 through LQ-11 and LQ-16.

Learning LLOTI560.05 0bjective:

~ ~~~~

KnowledgelAbility 295037 Importance: RO / SRO KIA EK.2.09 4.0 14.2 (Description of K&A, from catalog)

Knowledge of the interrelations between SCRAM cond. 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

P NRC Question Data Sheet

23. Unit 2 was operating at 100% when a Turbine Trip occurs. Two minutes later the following conditions are noted:

Reactor Power is 0%

Reactor Level is 35 Reactor Pressure: 960 psig and steady Rod 26-1 1 is at position 48 Rod 50-31 is at position 48 Rod 22-51 is at position 48 All other control rods are at 00 SBLC is not running WHICH ONE of the following meets the criteria for no ATWS?

A. Rods 26-1 I,50-31, and 22-51 inserted to position 04 B. Rod 26-1 1 and 50-31 at position 02 and 22-51 at position 04 C. Rods 26-1 Iand 50-31 at position 00 and 22-51 at position 48 D. Rod 26-11 at position 00 and rods 50-31 and 22-51 at position 48 Page 46 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 023'Both RC $RQ Choice Basis or Justification Correct: C Meets the Tech Spec definition of shutdown margin with the single strongest rod fully withdrawn and all other rods fully inserted Incorrect A Does not meet the Tech Spec SDM criteria Incorrect B Criteria stipulate that if one rod is fully withdrawn or less, all other rods must be fully inserted. Having one out and all others to or beyond 02 does not met the definition Incorrect D Does not meet the Tech Spec SDM criteria I Psychometrics 1 Time Allowance PRA RO SRO (minutes) 10CFR55.41 10CFR55.43 High 3.0 4 Y (b) ( 10) (b) (5)

Source: [x1 New Exam Item Previous NRC Exam c]Modified Bank Item Other Exam Bank c]ILT Exam Bank Reference(s): T-101, note 14, Tech Specs definition of Shutdown Margin Learning LLOTI560.03 0bjective:

Knowledge/Ability 295037 Importance: RO / SRO WA EA 2.05 4.2 14.3 Required Materials:

Notes a n d Comments Prepared By:

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

NRC Question Data Sheet

24. A Radiological accident has caused the following Annunciator to alarm:

0 North Stack Hi-Hi Radiation (003 E l )

0 North Stack Hi Radiation (003 E2)

WHICH ONE of the following areas is the location of the radiation release, and 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 Exhaust (REECE)

Evacuate all unnecessary personnel per SE-24, Plant Evacuations D. Reactor Enclosure Equipment Exhaust (REECE)

Enter and execute T-I 03, Secondary Containment Control Page 48 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key I Choice I Basis or Justification Correct: Possible source, ST must be performed and LGS Emergency Plan annex, Table 3-1 must be consulted Incorrect IAl Possible source but alarm alone is not sufficient reason to enter and execute T-I 04 Incorrect lcl Not a possible source based on the given conditions, although the action is plausible given this source Incorrect ID1 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 IOCFR55.43 High 3.5 4 N (b) (7) N Source: New Exam Item Previous NRC Exam 0Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): ARC-MCR-003-E1, ST-6-104-880-0, T-I 04 Learning LLOT0720.03 0bjective:

I KnowledgelAbility 295038 I Importance: RO 1 SRO WA 1 EK2.03 3.6 13.8 Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

25. Unit 1 is at 100% reactor power when the following Fire alarms are received:

REAC 1 El 177 HPCl PUMP ROOM (006 F-2-U) 0 REAC IEL 217 WEST SIDE (006 E-3-U)

WHICH ONE of the following identifies the appropriate immediate operator action?

A. Dispatch the fire brigade to respond to the fire B. Dispatch the Fire Brigade Leader to investigate the alarms C. Evacuate The entire Unit 1 Reactor Enclosure to support personnel accountability D. Start the motor and Diesel Driven Fire Pumps to prepare for fire suppression system actuation Page 50 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Choice Basis or Justification Correct: Since the SE-8 is entered based on alarms only,the Fire Brigade Leader is I B dispatched to investigate first

~

Incorrect Incorrect IA C This would be appropriate if there was a report of a fire or the alarm was accompanied by Fire pump auto start This would be considered a partial plant evacuation, which is only appropriate in the event of a fire in 2 or more large operating areas.

-T Incorrect Auto start is only verified if an actual fire is in progress, which has not been determined yet.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.5 3 N N N Source: New Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): SE-8 step 3.2, SE-24 Learning LLOTI 563.02 0bjective:

_ _ _ _ ~ ~ ~

KnowledgeIAbility 600000 Importance: RO I SRO KIA AK 3.04 2.8 13.4 (Description of K&A, from catalog)

Knowledge of the reasons for the following responses as they apply to FIRE ON SITE: actions contained in abnormal procedures for plant fire on site.

Required Materials:

Notes and Comments Prepared By:

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

~

NRC Question Data Sheet

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 and coasting down at 100 RPM 0 Sealing Steam header pressure is 0 psig The CRS orders the PRO to break Main Condenser vacuum WHICH ONE of the following describes the reason for this action?

A. Rapidly reduce turbine speed in order 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 in order to prevent damage due to uneven rotor heating D. Reduce differential pressure across turbine seals to prevent damage due to drawing cold air across the hot rotor.

Page 52 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Kev Nestion ID# 026 Both RC $gq Choice Basis or Justification D

~ ~

Correct: 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 l 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 I OCFR55.43 Low 3.5 4 Y (b) (7) N

~~

Source Documentation Source: New Exam Item Previous NRC Exam Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): OT-I16 BASES, step 3.3 Learning LLOTI 540.05 0bjective:

KnowIedgelAbiI ity 295002 Importance: RO / SRO WA AK2.11 2.6 / 2.7 (Description of K&A, from catalog)

Knowledge of the interrelationship between LOSS of MAIN Condenser VAC and ... Seal steam:

Required Materials:

Notes and Comments Prepared By:

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

-__

NRC Question Data Sheet 27, A Reactor Startup is in progress on Unit 2 Reactor Power is 3%

A Reactor Scram is attempted Ten Control Rods Remain at Positions 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 - I 00, Insert Control Rods with T-213 C. Enter T-101, Bypass RWM and Insert Control Rods with S73.0.D D. Enter T-101, Insert Control Rods with T-213 Page 54 of 200

LIMERICK October 2006 Initial License Operator NRC Examination 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-100 I

Incorrect C I As Reactor power is below 4% entry into T-100 (vice T-101) is appropriate

~

Incorrect power is below 4% entry into T-I00 (vice T-I 01) is appropriate and T-213 is not directed in T-I00 Psvchometrics Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 N N Source Documentation Source: @ New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): T-100 Bases step RCIQ-3 Learning LLOTI 540.02 0bjective:

Knowledge/Ability 295015 Importance: RO I SRO WA AA2.01 4.1 14.3 (Description of K&A, from catalog)

Ability to determine and/or interpret the following as they apply to INCOMPLETE SCRAM...Reactor Power Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

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 one minute later?

A. A loop in Service ONLY B. B loop in Service ONLY C. Both loops in service D. No loops in service Page 56 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Difficulty Time Allowance PRA RO SRO (minutes) 10CFR55.41 10CFR55.43 Low 2.5 2 N (b) (8, 9, 10) N Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): GP-8.1 for Group VlllA Learning LLOTO180.05 0bjective:

~~

KnowledgelAbility 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

NRC Question Data Sheet

29. Unit Iplant conditions are as follows:

Reactor Power is 100%

Hydrogen Water Chemistry is not in service The following annunciators are received:

0 MAIN STEAM LINE DIV IRAD MONITOR HVDOWNSCALE (109 F I )

0 MAIN STEAM LINE DIV 2 RAD MONITOR HVDOWNSCALE (109 F2)

Subsequently the following annunciator is received:

0 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

6. Enter T-103 ONLY, perform a GP-3 Normal Plant shutdown C. Enter ON-I 02 and T - I 03, perform a rapid plant shutdown and close the MS IVs.

D. Enter ON-I02 and T-I03 perform a rapid plant shutdown and Emergency Blow down per T-I 12 Page 58 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Correct: C Main steam line high rad requires entry into ON-I02 and T-103. The high-high rad alarm indicates three times NFPB. Per T-103 this requires a rapid plant shutdown and closure of the MSIVs Incorrect A While reducing power is an immediate action per ON-I 02, question conditions also require entry into T-I 03 and the actions described in C above Incorrect B ON-I 02 entry is also required and a GP-3 shutdown would be appropriate per T-I03 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-103 if two or more areas exceeded MSO and a primary system was discharging into the Reactor Enclosure, but is not required for MSL High-High Rad only Difficulty Time Allowance PRA RO SRO (minutes) 10CFR55.41 10CFR55.43 High 4.0 5 Y y (b)(lO) y (b)(2)

Source Documentation Source: New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): ARC-MCR-109-FII ARC-MCR-109-F2, ARC-MCR-107-11, ON-I 02 Step 1.2, T-I 03 Learning LLOTl560.02, LLOTI 550.01 Objective:

LKnowledgelAbility 295033 G2.4.4 Importance: RO I SRO 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

__

NRC Question Data Sheet

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%

0 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-1 B. DW/G-2 and SP/G-2 C. DW/G-3 and SPIG-3 D. DW/G-2 and SP/G-1 Page 60 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Choice Basis or Justification Correct: Applying the containment H2and O2 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 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.

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: [XI New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank - Modified LOR 0ILT Exam Bank Exam bank item Reference(s): T-I 02, sheet 2 and T-I 02 Bases Step PC/G-5 Learning LLOTI560.06 Objective:

~

Knowledge/Ability 500000 Importance: RO I SRO WA EA 2.03 3.3 13.8 Required Materials:

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

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

NRC Question Data Sheet

31. Unit 2 was forced to shutdown due to a Main Condenser Hotwell leak.

Following the scram, a steam leak in the RClC room resulted in an 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 2A Core Spray Pump and take the HV-52-2F005A, Inboard Injection Valve, to OPEN C. Arm and depress the Core Spray Div. 3 Manual Initiation Pushbutton D. Start the 2C RHR Pump, HV-51-2F017C LPCI, Injection Valve, will OPEN Automatically Page 62 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Kev Choice Basis or Justification 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 Incorrect C Div 3 Manual Initiation Pushbutton will start the 1C Core Spray Pump, but it will not make up the open logic for the injection valves. Only the Div l(2)

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

Difficulty Time Allowance PRA RO SRO (minutes) 10CFR55.41 10CFR55.43 High 3.5 4 Y y (b)(7) N Source: New Exam Item Previous NRC Exam

[7 Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): S52.7A, note above step 4,4 Learning LLOT0350.10 Objective:

Knowledge/Ability 209001 Importance: RO / SRO WA PWG 2.1.30 3.9 13.4 Notes and Comments Prepared By:

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

NRC Question Data Sheet

32. Unit 2 plant conditions are as follows:

0 Reactor power is 100%

0 Division 3 Safeguard 125V /1250V DC is inoperable due to maintenance on the battery charger An inadvertent Group 1 isolation causes a reactor scram 0 Unit 2 RClC starts on low reactor level 0 A steam leak develops in the RClC room. RClC room temperature reaches 21O°F WHICH ONE of the following describes the required action?

A. Trip the RClC Turbine B. Close the HV-49-2F007, RClC Steam Line Inboard isolation C. Close the HV-49-2F008, RClC Steam Line Outboard isolation.

D. Depress the RClC Manual Isolation Pushbutton Page 64 of 200

. LIMERICK October 2006 Choice Correct:

Incorrect Incorrect Incorrect IC ID A

Room temperature Initial License Operator NRC Examination Answer Key Basis or Justification With a loss of Div 3 DC, the 2F007 will fail to isolate on High RClC room temperature (205°F) and must be closed The RClC Turbine will trip on a Div 1 NS4 isolation signal on High RClC The 2F008 will close on a Div 1 NS4 Isolation signal on High RClC Room temperature Manual isolation will not close 2F007 valve due to loss of Div 3 DC Difficulty Time Allowance PRA RO SRO (minUtes) 10CFR55.41 10CFR55.43 High 3.0 4 Y y W(5) N Source: New Exam Item c]Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): E-2FC, GE DWG M-1-E51-1040-E-028, Sht.1 Learning LLOT0380.05, LLOT0380.12 Objective:

1 Knowledge/Ability 217000 I Importance: RO / SRO WA I A2.05 3.3 i 3.3

quired Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

33. Unit Iconditions are as follows 0 Reactor water level is 35 0 Y B RHR is in Suppression Pool Cooling Div 2 Safeguard DC Bus is subsequently deenergized WHICH ONE of the following describes the effect on 1B RHR Loop if Reactor Water level lowers to -140 A. 7 B RHR loop will realign to the LPCl mode B. 1B RHR pump will load shed and remain shutdown C. 1B RHR loop will remain in Suppression Pool Cooling D. 1B RHR pump will continue to run; minimum flow valve will open Page 66 of 200

LIMERICK October 2006 Initial License Operator NRC Examination SE?

Basis or Justification Correct: 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:

Incorrect:

lA B F024 and F017B will not reposition due to loss of Div 2 DC RHR pump will not load shed during a LOCA

~~ ~ ~ ~

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

Knowledge/Ability 203000 Importance: RO / SRO WA K6.02 2.8 13.0 Required Materials:

Notes and Comments:

Existing bank question, Stem and Distractors Modified Prepared By:

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

NRC Question Data Sheet

34. Unit 1 Plant conditions are as follows:

0 Opcon4 0 1A RHR is in shutdown cooling Reactor water level drops from +70 to -1 0 WHICH ONE of the following identifies a RHR pump and valve response to the above conditions?

HV-51-F006A HV-51-FOO9 Shutdown Cooling Shutdown Cooling RHR A 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 October 2006 Initial License Operator NRC Examination Answer Key Choice 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 Incorrect A Incorrect as FOO9 will close with level below +125 and pump will trip I Incorrect Incorrect as pump will trip when level drops below 12.5 due to FOO9 closure Incorrect Incorrect as F006A will not automatically close and FOO9 close when level drops below +125 Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 Y y (W7) N Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s ): S51.8.B, step 3.2 Learning LLOT0370.14~

0bjective:

KnowledgeJAbility 205000 Importance: RO 1 SRO KIA K6.04 3.6 13.6 Required Materials:

Notes and Comments Prepared By:

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

~~

NRC Question Data Sheet

35. Unit One Plant conditions are as follows:

0 Reactor Power is 100%

e The RO Selects Single-Element control on the Feedwater Master Level Controller (LIC-MI-1 R600)

WHICH ONE of the following describes the response of this 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

.

I m

I I

LIMERICK October 2006 Choice Correct:

Incorrect Incorrect Incorrect Level of Knowledge High l A I D Difficulty 3.0

%E!$

selected single element.

Initial License Operator NRC Examination Answer Key Basis or Justification SCRAM profile will swap controller to three element even if operator This is incorrect as Fw will swap to single element when SCRAM profile is reset This is incorrect as FW will swap to single element at -20%

This is incorrect a controller will not remain in single element if single is selected (IF FW flow failure had caused swap to single element this would be correct).

Time Allowance (minutes) 3 PRA Y

RO 10CFR55.41 y (W7)

SRO 10CFR55.43 N

Source: New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): S.06.1 .D Unit 1, Attachment 1 Learning LLOT0550.08 0bjective:

KnowledgeIAbility 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

~-

NRC Question Data Sheet

36. Unit One conditions are as follows:

0 HPCl is in service for Reactor Vessel Pressure Control (CST to CST) 0 FIC-055-1R600 HPCI FLOW CONTROL VALVE AUTO/MAN switch is in auto 0 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 identifies the effect of throttling HV-55-1F008 on HPCl Turbine Speed and Flowrate one minute later?

HPCl Turbine Speed Flowrate A. Nochange Goes up B. Goesup No change C. Goesdown No change D. Nochange Goes down Page 72 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key I Choice I Basis or Justification Correct: B With Flow Controller in AUTO, system flow is maintained constant. IF F008 is throttled closed HPCI speed will need to increase to maintain the same flow I Incorrect A Flow Controller is in Auto, maintaining system flow constant Incorrect C To maintain constant flow w/F008 throttled closed , speed goes up.

I Incorrect D Flow Controller is in Auto, maintaining system flow constant.

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

Knowledge/Ability 206000 HPCI Importance: RO / SRO WA A I .09 3.4 / 3.5 Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

37. Unit One plant conditions are as follows:

0 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 1B and 1 D are Running 0 Core Spray pumps 1 A and 1C are Tripped and cannot be started 0 ALL RHR pumps are Tripped and cannot be started RPV Water level drops below -129.

WHICH ONE of the following identifies the response of DIV I and/or DIV Ill ADS subsystems?

DIV 1 ADS DIV 3 ADS A. Initiates after 105 second TD Will not initiate B. Initiates after 525 second TD Will not initiate C. Will not initiate Initiates after 105 second TD D. Will not initiate Initiates after 525 second TD Page 74 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key S-RO

~

Choice Basis or Justification Correct: C DIV I ADS will not initiate as no Div I Core Spray or RHR pumps are running DIV Ill will initiate as B & D core spray pumps are running 105 sec is correct as -129 and HI DW pressure are met.

Incorrect: A DIV I will not initiate without correct pumps running DIV Ill will initiate as described above

Incorrect Incorrect I D DIV I ADS will not initiate without correct pumps running DIV I l l will initiate as described above

~~ ~

DIV I will not initiate is correct but,

~

DIV Ill initiating after 525 seconds is incorrect as -129 and 1.68# conditions bypass 420 sec timer.

-

Psychometrics 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: 1 0New Exam Item 0Previous NRC Exam I a Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): B21-1060 (ADS) Sh. 3 Learning LLOT0350.04~

0bjective:

Knowledge/Ability 209001 Importance: RO / SRO KIA K3.02 3.8 13.9 REQUIRED MATERIALS:

Notes and Comments:

Existing Question, Stem and Distractors Modified Prepared By:

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

-~

NRC Question Data Sheet

38. Unit One plant conditions are as follows:.

0 An ATWS has occurred Reactor level is -20 and lowering 0 Reactor power is 30% and steady 0 No operator action are taken Reactor level drops to -40 Three Minutes Later Reactor Power is 27% and slowly lowering WHICH ONE of the following identifies expected lights and alarms for the given conditions :

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 % RRCS channel activated.

Page 76 of 200

~~ ~~

LIMERICK October 2006 Initial License Operator NRC Examination 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.

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

Knowledge/Ability 21 1000 Importance: RO / SRO K/A AI.IO 3.7 / 3.7 REQUIRED MATERIALS:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

39. Unit 2 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 panel 10609/10C611 in the Aux Equipment Room WHICH ONE of the following identifies the expected plant response A. Full Reactor SCRAM on Turbine Stop Valve closure B. Full Reactor SCRAM on Turbine Control Valve closure C. Half SCRAM on Turbine Stop Valve closure.

D. Half SCRAM on Turbine Control Valve closure.

Page 78 of 200

LIMERICK October 2006 Initial License Operator NRC Examination I Answer Key Choice Basis or Justification Correct: A A full Reactor SCRAM will occur on 3 out of 4 stop valve closed with Reactor power greater than 30%. Reactor power greater than 30% is indicated by pressure lights lit in AER Incorrect B Turbine control valve closure scram is wrong as turbine control valves are open to support shell warming Incorrect IC/ 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 (bN7) N Source Documentation Source: New Exam Item [7 Previous NRC Exam 0Modified Bank Item 0Other Exam Bank ILT 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 REQUIRED MATERIALS:

Notes and Comments Prepared By:

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

~ -~

NRC Question Data Sheet

40. Unit 1 plant conditions are as follows:

Reactor power 100%

Reactor level 35 LT-42-1N004A Feedwater Narrow Range Level Transmitte r fa iI s downsca Ie Half hour later LT-42-IN004C Feedwater Narrow Range Level Transmitter fails upscale.

WHICH ONE of the following describes the impact on feedwater level control, and impact on 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 October 2006 Initial License Operator NRC Examination Answer Kev I

Choice I 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 Documentation Source: 0New Exam Item Previous NRC Exam 0Modified Bank Item [XI 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 (Description of K&A, from catalog)

Knowledge of the effect that a loss or malfunction of the following: Reactor Water Level control system REQUIRED MATERIALS:

Notes and Comments:

Modified Question from LOR bank Prepared By:

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

NRC Question Data Sheet

41. Unit 1 plant conditions are as follows:

0 An ATWS is in progress 0 Reactor Power is 50% and Steady 0 Reactor Water Level is 35 and Steady Reactor Pressure is 1045 psig and Steady RRCS DIV 1 B AND DIV II A 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 118 seconds D. DIV 1/11 RRCS Annuciators ONLY, ARI solenoids remains deenergized Page 82 of 200

LIMERICK October 2006 Initial License Operator NRC 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 C SLC will not initiate as RRCS is not initiated, and conditions for automatic initiation are not met

' Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 Y Y tbM71 N Source: New Exam Item Previous NRC Exam 0Modified Bank Item 17 Other Exam Bank 0ILT Exam Bank Reference(s): GP-18 Attachment 4, ANN 004 F-5 Learning LLOT0315.05 0bjective:

Knowledge/Ability 212000 Importance: RO / SRO WA A4.16 4.4 / 4.4 REQUIRED MATERIALS:

Notes and Comments Prepared By:

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

-~

NRC Question Data S h e e t

42. Unit 1 plant conditions are as follows:

0 Reactor Power is 100%

0 Normal Reactor Enclosure ventilation is in service Both Standby Gas Treatment System fans are in AUTO LIS-42-1N681A and LIS-42-1N681B fail downscale resulting in the following annunciator:

1A REACTOR ENCL ISOLATION SIGNAL INITIATED (004 E-I)

WHICH ONE of the following identifies the status of Standby Gas Treatment 5 minutes later?

A. OAFan and OB Fan running B. Only O A Fan running C. Only OB Fan running D. Both Fans off Page 84 of 200

LIMERICK October 2006 Initial License Operator NRC Examination

~~

Answer Key Question ID# 042 Both RC Choice Basis or Justification Correct: B A Reactor enclosure isolation and ASGTS 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 lncorrect: D Incorrect as A Fan will start Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 4.0 4 N 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): ANN 004 E-I Learning LLOT0200.1OB 0bjective:

Knowledge/Ability 26 1000 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

NRC Question Data Sheet

43. Unit 1 plant conditions are as follows:

e Reactor Power is 100%

e Reactor Level is 35 A Condensate Min Flow controller malfunction results on the following:

Reactor Feed Pump (RFP) Suction Pressure drops to 230 psi for 6 seconds, and then goes up to 250 psi.

WHICH ONE of the following identifies the impact on the feedwater system?

A. Y A RFP has tripped 1B and 1C RFPs are running B. 1C RFP has tripped Y A and 1B RFPs are running C. 1 B and IA RFP have tripped 1C RFPs is running D. All RFPs have tripped Page 86 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 043 Both RC Choice Basis or Justification Correct: 1 B 1C RFP will trip on Low suction after 5 seconds pressure due to suction pressure less than 233 psi for 5 Incorrect A 1A RFP will not trip as C RFP trips first followed by 1 6 at 10 seconds and 1 A at 15 seconds Incorrect C IB and ?A tripped is wrong as IC RFP will trip first Incorrect D All RFPs tripped is wrong as suction pressure stabilized prior to trip of all 3 RFPs Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.5 3 Y Y (b)(3) N Source: New Exam Item Previous NRC Exam Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): ANN 104 Cond E-2 ANNs 102 Feed AI, B l , C1 Learning LLOT0520.08 0bjective:

Knowledge/Ability 256000 Importance: RO ISRO WA K1.02 3.3 13.3 REQUIRED MATERIALS:

Notes and Comments Prepared By:

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

_ _ _ ~ ~

NRC Question Data Sheet

44. Unit Ihas been scrammed due to a LOCA.

RClC auto-initiated following the SCRAM. Conditions are as follows:

0 RPV water level has recovered to +35and 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-50-1 F045)

Reset the RClC trip throttle valve (HV-50-112)

C. Reset the RClC initiation signal seal-in Depress the RClC turbine trip pushbutton Close the RClC Steam Supply valve (HV-50-1F045)

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 October 2006 Initial License Operator NRC Examination Answer Key gR6

~~~

Basis or Justification Since the initiation signal is no longer present the operator can reset it, Trip the turbine and close the steam supply. Resetting the Trip throttle valve leaves RClC ready for auto injection 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 RClC if the initiation signal were still present.

RCIC 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 (b)(7) N Source: New Exam Item 0Previous NRC Exam Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): S49.2A section 4. I,S49.1C section 4.3 Learning LOT0380.08 Objective:

Knowledge/Ability 217000 Importance: RO / SRO KIA A4.04 3.6 / 3.6 Notes and Comments Prepared By:

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

NRC Question Data Sheet

45. WHICH ONE of the following identifies the expected SRV indications DURING an ADS Automatic Blowdown?

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

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 045 Both RC FRO

~~~~

Basis or Justification Correct: B During an automatic blowdown both amber has lifted (Acoustic monitor) and white solenoid (ADS Div I & 111) lights will light.

A This is incorrect as white solenoid energized light will be lit on ADS auto initiation Incorrect C This is incorrect as Amber has lifted light will be lit Incorrect D This is incorrect as both lights will be lifted if there was no increased Drywell pressure this would be true I Psvchometrics I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.0 2 Y y (b)(7) N Source: New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): OT-I 14, 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

NRC Question Data Sheet

46. Unit 1 is operating at 100%

An inadvertent RPV Low, Low Level signal (-38) results in NSSSS isolations 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 October 2006 Initial License Operator NRC Examination Answer Key Choice Basis or Justification Correct: N2 Supply valve closes and vent valve opens on a Lo-Lo Reactor level signal (VIIIB)

Incorrect: A This is incorrect as instrument gas block valves isolate at Lo-Lo-Lo Level Incorrect B This is incorrect as recirc vent valves do not automatically open on an isolation

~~ ~~ ~

Incorrect 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: New 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:

Knowledge/Ability 223002 Importance: RO / SRO WA A2.05 3.3/ 3.6 Notes and Comments:

Modified LOR Bank Question Prepared By:

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

NRC Question Data Sheet

47. D11 Diesel Generator is operating in parallel with the 101 Safeguard Bus with the following indications:

.

0 0

60Hz 2000KW 1600 KVAR WHICH ONE of the following actions will restore the Diesel generator within operating limits?

A. Place Speed Governor in RAISE to adjust real load to 2100 KW B. Place Speed Governor in LOWER to adjust real load to I 9 0 0 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 I500 KVAR Page 94 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key I Choice I Basis or Justification Correct: D Reducing VARS to less than 1500 restores WARS to less than 75% KW, which corresponds to a Power Factor of 0.8 Incorrect:

IAl Raising W 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: C 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 (b)(7) N Source: New Exam Item Previous NRC Exam 0Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): S92.1 .O, caution above step 4.5.5 Learning LLOT0670.02 Objective:

~ ~

Knowledge/Ability 264000 Importance: RO / SRO WA A4.01 3.3 / 3.4 Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

48. Unit 1 Plant conditions are as follows:

0 1 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:

0 EXCESS FLOW CHECKVALVE OPERATED C218 (112 E5) 0 DIV 3 REACTOR LO-LO-LO- Level (1 13 E3)

WHICH ONE of the following identifies the effect on the CRD system and the Action required to restore CRD?

A. 1 A CRD pump trips Can be restarted from the MCR B. Y A CRD pump remains running No action required C. I A CRD pump trips and cannot be restored 1B CRD pump must be placed in-service from the MCR D. YA CRD pump trips Can only be restarted from 4 KV switchgear Page 96 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 048 Both RC SBo Choice 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 I B

,

Incorrect This is incorrect as a CRD pump will trip due to Div Ill LOCA load shed Incorrect I C This is incorrect as a CRD can be restarted Incorrect This is incorrect as CRD can be restarted from the MCR Psvchometrics 1 Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 2.5 3 Y Y (b)(5) N Source: UNew Exam Item 17 Previous NRC Exam Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): SE-IO, step 4.6 Learning LLOT0660.05b 0bjective:

WA I Knowledge/Ability 262001 A2.02 (Description of K&A, from catalog)

Importance: RO t SRO 3.6 t 3.9 Ability to predict the impact of a LOCA on A C electrical distribution; 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:

This question was extensively modified from Question 373224 (ILT LERT EXAM 2005)

Prepared By:

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

~~

NRC Question Data Sheet

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 October 2006 Initial License Operator NRC Examination Answer Kev Question ID# 049 Both RC Basis or Justification Correct: D S SRV is a 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 A 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 Incorrect I B 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 1 DC Incorrect I C While J SRV is one of the preferred SRVs for use with high level, control is not available in the AER I Psvchometrics I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 Y y (b)(7) N Source Documentation Source: New Exam Item 0 Previous NRC Exam 0801#221 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Referencekl: OT-I10 Ster, 3.1.4 Learning LLOTOI20.12a 0bjective:

Knowledge/Ability 239002 Importance: RO / SRO KIA K4.05 3.6 13.7 (Description of K&A, from catalog)

Knowledge of SRV design features and/or interlocks which provide for allowing SRV operation from more than one location Required Materials:

Notes and Comments Prepared By:

Rick Rhode (61 0) 718-4085 Limerick Regulatory Exam Author

- ~~~~~ ~~-

NRC Question Data Sheet

50. Unit 1 plant conditions are as follows:

0 Reactor Power is 100%

1A RECW pump is blocked for bearing replacement 0 I B 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 ZOOOF.

B. Seal cavity temperature rises Trip the RECIRC pumps within 10 minutes C. Pump motor temperature rises Trip the RECIRC pumps if motor winding temperature exceeds 2OO0F D. Pump motor temperature rises Trip the RECIRC pumps within 10 minutes Page 100 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 050 Both-RC Choice Basis or Justification Correct: B 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 2OO0F

!

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

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

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 2.5 3 Y y (b)(5 ) N Source: [xi New Exam Item [7 Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): ON-I 13 step 2.1, S43.0.D Learning LLOT0030.07b:

Objective:

KnowledgefAbility 202001 Importance: RO / SRO K/A A2. 17 3.1 f 3.2 Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

51. Unit 2 Plant conditions are as follows:

0 2 A RECW pump is running with its handswitch in AUTO after START 0 2BRECW pumps 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 2BRECW pump auto starts in standby B. 2A RECW pump auto re-starts.

2BRECW pump does NOT auto start in standby C. 2 A RECW pump does NOT auto re-start 2BRECW pump auto starts in standby D. 2ARECW pump does NOT auto re-start 2BRECW pump does NOT auto start in standby Page 102 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Choice Basis or Justification Correct: A When their respective safeguard MCCs re-energized both RECW pumps auto start on low heat exchange outlet pressure

~

Incorrect IBI 2A portion of this distractor is correct, 2B 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 PFW RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 Y y W(7) N I Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank c]ILT Exam Bank Reference(s): E-565 Learning Objective: I LL0T0460.07 Knowledge/Ability 400000 Importance: RO / SRO WA K4.01 3.4 / 3.9 Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

52. Unit 1 plant conditions are as follows:

0 Reactor Startup is in progress 0 Reactor power is 20%

Control rod withdraw 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. RMCS Activities Control Disagree Alarm Page 104 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Choice I Basis or Justification Correct: Activities control disagree results in a Rod withdrawn and insert block due to a malfunction of RMCS

~~

Incorrect RBM upscale will not result in a rod block as Reactor power is less than A 130%

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

Incorrect CR withdraw will not result in a Rod block as Reactor power is above RWM LPSP (18%)

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 10CFR55.43 Low 3.0 3 Y y (b)(7) N Source Documentation Source: [XI New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): S73.0.9, step 4.2 & note above step, ANN 108 D-4 Learning LLOT0080.06 =

Objective:

Knowledge/Ability 201002 Importance: RO / SRO K/A K3.02 2.9 13.2 (Description of K&A, from catalog)

Knowledge of the effect that a loss or malfunction of RMCS will have on RBM Required Materials:

Notes and Comments Prepared By:

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

__ --~

NRC Question Data Sheet

53. Unit 1 plant conditions are as follows:

0 Reactor STARTUP is in progress 0 Reactor Power is 12%

0 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 taken.

WHICH ONE of the following identifies the ability to move control rod 10-39?

A. Rod can be withdrawn and inserted without additional actions B. Rod can only be inserted without additional action C. Rod insertion requires Rod to be bypassed in the RWM D. Rod insertion or withdraw requires a substitute position to be entered into RWM Page 106 of 200

-

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 053 Both RC SRp I Choice Basis or Justification Correct: B RWM allow correction (insert) as it is a single notch error Incorrect IA 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 Psychometrics Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43

/ Low 3.0 3 Y b)7 N Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): ON-I 23 step 2.12 Learning LLOT0093f 0bjective:

Knowledge/Ability 201006 Importance: RO I SRO KIA K4.06 3.2 13.4 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (61 0) 718-4085 Limerick Regulatory Exam Author

NRC Question Data Sheet

54. A Unit Iplant conditions are as follows:

0 Reactor was scrammed due to a condensate line rupture.

0 Reactor level is -35 and lowering 0 D124 safeguard load center transformer breaker tripped on over current The RO is directed to start Standby Liquid Control for Reactor Level Control 0 1 A and 1C SLC injection pumps are started and verified to be injecting WHICH ONE of the following describes the expected RWCU response?

A. HV-44-1F004 RWCU Outboard Suction Valve closes B. HV44-I Fool RWCU Inboard Suction Valve closes C. HV-44-1F004 RWCU Outboard Suction Valve and HV-44-1Fool RWCU Inboard Suction Valve close D. HV-44-1F040 RWCU Inlet Suction Valve closes Page 108 of 200

LIMERICK October 2006 Initial License Operator NRC Examination I Basis or Justification Correct: B A or C SLC pump start close Fool valve as B was not started (D124 is power supply for the 6pump) F004 did not close Incorrect C While Fool did close answer is incorrect as F004 did not close due to B SLC pump not started incorrect D 1 F040 does not receive and isolation signal on SLC start Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 N y (W7) N Source Documentation 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 LLOTOI 10.05 Objective:

KnowledgeIAbility 204000 Importance: RO / SRO KIA A3.03 3.6 13.6 (Description of K&A, from catalog)

Ability to monitor automatic operation of RWCU including: response to system isolations:

Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

55. Unit 1 plant conditions are as follows:

0 Reactor Power is 100%

0 1AY160 is lost due to a ground 30 minutes later a Reactor SCRAM and Turbine trip occur Reactor pressure is 900# 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 October 2006 Initial License Operator NRC Examination Answer Key gm I Choice Basis or Justification I 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 L

I Incorrect D Raising max combine flow (115%) will not open bypass valves (CVs are closed)

Psvchometrics I Level of Difficulty Time Allowance PW RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 Y y (W7) N Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): E-IAY160 Attachment # I Learning LLOT0560.01Ok 0bjective:

Knowledge/Ability 262002 Importance: RO / SRO KIA K3.15 2.6 / 2.7 Required Materials:

Notes and Comments Prepared By:

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

-

NRC Question Data Sheet

56. WHICH of the following identifies one of the long term impacts of a complete loss of instrument air?

A. Only Outboard MSlVs close All SRVs can be opened B. Only Inboard MSlVs close Only ADS and RSP SRVs can be opened C. Inboard and Outboard MSIVs 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 October 2006 Initial License Operator NRC Examination Choice Basis or Justification Correct: D Outboard MSlVs 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 1 Incorrect B This is incorrect as outboard MSlVs also close L Incorrect C This is incorrect as non-ADS SRVs cannot be opened from handswitches due to loss of PClG I

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 4.0 3 Y Y (b)(9) N Source: New Exam Item Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): ON-I I 9 Attachment 1 Learning LLOT0730.08 Objective:

Knowledge/Ability 300000 Importance: RO / SRO K/A K1.03 2.8 12.9 (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

~ ~

NRC Question Data Sheet

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 40%

WHICH ONE of the following identify 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 October 2006 Initial License Operator NRC Examination Answer Key

$Rp Choice Basis or Justification Correct: B RRCS Feedwater runback occurs IF Reactor power is greater then than 4%

and Reactor pressure is greater than 1149. Additionally runback occurs with a 25 second time delay Incorrect A 118 seconds is incorrect ( I 18 seconds is the RRCS SBLC initiation time delay)

Incorrect C Reactor pressure 1096 is incorrect (1096 is the Reactor Scram setpoint) additionally 30 seconds is the Feedwater runback length once initiated Incorrect D 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 PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 HIGH 3.0 3 Y NIA NIA Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): GE Elementary Drawing G31-1020 ARC 004, B-4 Learning LLOT0315.04 Objective:

KnowledgelAbility 216000 Importance: RO / SRO K/A 2.4.50 3.3 13.3 (Description of K&A, from catalog) Ability to verify system alarm setpoints and operate controls identified in the alarm response manual Nuclear Boiler Instrumentation Required Materials:

Notes and Comments:

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

NRC Question Data Sheet

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 Pumps 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 October 2006 Initial License Operator NRC Examination Answer Key Question ID# 058 Both RC SEQ I 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: B Primary RPS/UPS inverter Power is a Safeguard DC load Incorrect: C Reactor Enclosure HVAC Isolation logic and 4RV Breaker Control Power are Safeguard DC loads I

Level of Difficulty Time Allowance PFW RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 Y (b) (7) N Source Documentation Source: New Exam Item 0Previous NRC Exam Modified Bank Item Other Exam Bank

~

0ILT Exam Bank Reference(s): E-33, Sh 1-3 E-619, S h 1-3 Learning LLOT0690.04 0bjective:

Knowledge/Ability 263000 Importance: RO / SRO WA 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

NRC Question Data Sheet

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 October 2006 Initial License Operator NRC Examination Answer Key Suppression Pool Pressure Incorrect B Vacuum Breaker Operate on to ensure Drywell is not drawn negative Incorrect IcI 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.

I I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 Y y W(5) N Source: 0New Exam Item Ix] Previous NRC Exam 0999#119 0Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): ANN 114 G-I Learning LLOTOI30.02f Objective:

Knowledge/Ability 223001 Importance: RO 1 SRO KIA K5.01 3.1 1 3.3 Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

60. Unit 1 at 100% power when the following Alarm is received:

0 1DB-1 250V DC MCC undervoltage (122 G-2)

WHICH ONE of the following identifies the system that is no longer operable, and the required action?

A. ADS, Station an Equipment Operator in the AER for SRV operation B. RPS, Stop all B side RPS testing C. HPCI, Declare HPCI Inoperable per Technical Specification D. RCIC, Perform T-249 for RCIC Page 120 of 200

LIMERICK October 2006 Initial License Operator NRC Examination I Answer Key k e d i o n ID# 060 Both RC Sam I Choice Basis or Justification Correct:

IC 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 loaic Incorrect: A ADS is supplied by Div 1 and Div 3 DC Incorrect: B While B RPS will swap to its AC power source, it is still operable Incorrect: D RCIC 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) (10) N Source: New Exam Item Previous NRC Exam 17 Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): ARC-MCR-122 G2, ARC MCR-117 A I Learning LLOT0690.02 0bjective:

Knowledge/Ability 263000 Importance: RO I SRO WA 2.4.31 3.3 13.4 Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

61. LOCNLOOP Testing is in progress during a refueling outage on Unit I The PRO is monitoring D11 Diesel Generator indications as the Team prepares to drop power to the bus.

WHICH ONE of the following identifies values for both frequency and voltage that will satisfy the requirement for the D1 IDiesel Generator breaker to close in on the bus?

Frequency Voltage A. 56.2 H, 4.1 KV B. 57.4 H, 4.0 KV C. 58.6 H, 3.9 KV D. 59.8HZ 3.8 KV Page 122 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 061 Both RC SRQ I Choice 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 D 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 0Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): E-I64 Learning LLOT0670.02. LLOT0660.04 0bjective:

KnowledgelAbility 264000 Importance: RO I SRO K/A A3.03 3.4 13.4 (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

__-

.

NRC Question Data Sheet

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 7 A RHR is placed in Suppression Pool Spray 0 Reactor pressure drops to 280 psig 0 Div 1 LPCl INJECTION VALVE DELTA P PERMISSIVE (1 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 ALPCl 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 ALPCl injection valve remains closed Page 124 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key S@O 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 This is incorrect as spray does not isolate (LOCA) signal received previously) additionally, it cannot be re-establisheduntil LPCl injection valve is closed Incorrect This is incorrect as spray does not isolate (LOCA signal received previously)

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

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43 Low 4.0 3 Y y (W7)

Source: E New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): ARC-MCR-113 F4, T-225 step 4.2.2 Learning LLOT0370.09b 0bjective:

Knowledge/Ability 230000 Importance: RO / SRO WA A4.02 3.81 3.6 Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet ATTACHMENT: ON-126 Provided

63. Unit 1 plant conditions are as follows:

0 1200MWe 0 240 MVARs (lagging) 0 Generator Hydrogen Pressure is 60 psig and steady WHICH ONE of the following actions is required?

A. Reduce Reactive Load to 200 MVARs lagging B. Reduce Generator Output below 1125 MWe C. Raise Service Water Flow to Stator Coolers D. Raise Hydrogen Pressure to 65 psig Page 126 of 200

LIMERICK October 2006 Initial License Operator NRC Examination I Choice I Basis or Justification Correct: B Reduction in real load to less than 1125 Mwe will restore the MW lMWe output to a value consistent with 60 psig H2 heating curve. Pressure and within the armature Incorrect: A Reducing MVAR will not reduce the MWiMWe output to within the armature heating curve

~ ~ ~

Incorrect: C While stator cooling removes heat from the armature the only way to prevent armature overheating is to operate within the Generator Output capability curve.

Incorrect: D HZPressure would have to be restored to 75 psig in order to restore the MWiMWe output to within the armature heating curve Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.5 4 N Y (b)(5) N Source: 0New Exam Item 0Previous NRC Exam Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): ON-I 26, Attachment I Learning LLOT0600.10 Objective:

Knowledge/Ability 245000 Importance: RO / SRO WA A I .01 2.7 i 2.7 Required Materials:

ON-126 Notes and Comments Prepared By:

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

NRC Question Data Sheet

64. Unit 1 conditions are as follows 0 Reactor power is 100%

A failure of 1BY185 occurs WHICH ONE of the following identifies the expecteb plant response?

A. Rod Insert and Withdrawal Block RPS Aside % SCRAM B. Rod Insert and Withdrawal Block RPS B side % SCRAM C. Rod Withdrawal Block only RPS A side /2 SCRAM D. Rod insert Block only RPS B side /2 SCRAM Page I 2 8 of 200

LIMERICK October 2006 Initial License Operator NRC Examination I Answer Kev 5RQ Basis or Justification Correct: B A loss of 1BY185 results in a W SCRAM Loss of power to 2 PRNMS voter units, RBM Rod Blocks occur due to data fault on RPlS INOP I Incorrect A This is incorrect as W SCRAM occurs on B channel Incorrect C This is incorrect as Rod Block occurs on both insert and withdrawal due to data fault on RPlS INOP and W SCRAM occurs on B channel.

I Incorrect D This is incorrect as Rod Block occurs on both insert and withdrawal due to data fault on RPlS INOP I Psvchometrics I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.5 3 N y W(7) N Source Documentation Source: New Exam Item 0Previous NRC Exam c]Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): ANN 108 Reactor D-4, ANN 108 Reactor F-3 Learning Objective: 1 LL0T0280-03d Knowledge/Ability 215002 Importance: RO / SRO WA K2.03 2.8/ 2.9 (Description of K&A, from catalog)

Knowledge of electrical power supplies to the APRM channels Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

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 D channel only WHICH ONE of the following is the expected 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 October 2006 Initial License Operator NRC Examination I Choice Basis or Justification Correct: 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)

I Incorrect: A 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: B OA Fan will not start on a D RAD signal C Same text as Adistractor Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 4.0 4 N y (W(7) N Source: New Exam Item c]Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): P&ID M-26 sht 5 detail D, M-78 sht 1 Learning LLOT0450.7a 0bjective:

KnowledgeIAbility 290003 Importance: RO I SRO WA K4.01 3.1 I 3.2 Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet ATTACHMENT: TSG 3.2 Provided

66. Unit Iplant conditions are as follows:

0 SAMP-1 and SAMP-2 were entered 90 minutes ago 0 Drywell pressure and temperature are increasing 0 RPV lower head temperature has been upscale for 40 minutes 0 RPV level has been downscale for 60 minutes 0 No RPV injection has occurred for 90 minutes In conjunction with the above conditions, WHICH ONE of the following would indicate a core breach?

RPV Pressure DW Pressure DW H:-,

A. 1000 psig 20 psig 0.8%

B. 1000 psig 20 psig 7.0%

C. 50 psig 50 psig 0.8%

D. 50 psig 50 psig 7.0%

Page 132 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 066 Both RC Choice Basis or Justification Correct: D Core breach is indicated by RPV and Drywell pressure equal and hydrogen consistent with fuel damage Incorrect: A Reactor Pressure is too high to indicate a core breach Incorrect: B Reactor pressure is too high to indicate a core breach

~ ~

Incorrect: C Hydrogen is not present in a quantity that would indicate a core breach 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: ONew Exam Item 0Previous NRC Exam

@Modified Bank Item Other Exam Bank (LOR) 0ILT Exam Bank Reference(s): TSG-3.2 Learning LLOTI562.02 Objective:

Knowledge/Ability 2.4.21 Importance: RO / SRO K/A 3.7/ 4.3 (Descriptionof K&A, from catalog)

Knowledge of the parameters and logic used to assess the status of safety functions

?quiredMaterials:

TSG 3.2 Notes and Comments:

Question taken from LOR Bank Prepared By:

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

NRC Question Data Sheet

67. WHICH ONE of the following ALARMS is consistent with the noted conditions?

A. B REAC ENCL HVAC PCL 1BC208 trouble (004 A3)

HPCl Room temperature 175'F and rising B. DIV 1 DRYWELL HI PRESS ( I 1 3 E4)

Drywell pressure 0.5 psig and rising C. REACTOR HI PRESSURE TRIP (107 G I )

Reactor pressure 1045 psig and steady D. SCRAM DISCHARGE VOLUME HI LEVEL TRIP (107 C l )

SDV level in AER is 10% and rising Page 134 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Choice I Basis or Justification Correct: A 1BC208 panel trouble and HPCI room temp are consistent Incorrect:

Incorrect:

Bl C

Drywell pressure value is below Alarm setpoint Reactor pressure valve is below the ALARM setpoint Incorrect: D SDV level is below the ALARM setpoint I

Psychometrics 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 17 Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Modified Reference(s): ANNs 004 A3 Learning LLOTI560.02 0bjective:

~~ ~~

Knowledge/Ability 2.4.46 Importance: RO / SRO WA 3.5 / 3.6 Required Materials:

Notes and Comments Prepared By:

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

~

NRC Question Data Sheet

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/NOP (OA304, C-I)

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. Floor Drain Sample Tank discharge to Cooling Tower Blowdown Line D. Reactor Enclosure flow Drain Sump discharge to Liquid Radwaste Page 136 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Kev Choice I Basis or Justification Correct: Liquid Radwaste discharge to Cooling Tower Blowdown Line isolates on Hi Hi Rad.

Incorrect A Equipment Drain Sample Tank to CST isolation ion EDST LevelJ n o

(Pump off, discharge valve closes)

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

Incorrect D The only central functions associated with RE Flow Drain Suppression pumps are -off on Low Level and Lockout in Primary Containment isolation Hi Rod (Post LOCA Rad Monitor HiHi)

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 N N N Source Documentation Source: New Exam Item Previous NRC Exam Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): ARC-MCR-003 RAD-A-5, ARC-BOP-OAC304-C-1 Learning LLOT-0705.04 0bjective:

KnowledgelAbility 2.3.1 1 . Importance: RO I SRO WA 2.7 13.2 (Description of K&A, from catalog)

Ability to control radiation releases Iquired Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

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 investigate an EHC leak.

The EOS radiation history is as follows:

0 1760 mrem cumulative exposure for the current year (TEDE) 0 19 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 138 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key I

Choice I Basis or Justification Correct: B 3 Rem = 3000 mrem 3000 mrem X .75 = 2250 mrem 2250 mrem + 1760 mrem = 4010 mrem 4010 mrem exceeds Admin Dose Control Level Incorrect A Admin Dose Control Level is exceeded Incorrect C I 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 W(4)

Source: 0New Exam Item 0Previous NRC Exam 2002 Modified Bank Item 0Other Exam Bank

[XI ILT Exam Bank Reference@): RP-AA-203 sects 4.1 .I, 4.2,4.5 Learning LLOTI760.04,.05 Objective:

KnowledgefAbility 2.3.4 Importance: RO f SRO KIA 2.5 f 3.1 (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

NRC Question Data Sheet ATTACHMENT: GP-2 Appendix 1 Provided

70. Unit 2 plant conditions are as follows:

Reactor Startup in progress 0 All Group Iand Group 2 control rods are fully withdrawn 0 SRM count rates have doubled twice since the startup began WHICH ONE of the following describes the control rod notch positions where single notch withdrawal is required?

A. between 00 and 12 B. between 00 and 30 C. between 04 and 30 D. between 12 and 48 Page 140 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Kev g)g Choice Basis or Justification After 75% rod density (Group 1-2 fully withdrawn), control rod withdraw between notch positions 00 to 12 shall be restricted to single notch

~~

movements until criticality is achieved Incorrect I B See above Incorrect C Single notch requirement between 04 to 30 applies once my SRM count rate reaches four doublings, until the reactor is critical and one Turbine Bypass Valve is partially open Incorrect ID See A I Psvchometrics I 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 LLOTI 530.02 0bjective:

Knowledge/Ability 2.2. I Importance: RO / SRO KIA 3.7/ 3.6 Required Materials:

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

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

- -~

NRC Question Data Sheet

71. Unit 1 PRO is performing ST-6-051-231-1 A RHR pump, valve, and Flow Test At step 4.3.6, the PRO discovers that HV-51-IF021A 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. Create a Partial Procedure to delete the affected portion of the procedure per AD-LG-101-1002 Temporary Changes to Approved Documents and Partial Procedure Use prior to resumption of 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 resumption of the ST.

C. Continue the test. When it is complete, identify the component number error in an Action Tracking item to permanently revise the procedure per AD-AA-101 , Processing of Procedures and T & RMs.

D. Continue the test. When it is complete, identify the component number error in an Action Tracking item to permanently revise the procedure per AD-LG-101-1004 Procedure Performance Improvement System (PPIS).

Page 142 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 071 Both RC >Fag Choice ~~ ~~~~~ ~

Basis or Justification Correct: B An equipment number error requires a TC IAW AD-LG-101-1002, before the test can continue Incorrect: A See above Incorrect: C See above Incorrect: D See above Psychometrics Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 3 N Y (b)(lO) y W(3)

Source Documentation Source: New Exam Item 0Previous NRC Exam

[7 Modified Bank Item Other Exam Bank

[7 ILT Exam Bank Reference(s): AD-LG-101-1002, step 4.2.2 Learning LLOTI 570.01 Objective:

KnowledgelAbility 2.2.1 1 Importance: RO ISRO K/A 2.5 13.4 (Description of K&A, from catalog)

Knowledge of the process for controlling temporary changes..

Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

72. 1A Reactor Feed Pump needs to be worked at power.

0 Only one 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?

A. A Clearance Technical Evaluation shall be performed B. The work shall be performed under an Exceptional Clearance C. A Component Walkdown must be performed prior to application D. The single isolation valve must be restrained and locked in the closed position Page 144 of 200

~

LIMERICK October 2006 Initial License Operator NRC Examination I

Answer Key

$@

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 information or 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.

I I Psvchometrics I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.5 3 N y (b)(lO) N Source Documentation Source: New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank (CAT)

ILT Exam Bank Reference(s): OP-MA-109-101, attachment 4 Learning OP-MA-109-101 DB16 objective #2 Objective:

Knowledge/Ability 2.2.1 3 Importance: RO ISRO KIA 3.6 13.8 Required Materials:

Notes and Comments Prepared By:

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

-~

NRC Question Data Sheet

73. Given the following values from the most recent P - I :

MFLCPR 0.954 0 MFLPD 1.015 MAPRAT 0.991 0 FLLLP 0.967 WHICH ONE of the following identifies the thermal limit(s) that require action, if any?

A. MFLPD B. MFLPD and MAPRAT C. MFLPD, MAPRAT, and FLLLP D. All values are acceptable; no action is required Page 146 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Kev SFd, Choice Basis or Justification MFLPD (>1.0) and MAPRAT (>0.99) require entry into GP-14 Incorrect: A MFLPD does require action (see above) but this choice omits MAPRAT, which also requires action Incorrect:

IC FLLLP does not require action Incorrect: I D MFLPD and MAPRAT require action Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 HIGH 2.5 3 N N N Source: 0New Exam Item 0Previous NRC Exam 0Modified NRC Bank Item Other Exam Bank (LOR-modified) c]ILT Exam Bank Reference@): GP-5, Sect 3.1 .I Learning LLOT0741.04 Objective:

Knowledge/Ability 2.1 .I 9 Importance: RO 1 SRO WA 3.0 13.0 Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

74. ST-6-011-232-0, B LOOP ESW PUMP VALVE and FLOW TEST has been completed.

0 Restoration is in progress and Unit Cooler Throttle Valve 11-2023B must be returned to its throttled position WHICH ONE of the following verification techniques shall be used to restore this valve?

A. Peer Check.

B. First Check C. Concurrent Verification D. Independent Verification Page 148 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key I Choice I Basis or Justification I Correct:

lCl Valve throttling is an example when concurrent verification is appropriate IAW HV-AA-101, step 4.3.3.1 Incorrect: A Peer check is used to verify manipulation of components however in peer check, audio and/or visual cues are permitted in identifying the component.

This would not be permitted int his circumstance.

Incorrect: B First check verifies the first component manipulation in a specific task. It would not be used for restoration.

Incorrect: D In Independent verification, the verifying party does not witness the manipulation. This does not work for a throttle valve because you can not visually verify it is in the correct throttle position without touching the component or witnessing the operation.

Level of Difficulty Time Allowance PF!A RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.0 2 N y (b)(10) N Source: New Exam Item Previous NRC Exam Modified Bank Item Other Exam Bank ILT Exam Bank ReferenceCs): HU-AA-101, step 4.3.3.1 Learning LLOTI574.05d 0bjective:

1 Knowledge/Ability 2.129 1 Importance: RO I SRO KIA 3.4 / 3.3 Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet

75. Given the following conditions:

0 Both units are operating at full power 0 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 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 update plant status The relief duration shall be a MAXIMUM of 30 minutes.

D. Review the Shift Turnover Checklist and get an updated plant status.

The relief duration shall be a MAXIMUM of 60 minutes Page 150 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 075 Both RC $e*q Choice Basis or Justification Correct:

ID 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:

l 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: D Turnover criteria is correct, short turnover duration is 60 minutes, not 30 Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.5 3 N Y (b)(10) N Source: New Exam item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): OP-AA-112-101, Sect 4.1.7 Learning LLOTI574.24 0bjective:

Knowledge/Ability 2.1.3 Importance: RO I SRO KIA 3.0 13.4 Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet ATTACHMENT: S06.1 .H, Partial Provided 76 Unit 1 Plant conditions are as follows:

0 Reactor power is 100%

0 Reactor level is 35 and steady 1 A Reactor Feed Pump Primary and Secondary Feed Flow Transmitters fail downscale resulting in the following:

FEEDWATER TROUBLE (107 D5)Annunciator is in alarm 0 Feedwater Operator Station, Alarm Identity 1XX-FW302.1TFFE is displayed WHICH ONE of the following identifies the immediate impact on Feedwater Level Control and capability of Feedwater to control level during a Reactor SCRAM?

A. Will continue to control level automatically Will automatically control level post SCRAM B. Will continue to control level automatically RO will need to manually control feedwater post SCRAM C. Will not control level automatically Will automatically control level post SCRAM D. Will not control level automatically RO will need to manually control level post SCRAM Page 152 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key 1 I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 4 Y y W(5) y (b)(5)

Source Documentation Source: New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): S06.1.H U/1, Alarm Identity IXX-FW302.1TFFE S06.1.D U/1 Appendix 1 Learning LLOT0550. IOd Objective:

Knowledge/Ability 259002 Importance: RO / SRO WA A2.02 3.3 / 3.4 (Description of KBA, 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 any number of Reactor feedwater flow inputs.

kquired Materials:

Partial copy of S06.1 .H (exclude pages regarding level transmitters)

Notes and Comments:

Prepared By:

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

NRC Question Data Sheet 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 report T-251 is complete for Unit 1 WHICH ONE of the following identifies the required operator action?

A. Immediately inject with HPCl Restore level to -60 to -1 00 B. Immediately inject with HPCl 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 October 2006 Initial License Operator NRC Examination Answer Kev I

Basis or Justification 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 -1 86 as Supp pool temp is greater than I 10 degrees Incorrect: A Injecting immediately is incorrect as Blowdown has already started. - 6 0 to

-100 is incorrect as Supp pool temp is greater than I 1 0 degrees Incorrect B Injecting immediately is incorrect as Blowdown has already started.

r Incorrect C -60 to -1 00 is incorrect as Supp pool temp is greater than 110 degrees Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 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): T-I 17 BASES, Step LQ-21 Learning LLOTI 560.05 0bjective:

KnowledgelAbility 295037 Importance: RO / SRO KIA 2.1.20 4.3 14.2 (Description of K&A, from catalog)

SCRAM condition present and Reactor power above APRM downscale or unknown: Ability to execute procedural steps Required Materials:

T-I 17 Notes and Comments Prepared By:

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

NRC Question Data Sheet ATTACHMENT: SAMP-I, Sht IProvided 78 Unit Iplant conditions are as follows:

SAMP-I and SAMP-2 have been entered The Reactor was shutdown 20 minutes ago Reactor Level is unknown 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 25 Suppression pool pressure is 24 psig WHICH ONE of the following SAMP-I sheets must be executed?

A. Sheet4 B. Sheet 5 C. Sheet6 D. Sheet 7 Page 156 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key I

Choice I ~~ ~

Basis or Justification Correct: is required as injection is below MDRIR, and conditions are unsafe on

~~ ~~

Incorrect: A 1 Sht 4 is incorrect as level in unknown Incorrect B Sht 5 is incorrect as RPV injection is below MDRIR Incorrect C Sht 6 is incorrect as conditions are unsafe on PSP Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 4.0 4 Y Y (b)(lO) Y (b)(5)

Source Documentation Source: New Exam Item 0Previous NRC Exam Modified Bank Item Other Exam Bank (LOR) c]ILT Exam Bank Reference(s): SAMP 1, Sheet 1 Learning LLOTI 562.6 0bjective:

KnowledgelAbility 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

NRC Question Data Sheet 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 1A 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 42.00E6#

WHICH ONE of the following is the required operator action?

A. Insert control rods until the Restricted Region of the Power/Flow Map is exited B. Immediately Scram the Reactor C. Restart IB Recirc pump, and raise core flow with 1B Recirc pump D. Reduce Recirc pump speed to less than 60% and manually Scram the reactor.

Page 158 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 079 SRO Or Y Choice Basis or Justification Correct: A 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: B 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 C Restart 1B Recirc Pump and raise core flow with IB recirc pump is wrong as restarting a pump to raise flow is not allowed in OT-I 12 Incorrect D Reduce Recirc pump speed to less than 60% and manually scram the reactor is not correct as reducing speed drive the reactor further into the restricted region.

I Psvchometrics I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 5 N y (b)(lO) y Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): OT-I 12, Step 3.7 Learning LLOT0040.07g 0bjective:

Knowledge/Ability 295001 Importance: RO / SRO WA AA2.01 3.5 / 3.8 (Description of K&A, from catalog)

Ability to determine and/or interpret the following as they apply to a partial or complete loss of forced core flow circulation: Power/Flow map iquired Materials:

OT-I 12, Power to Flow Maps Attachment 1 & 2 only Notes and Comments Prepared By:

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

NRC Question Data Sheet ATTACHMENT: S61.O.A Provided 80 Unit 1 plant conditions are as follows:

0 A steam leak exists in the Drywell Drywell Pressure is .7 psig and steady Drywell Temperature is 134 degrees F and steady The following alarms/indicators have been received a Drywell Equipment Drain/Floor Drain Sump Leakage Hi Flow (I 12 C-5) 0 Drywell Equipment Drain Hi Total Flow (112 J-1) 0 Drywell Floor Drain Tank Hi/Lo Level ( I 12 K-2)

OOC424 Unit IDW Equipment Drain Tank Leak Rate Change Exceeding 2 GPM red light lit WHICH ONE of the following Annunciators/lndications require the highest priority?

A. Drywell Equipment Drain/Floor Drain Sump Leakage Hi Flow (112 C-5)

B. Drywell Equipment Drain/floor Drain Sump Leakage Hi Flow (1 12 C-5) with Unit One Drywell Equipment Drain Hi Total Flow ( I 12 J-I)

C. Drywell Equipment Drain Hi-Total Flow (1 12 J-I)

D. Drywell Floor Drain Tank Hi/Lo Level (1 12 K-2)

Page 160 of 200

LIMERICK October 2006 Initial License Operator NRC Examination I Answer Key Question ID# 080 SRO Or $

I Choice Basis or Justification Correct: D Floor drain tank HilLo level is priority 2 which is higher than any distractor, This requires use of S61.OA to determine t--- Incorrect:

Incorrect A

B Leakage Hi Flow and Leak rate change exceeding 2 GPM is priority 3 Leakage Hi Flow and Drywell equipment total flow is priority 4 Incorrect C Drywell equipment drain Hi Total flow is priority 4 Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 10CFR55.43 Low 4.0 4 N N N Source Documentation Source: 0New Exam Item 0Previous NRC Exam 0Modified Bank Item [XI Other Exam Bank 0ILT Exam Bank Reference(s): S61.OA step 4.2014.22 Learning LLOTOI35.02 0bjective:

Knowledge/Ability 295024 Importance: RO / SRO WA 2.1.23 3.9 I 4.0 (Description of K&A, from catalog)

High Drywell pressure ability to perform specify system an integrated plant procedures during different modes of plant operations.

quired Materials:

Notes and Comments:

Question from LOR Bank Prepared By:

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

~

NRC Question Data Sheet 81 Unit 2 conditions are as follows:

0 2B loop of SDC is in service 0 SDC flowrate is 9000 gpm 0 RPV pressure is 25 psig 0 2B RHR Heat Exchanger inlet temperature on DAS is 145OF 0 2B RHR Heat Exchanger outlet temperature on 20C601 T I 227B is 125OF 2B Recirculation Pump Suction and Discharge Valves are discovered to be OPEN.

WHICH ONE of the following represents actual reactor coolant temperature based on plant conditions?

A. 125OF B. 145OF C. 22OoF D. 268F Page 162 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 081 SRO 01 _ _ _ _ ~

Choice Basis or Justification Correct: D Answer requires operator to determine that shutdown cooling bypass leakage path exists, and use STM tables to interpret Reactor pressure to determine coolant temperature Incorrect: A This is incorrect as RHR and heat exchanger outlet temperature cannot be used as Recirc pump valves open are creating bypass leakage Incorrect B This is incorrect as it does not match Reactor pressure valve on STM table Incorrect C This is incorrect as it does not match Reactor pressure valve on STM table Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 4.0 4 Y y (b)(10) Y (b) (5)

Source: New Exam Item Previous NRC Exam Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): S51.8 B step 3.13 Learning LLOT0370.13 Objective:

KnowledgelAbility

- 295021 I Importance: RO 1 SRO K/A AA2.06 3.2 13.3 (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:

Steam Tables Notes and Comments:

Prepared By:

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

NRC Question Data Sheet ATTACHMENTS: ANN 106, 0 2 and GP-5, Partial Provided 82 Unit 1 conditions are as follows:

Reactor Power is 50%

BESSI System is not in operation LP Turbine Inlet Pressure is 100 psig LP Turbine Back Pressure is 7.1 in Hg abs The following annunciators are received TURBINE HIGH BACK PRESSURE (106 D2)

I A CONDENSOR LO VACUUM (104 E-5)

WHICH ONE identifies the required operator action A. Immediately Perform A GP-4 shutdown B. Reduce reactor power to place turbine in limited operation region C. Reduce reactor power to place turbine in unlimited operation region D. Immediately lower turbine inlet pressure with pressure set Page 164 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Correct: C Student must plot values on GP-5 attachment 7 to determine that turbine is operating in the limited region. And determine corrective action per ARC 106 D2 incorrect: A An immediate GP-4 is not required based on valves Incorrect B This is incorrect as valves due not place turbine outside of limited region.

Additionally operation above limited region would result in a turbine trip Incorrect D Lower turbine inlet pressure would not take turbine to unlimited region Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 Y Y (b) (IO) y (b) (5)

Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s ): ANN 102 D-2, GP-5 Attachment 7 Learning LLOT0500.06a 0bjective:

Knowledge/Ability 295002 Importance: RO I SRO KIA AA2.01 2.9 13.1 (Description of K&A, from catalog)

Ability to determine and/or interpret condenser vacuumlabsolute pressure as it applies to a loss of main condenser vacuum

?quiredMaterials:

ANN 106 D-2 and GP-5 Attachment 7 Notes and Comments Prepared By:

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

~

NRC Question Data Sheet 83 Unit 1 conditions are as follows 0 Reactor Power is 100%

0 No testing which adds heat to the Suppression Pool is occurring 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 for SBLC injection during an ATWS B. 105OF Bulk water temperature following a blowdown maintain NPSH for RHR and core Spray pumps C. 95OF Provide sufficient temperature margin for SBLC injection during an ATWS D. 95OF Bulk water temperature following a blowdown maintains NPSH for RHR and Core Spray pumps Page 166 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Choice Basis or Justification Correct: D Tech Spec 3.6.2.1 limits suppression pool max temperature to 95'F w h o testing that adds heat to the suppression pool and maintain water temperature and suppression chamber conditions following a blowdown to support ECCS NPSH Incorrect: A 105OF is incorrect as no testing is in progress that adds heat to the suppression pool Incorrect B 105OF is incorrect as no testing is in progress that adds heat to the suppression pool Incorrect Is incorrect as temperature limit is not based on providing sufficient temperature margin for SBLC injection during an ATWS Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.0 3 N N y (bP)

-

Source Documentation Source: [XI New Exam Item Previous NRC Exam ILT Exam Bank Reference(s): Tech Spec basis 3.6.2.1 Learning LLOTOI30.04f 0bjective:

KnowledgelAbility 295013 Importance: RO / SRO WA 2.2.25 4.0 14.0 Required Materials:

Notes and Comments Prepared By:

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

___

NRC Question Data Sheet 84 Given the following plant conditions:

0 A Loss Of Offsite Power and failure of all diesels to start, has occurred WHICH ONE of the following identifies the method used to verify that a successful Reactor Scram has occurred?

A. APRMs indicate 0%

B. PMS reads SCRAM-ALL RODS IN C. GreenlN lights is Lit on the Full Core Display D. RPS A and 6channel indicating lights are NOT Lit Page 168 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Question ID# 084 SRO Or Choice Basis or Justification Correct:

Incorrect:

l1 AB E-I directs APRMs be referencedto ensure SCRAM This would normally indicate a successful SCRAM but PMS will lose power in a station blackout

!

~

Incorrect These lights will be out indicating RPS de-energized but that does not ensure that rods actually went in Incorrect This would normally indicate a successful scram but the Full Core Display will lose power in a station blackout Psychometrics -

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

Low 2.0 3 Y y (b)(W y (b)(5)

Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): E-I Learning LLOT0275.13 Objective:

Knowledge/Ability 295003 Importance: RO / SRO KIA AA2.02 4.2 14.3 Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet ATTACHMENT: T-291 Provided 85 Unit Iplant conditions are as follows:

A steam leak occurred in the Reactor enclosure T-290 readings are reported as follows:

TE41-1 NOIOA, B,C and D (Outboard MSIV Room) all indicate 190°F TE41-1 NO14 (Outboard MSlV Room) indicates 195OF 1B Wide Range level recorder (XR-42-1R623B) is indicating -1 30 Fuel Zone Level indicator (LI-42-1R610) is indicating -1 60 WHICH ONE of the following statement below describes the effect on reactor water level indication?

XR-42-1R623B LI-42-1R610 A. Valid Not Valid B. Valid Valid C. NotValid Valid D. Not Valid Not Valid Page 170 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 085 SRO Or f

______~ ~

I Choice Basis or Justification Correct: C Indicators are valid if temp is below MRT, and level is above MIL. As temp is above MRT only level distinguishes answer.

MIL for IR623B is -124 therefore it is invalid.

MIL for 1R610 is -303 therefore it is valid Incorrect: A 1R623B is not valid as level is below MIL (-124)

B 1R623B is not valid as level is below MIL (-124)

I Incorrect D 1R610 is valid as level is above MIL (-303)

Psychometrics Level of Difficulty Time Allowance PRA RO SRO Knowledge (minUtes) 10CFR55.41 10CFR55.43 Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): T-291 Attachment 2 Learning LLOTI561.03 0bjective:

KnowledgeiAbility 295032 Importance: RO i SRO WA EA2.02 3.3 i 3.5 (Description of K&A, from catalog) Ability to determine and/or interpret equipment operability as it applies to high secondary containment area temperature Required Materials:

T-291 Notes and Comments Prepared By:

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

~

NRC Question Data Sheet 86 Unit 1 conditions are as follows:

A Startup is in progress following a refueling outage 0 Reactor Power at 18%

0 Main Turbine is synched to the grid House Loads are being transferred to the Unit Aux Buses with the lineup as follows:

I 1 Bus Unit Aux Feeder BKR is closed 0 l o l l 1 Feeder BKR is open 0 12 Bus Unit Aux Feeder BKR is open 0 20/12 Feeder BKR is closed A Generator Protection Relay failure causes a Generator Lockout and Main Turbine trip WHICH ONE of the following describes the status of the startup Bus Breakers and Recirc Pump MG set Drive Motor Breakers following the Turbine Trip?

10/11 BKR 20/12 BKR IA MG DM BKR IB MG DM BKR A. CLOSED CLOSED OPEN OPEN B. OPEN CLOSED OPEN CLOSED C. CLOSED CLOSED OPEN CLOSED D. CLOSED CLOSED CLOSED CLOSED Page 172 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key I

Basis or Justification Correct: C The 11 Bus fast transfers on the Turbine trip, the 1A Recirc pump MG set Drive Motor trips on the generator lockout because the 11 Bus was powered from the Unit Aux transformer at the time.

Incorrect: A This would have been the lineup if the transfer of House loads had been complete and the 12 Bus was powered from the Unit aux transformer at the time of the Turbine Trip Incorrect B This lineup supposes that the fast transfer of the 11 Bus did not take place therefore the 1A MG set DM BKR tripped. There is no information to support this scenario 1 Incorrect I D This lineup supposes that the 1A MG set drive motor breaker would stay closed during the fast transfer of the 11 Bus. This is not true.

Level of Difficulty Time Allowance PRA RO SRO Know1edge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 Y Y (b)(lO) Y (b)(5)

Source Documentation Source: New Exam Item Previous NRC Exam Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(sk E-I 40, E-145, E-I 51 Learning LLOT0640.03b Objective:

Knowledge/Ability 295005 Importance: RO ISRO KIA AA2.08 3.2 13.3 (Description of K&A, from catalog) Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP. ..Electrical distribution status REQUIRED MATERIALS:

Notes and Comments Prepared By:

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

NRC Question Data Sheet 87 Unit 1 Plant conditions are as follows 0 Reactor Power is 100%

0 I&C reports that 1C Main Steam Line (MSL) High Flow Transmitters 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 MSlV Isolation logic and the required action?

A. 1C MSL MSlV isolation logic is 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 />.

B. Div 1 MSlV isolation logic is INOPERABLE Place ONE Channel tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> C. Div 1 and 2 MSlV isolation logic are INOPERABLE SCRAM Unit one, and place BOTH Channels 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 /> 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 October 2006 Initial License Operator NRC Examination Answer Key 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 A common misconception is that a streamline is a trip system. If only one trip system is affected, you have 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> until having to place it in the tripped condition Incorrect B If only one trip system were affected, this would be correct Incorrect C The number of affected systems per line is correct however placing both in the tripped condition would cause a group 1 isolation. Tech Spec does not require this..

Psychometrics I Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 5 N y (b)(5) y (b)(2)

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

Knowledge/Ability 223002 Importance: RO I SRO KIA A208 2.7 I 3.1 REQUIRED MATERIALS:

Notes and Comments Prepared By:

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

-~ - ~~~ ~

NRC Question Data Sheet 88 Unit 2 is in OPCON 5 and all fuel movements have been completed and core verification has been performed. Plant status is as follows:

0 The 201 Safeguards Transformer has been de-energized 0 The 101 Safeguards Transformer is supplying all 4KV uses 0 021 and D23 Diesel Generators are INOPERABLE for planned maintenance 0 Surveillance testing has just been completed on D24 Diesel Generator 0 Control rod stroke time testing is in progress in the MCR 0 The Steam Separator is being seated in the Dryer/Separator pit The inside EO reports that D24 Fuel Oil Transfer pump has seized WHICH ONE of the following describes the most limiting action required by Tech Specs?

A. Stop control rod stroke time testing immediately B. Stop movement of the steam separator immediately C. Demonstrate the operability of D22 Diesel Generator within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D. Restore the 201 Safeguard Transformer to operability within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Page 176 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 088 SRO Or r

_ _ _ _ _ ~

Basis or Justification Correct: A Tech Spec 3.8.1.2 requires suspension of Core ALTERATIONS with the AC Powr sources inoperable in OPCON 5. Control rod movement with fuel in the vessel must be stopped.

Incorrect: B Movement of the Steam Separator does not qualify as a core alteration Incorrect C Would be required if in OPCON I,2 or 3. Not required in OPCON 5 Incorrect D Would be required if Unit 2 were in OPCON 1,2, or 3 or if a Unit 1 DfG were INOP Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43 High 4.0 4 Y N Y (b)(2)

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

Knowledge/Ability 264000 Importance: RO f SRO K/A 2.2.22 4.0 f 4.0 (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

NRC Question Data Sheet 89 Unit 2 conditions are as follows:

An inadvertent Group 1 isolation resulted in MSlV closure and Unit Scram 0 RPV level is 35 being maintained by RClC in Auto 0 RPV pressure is 900 psig and lowering slowly The RClC flow controller fails in AUTO Controller is switched to MANUAL and adjusted so that level is +35 and steady.

0 No other operator action is taken.

WHICH ONE of the following describes the expected RPV level trend over the next 30 minutes, and the required operator action?

A. RPV level will go down RClC flow controller output must be raised to increase flow demand signal B. RPV level will go up RClC flow controller output must be lowered to reduce flow demand signal C. RPV level will go down RClC flow controller output must be raised to increase turbine speed D. RPV level will go up RClC flow controller output must be lowered to reduce turbine speed Page 178 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key I

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 must be dialed down to reduce turbine speed.

Incorrect: A RPV level will go up not down. The RClC flow controller maintains a flow demand in AUTO, not MANUAL

~~ ~

Incorrect B The RClC flow controller maintains a flow demand in AUTO not MANUAL

-

Incorrect C RPV level will go up not down as RPV pressure decreases Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 Y Y (b)(5) y (b)(5)

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

Knowledge/Ability 217000 Importance: RO / SRO WA A2.10 3.1 13.1 REQUIRED MATERIALS:

Notes and Comments Prepared By:

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

NRC Question Data Sheet ATTACHMENT: OT-I 02, Partial Provided 90 Unit IPlant conditions are as follows:

0 Reactor Power is 100%

0 A Turbine Control Valve Solenoid failure results in the closure of the #2 Turbine Control Valve.

WHICH ONE of the following identifies the impact on plant operations and required operator act ions?

A. Reactor Pressure remains constant Reduce reactor Power to less than 75%

B. Reactor Pressure remains constant Ensure reactor power remains above 90%

C. Reactor Pressure rises Reduce reactor power to less than 90%

D. Reactor Pressure rises Reduce reactor power to less than 25%

Page 180 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Choice I Basis or Justification Correct: C Reactor pressure will increase slightly requiring entry into OT-102. OT-102 requires power to be lowered to below 90% on a control valve closure.

Incorrect:

lA This is incorrect as Reactor pressure will rise and action to lower power requires a reduction to 90% (75% is for an MSlV closure)

Incorrect IB Reactor pressure remains constant is incorrect and maintaining power greater than 90% is not correct (this would be correct for a regulator failure)

Incorrect ID Reducing Power to below 25% is incorrect Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High '3.0 4 N y (b)(5) y (b)(5)

Source Documentation Source: [XI New Exam Item 0Previous NRC Exam 0Modified Bank Item 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 I SRO KIA A2.04 3.7 13.8 (Description of K&A, from catalog)

Ability to predict the impact of the following on the ReactorITurbine Pressure Regulating System; and based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations: Failed openlclosed control valve

quired Materials:

OT-102, remove last page Notes and Comments Prepared By:

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

NRC Question Data Sheet 91 Unit IPlant conditions are as follows:

0 95%power 0 IC RHR pump has been INOP for 19 days 0 HPCl speed cannot be raised above 2250 RPM during a full flow test 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 I C RHR Pump to operable within the next 11 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN in the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> C. Restore the I C RHR pump or the HPCl system to operable within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in HOT SHUTDOWN in the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN in the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 Page 182 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Kev I

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 LLCOs cannot be met Incorrect B This would be the correct action if HPCl were operable.

Incorrect D This would be correct if I C 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: n N e w Exam Item Previous NRC Exam Modified Bank Item Other Exam Bank (LOR modified) 0ILT Exam Bank Reference(s): T. S . 3.5.l.b and 3.5.1.c.2 Learning LLOT0340.16 0bjective:

Knowledge/Ability 206000 Importance: RO ISRO WA 2.1.12 2.9 14.0 I .

Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet ATTACHMENT: EAL Matrix Provided 92 LGS Units 1 and 2 are at 100%

A cold weather front is passing through the Pottstown area accompanied by severe thunderstorms and hail. A tornado watch is in effect, with wind gusts currently at 70 MPH 0 The outside EO reports that a Tornado has damaged the Kemper Building.

WHICH ONE of the following is the correct event classification and EAL Threshold value per the LGS Radiological Emergency Plan Annex for the given conditions?

A. HU5 - Threshold 2 B. HU5 -Threshold 3 C. HA5 -Threshold 2 D. HA5 -Threshold 3 Page 184 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Choice I Basis or Justification Correct: A Report of a Tornado Strike in the protected area is a HU5 Threshold 2 Incorrect: B This is incorrect as wind speed must be greater than 75 mph for 15 minutes for HU5, Threshold 3 Incorrect C This is incorrect as damage to vital structure has not occurred Incorrect D This is incorrect as damage to vital structure has not occurred Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 Y Y (b) 11 Y (b)(5)

Source Documentation Source: 0New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank (LOR modified) 0ILT Exam Bank Reference(s): Emergency Action Level Matrix (Table 3-1)

Learning Emergency Preparedness module G-16, Objective 8 Objective:

KnowledgelAbility 2.4.41 1 Importance: RO I SRO KIA 2.3 14.1 (Description of K&A, from catalog)

Knowledge of the emergency action level thresholds and classifications.

Required Materials:

EAL Matrix Notes and Comments Prepared By:

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

NRC Question Data Sheet 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-102 have been implemented 0 T - I 02 has directed inerting/purging the Drywell 0 Suppression Pool level is 24 Feet 0 Drywell Pressure 2 psig The following containment parameters exists:

0 DW H2 5% and increasing 0 DW 024% and increasing 0 SP H2 3% and increasing 0 SP 022% 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 October 2006 Initial License Operator NRC Examination Answer Key Question ID# 093 SRO Or bf Basis or Justification Correct: B 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 Incorrect: A Not allowed due to high drywell pressure (>.75 psig)

Incorrect C Allowed but not preferred per the note in section 4.3 and Table 1 of T-228 1 Incorrect I D Does not apply to the given conditions Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 4 Y N y (b) (4)

Source: New Exam Item Previous NRC Exam Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): T-228 section 4.3,4.5 and 4.6 Learning LLOTI 561.03 0bjective:

Knowledge/Ability 2.3.9 Importance: RO / SRO WA 2.5 13.4 (Description of K&A, from catalog)

Knowledge of the process for performing a containment purge Required Materials:

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

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

__

NRC Question Data Sheet 94 Unit Iplant conditions are as follows:

0 96%power 0 Control Rod Scram time testing is in progress per ST-6-107-790-1 0 Control Rod 30-31 is at position 48 The following sequence of events occur 13:OO:OO - RDCS INOP (108 E4) Annunciator is in alarm 13:00:02 - Control Rod HCU Toggle Switches Aand B for Rod 30-31 are taken to TEST 13:00:08 - Control Rod 30-31 is at Position 00 WHICH ONE of the following describes the status of the Full Core Display indication for Control Rod 30-31 and the reason for the indication?

Blue SCRAM Light Reason for Indication A. On Control Rod at position 00 B. On Scram Inlet and Outlet valves are OPEN C. Off The Full Core Display will NOT update D. Off Scram Inlet and Outlet valves are CLOSED Page 188 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 094 SRO Or Choice Basis or Justification I Correct: C With an RDCS INOP, the Full Core Display will not update, therefore, although the Blue SCRAM light would normally be lit with the rod scrammed. it will not be due to the RDCS INOP Incorrect: A The light will not be lit and the blue SCRAM light does not look at rod position.

Incorrect B The light will not be lit due to the RDCS INOP, but this would be the correct indication and reason fi not for the RDCS INOP Incorrect D This indication and reason are right for normal operation but the reason the SCRAM light is off is due to the RDCS INOP r

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

Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): ARC-MCR-108-E4 Learning LLOT0080.04 Objective: I Knowledge/Ability 201002 2.1.32 Importance: RO I SRO WA 3.4 13.8 Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet ATTACHMENT: ON-I22 Provided 95 Unit 2 plant conditions are as follows:

e Reactor Power is 100%

e 1PP02 125 VDC DlST PANEL UNDERVOLTAGE (1 25 A-4) Annunciator is in Alarm An EO Reports 1PPO2 is DEENERGIZED WHICH ONE of the following identifies the required operator actions A. Enter T-101 and T - I 03 B. Enter T - I 02 C. Enter T-I 03 D. Enter T-101 and T-I02 Page 190 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 095 SRO Or I Choice Basis or Justification Correct:

I C A Loss of 1PPOl impacts ANN Panels that contain T-I 03 entry requiring entry into T-103 Incorrect: A Entry into T-101 is not required as no scram will occur Incorrect lB Entry into T-I 02 is not required due to a loss of annunciator 7

~

Incorrect Entry into T-101 and T-102 is not required due to a loss of annunciators I

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.5 4 N Y (b)(lO) y (W5)

Source: [XI New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT ExamBank Reference(s): ON-122, Page 2, Step 2.5 Learning Objective: I Knowledge/Ability 2.4.32 LL0T1550*03 Importance: RO / SRO KIA / 3.3 13.5 Required Materials:

ON-122 Notes and Comments Prepared By:

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

~ ~~

NRC Question Data Sheet 96 WHICH ONE of the following Identifies Work Execution CenterNork Control Center Supervisor Staffing requirements?

A. May be credited as Shift Technical Advisor (STA) and Incident Assessor (IA) Simultaneously B. May be credited as Incident Assessor (IA) and NRC Communicator SimuItaneously C. If credited as Shift Technical Advisor (STA) then Incident Assessor function is not required.

D. If credited as Incident Assessor (IA) then Shift Technical Advisor (STA) function is not required Page 192 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Choice Basis or Justification Correct: C If WCS is STA then IA function is not required (OP-AA-101-1 11, 4.5.2)

Incorrect: A WCS cannot be both STA and IA (OP-LG-101-111, Attachment 3)

Incorrect B WCS cannot be both IA and NRC Communicator (OP-LG-101-111, Attachment 3)

Incorrect D If WCS is the IA, they support the STA function, the STA is still required Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.0 3 N N y Source Documentation Source: [XI New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): OP-AA-101-111, page 5,step 4.5 OP-LG-101-111, page 11 #3 Learning LLOTI 574.01a 0bjective:

KnowledgelAbility 2.1.4 1 Importance: RO / SRO WA 2.3 13.4 (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

NRC Question Data Sheet ATTACHMENT: ON-I 15 Provided 97 Plant Conditions are as follows:

0 Unit 1 is at 100% power Unit 2 is in OPCON 5 for refueling Outside Air Temperature is 77OF A piping rupture in the Control Enclosure Chilled Water system results in the following conditions.

0 Main Control Room (MCR) temperature is 79OF and rising 0 MCR humidity is 60% and rising 0 Aux Equipment Room (AER) temperature is 74 OF and steady 0 AER humidity is 52% and steady WHICH ONE of the following describes the potential consequence of these conditions and the action required to prevent it?

Consequence Action A. Spurious Activation of Equipment Purge the MCR B. Spurious Activation of Equipment Purge the AER C. Exceeding Tech Spec temperature limit Purge the MCR D. Exceeding Tech Spec temperature limit Purge the AER Page 194 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 097 SRO Or Y I Choice Basis or Justification 1 Correct:

Incorrect:

C A

Main Control room temperature >78 F and > outside air temperature requires a purge of the MCR. The limit of 78 F is based on not exceeding the Tech Spec limit of 85 F effective Action is correct. Consequence is the basis if AER temperature is >78 F Incorrect B IF AER temperature were >78 F, this would be correct r------Incorrect D AER does not require purge ( ~ 7 8 'F). There is no Tech Spec temperature limit for the AER Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 4 N N Y (b)(2)

Source Documentation Source: New Exam Item Previous NRC Exam 0Modified Bank Itern Other Exam Bank 0ILT Exam Bank Reference(s): On-I 15, Tech Spec 3.7.2 Learning LLOT0450.05 Objective:

KnowledgeIAbility 290003 Importance: RO I SRO KIA A2.02 3.1 13.4 Required Materials:

ON-I 15 Notes and Comments Prepared By:

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

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NRC Question Data Sheet 98 Which one of the following Procedure revisions would required a Station Qualified Reviewer (SQR) review?

A. Changes to references in a Surveillance Test B. Editorial changes to an Operations T&RM C. Addition of clarifying information in the form of a list of required tools in a Systems Procedure D. Changes to activates in an Off-Normal Procedure Page 196 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 098 SRO Or if Choice Basis or Justification Correct: D Changes to activates in a procedure requires a SQR review Incorrect: A Changes to reference are excluded from requiring SQR review Incorrect lB Editorial change are excluded from requiring SQR review c Incorrect 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)(b)

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

Knowledge/Ability 2.2.6 Importance: RO / SRO K/A 2.3 f 3.3 (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

NRC Question Data Sheet 99 Fuel is being loaded into the core on Unit 1, with the following conditions:

1 A SRM count rate is 3.5 cps and has a signal-to-noise ratio of 2.0 1 B SRM was declared inoperable last shift due to spiking 0 1C SRM count rate is 2.0 cps and has a signal-to-noise ratio of I.5 1D SRM count rate is 2.5 cps and has a signal-to-noise ratio of 2.0 WHICH ONE of the following describes the ability to continue 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 D core quadrants ONLY Page 198 of 200

LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Question ID# 099 SRO 00 r Choice Basis or Justification Correct: C B and C SRMs are inoperable (C due to inadequate signalhoise ratio, per T.S. fig 3.3.6-1) Therefore, Fuel movement is only permitted in quadrants A and D per T.S. 3.9.2 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 Source: New Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): T.S. 3.9.2 and Figure 3.3.6-1 Learning LLOT0240.10 Objective:

KnowledgelAbility 2.2.28 Importance: RO / SRO WA 2.6 13.5 Required Materials:

Notes and Comments Prepared By:

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

NRC Question Data Sheet I00 Unit 1 is at 100% power when the follows occurs:

At 0100, Chemistry reports the following results of a Reactor Water Sample:

0 Conductivity is 2.5 mmhokm 0 pH is 5.4 0 Chlorides is 0.1 ppm 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 and maximize RWCU flow 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 /> E. 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

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LIMERICK October 2006 Initial License Operator NRC Examination Answer Key Basis or Justification I Correct: A ON-I 16 directs that with Conductivity > I .O mmhokm 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 fi GP-12 action level 3 (>5mmhokm) were reached Incorrect ID This action would be appropriate if the plant was in any OPCON other than 1, 2 o r 3 I Psvchometrics I 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 Referencek): GP-12, Sect 2.3, ON-I 16, T&RM 3.4.4 Learning LLOT1030.12 Objective:

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:

Notes and Comments Prepared By:

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