ML15287A477

2015 Dresden Station Initial License Examination Proposed Reactor Operator Written Examination

ML15287A477
Person / Time
Site:	Dresden
Issue date:	04/30/2015
From:	Randy Baker Operations Branch III
To:	Exelon Generation Co
References
Download: ML15287A477 (132)

Text

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 1 ID: 24144 Points: 1.00 Given the following set of conditions on Unit 3:

• Single loop operation is in effect.

• 3A Recirc pump is secured.

• A leak develops causing Drywell pressure to rise to 3.3 psig, and it slowly continues to rise.

• LPCI loop select logic has just sent a trip signal to the 3B Recirc pump.

• RPV water level is currently 20 inches and slowly lowering.

• RPV pressure is currently 920 psig and slowly lowering.

Under these conditions, LPCI loop select logic will FIRST select a loop for injection when RPV (1) drops to (2) .

A. (1) pressure; (2) 350 psig B. (1) pressure; (2) 870 psig C. (1) water level; (2) +8 inches D. (1) water level; (2) -59 inches Answer: B ILT EXAM Page: 1 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 1 Details Question Type: Multiple Choice Topic: 01 - 295001.K2.05 System ID: 24144 User ID: 24144 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE203LN001.06

Reference:

12E-2437A, DAN 902-3 A-4 K/A: 295001.K2.05 3.2 / 3.6 K/A: Knowledge of the interrelations between Partial or Complete Loss of Forced Core Flow Circulation and the following: LPCI loop select logic: Plant-Specific CFR: 41.7 PRA: Yes Pedigree: Bank Level: High History: 06-1 CERT EXAM Explanation: With one pump running, a trip signal is sent to BOTH Recirc pumps immediately after loop select logic begins. To ensure accurate DP comparison is made between the two loops, the logic waits until RPV pressure drops below 900 psig to compare the loops. LPCI Loop select can be initiated due to either Drywell pressure or Reactor water level making all answers plausible. The question is higher order due to having to determine the impact of single loop operation on Loop Select logic.

REQUIRED

REFERENCE:

None.

ILT EXAM Page: 2 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 2 ID: 24145 Points: 1.00 Unit 2 was operating at near rated conditions, when the following occurred:

• Unit 2 experienced a Loss of Off-Site Power (LOOP).

• Unit 2 experiences a Reactor Scram

• Annunciator 902-8 E-4 2/3 DG OVERLOAD alarmed.

• Annunciator 902-8 D-4 2/3 DG GROUND FAULT alarmed.

• Annunciator 902-8 E-5 4KV BUS 24-1 OVERCURRENT alarmed.

• 2/3 DIESEL GENERATOR KILOWATT meter reads 2850 Kilowatts.

What action(s) is/are the NSO required to take?

A. Dispatch an EO to open 2/3 D/G to Bus 23-1 ACB.

B. Trip ALL loads connected to 2/3 DG, then close breakers one at a time to locate ground fault to prevent damage to the 2/3 EDG.

C. Trip ALL loads connected to 2/3 DG, then close breakers one at a time to locate ground fault to prevent damage to the load when Off-Site power restored.

D. Trip all UNNECESSARY loads connected to 2/3 DG, then close breakers one at a time to locate ground fault to prevent damage to the load when Off-Site power restored.

Answer: D ILT EXAM Page: 3 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 2 Details Question Type: Multiple Choice Topic: 02 - 295003.K3.04 System ID: 24145 User ID: 24145 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 3 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE264LN004.10

Reference:

DAN 902-8 D-4, DAN 902-8 E-4 K/A: 295003.K3.04 3.0 / 3.2 K/A: Knowledge of the reasons for the following responses as they apply to Partial or Complete Loss of AC: Ground isolation.

Level: High Pedigree: Bank History: 2007 NRC Explanation: The operator must determine which trips are bypassed with an automatic initiation signal vs a manual start. With the 2/3 EDG running via an AUTO start signal (LOOP), the actions required are to trip ALL unnecessary loads connected, then close breakers one at a time to locate ground fault to prevent damage to the load when Off-Site power restored.

REQUIRED

REFERENCES:

None.

3 Points: 1.00 Unit 3 was operating at near rated power, when Bus 33-1 tripped on overcurrent.

The 3A Pumpback compressor will have . . . . .

A. NO cooling water flow supplied to it.

B. FULL cooling water flow supplied to it.

C. partial cooling water flow supplied to it from 3A RBCCW Pump ONLY.

D. partial cooling water flow supplied to it from 3B RBCCW Pump ONLY.

Answer: B ILT EXAM Page: 4 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 3 Details Question Type: Multiple Choice Topic: 03 - 295018.K1.01 System ID: 24251 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 0.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 223LN001.03

Reference:

DOA 3700-01, DOP 1600-19 K/A: 295018.K1.01 3.5 / 3.6 K/A: Knowledge of the operational implications of the following concepts as they apply to Partial or Total Loss of CCW: Effects on component / system operations.

PRA: No CFR: 41.8 to 41.10 Level: Memory Pedigree: Bank History:

Explanation:

This question meets the K/A because a partial loss of CCW has occurred on Unit 3 however, the Unit 3 Pumpback air compressors are cooled by Unit 2 RBCCW which is not effected. This examines the knowledge of the effect (or lack thereof) on Unit 3 pumpback air compressor operations. If Unit 2 experienced a loss of RBCCW, Unit 2 and 3 pumpback air compressors would lose cooling.

This question also tests the differences between the Units at Dresden Station, as cooling water for the Unit 3 Pumpback air compressors can ONLY be supplied from UNIT 2 (not Unit 3).

When Bus 33-1 is de-energized, the 3A RBCCW pump would lose electrical power, but there is no loss of cooling to the Pumpbacks.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 5 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 4 ID: 24148 Points: 1.00 Given the following conditions:

• Unit 2 is at full power.

• 2A and 2B Instrument Air Compressors (IAC) are running.

• 2A IAC trips due to low lube oil pressure.

• Unit 2 Instrument Air pressure is 78 psig and dropping slowly.

• An operator has been dispatched to start and align 3C IAC to Unit 2.

The reason for this action is to prevent the __________.

A. FRVs from failing closed B. outboard MSIVs from drifting closed C. Target Rock from becoming inoperable in ERV mode D. Unit 2 Instrument Air to Unit 2 Service Air cross tie from opening Answer: B ILT EXAM Page: 6 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 4 Details Question Type: Multiple Choice Topic: 04 - 295019.K3.02 System ID: 24148 User ID: 24148 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 278LN001.12

Reference:

DOA 4700-01, LP DRE239LN001 K/A: 295019.AK3.02 3.5 / 3.4 K/A: Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR : Standby air compressor operation CFR: 41.5 Safety Function: 8 PRA: No Level: Memory Pedigree: Bank History:

Comments: High order due to having to determine the impact of loss of instrument air on the systems with U2 air not available and the flowpath for the use of U3 Instrument air.

a) Incorrect - The FRVs lock up on a loss of air pressure.

b) Correct - A reactor scram and manually closing the MSIVs is required on a loss of instrument air due to the potential of the MSIVs drifting closed.

c) Incorrect - The target rock would be inop in ERV mode with a loss of Drywell Pneumatics.

d) Incorrect - The Unit 2 IA to Unit 2 Service Air cross-tie would already be open (85 psig).

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 7 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 5 ID: 24153 Points: 1.00 Why is HPCI secured when the Torus level drops below 12 feet?

A. To prevent exceeding ECCS Vortex limit.

B. To prevent the suction from swapping to the Torus.

C. To prevent the HPCI exhaust line from being uncovered.

D. To conserve Torus water inventory for an ADS blowdown.

Answer: C Question 5 Details Question Type: Multiple Choice Topic: 05 - 295030.K2.01 System ID: 24153 User ID: 24153 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 2 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 29502LK01

Reference:

EPG B-7-51, TSG - 2, PSTG T/L-2.1 K/A: 295030.K2.01 3.8/3.9 K/A: Knowledge of the interrelations between LOW SUPPRESSION POOL WATER LEVEL and the following: HPCI: Plant-Specific.

CFR: 41.7 PRA: Yes Level: Memory Pedigree: Bank History: 2011 Cert Comments: DEOP 200-1 requires HPCI to be secured if you cannot hold torus level above 12 feet so that the HPCI exhaust remains underwater and does not exhaust steam to the Torus air space. ECCS Vortex limit is 10'4 inches for the conditions stated in the question.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 8 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 6 Points: 1.00 Which of the following describes the HIGHEST RPV pressure where the Low Pressure Coolant Injection (LPCI) system INJECTION flow is expected, following an auto initiation signal?

A. 300 psig B. 330 psig C. 360 psig D. 390 psig Answer: B Question 6 Details Question Type: Multiple Choice Topic: 06 - 295007.K2.03 System ID: 24154 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE206LN001.06

Reference:

DAN 902-3 A-4, DAN 902-3 H-16 K/A: 295007.K2.03 3.1 / 3.2 K/A: High Reactor Pressure: Knowledge of the interrelations between HIGH REACTOR PRESSURE and the following: RHR/LPCI Level: Memory Pedigree: Bank History: Clinton 2001 NRC, 2008 NRC Comments: LPCI and Core Spray systems will start upon an initiation signal, but the injection valves will not open until RPV pressure drops to <312.4 psig to 332.4psig. This makes 330 psig the highest pressure that injection will occur.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 9 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 7 ID: 24246 Points: 1.00 Unit 3 was operating at near rated power, with TIP traces being performed. The TIP is in the process of being driven to the full in-core position, in MANUAL.

Then the following occurs:

• A small leak develops inside the Drywell.

• Drywell pressure is 1.45 psig and steady.

Drywell Rad Monitors read as follows:

• 3-2419A: 15 R/hr

• 3-2419B: 15 R/hr Without Operator action, what is the expected response of the TIP system?

A. Detector will CONTINUE to CORE TOP position, then stop.

B. Detector will CONTINUE to CORE TOP position, then REVERSE direction and the ball valve remains open.

C. Detector will immediately REVERSE direction and ball valve will close when the detector is "in-shield".

D. Detector will CONTINUE to CORE TOP position, then REVERSE direction and the ball valve will close when the detector is "in-shield".

Answer: A ILT EXAM Page: 10 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 7 Details Question Type: Multiple Choice Topic: 07 - 295010.A2.03 System ID: 24246 User ID: 24246 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE223LN005.02

Reference:

DAN 902-5 E-5, DOP 0700-06 K/A: 295010.A2.03 3.3 / 3.6 K/A: Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE: Drywell radiation levels.

Level: Memory Pedigree: Bank History: 2006 NRC Explanation: While the Drywell pressure is an abnormal level (1.5 psig), it is not to the level to cause a Group II isolation (1.8 psig). TIPS will only withdraw to in-shield position, if a Group II was received (not received by Drywell pressure). Ball valves will close only if a Group II was received. The TIPS will not reverse direction given the conditions in the stem.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 11 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 8 ID: 24157 Points: 1.00 Unit 2 was operating at near rated power when a LOOP occurred, resulting in the following set of conditions:

• HPCI failed to inject.

• 2/3 EDG failed to start.

• Three (3) ADS valves are open.

• 2B Core Spray pump failed to start.

• RPV pressure is 275 psig and lowering.

• RPV water level is -110 inches and rising.

Core cooling is . . . . .

A. assured due to the core being submerged.

B. assured due to the steam cooling effects of the open SRVs.

C. NOT assured due to ONLY 3 ADS valves open.

D. NOT assured due to only two LPCI pumps injecting.

Answer: A ILT EXAM Page: 12 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 8 Details Question Type: Multiple Choice Topic: 08 - 203000.K5.02 System ID: 24157 User ID: 24157 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 3 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 299LN049-2

Reference:

TSG Attach L, DEOP 0010-00 K/A: 203000.K5.02 3.5 / 3.7 K/A: Knowledge of the operational implications of the following concepts as they apply to RHR/LPCI:

INJECTION MODE: Core cooling methods.

Level: High Pedigree: Bank History: 2009 Cert Explanation: With a LOOP, the Unit scrams. With the loss of HPCI, Bus 23-1 (2/3 EDG failure), and 2B Core Spray pump, the only possible injection source is C and D LPCI pumps. With RPV pressure <340, the LPCI pumps are allowed to inject. This injection is sufficient to provide core submergence. Top of active fuel is not reached until -143 inches (with RPV pressure less than 500 psig). Steam cooling would not come into effect unless RPV level was less than

-164 inches (with RPV pressure less than 500 psig).

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 13 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 9 Points: 1.00 Unit 2 was operating at near rated power and the Operating team is preparing to perform DOS 2300-03, HIGH PRESSURE COOLANT INJECTION SYSTEM OPERABILITY AND QUARTERLY IST VERIFICATION TEST.

Which of the following can be expected during the surveillance?

A Torus water . . . . .

A. level rise of 5 to 10 inches.

B. level drop of 5 to 10 inches.

C. temperature rise of 5 to 10°F.

D. temperature rise of 15 to 20°F.

Answer: C ILT EXAM Page: 14 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 9 Details Question Type: Multiple Choice Topic: 09 - 206000.A1.05 System ID: 24158 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE206LN001.02

Reference:

DOS 2300-03 K/A: 206000.A1.05 4.1 / 4.2 K/A: Ability to predict and/or monitor changes in parameters associated with operating the HIGH PRESSURE COOLANT INJECTION SYSTEM controls including: Suppression pool temperature.

Level: Memory Pedigree: Bank History: 2009 Cert Explanation: The answer can be found in the limitations and actions of the above procedure. When HPCI is run for a surveillance, its suction is from the Torus (not CSTs) and its discharge is to the Torus. HPCI does cause a small temperature increase (5 to 10 degrees),

but since the suction and discharge is the same, there is no significant change in Torus level.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 15 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 10 Points: 1.00 Unit 2 was operating at near rated power when an RPV water level transient occurred.

HPCI auto started and is being utilized for RPV water level control.

Several minutes later, annunciator 902-3 A-12, HPCI COND STG TK LVL LO LO alarmed.

What is the expected response of the HPCI system and what actions must the Operating team take to mitigate the consequences of the event?

A. The CST suction valve closes; Swap U2 HPCI suction to U3 Torus.

B. The U2 HPCI system loses suction but does NOT trip; Manually trip the U2 HPCI turbine.

C. Both U2 Torus suction valves open, THEN the CST suction valve closes; Place Makeup Demineralizer in service to raise CST water level, if available.

D. The CST suction valve remains open and both U2 Torus suction valves open; Place Makeup Demineralizer in service to raise CST water level, if available.

Answer: C ILT EXAM Page: 16 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 10 Details Question Type: Multiple Choice Topic: 10 - 206000.A2.09 System ID: 24159 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE206LN001.06

Reference:

DAN 902-3 A-12, A-11 K/A: 206000.A2.09 3.5 / 3.7 K/A: Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low condensate storage tank level:

BWR-2,3,4.

Level: Memory Pedigree: Bank History: 2009 NRC Explanation: With HPCI injecting, when the CST level low alarm comes in, the U2 Torus suction valves fully open THEN the CST suction valve closes (to maintain a suction path). Then the Operating team is directed by the procedure to refill the CSTs with the Makeup Demins, if available. With an auto start of the HPCI system the low suction pressure trip is bypassed as well as the 2301-8 will not close.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 17 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 11 ID: 24194 Points: 1.00 Given the following:

• A scram has occurred on U3.

• Rx level is +15 inches and dropping at 2 inches per minute.

• DW Pressure is 1.7 psig and rising 0.1 psig per minute.

Which DEOP 100 Entry condition will be reached FIRST, and which system will have automatic initiations/isolations when that entry condition is met?

ENTRY CONDITION SYSTEM AUTO ACTUATIONS AND/OR ISOLATIONS A. Rx Level SDC, RWCU B. Rx Level HPCI, RWCU C. DW Pressure HPCI, EDG's, RWCU D. DW Pressure HPCI, DW pneumatics, EDG's Answer: D ILT EXAM Page: 18 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 11 Details Question Type: Multiple Choice Topic: 11 - 295006.G4.02 System ID: 24194 User ID: 24194 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE209LN001.06

Reference:

DEOP 100, DAN 902(3)-5 D-11 K/A: 295006.G.4.02 SCRAM: Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions CFR:

Safety Function: 1 PRA: N/A Level: High Pedigree: New History: N/A Comments:

a) Is incorrect due to Rx level reaching the DEOP entry at 3.5 minutes b) Is incorrect due to Rx level reaching the DEOP entry at 3.5 minutes as well as HPCI does not initiate until

-59 inches c) Is incorrect due to RWCU's isolate on a group 3 for level but not on a 2 # signal d) Correct due to drywell pressure reaching 2# in 3 minutes causing HPCI to initiate, EDG's to start, and a GR II isolation causing loss of DW pneumatics REQUIRED

REFERENCES:

None.

ILT EXAM Page: 19 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 12 ID: 24203 Points: 1.00 Unit 2 was operating at 30% when a spurious turbine trip occurred.

Which of the following best describes the plant reactor pressure response with respect to this transient three minutes after the turbine tripped?

A. RPV pressure goes up and stabilizes at a higher than initial value B. RPV pressure goes down and stabilizes at a lower than initial value C. RPV pressure initially goes up then stabilizes at a lower than initial value.

D. RPV pressure initially goes down and stabilizes at a higher than initial value.

Answer: A ILT EXAM Page: 20 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 12 Details Question Type: Multiple Choice Topic: 12 - 295005 A02.04 System ID: 24203 User ID: 24203 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 245LN001.06.B

Reference:

UFSAR Figure 7.7-4a, DGP 2-3 K/A: 295005 A2.04 3.7/3.8 K/A: Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP:

Reactor Pressure CFR: 41.10 Safety Function: 3 PRA: No Level: High Pedigree: New History:

Comments: Pressure and power will initially go up due to loss of FW heating loss. After the plant stabilizes the pressure will be at a higher new value due to the positive bias and high value gate in the EHC logic.

A) Correct- RPV pressure will initially go up and then stabilize at a slightly higher value due to bypass valves being biased. This will cause the bypass valves to allow less steam flow from the RPV to the main condenser, therefore RPV pressure will be maintained slightly higher than the pre transient value.

B) Incorrect - RPV pressure will not go down initially.

Bypass valves will maintain RPV pressure slightly higher than the initial value.

C) Incorrect - RPV pressure will initially go up and then stabilize at a slightly higher value due to bypass valves being biased. This will cause the bypass valves to allow less steam flow from the RPV to the main condenser, therefore RPV pressure will be maintained slightly higher than the pre transient value.

D) Incorrect - RPV pressure initially go up with turbine stop and control valve closure. RPV pressure will not lower below the initial pre transient value during the time period specified.

ILT EXAM Page: 21 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 13 ID: 24265 Points: 1.00 The following alarms are received on the XL3 fire computer.

• 71-24 MAIN TRANSFORMER T3 SYSTEM FIRE

• 71-27 U-3 TRANSFORMERS DELUGE TROUBLE Upon arriving at the scene you would expect to find:

A. the local area temperature recorder reading 175 degrees ONLY.

B. a local high temperature alarm sounding on fire panel 2253-45 ONLY.

C. transformer 3 deluge system activated without a local alarm sounding on fire panel 2253-45.

D. transformer 3 deluge system activated, and local alarms sounding from system actuation and high temperature on fire panel 2253-45.

Answer: D Question 13 Details Question Type: Multiple Choice Topic: 13 -600000.G.1.19 System ID: 24266 User ID: 24265 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 286LN003.11

References:

DAN XL3 71-24 and 71-27 K/A: 600000.G.2.1.19 3.9/3.8 K/A: Plant Fire On Site: Ability to use plant computers to evaluate system or component status.

Level: High Pedigree: Bank History: N/A Comments: With both alarms in, a deluge condition on TR3 has occurred and not just a trouble alarm.

Therefor the actions of DAN SL-3, 71-24 are required to be verified: transformer 3 deluge system activated and local alarms sounding from system actuation and high temperature on fire panel 2253-45.

ILT EXAM Page: 22 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 14 ID: 24204 Points: 1.00 Unit 2 is operating at rated power when a transient occurred resulting in the following conditions:

? Drywell pressure is 6 psig

? All MSIVs are closed

? All rods are in

? RPV pressure is 600 psig and steady

? RPV level is trending down When is the EARLIEST an Emergency Depressurization can be performed and why?

A. When RPV level reaches -143" to maintain PCT < 1500F B. When RPV level reaches -170" to maintain PCT < 1500F C. When RPV level reaches -185" to maintain PCT < 1800F D. When RPV level reaches -204" to maintain PCT < 1800F Answer: B ILT EXAM Page: 23 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 14 Details Question Type: Multiple Choice Topic: 14 - 295031 K03.05 System ID: 24204 User ID: 24204 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 29501LK028

Reference:

EPG Appendix B Chapter 10, EPG Appendix B Chapter 17 K/A: 295031 K03.05 4.2/4.3 K/A: Knowledge of the reasons for the following responses as they apply to REACTOR LOW WATER LEVEL: Emergency Depressurization CFR: 41.5 Safety Function: 2 PRA: No Level: High Pedigree: New History:

Comments: While the bases for the blowdown is expected to be from memory, the candidate must work through the DEOP charts to determine when the blowdown is required.

A) Incorrect - With RPV pressure > 500 psig, TAF is

-170". ED due to RPV level prior to reaching TAF is not permitted by procedure B) Correct. With RPV pressure > 500 psig, TAF is

-170". Per EPGs, an ED may be performed when RPV level reaches TAF and MUST be performed prior to reaching MSCRWL (-164")

C) Incorrect - With injection sources available, Steam Cooling without injection is not permitted, therefore PCT limit of 1800F is not correct. Also, -185" is Minimum Zero Injection RPV Water Level when RPV Pressure is < 500 Psig D) Incorrect - With injection sources available, Steam Cooling without injection is not permitted, therefore PCT limit of 1800F is not correct. If Steam Cooling without injection were employed, the correct level to perform an ED would be -204".

ILT EXAM Page: 24 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 15 Points: 1.00 DOA 3300-02, Loss of Condenser Vacuum, actions are in progress due to lowering vacuum on Unit 2.

The Unit 2 NSO reports offgas system flow is HI.

Based on the offgas flow, what actions are directed by DOA 3300-02?

A. Bypass the filter building.

B. Secure hydrogen addition.

C. Swap cooler condenser trains.

D. Start all available condensate pumps.

Answer: A ILT EXAM Page: 25 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 15 Details Question Type: Multiple Choice Topic: 15 - 295002 A01.02 System ID: 24202 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 271LN001.11

Reference:

DOA 3300-02 K/A: 295002 A01.02 2.9/2.9 K/A: Ability to operate and/or monitor the following as they apply to LOSS OF MAIN CONDENSER VACUUM: Offgas System CFR: 41.7 Safety Function: 3 PRA: No Level: Memory Pedigree: New Comments:

A) Correct - Per DOA 3300-02, if offgas flow is HIGH, bypass the filter building.

B) Incorrect - Per DOA 3300-02 securing H2 addition would cause flow to increase flow by 20 scfm.

C) Incorrect - Condensate is the cooling for the Off Gas condenser but starting additional pumps would not help loss of vacuum.

D) Incorrect - DOA 3300-02 does not provide guidance for swap of cooler condenser trains.

ILT EXAM Page: 26 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 16 ID: 23505 Points: 1.00 The SPDS screen RADIATION RELEASE box will be _______ if the Liquid effluent radiation output signal is/are above the action setpoint.

A. RED B. BLUE C. CYAN D. YELLOW Answer: A Question 16 Details Question Type: Multiple Choice Topic: 16 - 295038.A.2.03 System ID: 23505 User ID: 23505 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 283LN002.03

Reference:

DOP 9950-17 K/A: 295038.A 2.03 3.5 / 4.3 K/A: High Off-Site Release Rate: Ability to determine and/or interpret the following as they apply to High Off-site Release Rate: Radiation levels.

Level: Memory Pedigree: Bank History: 2013 Cert Explanation: RED: SPDS parameter in Alarm condition.

BLUE: There are NOT a sufficient number of required instrumentation channels operable for monitoring a given SPDS parameter.

CYAN: SPDS parameter is invalid parameter.

YELLOW: Pre alarms (low and high).

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 27 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 17 ID: 331982 Points: 1.00 Which of the following statements describes how EDG will respond to a start signal if the Upper air start motor does NOT engage?

A. With only one of the two air start motors turning the engine, there is insufficient speed to start the engine.

B. Air will NOT be ported to the Air Start Relay valve to open the valve and allow the main air supply to drive the starting motors.

C. Without the Upper air start motor engaged, a vent path to atmosphere is NOT provided and the Lower air start motor will lock-up pneumatically.

D. The diesel generator will start normally. Two air start motors are provided for redundancy, but only one motor is needed to allow starting the engine.

Answer: B ILT EXAM Page: 28 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 17 Details Question Type: Multiple Choice Topic: 17 - 264000 K1.06 System ID: 24198 User ID: 331982 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Topic: 264000 K1.06 Objective: DRE264LN00.02

Reference:

DOS 6600-01 K/A: 264000 K1.06 3.2/3.2 K/A: EDGs: Knowledge of the physical connections and/or cause-effect relationships between EDGs and the following: Starting system.

CFR: 41.2 to 41.9 Safety Function: 6 PRA: Yes Level: Memory Pedigree: Bank History:

Comments:

When the D/G is started, the air start solenoid is powered, allowing air from the air receivers to pass through the solenoid valve to the pinion gear end of the lower start motor. This causes the pinion gear to move forward and engage the ring gear.

Movement of the pinion gear uncovers a port that allows air passage to the upper motor, engaging its pinion gear. Only when both pinion gears are engaged does air reach the air start relay valve that then opens the main air supply to drive each of the starting motors.

If the main air supply does NOT reach the air start motors in two seconds as sensed by the multiple start pressure switch, the air start solenoid will re-power to start the sequence again. This multiple start sequence will continue until the D/G reaches 200 RPM.

ILT EXAM Page: 29 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 18 ID: 323660 Points: 1.00 While performing the weekly battery checks of the Unit 2 250 Vdc safety related battery, which of the following values is an acceptable voltage if the battery charger is operation in the FLOAT mode?

A. 260.0 Vdc B. 262.0 Vdc C. 264.0 Vdc D. 266.0 Vdc Answer: C ILT EXAM Page: 30 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 18 Details Question Type: Multiple Choice Topic: 18 - 263000 G2.12 System ID: 24197 User ID: 323660 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Topic: 263000 G.2.12 Objective: 263LN001.14

Reference:

DOS 8300-07 K/A: 263000 G.2.12 3.7/4.1 K/A: DC Electrical Distribution; Knowledge of surveillance procedures.

CFR 41.10 Safety Function: 6 PRA: Yes Level: Memory Pedigree: Bank History: LGS NRC-05 Comments:

Per DOS 8300-07, Float voltage should be adjusted to within the range of 262.8 to 265.2 VDC.

a) incorrect below the lower limit of 262.8 VDC b) incorrect below the lower limit of 262.8 VDC c) correct above the lower limit of 262.8 VDC and below the upper limit of 265.2 VDC d) incorrect above the upper limit of 265.2 VDC ILT EXAM Page: 31 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 19 ID: 24258 Points: 1.00 Unit 2 and Unit 3 are operating at near rated power when Transmission Systems Operations (TSO) notifies the Control Room that the predicted post Unit trip with LOCA switchyard voltages are:

• Unit 2: 325 KV

• Unit 3: 350 KV What are the required actions from the Operating team AND the reason for these actions?

A. Adjust TR 32 Tap Changer; to restore system operability B. Adjust TR 32 Tap Changer; to reduce circulating currents C. Adjust TR 86 Tap Changer; to restore system operability D. Adjust TR 86 Tap Changer; to reduce circulating currents Answer: C ILT EXAM Page: 32 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 19 Details Question Type: Multiple Choice Topic: 19 - 700000.K1.03 System ID: 24258 User ID: 24258 Status: Active Always select on test: No Authorized for practice: No Difficulty: 0.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE262LN003.12

Reference:

DOA 6500-12 K/A: 700000.K1.03 3.3 / 3.4 K/A: Knowledge of the reasons for the following responses as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Actions contained in abnormal operating procedure for voltage and grid disturbances.

CFR: 41.10 Safety Function: 7 PRA: Yes Level: High Pedigree: Bank History: ILT 11-1 NRC Explanation: Given the voltages, only Unit 2 is below the procedural setpoint. TR-32 would be adjusted for Unit 3; TR-86 would be adjusted for Unit 2. The actions are to adjust the TR-86 Tap Changer (to position 31) to raise VOLTS (not VARs) to restore system operability.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 33 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 20 Points: 1.00 Which of the following sets of parameters are within the capacity of the Torus to accept a Blowdown?

Torus water level of ___(1)___ ft RPV pressure of ___(2)___ psig Torus bulk temperature of ___(3)___ oF A. (1) 16.5; (2) 500; (3) 180 B. (1) 16.5; (2) 600; (3) 175 C. (1) 17.5; (2) 350; (3) 170 D. (1) 17.5; (2) 400; (3) 150 Answer: D ILT EXAM Page: 34 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 20 Details Question Type: Multiple Choice Topic: 20 - 295026.G1.25 System ID: 24200 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE223LN001.12

Reference:

DEOP 200-01, TSG K/A: 295026.G1.25 3.9 / 4.2 K/A: SUPPRESSION POOL HIGH WATER TEMPERATURE: Ability to interpret reference materials, such as graphs, curves, tables, etc.

Level: High Pedigree: Bank History: 2010 NRC Explanation: The only above set of parameters that are NOT outside the capacity of the Torus to accept a Blowdown are a Torus Water level of 17.5 ft, with an RPV pressure of 400 psig and a Torus bulk temperature of 150oF. The Examinee will have to utilize both the Heat Capacity Limit curves to decide which set of parameters do NOT violate the curves.

REQUIRED

REFERENCES:

DEOP 200-1 figure M (Heat Capacity Limit) and TSG attachment G (Optimized Limit Curve).

ILT EXAM Page: 35 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 21 ID: 24196 Points: 1.00 U2 is operating at 90% Reactor Power when an inadvertant Group I occurs.

10 seconds later Rx water level will have_____ due to ______.

A. risen Iso Condenser initiation B. risen MSIV closure preventing inventory loss C. dropped ERV open actuation D. dropped Inventory shrink after the SCRAM Answer: D ILT EXAM Page: 36 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 21 Details Question Type: Multiple Choice Topic: 21 - 295020 K3.05 System ID: 24196 User ID: 24196 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 223LN005.12A

Reference:

UFSAR figure 15.2-2, UFSAR table 15.0-2 K/A: 295020 K3.05 K/A: Knowledge of the reasons for the following responses as they apply to Inadvertant Cont. Isolation:

Reactor water level response.

CFR: 41.5 Safety Function: 5 & 7 PRA: No Level: High Pedigree: New History:

Comments: Higher order due to having to evaluate system interrelationships and actuation time limits and the overall impact on reactor water level over time.

a) incorrect Iso condenser will not have initiated in the first 10 seconds b) incorrect MSIV will stop the loss of inventory, but level will still decrease due to shrinkage voids collapsing.

c) incorrect ERVs will not open with all rods in, with a group 1 at this power.

d) correct level will decrease due to shrink, and voids will collapse due to pressure spike.

ILT EXAM Page: 37 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 22 ID: 13188 Points: 1.00 Unit 3 was operating at 400 MWe, with the 3A CRD pump out of service for an oil change, when the following events occurred:

• Time 02:15:00 - Bus 34 experienced an overcurrent fault.

• Time 02:19:00 - CRD F-06 ACCUMULATOR TROUBLE light illuminated and is verified at position 28.

• Time 02:20:00 - CRD N-09 ACCUMULATOR TROUBLE light illuminated and is verified at position 32.

• Time 02:23:00 - EO reported CRD F-06 accumulator pressure was 900 psig.

• Time 02:24:00 - EO reported CRD N-09 accumulator pressure was 880 psig.

If the above conditions do NOT change, at time 02:45:00, what action(s) is/are required?

A. Place the Reactor Mode switch in SHUTDOWN and enter DGP 02-03.

B. Restore charging water header pressure to 940 psig by time 03:20:00.

C. Insert BOTH Control Rod F-06 AND N-09 with the Scram toggle switches.

D. Insert EITHER Control Rod F-06 OR N-09 with the Scram toggle switches.

Answer: A ILT EXAM Page: 38 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 22 Details Question Type: Multiple Choice Topic: 22 - 295022.K1.01 System ID: 24260 User ID: 13188 Status: Active Always select on test: No Authorized for practice: No Difficulty: 0.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE201LN001.12

Reference:

DOA 0300-01 K/A: 295022.K1.01 3.3 / 3.4 K/A: Knowledge of the operational implications of the following concepts as they apply to LOSS OF CRD PUMPS: Reactor pressure vs. rod insertion capability.

Level: High Pedigree: Bank History: 2008 NRC Comments: The candidate must understand with the reactor in mode 1 (indicated by full power) and a loss of all charging water pressure being lost for 20 minutes (indicated by 3A CRD pump out of service and 3B being lost when Bus 34 de-energizes) and a two or more CRD trouble alarms for low pressure, for CRDs not at position 00, the correct action is to place the mode switch in SHUTDOWN and enter DGP 02-03.

Restoring charging water pressure is not the action to take since the 20 minute procedural time has already expired.

Inserting any CRD with the scram toggle switch is not the appropriate action, since the reactor is NOT in mode 3, 4, or 5.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 39 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 23 ID: 24206 Points: 1.00 Unit 2 was operating at rated power when the following occurred:

? A SCRAM signal was received

? ALL rods did NOT fully insert

? ARI was initiated and was unsuccessful

? All APRMs indicate downscale

? Torus Temperature is 112F

? Drywell Pressure is 2.7 psig

? RPV level is being controlled at -40 inches If power was rising, when would the control room operators FIRST be required to TERMINATE and PREVENT INJECTION?

A. IRM reading 110 on range 8.

B. IRM reading 20 on range 9 C. IRM reading 60 on range 10 D. IRM reading 100 on range 10.

Answer: B ILT EXAM Page: 40 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 23 Details Question Type: Multiple Choice Topic: 23 - 295037 A1.06 System ID: 24206 User ID: 24206 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE215LN003.03

Reference:

As described in LP, DGP 1-1 K/A: 295037 A1.06 4.1/4.1 K/A: Ability to operate and/or monitor the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: Neutron monitoring system CFR: 41.7 Safety Function: 1 PRA:Yes Level: High Pedigree: New History:

Comments:

The operator must first determine the conditions necessary for a terminate and prevent order. Given in the stem all conditions with the exception of reactor power are given necessary to invoke the second override in the level control leg of DEOP 400-5. When Reactor power exceeds APRM downscale (6%,

177MWth), the requirements to terminate and prevent injection are met.

A) Incorrect - 110/125 on Range 8 equates to 110 MWth. APRM downscale is 177MWth B) Correct - 20/40 on Range 9 equates to 200 MWth.

APRM downscale is 177MWth C) Incorrect - 60/125 on Range 10 is 600MWth.

APRM downscale is 177MWth.

D) Incorrect - 100/125 on Range 10 is 1000MWth.

APRM downscale is 177MWth.

ILT EXAM Page: 41 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 24 ID: 24205 Points: 1.00 A steam leak has developed in the Unit 3 X-Area.

Which combination of temperature and trip channels will FIRST result in a PCIS actuation?

A. 180F sensed on channel A OR B B. 190F sensed on channel A OR B C. 210F sensed on channels A AND B D. 212F sensed on channels A AND B Answer: C ILT EXAM Page: 42 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 24 Details Question Type: Multiple Choice Topic: 24 - 295032 K01.03 System ID: 24205 User ID: 24205 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 223LN005.02 Ref: DAN 920(3)-5 D-9 K/A: 295032 K01.03 3.5/3.9 K/A: Knowledge of the operation implication of the following concepts as they apply to High Secondary Containment Area Temperature: Secondary Containment Leakage Detection CFR: 41.8 Safety Function: 5 PRA: No Level: Recall Pedigree: New History:

Comments: All distracters are plausible due to High Energy Line Break for the RWCU area and X-Area are actuated with a single channel high.

A) Incorrect - 180F is within the setpoint band for channel actuation, BOTH channels are required for PCIS actuation B) Incorrect - 190F is above the setpoint band for channel actuation however, BOTH channel are required for PCIS actuation C) Correct - Temperature is above setpoint and both channels will actuate resulting in a PCIS actuation D) Incorrect - Although conditions to actuate PCIS GRP I are met, this will occur after 210F therefore this answer is not the FIRST to occur.

ILT EXAM Page: 43 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 25 ID: 24201 Points: 1.00 Given the following conditions:

? Unit 2 startup in progress

? Rx Pressure is 950 psig

? Core flow is 30%

? Both recirc loops in operation A feedwater transient occurs on Unit 2.

Which one of the following violates a reactor core Safety Limit under these conditions?

A. MCPR at 1.08 B. Rx power rises to 30%

C. RPV level drops to -130 inches D. Steam dome pressure rises to 1300 psig Answer: A ILT EXAM Page: 44 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 25 Details Question Type: Multiple Choice Topic: 25 - 295014 G2.38 System ID: 24201 User ID: 24201 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 299LN001.03

Reference:

TS 2.0 K/A: 295014 G2.38 K/A: Inadvertent Reactivity Addition: Knowledge of conditions and limitations in the facility license.

Level: Memory Pedigree: New History:

Explanation: Per TS 2.1.1.2, MCPR is required to be

> 1.12 for 2 loop operation. The safety limit for level is TAF. Power must be < 25% if pressure is < 785 psig and core flow is > 10% rated core flow. Pressure safety limit is 1345 psig.

ILT EXAM Page: 45 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 26 Points: 1.00 Unit 2 was operating in MODE 3, with the following set of conditions:

• SDC in operation, with the 2B pump and heat exchanger in service.

• RBCCW in operation, with the 2B AND 2/3 pumps and heat exchangers in service.

The following annunciators are then received:

• Time 05:15:00; 902-4 A-23, SDC HX/FUEL POOL WTR TEMP HI.

• Time 05:25:00; 902-4 B-23, SDC PP TRIP.

Which of the following actions could have caused the SDC Pump to trip?

A. Loss of U2 250 VDC.

B. Bus 23-1 undervoltage.

C. Trip of the 2B RBCCW pump.

D. The 2B SDC pump discharge AOV drifting closed.

Answer: C ILT EXAM Page: 46 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 26 Details Question Type: Multiple Choice Topic: 26 - 295021.K2.04 System ID: 24149 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 3 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE205LN001.06

Reference:

DAN 902-4 B-23 K/A: 295021.K2.04 3.0 / 3.1 K/A: Knowledge of the interrelations between LOSS OF SHUTDOWN COOLING and the following: Component cooling water systems: Plant-Specific.

Level: High Pedigree: Bank History: 2008 NRC Comments: With the conditions given, only a trip of the 2B RBCCW pump would cause the SDC pump to trip.

This occurs because after the RBCCW pump trips, the SDC temperatures start to rise (as indicated by both annunciators). When the SDC temperature reaches 339oF at the suction of the pumps, this causes the SDC pump to trip. Loss of U2 250 VDC would not effect the system flows. U2 SDC cooling valves are fed from U3 250 VDC and would fail as is. Closing of the 2B SDC pump discharge valve is incorrect as it would cause SDC pump suction pressure to increase (which is the opposite of the SDC pump trip on LOW suction pressure). Bus 23-1 undervoltage is incorrect as the pumps listed as operating in the initial conditions are powered from Bus 24-1 (common misconception of power supplies since both the SDC and RBCCW systems have 3 pumps - with opposite power supplies from each other).

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 47 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 27 ID: 295023.K1.03 Points: 1.00 Unit 3 is in Mode 5 with fuel moves in progress. SRM counts begin to steadily go up and continue to go up over a 5 minute period in the quadrant containing the fuel moves.

How are fuel moves affected?

A. Stop ALL fuel moves. The grapple may be lowered, but NOT raised.

B. Stop ALL fuel moves. The grapple may be raised, but NOT lowered.

C. Stop ALL fuel moves. Do NOT attempt to raise or lower the grapple.

D. Fuel moves may continue. SRM response is normal for these conditions.

Answer: C ILT EXAM Page: 48 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 27 Details Question Type: Multiple Choice Topic: 27 - 295023.K1.03 System ID: 24256 User ID: 295023.K1.03 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE272LN002.06

Reference:

DOA 0800-03, DFP 800-1 K/A: 295023K1.03 3.7/4.0 K/A: Knowledge of the operational implications of the following concepts as they apply to REFUELING ACCIDENTS: Inadvertant criticality CFR: 41.8 to 41.10 PRA: Yes Level: High Pedigree: New History: None.

Explanation:

Per DOA 0800-03, conditions in the stem should be interpreted as inadvertant criticality. Immediate actions of DOA 0800-03 require operators to suspend fuel moves and NEITHER raise nor lower the grapple.

This question meets the high cognitive level criteria because it requires the candidate to determine inadvertant criticality has occurred and then determine the correct operational implications.

ILT EXAM Page: 49 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 28 ID: 295025.A2.04 Points: 1.00 A transient occurred on Unit 2 resulting in the following conditions:

Unit 2 125vDC Bus 2B-1 is tripped and will NOT reclose Reactor Pressure is 1050 psig and trending up The Unit Supervisor has directed you verify Torus level is within band for ERV operations.

How is Torus Level determined?

A. Wide Range Torus Level indication on 902-3 panel ONLY.

B. Narrow Range Torus Level indication on 902-3 panel ONLY.

C. BOTH Narrow and Wide Range Torus Level control room panel indications are available.

D. ALL control room panel indications for Torus Level are lost; an operator must be dispatched to verify Torus Level using the local sightglass.

Answer: A ILT EXAM Page: 50 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 28 Details Question Type: Multiple Choice Topic: 28 - 295025.A2.04 System ID: 24252 User ID: 295025.A2.04 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: 29501LK100 K/A: 295025.A2.04 3.9/3.9 K/A: Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE:

Suppression Pool Level

Reference:

DOP 6800-05, 12E-6822 Level: High PRA: No Pedigree: New History: None.

Comments:

This question examines the candidate's knowledge of the suppression pool capability to accept discharge from the ERVs as well as the control room indications available on a loss of power. 125vDC Bus 2B-1 feeds the DC portion of ATS Panel 2202-73B. Upon a loss of 125vDC Bus 2B-1, the narrow range torus level indication as well as HI and LO level annunciators are lost. Wide Range Torus level indications are still available on the 902-3 panel. Use of the local sight glass is an option, however, this distracter is not correct because control room indications of Torus Level are still available. Computer points for NR torus level are lost due to the DC power failure as well.

ILT EXAM Page: 51 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 29 Points: 1.00 Unit 2 was operating at near rated power, when a LOCA occurred. The following conditions exist:

• RPV pressure is 200 psig and lowering slowly.

• Indicated Wide Range RPV water level is 80 inches and rising slowly.

• Drywell pressure is 5.5 psig and rising slowly.

• Drywell temperature is 300oF and steady.

Wide Range RPV water level instrumentation is . . . . .

A. accurate and can be used for trending.

B. NOT accurate and CAN be used for trending, since WR level is above indicated usable level.

C. NOT accurate and CANNOT be used for trending, since WR level is below indicated usable level.

D. NOT accurate and CANNOT be used for trending since D/W temperature is above saturation temperature.

Answer: A ILT EXAM Page: 52 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 29 Details Question Type: Multiple Choice Topic: 29 - 295028.K1.01 System ID: 24152 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE216LN001.12

Reference:

DEOP 100 table 'A', EPG B-5-3 K/A: 295028.K1.01 3.5 / 3.7 K/A: Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL TEMPERATURE: Reactor water level measurement.

Level: High Pedigree: Bank History: 2009 Cert Comments: Utilizing DEOP 100 chart B, the parameters are below the line, so the instruments would be accurate in this situation, AND the instrument could be used to determine the level trend. Changes in instrument run temperatures can produce on-scale readings on some instruments even when the actual level is below their variable leg taps. Since DP is not affected by level changes below the variable leg tap, the indicated level would then no longer reflect changes in actual level (could not be used for trending).

REQUIRED

REFERENCES:

DEOP charts, with the entry conditions blanked out.

ILT EXAM Page: 53 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 30 ID: 24160 Points: 1.00 Unit 2 was operating at near rated power, when a LOCA occurred, resulting in the following set of conditions:

• Torus temperature is 109°F and steady.

• Drywell pressure is 10 psig and lowering slowly.

• Torus level is 15 ft.

• Off site power is available and grid voltage is stable.

• Core Spray flow is fluctuating between 2000 gpm to 4000 gpm.

• Core Spray discharge pressure is fluctuating between 150 psig and 325 psig.

What is the cause of the Core Spray indications?

A. Vortexing due to high ECCS flow.

B. ECCS suction strainers are plugging.

C. A loss of NPSH caused by Torus temperature.

D. Leak in the piping downstream of the PP DISCH VLV MO 2-1402-25A.

Answer: B ILT EXAM Page: 54 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 30 Details Question Type: Multiple Choice Topic: 30 - 209001.K5.01 System ID: 24160 User ID: 24160 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 4 Point Value: 1.00 Cross Reference Number:

Num Field 1: 0.00 Num Field 2: 0.00 Text Field:

Comments: Objective: DRE209LN001.08

Reference:

NRC Bulletin 93-02 K/A: 209001.K5.01 2.6 / 2.7 K/A: Knowledge of the operational implications of the following concepts as they apply to LOW PRESSURE CORE SPRAY SYSTEM: Indications of pump cavitation.

Level: High Pedigree: Bank History: 2007 NRC, 2011 Cert Explanation:

A) Torus parameters are within the operating curves to prevent vortexing from occurring B) With the fluctuations in pump flow and discharge pressure, it is an indication that the suction strainers are the failure mode.

C) Torus temperature is well within the band of ECCS operating curves at this Drywell pressure.

D) A leak downstream of the disch valve would cause an increase in flow and amps without fluctuations.

REQUIRED

REFERENCES:

DEOP Charts with entry conditions blanked out.

ILT EXAM Page: 55 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 31 ID: 24248 Points: 1.00 Unit 2 was operating at near rated power, when a fire caused an overcurrent condition on Bus 29.

Subsequently a feedwater transient caused the RPV to scram on RPV water level.

The SRO directs you to inject SBLC as an Alternate Injection System per DOP 1100-02, INJECTION OF SBLC Hard Card.

What would be the expected system response?

A. NEITHER Squib valve would fire B. 'A' Squib valve would fire ONLY C. 'B' Squib valve would fire ONLY D. BOTH Squib valves would fire Answer: B ILT EXAM Page: 56 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 31 Details Question Type: Multiple Choice Topic: 31 - 211000.A3.03 System ID: 24248 User ID: 24248 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 4 Point Value: 1.00 Cross Reference Number:

Num Field 1: 0.00 Num Field 2: 0.00 Text Field:

Comments: Objective: DRE211LN001.02

Reference:

M-33, DOP 6700-13 K/A: 211000.A3.03 3.8 / 3.8 K/A: Ability to monitor automatic operations of the SLC including: Explosive valves indicating lights Level: High Pedigree: Bank History: 2011 Cert Comments:

This question meets the K/A because it examines the candidate's ability to determine the status of the squib valves following a loss of power. The status of the squib valve will be determined through the change in light indications on the control panel.

b) With a loss of Bus 29, MCC 29-1 would be lost.

MCC 29-1 is the power supply to both the 'B' pump and squib valve, thus neither of them could become energized. 'A' pump and squib is powered from MCC 28-1, so when the control switch is taken to position "SYS 1 & 2" (per the hard card) they would become energized and operate as designed.

a) The candidate may choose neither if they did not understand the power supplies c) The candidate may choose 'B' if they didn't know that the hard card has the NSO take the control switch to SYS 1 & 2, as opposed to SYS 1 or SYS 2.

d) The candidate may chose both if they did not understand the power supplies.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 57 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 32 Points: 1.00 Unit 2 was operating at near rated power, when APRM 3 failed downscale.

A Half Scram will be generated on RPS ___(1)___ if IRM ___(2)___ becomes INOP.

A. (1) A; (2) 13 B. (1) B; (2) 13 C. (1) A; (2) 15 D. (1) B; (2) 15 Answer: A ILT EXAM Page: 58 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 32 Details Question Type: Multiple Choice Topic: 32 - 215003.K1.01 System ID: 24162 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE215LN003.06

Reference:

DOP 0700-02, DAN 902-5 C-6 K/A: 215003.K1.01 3.9 / 3.9 K/A: Knowledge of the physical connections and/or cause effect relationships between INTERMEDIATE RANGE MONITOR (IRM) SYSTEM and the following:

RPS.

Level: Memory Pedigree: Bank History: 2010 NRC Explanation: A Half Scram is generated if an APRM downscale is received concurrent with its companion IRM being INOP. In this case APRM 3 and the companion IRM 13, cause a half-scram on RPS "A" side.

REQUIRED

REFERENCES:

None.

33 ID: 24163 Points: 1.00 A fully withdrawn SRM detector transmits 300 pulses in one second.

100 of these pulses are cause by neutrons.

200 of the pulses are caused by gammas.

What is the expected reading on the 902-5 SRM LEVEL meter?

A. 100 cps B. 200 cps C. 300 cps D. 400 cps Answer: A ILT EXAM Page: 59 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 33 Details Question Type: Multiple Choice Topic: 33 - 215004.K4.03 System ID: 24163 User ID: 24163 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE215LN004.03

Reference:

LP DRE215LN004.03 K/A: 215004.K4.03 2.5 / 2.5 K/A: Knowledge of SOURCE RANGE MONITOR (SRM) SYSTEM design feature(s) and/or interlocks which provide for the following: Gamma compensation.

Level: Memory Pedigree: Bank History: 2011 Cert Comments: The purpose of the pulse height discriminator is to provide gamma compensation.

The PHD sets a threshold level. The neutron pulses are large enough to pass through the threshold level and are allowed to be counted. The gamma pulses are smaller than the threshold value and are not passed on to be counted, therefore they are eliminated.

The pulse pre-amplifier boosts the signal strength to separate out noise and get the pulses to the control room. SRMs count neutron pulses, not gamma pulses. The PHD only eliminates the smaller, gamma pulses.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 60 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 34 Points: 1.00 Unit 2 was operating at near rated power, when an ATWS occurred and the following conditions exist:

? Reactor power is 5%.

? ALL APRM downscale lights are illuminated.

? RPV level is -60 inches.

? Drywell pressure is 15 psig.

? Drywell AND Torus sprays have been initiated.

Given the above conditions, which of the following actions taken prior to timeout of the 120 second timer will PREVENT all automatic actuation of ADS?

A. Restore drywell pressure below 2 psig.

B. Maintaining RPV pressure below 150 psig.

C. Placing low pressure ECCS pumps in PTL.

D. Depressing AND releasing the TIMER RESET pushbutton.

Answer: C ILT EXAM Page: 61 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 34 Details Question Type: Multiple Choice Topic: 34 - 218000.K4.03 System ID: 24164 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 4 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE218LN001.06

Reference:

DAN 902-3 B-13 K/A: 218000.K4.03 3.8/4.0 K/A: Automatic Depressurization System: Knowledge of the physical connections and/or cause effect relationships between AUTOMATIC DEPRESSURIZATION SYSTEM and the following:

Low pressure core spray: Plant-Specific.

Level: High Pedigree: Bank History: 2008 NRC, 2011 Cert Comments: With RPV level lo-lo and/or Drywell pressure high AND any low pressure pump (LPCI or CS) running (discharge pressure greater than 100 psig) is a permissive to seal in the 120 sec ADS timer (DAN 902-3 B-13 references this as one of the conditions needed).

Once drywell pressure is above 2 psig, it seals in until reset (will not prevent actuation).

Reactor pressure is not an ADS permissive, but is a common misconception that the ADS will not open when RPV pressure is too low (150 psig).

Depressing and releasing the TIMER RESET pushbutton would only reset the timer and delay the ADS actuation (not prevent).

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 62 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 35 Points: 1.00 Unit 2 was operating at near rated power, when the following occurred sequentially:

• RPV pressure rose to 1085 psig for 30 seconds and then stabilized at 1005 psig.

• A fire in Unit 2 125 VDC Bus 2B-1 caused it to de-energize.

The effect this has on the plant is . . . . .

A. ALL Isolation Condenser isolation valves will close.

B. ONLY the Isolation Condenser VENT valves will close.

C. A loss of Control Room indications for components powered from Bus 23 AND Bus 24.

D. A loss of Control Room indications for components powered from Bus 23-1 AND Bus 24-1.

Answer: A ILT EXAM Page: 63 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 35 Details Question Type: Multiple Choice Topic: 35 - 223002.K6.05 System ID: 24165 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE207LN001.12

Reference:

DAN 902-3 H-2, 12E-2506 sheets 1-3 K/A: 223002.K6.05 3.0 / 3.3 K/A: Knowledge of the effect that a loss or malfunction of the following will have on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF: Containment instrumentation.

Level: High Pedigree: Bank History: 2010 Cert Explanation: With reactor pressure of 1085 psig, for 30 seconds, the Isolation Condenser will have actuated (1070 for 17 seconds). The power supplies for the Group 5 (Iso Cond) isolation instrumentation are 125VDC distribution panels 2A-1 & 2B-1. A Group 5 isolation is initiated whenever there is a loss of EITHER power supply circuits (de-energize to actuate). A Group 5 causes ALL isolation valves to close (NOT just the vent valves). Dist panel 2B-1 is normal control power to (and a loss of control room indication would only happen for) Bus 24 and Bus 24-1, and NOT Bus 23 (2A-1) OR Bus 23-1 (Rx Bldg Dist Pnl).

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 64 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 36 ID: 24166 Points: 1.00 Given the following plant conditions:

• Unit 3 is at 73% power.

• Torus bulk temperature is slowly rising.

• Div 2 torus water temperature Bay 1 is 95°F and slowly rising.

• DOA 0250-01, RELIEF VALVE FAILURE, has been entered for 3-203-3B ERV leaking by.

• Attempts to close the 3-203-3B ERV from the control room have failed.

The HVO has pulled the 3-203-3B ERV control power fuses.

All of the following indications can be used to verify the 3-203-3B ERV is closed EXCEPT:

A. Torus temperature recorder trend B. Control switch valve position indication lights C. Valve leak detection temperature recorder trend D. Acoustic monitor valve position indicating lights Answer: B ILT EXAM Page: 65 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 36 Details Question Type: Multiple Choice Topic: 36 - 239002 K5.04 System ID: 24166 User ID: 24166 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 239LN001.03

Reference:

DOA 0250-01; 12E-3461 & 3461A K/A: 239002 K5.04 3.3/3.5 Knowledge or the operational implications of the following concepts as they apply to SRV: Tail pipe temperature monitoring.

CFR:

Safety Function: 3 PRA: Yes Level: High Pedigree: Bank History: None Comments:

Options A,C, and D are all valid indications to confirm ERV closure. Option B is invalid due to ERV fuses being removed as indicated in the stem. Since the fuses are pulled, the CS indicating lights are extinguished.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 66 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 37 ID: 24249 Points: 1.00 U3 is operating at full power when a storm causes a loss of 345KV BUS 8.

What is the impact on the U3 4KV distribution system?

A. Bus 31 AND 33 trip then fast xfer to TR 31 B. Bus 32 AND 34 trip then fast xfer to TR 31 C. Bus 31 AND 33 trip then fast xfer to TR 32 D. Bus 32 AND 34 trip then fast xfer to TR 32 Answer: B Question 37 Details Question Type: Multiple Choice Topic: 37 - 262001.K6.02 System ID: 24249 User ID: 24249 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 262LN001.06

Reference:

DAN 903-8 E-2 K/A: 262001.K6.02 3.6/3.9 K/A: Knowledge of the effect that a loss or malfunction of the following will have on the A.C. Electrical Distribution: Off-Site Power.

Safety Function: 6 PRA: Yes Level: High Pedigree: New History:

Comments:

A) is incorrect, Bus 8 feeds the U3 division 2 buses.

B) is correct, Bus 8 feeds the U3 division 2 buses. On a trip a fast transfer occurs within 6 cycles.

C) is incorrect, Bus 8 feeds the U3 division 2 buses.

D) is incorrect, Bus 8 feeds the U3 division 2 buses, but TR 32 is dead with a loss of BUS 8 ILT EXAM Page: 67 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 38 Points: 1.00 Unit 3 was operating at near rated power, when Bus 37 experienced an overcurrent condition.

Which of the following Instrument Air Compressor(s) will lose its/their power supply?

A. 3A ONLY B. 3B ONLY C. 3C ONLY D. 3B and 3C ONLY Answer: D Question 38 Details Question Type: Multiple Choice Topic: 38 - 300000.K2.01 System ID: 24168 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE278LN001.02

Reference:

DOA 4700-01 K/A: 300000.K2.01 2.8 / 2.8 K/A: Knowledge of electrical power supplies to the following: Instrument air compressor.

Level: Memory Pedigree: Bank History: 2009 NRC Explanation: The power supplies are 3A - Bus 36, 3B -

Bus 37, and 3C - Bus 37.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 68 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 39 ID: 13452 Points: 1.00 Unit 2 was operating at near rated conditions, when the following occurred:

• 2A Recirc pump temperatures are rising rapidly.

• Annunciator 902-4 G-3 2A RECIRC PP SEAL CLG WTR FLOW LO alarms.

All other RBCCW parameters are normal.

The expected plant response is . . . . .

A. 2A Recirc pump will go to hold.

B. 2A Recirc pump seals and bearings could be damaged within one minute.

C. 2A Recirc pump seals will operate normally as long as CRD flow is maintained.

D. RWCU system could isolate since cooling is lost to the non-regenerative heat exchanger.

Answer: B ILT EXAM Page: 69 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 39 Details Question Type: Multiple Choice Topic: 39 - 400000.K3.01 System ID: 24255 User ID: 13452 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 3 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE202LN001.08

Reference:

DOA 3700-1, DAN 902-4 G-3, P+ID M-20 K/A: 400000.K3.01 2.9/3.3 K/A: Knowledge of the effect that a loss or malfunction of the CCWS will have on the following.

Level: High Pedigree: Bank History: 2005 NRC Comments: The conditions in the stem indicate a loss of RBCCW to the Recirc pump seals. All other RBCCW parameters are stable. Per the DOA if cooling flow is lost and cannot be restored within one minute the operator must trip the recirc pumps. In the discussion section of the DOA it is stated that loss of cooling flow resulting from failures in the RBCCW system will cause damage to plant equipment. If RBCCW flow cannot be restored to the Recirc pumps within one minute, damage may occur to the pump seal and bearings.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 70 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 40 ID: 2461 Points: 1.00 Unit 3 is conducting a special test with the Main Generator conditions as follows:

? Real load is 800 MWe

? Terminal Voltage is 17.1 kV

? Reactive Load is 0 MVAR

? Voltage Regulator Mode Switch is in MANUAL

? Generator hydrogen pressure is 30 psig If an operator placed the Voltage Regulator Mode Switch to AUTO, and the voltage regulator failed to its MINIMUM limit for the current voltage, which of the following indicates the final value of Main Generator reactive loading three minutes later (i.e. plant stable)?

(Assume terminal voltage remains constant.)

A. positive (+) 220 MVAR B. negative (-) 100 MVAR C. negative (-) 120 MVAR D. negative (-) 220 MVAR Answer: B ILT EXAM Page: 71 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 40 Details Question Type: Multiple Choice Topic: 40 - 245000.A1.08 System ID: 24261 User ID: 2461 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 245LN003.11

Reference:

DOP 6400-08 K/A: 245000.A1.08 2.5 / 2.7 K/A: Ability to predict and/or monitor changes in parameters associated with operating the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS controls including: Generator output voltage/reactive load CFR: 41.5 Safety Function: 6 PRA: No Level: High Pedigree: Bank History: ILT 11-1 NRC Comments:The examinee must identify the correct Minimum Excitation Limiter (MEL) curve from the supplied references. The MEL limits the excitation dependent on the current terminal voltage of the generator. The point on the graph will move straight down the 800MWE line until it reaches the 17.1 Kv limit Distracters indicates a misunderstanding of system operation or inability to read the graph.

REQUIRED

REFERENCES:

Figures 5, 6 & 7 from DOP 6400-08 ILT EXAM Page: 72 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 41 Points: 1.00 Unit 3 was in STARTUP, with the following conditions:

• Step 20 of the CRSP contains Control Rods H-8, F-10, H-6 and K-8 with a rod limit from position 08 to 12.

• Control Rod H-8 is withdrawn to position 12.

• Control Rod F-10 is withdrawn to position 10.

The NSO then selects Control Rod H-6, which is currently at position 08.

Prior to selecting the rod, what color will Control Rod H-6 be indicated on the RWM?

A. Red B. Cyan C. White D. Green Answer: D ILT EXAM Page: 73 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 41 Details Question Type: Multiple Choice Topic: 41 - 201006.A3.01 System ID: 24171 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1: 0.00 Num Field 2: 0.00 Text Field:

Comments: Objective: DRE201LN006.06

Reference:

DOP 0400-02 K/A: 201006.A3.01 3.2/3.1 K/A: Ability to monitor automatic operations of the RWM including: System window and light indications:

P-Spec(Not-BWR6).

Level: Memory Pedigree: Bank History: 2002 Quad NRC, 2009 NRC Explanation: Control rods are in red when they are out of sequence, green when they are in the current latched step or selected for rod exercising, white if they are not the rod selected for exercising or not part of the in-sequence step. H-6 should remain green the entire time. Control Rods are indicated in Cyan when they are taken O.O.S.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 74 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 42 ID: 24172 Points: 1.00 Unit 2 was operating at near rated power when Bus 29 experienced an overcurrent condition.

What affect does this have on the Unit 2 LPCI system?

A loss of the Div ___(x)___ ability to ___(y)___ , from the Main Control Room.

A. (x) 1 ONLY; (y) initiate Torus Cooling ONLY B. (x) 1 ONLY; (y) initiate Torus Cooling, spray the Drywell, AND spray the Torus C. (x) 2 ONLY; (y) initiate Torus Cooling ONLY D. (x) 2 ONLY; (y) spray the Drywell, AND spray the Torus Answer: D ILT EXAM Page: 75 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 42 Details Question Type: Multiple Choice Topic: 42 - 219000.K1.05 System ID: 24172 User ID: 24172 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE203LN001.02

Reference:

Valve label power supplies in C/R, load list in LP DRE 203LN001, DOS 1500-1 K/A: 219000.K1.05 3.5 / 3.6 K/A: Knowledge of the physical connections and/or cause effect relationships between RHR/LPCI:

TORUS/SUPPRESSION POOL COOLING MODE and the following: A.C. electrical power.

Level: High Pedigree: Bank History: 2013 Cert Explanation:

This question meets the K/A because it examines the candidate's understanding of Torus Cooling flow paths and the loss of ability to perform TORUS COOLING operation caused by a loss of A.C. electrical power.

Bus 29 powers MCC 29-1, which if lost removes power from the following: Torus Cooling valves (20 and 38),

Drywell spray valves (27 and 28), and Torus Spray valves (18 and 19) for Division II only are fed from MCC 29-4.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 76 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 43 Points: 1.00 Unit 2 was operating at near rated power when a loss of coolant resulted in a Reactor Scram.

The following conditions exist:

• Drywell pressure is 18 psig.

• RPV water level is 10 inches.

• 902-8 E-5, 4 KV BUS 24-1 OVERCURRENT annunciator illuminated.

• 10 minutes later, the US notices that the Division II CAM H2/O2 system is NOT working.

What action(s) is/are required to initiate the CAM system?

A. Reset the Bus 29 UV device ONLY.

B. Place the OFF-STANDBY-ANALYZE switch to ANALYZE.

C. X-tie Bus 28 to Bus 29 the Reset the Bus 29 UV device.

D. Close the feed breaker to MCC 29-1, then place the OFF-STANDBY-ANALYZE switch to ANALYZE.

Answer: C ILT EXAM Page: 77 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 43 Details Question Type: Multiple Choice Topic: 43 - 223001.K6.11 System ID: 24173 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1: 0.00 Num Field 2: 0.00 Text Field:

Comments: Objective: DRE223LN006.08

Reference:

DAN 902-8 H-3, DGA-12, DOP 2400-01, DOP 7000-07 K/A: 223001.K6.11 3.0 / 3.2 K/A: Knowledge of the effect that a loss or malfunction of the following will have on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES: A.C.

electrical distribution.

Level: High Pedigree: Bank History: 2008 NRC Comments: When Bus 24-1 goes overcurrent, Bus 24-1 and Bus 29 are de-energized and will load shed some equipment. During load shed conditions the breaker to the MCC 29-1 (which powers div 2 CAM) does not load shed. Once power is restored to Bus 29 (Xtie Bus 28 to Bus 29), the Bus 29 UV relay must be reset and then MCC 29-1 will be re-energized. The CAM feed breaker does NOT trip and with an ECCS signal still present, the system will start up automatically as soon as power is restored.

This meets the K/a because the examinee has to have knowledge of the effect of an OC trip on Bus 24 on the load shed of Bus 29.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 78 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 44 Points: 1.00 Unit 2 was operating at near rated power, when the following occurred:

• Offgas flow dropped approximately 100 scfm.

• Offgas Recombiner temperature dropped approximately 600oF.

The Unit Supervisor has directed entering DOP 5400-14, EXTINGUISHING AN OFF GAS FIRE.

Which of the following actions are performed prior to executing the procedure above?

A. Ensure adequate margin in the Instrument Air system, to extinguish the fire.

B. Initiate Station Fire Watches for the Offgas system, to identify potential insulation fires.

C. Start all available Circ Water pumps to limit Condensate temperature rise from reduced Condenser vacuum.

D. Drain loop seals upstream of the fire, to allow for intrusion of Instrument Air to extinguish the fire.

Answer: C ILT EXAM Page: 79 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 44 Details Question Type: Multiple Choice Topic: 44 - 271000.A2.11 System ID: 24174 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE271LN001.08

Reference:

DOP 5400-14 K/A: 271000.A2.11 2.8 / 2.9 K/A: Offgas System: Ability to (a) predict the impacts of the following on the OFFGAS SYSTEM: and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: OFFGAS SYSTEM LOW FLOW Level: High Pedigree: Bank History: 2009 NRC Explanation: All available Circ Water pumps should be started to limit Condensate temperature rise from reduced Condenser vacuum.

A fire watch would be an acceptable practice, but is not required.

Service Air is used to extinguish an Offgas fire (NOT Instrument Air).

Loop seals are to be ensured filled (not drained).

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 80 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 45 Points: 1.00 Unit 2 was operating at near rated power with MCC 28-2 out of service, when the following annunciators are received:

902-8 B-8, 120/240 ESS BUS VOLT LO.

902-8 E-10, 120/240 ESS BUS ON EMERG SPLY.

An impact of this transient is that the _______ rad monitor(s) become(s) de-energized.

A. Channel 'A' Off Gas B. Channel 'A' Refuel Floor C. 2B and 2D Main Steam Line (MSL)

D. Outboard channel 'B' Reactor Building and Fuel Pool Answer: C ILT EXAM Page: 81 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 45 Details Question Type: Multiple Choice Topic: 45 - 272000.K2.01 System ID: 24175 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE272LN002.02

Reference:

DOA 0500-05, DOA 6800-01, DANs 902-8 B-8 and E-10 K/A: 272000.K2.01 2.5 / 2.8 K/A: Radiation Monitoring System: Knowledge of electrical power supplies to the following: Main steamline radiation monitors.

Level: High Pedigree: Bank History: 2009 Cert Comments: With MCC 28-2 O.O.S, the RESERVE power supply to the U2 ESS bus is lost. The two alarms that are received indicate that the ESS Bus ABT has transferred (irregardless of the reserve power supply being energized or not). These events remove ALL power from the ESS bus, which is the power supply for the B and D MSL rad monitors.

Channel A Off Gas rad monitor and Channel A Refuel Floor rad monitor are powered from RPS Bus A, which is still energized (from MCC 29-2 via the B RPS MG Set - cross divisional power).

Outboard channel B RBX & fuel pool high rad aux relays are powered from the Inst Bus (which is still energized from MCC 25-2).

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 82 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 46 Points: 1.00 A hydraulic ATWS has occurred on Unit 2.

The Unit Supervisor has directed you to perform repeated scram resets per DEOP 0500-05.

Which of the following describes the MINIMUM electrical safety precautions required to perform this task?

All metal removed and ...

A. safety glasses B. safety glasses, long sleeve cotton shirt and rubber gloves C. safety glasses, electrical safety coat, face shield and rubber gloves D. safety glasses, long sleave cotton shirt, electrical safety coat and rubber gloves Answer: B ILT EXAM Page: 83 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 46 Details Question Type: Multiple Choice Topic: 46 - Generic.1.26 System ID: 24189 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 295L105

Reference:

SA-AA-129 K/A: Generic 2.1.26 3.4 / 3.6 K/A: Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

CFR: 41.10 PRA: No Level: Memory Pedigree: Bank History: ILT 11-1 NRC Comments: SA-AA-129 states that for the voltage in the area being worked in for DEOP 500-5 the minimum PPE is all metal removed, long sleeve cotton shirt, safety glasses and rubber gloves REQUIRED

REFERENCES:

None.

47 Points: 1.00 You are about to take the shift as a Unit 2 NSO. The last time you were on shift was seven (7) days ago.

To meet the requirements of OP-AA-112-101, What is the MINIMUM number of days of turnover logs that MUST be reviewed prior to making a relief?

A. 1 day.

B. 2 days.

C. 4 days.

D. 7 days.

Answer: C ILT EXAM Page: 84 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 47 Details Question Type: Multiple Choice Topic: 47 - Generic.1.03 System ID: 24190 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 29900LK022

Reference:

OP-AA-112-101 K/A: Generic.1.3 3.7 / 3.9 K/A: Knowledge of shift or short-term relief turnover practices.

Level: Memory Pedigree: Bank History: 2008 NRC Comments: OP-AA-112-101 requires Reactor Operator log review through the last previous date on shift, or the preceding four days, whichever is less. The distracters for 1 or 2 days are common misconceptions, based on days off during normal rotation. The 7 day distracter would be the choice (incorrect) based on not being on shift for the last 7 days.

REQUIRED

REFERENCES:

None.

48 ID: 24191 Points: 1.00 A locked throttle valve in a safety related system is to be positioned three turns CLOSED FROM FULL OPEN.

Per OP-AA-108-101-1001, COMPONENT POSITION DETERMINATION, which of the following verification techniques is required for the valve's position?

A. Peer Check B. Double Verification C. Concurrent Verification D. Independent Verification Answer: C ILT EXAM Page: 85 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 48 Details Question Type: Multiple Choice Topic: 48 - Generic.1.29 System ID: 24191 User ID: 24191 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 29900LK051

References:

OP-AA-108-101-1001, HU-AA-101 K/A: Generic.1.29 4.1 / 4.0 K/A: Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

Level: Memory Pedigree: Bank History: 2008 NRC Comments: Per OP-AA-108-101-1001 for component position determination, concurrent verification is required for throttle valve position.

REQUIRED

REFERENCES:

None.

49 Points: 1.00 Unit 2 and Unit 3 are operating at rated power.

IAW OP-AA-109-101, Clearance and Tagging, which of the following equipment isolations requires an EXCEPTIONAL clearance order if single point of isolation is used?

A. 2B TBCCW Pump.

B. RWCU Aux pump.

C. Waste Collector Pump.

D. Stator Cooling Hx tube side.

Answer: B ILT EXAM Page: 86 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 49 Details Question Type: Multiple Choice Topic: 49 - Generic.2.13 System ID: 24192 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 29900LK012

Reference:

OP-AA-109-101 K/A: Generic.2.13 4.1 / 4.3 K/A: Knowledge of tagging and clearance procedures.

Level: High Pedigree: New History: None.

Comments: Per OP-AA-109-101 attachment 2 the RWCU Aux Pump would meet the EXCEPTION of lack of dual valve isolation when isolation greater than 500psig or greater than 200 degrees fahrenheit.

REQUIRED

REFERENCES:

None.

50 Points: 1.00 A Unit 2 Drywell entry is required to be made.

Which of the following statements are correct, with regards to dose concerns, for the personnel making the Drywell entry?

A. Reactor MUST be shutdown.

B. Reactor power is 34% OR lower.

C. If in operation, the HPCI system MUST be secured.

D. If in operation, the RWCU system MUST be secured.

Answer: B ILT EXAM Page: 87 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 50 Details Question Type: Multiple Choice Topic: 50 - Generic.3.12 System ID: 24193 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 299LK0028

Reference:

DOP 1600-22 K/A: Generic.3.12 3.2/3.7 K/A: Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Level: Memory Pedigree: Bank History: 2007 NRC Explanation: Reactor power must be 34.2% or less for entry (not shutdown). The RWCU and HPCI systems should NOT be secured if running, since this would change conditions.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 88 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 51 Points: 1.00 Unit 2 was in STARTUP with only the 2C SDC pump in operation, when the 2C SDC pump tripped on high suction temperature.

One minute later, the U2 125 VDC Rx Bldg Distribution Panel de-energized, due to a fire.

Which picture below correctly identifies the proper indications for the above situation?

A. A B. B C. C D. D ILT EXAM Page: 89 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Answer: A Question 51 Details Question Type: Multiple Choice Topic: 51 - 205000.K6.02 System ID: 22570 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 3 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE205LN001.12

Reference:

DOA 6900-T1 K/A: 205000.K6.02 2.7 / 2.9 K/A: Knowledge fo the effect that a loss or malfunction of the following will have on the Shutdown Cooling:

D.C. electrical power.

Level: High Pedigree: Bank History: NRC, 2009 NRC Explanation: With a loss of the U2 125 VDC Rx Bldg Dist Panel, all control power is lost to Bus 23-1. The 2A and 2C SDC pumps are powered from Bus 23-1.

When control power is lost to Bus 23-1, all indicating lights for the 2A and 2C SDC pumps are lost. The 2B SDC pump will still have indicating lights, as it is powered from Bus 24-1, which receives its control power from 2B-1 Dist Panel. The 2B SDC pump does not auto start in this situation, so there will be no ON indicating light for it.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 90 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 52 Points: 1.00 Unit 2 was operating at near rated power when the following events occurred, sequentially:

? Drywell pressure increased to 3.0 psig.

? Annunciator 902-3 H-4, CORE SPRAY SYS B TIMERS NOT HOME is received.

? Bus 24 to 24-1 Feed and Main Feed Breakers trip.

With no further operation actions taken, when power is restored to Bus 24-1, the 2B Core Spray pump will . . . . .

A. start as soon as the Bus 24-1 undervoltage condition clears.

B. start 5 seconds after the Bus 24-1 undervoltage condition clears.

C. start 10 seconds after the Bus 24-1 undervoltage condition clears.

D. start 15 seconds after the Bus 24-1 undervoltage condition clears.

Answer: C ILT EXAM Page: 91 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 52 Details Question Type: Multiple Choice Topic: 52 - 262001 A3.04 System ID: 24208 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE262LN001.06

Reference:

DAN 902-3 H-4 K/A: 262001 A3.04 3.4 / 3.6 K/A: Ability to monitor automatic operations of the AC Electrical Distribution including: Load Sequencing.

Level: High Pedigree: New History:

Comments: A high DW pressure signal causes the Reactor to scram, Core Spray pumps start, and EDGs to start. A loss of power to Bus 24 causes the temporary loss of Bus 24-1. The U2 EDG will close on to Bus 24-1. The 2B Core Spray Pump will have lost power on the loss of 24-1. The 2B Core Spray pump breaker on Bus 24-1 opens and will reclose 10 seconds after the Bus 24-1 is re-energized by the U2 EDG due to load sequencing.

REQUIRED

REFERENCES:

None.

53 Points: 1.00 Which of the following plant electrical systems supplies power to the detector and electronic circuitry of the the Source Range Monitoring (SRM) System?

A. 24 VDC station batteries B. 120 V ESS Bus C. 120 V Instrument Bus D. 125 VDC station batteries Answer: A ILT EXAM Page: 92 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 53 Details Question Type: Multiple Choice Topic: 53 - 215004.K2.01 System ID: 24209 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE 215LN004.02

Reference:

UFSAR 8.3.2.3, DOA 6900-01 K/A: 215004.K2.01 2.6/2.8 K/A: Knowledge of electrical power supplies to the following: SRM channels/detectors.

Level: Memory Pedigree: Bank History:

Comment: Per FSAR section 8.3.2.3 24/48/V System is supplied from the 24/48 dc battery system. DOA 6900-01 also list the SRMs as a system supplied by 24/48 dc.

ILT EXAM Page: 93 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 54 Points: 1.00 Unit 2 was operating at near rated power, with the following conditions:

? The Unit 2A 125 VDC Battery Charger is supplying the Unit 2 125 VDC system.

? The Unit 2/3 250 VDC Battery Charger is supplying the Unit 2 250 VDC system.

Then a fire caused Bus 28 to de-energize.

(1) What effect will this have on the batteries AND (2) what actions can be taken to mitigate the transient?

A. (1) The Unit 2 125 VDC batteries ONLY will begin to discharge; (2) place the Unit 2 125 VDC Battery Charger in service.

B. (1) The Unit 2 250 VDC batteries ONLY will begin to discharge; (2) place the Unit 2 250 VDC Battery Charger in service.

C. (1) The Unit 2 125 AND 250 VDC batteries will begin to discharge; (2) place the Unit 2 125 AND Unit 2 250 VDC Battery Chargers in service.

D. (1) The Unit 2 125 AND 250 VDC batteries will begin to discharge; (2) place the Unit 2 125 Alternate Battery AND Unit 2 250 VDC Battery Charger in service.

Answer: A ILT EXAM Page: 94 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 54 Details Question Type: Multiple Choice Topic: 54 - 295004.A1.01 System ID: 24210 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE263LN001.02

Reference:

DOA 6900-04, DOA 6900-T1, DOA 6900-02 K/A: 295004.A1.01 3.3 / 3.4 K/A: Ability to operate and/or monitor the following as they apply to Partial or Total Loss of DC Pwr: D.C.

electrical distribution systems.

CFR: 41.7 Safety Function: 6 PRA: Yes Level: High Pedigree: Bank History: ILT 11-1 NRC Comments: Explanation: With the 2A charger (MCC 28-2) supplying the 125 VDC system and the 2/3 charger (MCC 29-2 or 39-2) supplying the 250 VDC system, a loss of Bus 28 will cause ONLY the 125 VDC 2A charger to lose power, which will cause the 125 VDC batteries to begin to discharge. Transferring the 125 VDC system to the Unit 2 125 VDC charger is the correct action.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 95 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 55 ID: 24250 Points: 1.00 Which one of the following describes the reason for placing the ISOL COND RX INLET VLV 2-1301 local selector switch on panel 2202-76 in VLV1 position?

A. To disconnect local control circuits from the valve.

B. To disconnect Control Room control circuits from the valve.

C. To isolate wire runs to meet divisional physical separation criteria.

D. To prevent overloading the associated DG during a design basis LOCA.

Answer: B Question 55 Details Question Type: Multiple Choice Topic: 55 - 295016.K2.02 System ID: 24250 User ID: 24250 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 29501LP083

Reference:

DSSP 0100-CR K/A: 295016.K2.02 4.0/4.1 K/A: Knowledge of the interrelations between Control Room Abandonment and the following: Local control stations: Plant-Specific.

Level: Memory Pedigree: New History:

Comments:

Placing the ISO COND '1' and '4' valves in the VLV1 position, removes the control circuit from the Main Control Room, in case of fire/evacuation. Operating this switch does not change the physical routing or location of equipment. This switch switches valve power from MCCs 28-1 to/from 38-1, which are both powered from the 2/3 EDG.

ILT EXAM Page: 96 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 56 ID: 24263 Points: 1.00 Unit 2 was operating at near rated power when a spike occurs resulting in annunciator 902-5 C-12, CHANNEL 1-3 APRM HI-HI / INOP illuminated.

An NSO reported that APRM 1 is pegged full scale.

What actions are required to return RPS to its pre-spike state and reset the alarms?

1) Depress the TRIP RESET pushbutton on the 902-37 panel.

2) Turn the SCRAM RESET switch to the GP 1-4 position 902-5 panel.

3) Turn the SCRAM RESET switch to the GP 2-3 position 902-5 panel.

4) Place the APRM BYPASS switch in the CH-1 position on the 902-5 panel.

A. 1, 2, 3, AND 4 B. 2 and 3 ONLY C. 2 and 4 ONLY D. 2, 3, and 4 ONLY Answer: D ILT EXAM Page: 97 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 56 Details Question Type: Multiple Choice Topic: 56 - 215005.K3.01 System ID: 24263 User ID: 24263 Status: Active Always select on test: No Authorized for practice: No Difficulty: 0.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE215LN005.08

Reference:

DAN 902-5 C-12, DOP 0500-07 K/A: 215005.K3.01 4.0/4.0 K/A: Knowledge of the effect that a loss or malfunction of the APRM/LPRM will have on following: RPS.

Level: Memory Pedigree: Bank History: 2013 Cert Explanation: The actions to reset the half scram is to first bypass the alarming APRM and then place the SCRAM RESET switch in BOTH positions.

Depressing the TRIP RESET pushbutton on the 902-37 panel only clears the Hi-Hi indicator light on that panel and is NOT required.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 98 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 57 Points: 1.00 Unit 2 was operating at rated power when 2-203-1D, D Inboard MSIV, failed shut. The following conditions are currently present:

• RPV level is being controlled at -40" in automatic

• RPV pressure is 1040 psig and being controlled with the IC

• All attempts to open the 2-4399-74, CLEAN DEMIN VLV have failed Per DOP 1300-03, Manual Operation of the Isolation Condenser, the preferred RPV pressure control method is:

A. ADS valve operation B. HPCI operation in the pressure control mode C. IC operation with contaminated demin make up D. IC operation with fire suppression system make up Answer: B ILT EXAM Page: 99 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 57 Details Question Type: Multiple Choice Topic: 57 - 207000.A2.07 System ID: 24214 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 207LN001.08

Reference:

DOP 1300-03 K/A: 207000 A2.07 3.5/3.5 K/A: Ability to (a) predict the impacts of the following on the Isolation (Emergency) Condenser; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Valve Closures-BWR 2,3 CFR: 41.5 Safety Function: 4 PRA: Yes Level: High Pedigree: New History:

Comments:

This question meets the K/A because it examines the candidate's ability to PREDICT the IC will require shell side make up and use DOP 1300-03 knowledge to determine necessary pressure control methodology.

With the conditions stated in the stem, a PCIS GRP I has occurred due to high steam flow. A reactor scram followed with a failure of all control rods to fully insert.

IC shell side makeup is required due to inventory loss.

With the failure of MO 2-4399-74 normal shell side makeup is unavailable. Per DOP 1300-03, clean demin is the preferred source with IC makeup pumps unavailable, however the flowpath for clean demin also requires the use of MO 2-4399-74 thereby making IC with clean demin an incorrect choice. Since RPV level is being maintained by FWLC in auto, HPCI is NOT needed for RPV level control and therefore available in the pressure control mode. Per DOP 1300-03, this is the preferred RPV pressure control method. ADS valve operations are available, but not preferred. IC operation with Fire suppression makeup is also available, however this option is pursued after ADS valve operation.

ILT EXAM Page: 100 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 58 Points: 1.00 Unit 2 was operating at rated power when a small LOCA occurred resulting in Drywell Pressure of 1.8 psig and increasing 0.1 psig/min.

The US has directed you to establish Torus Cooling using Division 1 LPCI. In order to establish flow through the LPCI heat exchanger, you must....

A. wait 30 seconds following LPCI initiation and then close the 2-1501-11A, Hx Bypass vlv.

B. wait 30 seconds following LPCI initiation and then close the 2-1501-11B, Hx Bypass vlv.

C. wait 5 minutes following LPCI initiation and then close the 2-1501-11A, Hx Bypass vlv.

D. wait 5 minutes following LPCI initiation and then close the 2-1501-11B, Hx Bypass vlv.

Answer: A ILT EXAM Page: 101 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 58 Details Question Type: Multiple Choice Topic: 58 - 295024.A.1.13 System ID: 24215 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 203LN001.06 Ref: UFSAR Figure 7.3-2B K/A: 295024 A1.13 3.6/3.6 K/A: Ability to operate and/or monitor the following as they apply to High Drywell Pressure: Suppression Pool Cooling CFR: 41.7 Safety Function: 5 PRA: Yes Level: Memory Pedigree: New History:

Comments:

A - Correct. 2-1501-11A is the LPCI/CCSW heat exchanger bypass for Division 1. This valve is interlocked open for 30 seconds following an initiation signal.

B - Incorrect. 2-1501-11B is the LPCI/CCSW heat exchanger bypass for Division 2. This valve is interlocked open for 30 seconds following an initiation signal.

C - Incorrect. 2-1501-11A is the LPCI/CCSW heat exchanger bypass for Division 1. This valve is interlocked open for 30 seconds following an initiation signal. 5 minutes is a plausible distracter based on additional LPCI interlocks.

D - Incorrect. 2-1501-11B is the LPCI/CCSW heat exchanger bypass for Division B. This valve is interlocked open for 30 seconds following an initiation signal. 5 minutes is a plausible distracter based on additional LPCI interlocks ILT EXAM Page: 102 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 59 Points: 1.00 An ATWS occurred on Unit 2 with the following conditions present:

• DEOP 400-2 has been executed due to being unable to hold RPV level above -164"

• 1 ERV failed to open

• RPV Pressure is above the Minimum Steam Cooling Pressure

• SBLC Pump discharge pressure is 400 psig

• SBLC switch is selected to System 1 Is SBLC injecting into the RPV and what is the status of the SBLC FLOW light on the 902-5 panel?

A. No. Flow light is illuminated.

B. No. Flow light is extinguished.

C. Yes. Flow light is illuminated.

D. Yes. Flow light is extinguished.

Answer: B ILT EXAM Page: 103 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 59 Details Question Type: Multiple Choice Topic: 59 - 211000.A4.05 System ID: 24216 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 211LN001.11

Reference:

M-33, DEOP 400-5 K/A: 211000 A04.05 4.1/4.0 K/A: Ability to manually operate and/or monitor in the control room: Flow Indication: Plant Specific CFR: 41.7 Safety Function: 1 PRA: Yes Level: High Pedigree: New Comments:

A - Incorrect - With RPV pressure above 420 psig (Minimum Steam Cooling Pressure with 4 ERVs open),

and SBLC discharge pressure of 400 psig, SBLC is NOT injecting. The SBLC relief valve has lifted and the flow transmitter is downstream of the relief valve, therefore no flow is indicated and the light will be extinguished.

B - Correct - With RPV pressure above 420 psig (Minimum Steam Cooling Pressure with 4 ERVs open),

and SBLC discharge pressure of 400 psig, SBLC is NOT injecting. The SBLC relief valve has lifted and the flow transmitter is downstream of the relief valve, therefore no flow is indicated and the light will be extinguished.

C - Incorrect - With RPV pressure above 420 psig (Minimum Steam Cooling Pressure with 4 ERVs open),

and SBLC discharge pressure of 400 psig, SBLC is NOT injecting. The SBLC relief valve has lifted and the flow transmitter is downstream of the relief valve, therefore no flow is indicated and the light will be extinguished.

D - Incorrect - With RPV pressure above 420 psig (Minimum Steam Cooling Pressure with 4 ERVs open),

and SBLC discharge pressure of 400 psig, SBLC is NOT injecting. The SBLC relief valve has lifted and the flow transmitter is downstream of the relief valve, therefore no flow is indicated and the light will be ILT EXAM Page: 104 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC extinguished.

60 ID: 24217 Points: 1.00 You are inspecting a Fire Extinguisher type that does NOT have a pressure gauge and discover that the seal is missing/broken. What action is required per DFPS 4114-15?

A. Reseal the extinguisher ONLY.

B. Verify alternate fire suppression is available.

C. Verify correct weight of the extinguisher and replace the seal.

D. Establish fire watch until approved extinguisher is in place.

Answer: C Question 60 Details Question Type: Multiple Choice Topic: 60 - Generic 4.25 System ID: 24217 User ID: 24217 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE286286LN001.14

Reference:

DFPS 4114-15 K/A: Generic 2.4.25 3.3/3.7 K/A: Knowledge of fire protection procedures.

CFR: 41.10 Level: Memory Pedigree: Bank History: LSG NRC 05 Comments:

Per DFPS 4114-15 Annual Fire Extinguisher Inspection, if you are performing extinguisher checks on an extinguisher type without a pressure gauge and discover that the seal is broken, then the correct action is to weigh the extinguisher and replace the seal per DFPP 4114-04. Replacing the extinguisher is not required. Only logging and continuing inspection is not the correct action. Verifying alternate fire suppression is not required by the procedure.

ILT EXAM Page: 105 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 61 Points: 1.00 You have been tasked as the Unit 2 NSO with transferring ESS bus power from MCC 28-2 to Bus 25.

Per DOP 6800-01, to prevent the RWCU system from isolating during the transfer you are REQUIRED to....

A. Place ONLY the RWCU INBD ISOL MN STEAM BYP SW to the Bypass position B. Place ONLY the RWCU OUTBD ISOL MN STEAM BYP SW to the Bypass position C. Place RWCU INBD ISOL MN STEAM BYP SW AND RWCU OUTBD ISOL MN STEAM BYP SW to the bypass positions D. Perform a controlled shutdown of the RWCU system per DOP 1200-03, RWCU SYSTEM OPERATION WITH THE REACTOR AT PRESSURE Answer: C ILT EXAM Page: 106 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 61 Details Question Type: Multiple Choice Topic: 61 - 262002.A4.01 System ID: 24218 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 204LN001.11

Reference:

DOP 6800-01 K/A: 262002 A4.01 2.8/3.1 K/A: Ability to manually operate and/or monitor in the control room: Transfer from alternative source to preferred source CFR: 41.7 Safety Function: 6 PRA: No Level: Memory Pedigree: New History:

Comments:

This question meets the K/A because it examines the candidate's ability to manually operate control room panels to accomplish ESS bus transfer from alternative to preferred source.

When transferring ESS Bus power supplies DOP 6800-01 requires the manipulation of both the inboard and outboard main steam bypass switches to the bypass position. The use of one switch is not permitted per DOP 6800-01. DOP 6800-01 provides no direction to perform an orderly shutdown of RWCU.

ILT EXAM Page: 107 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 62 Points: 1.00 An ATWS has occurred on Unit 3. The Unit Supervisor has directed you to pull RPS scram solenoid fuses per DEOP 0500-05.

Where are these fuses located and why is it important to remove them in the specified order?

A. 903-15 and 903-17 panels; To prevent core oscillations.

B. 903-16 and 903-17 panels; To prevent core oscillations.

C. 903-15 and 903-17 panels; To prevent a direct vent path from the RPV to the reactor building.

D. 903-16 and 903-17 panels; To prevent a direct vent path from the RPV to the reactor building.

Answer: C ILT EXAM Page: 108 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 62 Details Question Type: Multiple Choice Topic: 62 - 212000 G.1.30 System ID: 24219 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 29502LK094

Reference:

DEOP 0500-05 K/A: 212000.G.1.30 4.4/4.0 K/A: Ability to locate and operate components, including local controls CFR: 41.7 Safety Function: 1 PRA: No Level: Memory Pedigree: New History:

Comments:

DEOP 0500-05 directs removal of RPS scram fuses from the 902(3)-15 and 902(3)-17 panels. DEOP 0500-05 caution warns the operator that pulling the fuses in the incorrect sequence may result in a discharge path from the RPV to the reactor building via the scram discharge volume vents and drains.

Uncontrolled control rod insertion is incorrect because the operator is taking actions to insert the control rods, therefore this in NOT uncontrolled. 903-16 and 903-17 panels are valid distracters due to the proximity of the panels.

ILT EXAM Page: 109 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 63 ID: 24220 Points: 1.00 Unit 2 was at full power when a transient occurred causing an entry into an 'ALERT' EP classification.

You have been assigned the Operations Shift Communicator role.

Per EP-AA-112-100 F05 Whose permission is required(if any), to transfer ENS notification responsibility to the TSC/EOF?

A. TSC Director B. Shift Manager C. Unit Supervisor D. No permission required Answer: B Question 63 Details Question Type: Multiple Choice Topic: 63 - Generic 4.37 System ID: 24220 User ID: 24220 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: EP-G-105.2b

Reference:

EP-AA-112-100-F05 K/A: Generic 4.37 K/A: Knowledge of the lines of authority during implementation of the emergency plan.

CFR: 41.10 PRA: N/A Level: High Pedigree: New History:

Comments: Per EP-AA-112-100-F-05 step 2.2.D, when directed by the Shift Manager, then Contact the TSC/EOF ENS Communicator, using the ERF Telephone Directory to transfer ENS notification responsibilities.

ILT EXAM Page: 110 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 64 Points: 1.00 DOS 7500-02 is in progress for post maintenance testing for the 'A' SBGT, when 902-3 F-14, RX BLDG VENT CH A RAD HI-HI is received. The NSO reports both CH A and CH B Rx Bldg Vent monitors on the 902-10 panel indicate 5.8 mr/hr.

What procedural actions are required?

A. Place C/S for running SBGT train to PRI B. Place C/S for non-running SBGT train to PRI C. Verify ONLY U2 RB Vent damper isolation has occurred.

D. Verify PCIS GRP III has occurred and SBGT flow rate is within limits Answer: B ILT EXAM Page: 111 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 64 Details Question Type: Multiple Choice Topic: 64 - 261000.A2.13 System ID: 24221 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 261LN001.08

Reference:

DOP 7500-01, DOS 7500-02 K/A: 261000 A2.13 3.4/3.7 K/A: Ability to (a) predict the impacts of the following on the SGTS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High secondary containment ventilation exhaust radiation CFR: 41.5 Safety Function: 9 PRA: No Level: High Pedigree: New History:

Comments: The operator must determine that the set point for the alarm is also the setpoint for RB Vent trip and SBGT auto start. With the A Train already running the operator must understand that the non-running train must be placed in primary to allow for proper operation with all automatic functions activated.

A - Incorrect. With BOTH channels A and B of RB Vent Radiation monitors above 4 mr/hr SBGT receives an autostart signal. Per DOS 7500-02, if an autostart signal is received during post maintenance testing, the operator is directed to place the CS for the running train to STBY.

B - Correct. With BOTH channels A and B of RB Vent Radiation monitors above 4 mr/hr SBGT receives an autostart signal. Per DOS 7500-02, if an autostart signal is received during post maintenance testing, the operator is directed to place the CS for the non-running train to PRI.

C - Incorrect. DOS 7500-02 directs the operator in these conditions to verify the RB Vent isolation on the 923-4 panel vice the 923-5 panel D - Incorrect. The conditions in the stem represent conditions necessary to actuate PCIS GRP II. A PCIS ILT EXAM Page: 112 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC GRP III signal is not present.

65 ID: 24222 Points: 1.00 U2 was at full power when the following occurs:

• A scram signal is received

• Reactor power is 10%

• A steam leak is occurring making the Rx Building inaccessible Under these conditions, how will the crew raise CRD Drive Water pressure?

A. open the CRD 2-0302-8 valve B. close the CRD 2-0302-8 valve C. open the CRD 2-0301-25 valve D. close the CRD 2-0301-25 valve Answer: B ILT EXAM Page: 113 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 65 Details Question Type: Multiple Choice Topic: 65 - 201001.A4.04 System ID: 24222 User ID: 24222 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE 201LN001.06

Reference:

DGP 2-3 K/A: 201001.A4.04 3.1/3.0 K/A: Ability to manually operate and/or monitor in the control room: Drive water header pressure control valve Level: High History: New Comments: This question requires an understanding of the flow paths for the CRD hydraulic system.

a) opening the CRD 2-0302-8 valve will decrease drive water pressure b) closing the CRD 2-0302-8 valve is the correct answer. This will cause drive water pressure to increase and is guided by DGP 2-3 c) opening the CRD 2-0301-25 valve will allow flow through to the charging water header decreasing drive water pressure. The valve is located in the reactor building and not accessible due to the steam leak d) closing the CRD 2-0301-25 would isolate flow to the charging water header and increase flow to the drive water header. The valve is located in the reactor building and not accessible due to the steam leak ILT EXAM Page: 114 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 66 ID: 24223 Points: 1.00 Unit 3 is operating at near rated power, with a Control Rod selected for withdrawal, when APRMs 3 and 5 failed downscale simultaneously.

RBM(s) ___(x)___ auto bypassed AND the operator is required to bypass APRM(s) ___(y)___ to allow rod movement.

A. (x) 8 ONLY; (y) 3 ONLY B. (x) 8 ONLY; (y) 5 ONLY C. (x) 7 ONLY; (y) 3 AND 5 D. (x) 7 AND 8; (y) 3 AND 5 Answer: C ILT EXAM Page: 115 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 66 Details Question Type: Multiple Choice Topic: 66 - 215002.A2.03 System ID: 24223 User ID: 24223 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1: 0.00 Num Field 2: 0.00 Text Field:

Comments: Objective: 215L-S2-06

References:

DAN 902-5 C-6, UFSAR 7.6.1.5.3.2 K/A: 215002.A2.03 3.1 / 3.3 K/A: Ability to predict the impacts of the following on the RBM; and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel:

Level: Memory Pedigree: Bank History:

Explanation: RBMs are set up with a primary and alternate reference APRM. For channel 7, APRM 3 is the primary and APRM 2 is the alternate. For channel 8, APRM 4 is the primary and APRM 5 is the alternate.

When APRM 3 failed downscale a rod block occurs and APRM 7 is auto bypassed. Since APRM 4 did not fail then APRM 8 is unaffected. Both APRM 3 and APRM 5 must be bypassed to clear the rod block.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 116 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 67 ID: 24224 Points: 1.00 The Reactor Water Cleanup pump room was recently surveyed and the following radiological conditions exist:

? General area radiation of 200 mrem/hr.

? Smearable contamination of 90 dpm/100cm2 (beta-gamma)

How should the area be posted IAW RP-AA-376 Radiological Postings, Labeling, and Markings?

A. "Caution - High Radiation Area" only.

B. "Caution - Locked High Radiation Area" only.

C. "Caution - High Radiation Area" AND "Caution - Contaminated Area" D. "Caution - Locked High Radiation Area" AND "Caution - Contaminated Area" Answer: A ILT EXAM Page: 117 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 67 Details Question Type: Multiple Choice Topic: 67 - Generic 3.07 System ID: 24224 User ID: 24224 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective:

Reference:

RP-AA-376 K/A: Generic 2.3.7 3.5/3.6 K/A: Ability to comply with radiation work permit requirements during normal or abnormal conditions.

Level: Memory Pedigree: Bank CFR: 41.12 History: None Comments: Per RP-AA-376, a high radiation area is an area that could result in an individual receiving a deep dose equivalent rate in excess of 100 mrem/hr at 30 cm from the radiation source. A contaminated area contains contamination present at levels > 1000 dpm/100cm2 beta/gamma. Knowledge of radiation and contamination area markings is required to comply with RWPs.

ILT EXAM Page: 118 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 68 ID: 24225 Points: 1.00 With Unit 2 at 95% power, the following transient is observed:

• Rise in indicated core flow.

• Drop in core thermal power.

• Drop in Main Generator power.

• Drop in Core differential pressure.

Which of the following is causing the above operating anomaly?

A. Failure of a jet pump B. Partial opening of an ERV C. Loss of RWCU system due to HELB isolation D. Failure of a condensate demineralizer post strainer Answer: A ILT EXAM Page: 119 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 68 Details Question Type: Multiple Choice Topic: 68 - 202001.K5.02 System ID: 24225 User ID: 24225 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 20200LK016

Reference:

DOA 0201-01 K/A: 202001.K5.02 3.1 / 3.2 K/A: Knowledge of the operational implications of the following concepts as they apply to RECIRCULATION SYSTEM: Jet pump operation: BWR-3,4,5,6 CFR: 41.5 Safety Function: 1 & 4 PRA: No Level: High Pedigree: Bank History: ILT 11-1 NRC Comments: DOA 0201-01 states the symptoms of a failed Jet Pump are:Rise in indicated core flow, drop in core thermal power, drop in main generator power and drop in core D/P. None of the distracters would have all of the symptoms listed.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 120 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 69 ID: 23475 Points: 1.00 Given the following:

• A Scram has occurred on U2.

• DW pressure is 3.1 psig and slowly rising.

• The US has ordered Torus Sprays to be placed in service per the Hard Card.

When operating the control switches for Torus Spray, in the OPEN direction, the TORUS SPRAY VLV MO 2-1501-18A MUST be___(1)___ , and the TORUS SPRAY VLV MO 2-1501-19A MUST be ___(2)___ .

A. (1) given a momentary open signal; (2) given a momentary open signal B. (1) given a momentary open signal; (2) held in the open direction until the valve is FULL open C. (1) held in the open direction until the valve is FULL open; (2) given a momentary open signal D. (1) held in the open direction until the valve is FULL open; (2) held in the open direction until the valve is FULL open Answer: A ILT EXAM Page: 121 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 69 Details Question Type: Multiple Choice Topic: 69 - 230000.G1.23 System ID: 24226 User ID: 23475 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE203LN001.11

Reference:

12E-2441 sht 1+2 K/A: 230000.G1.23 3.8 / 3.6 K/A: RHR/LPCI: Torus/Pool Spray Mode: Ability to perform specific system and integrated plant procedures during all modes of plant operation CFR: 41.10 Level: Memory Pedigree: Bank History: 2013 Cert Explanation: Both valves are "Seal In" type control switches, in the open direction regardless of whether or not an initiation signal is present.

REQUIRED

REFERENCES:

None.

70 ID: 24227 Points: 1.00 Unit 2 was operating at 25% power when 2 out of 3 DEHC Pressure Controller Processors failed LOW.

What is the plant response to the above failures?

A. The Backup Pressure Regulator will take control and turbine load remains steady.

B. The Turbine trips, causing a Reactor Scram on load reject.

C. The Turbine Control and Bypass Valves close, causing a Reactor Scram on High Pressure.

D. Turbine throttle pressure drops, causing a Reactor Scram on MSIV closure.

Answer: C ILT EXAM Page: 122 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 70 Details Question Type: Multiple Choice Topic: 70 - 241000.K3.08 System ID: 24227 User ID: 24227 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE241LN001.12

Reference:

DOA 5650-02 K/A: 241000.K3.08 3.7 / 3.7 K/A: Knowledge of the effect that a loss or malfunction of the REACTOR/TURBINE PRESSURE REGULATING SYSTEM will have on following:

Control/governor valves.

Level: High Pedigree: Bank History: 2013 Cert Explanation: When 2 of the 3 DEHC Pressure Controller Processors fail LOW then the Turbine Control Valves and Turbine Bypass Valves close, causing a Reactor Scram on high pressure.

The backup pressure regulator will NOT be able to take control, since it is lost anytime 1 of the DEHC Pressure Controller Processors fail (high or low).

The turbine trip will NOT cause a scram, if Reactor power is < 38.5% power.

A scram on MSIV closure will NOT occur, since this happens only if the Pressure Control Processors fail HIGH (which would cause the Turbine Control Valves to open, causing Turbine throttle pressure to drop to <

827 psig [if the Mode Switch is in RUN], then the MSIVs close causing a Reactor Scram).

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 123 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 71 ID: 24115 Points: 1.00 Unit 3 was in STARTUP, with the following PRIOR TO STARTUP and CURRENT conditions:

PRIOR TO STARTUP CURRENT SRM 21 at 9 cps SRM 21 at 38 cps SRM 22 at 11 cps SRM 22 at 47 cps SRM 23 at 8 cps SRM 23 at 39 cps SRM 24 at 10 cps SRM 24 at 44 cps Moderator temp 148oF Moderator temp 149oF The Reactor is NOT critical.

The next sequence step is to move Control Rod F-05 from notch 00 to notch 48.

Which of the following methods is the FASTEST method allowed by DGP 3-4, CONTROL ROD MOVEMENT, to move Control Rod F-05?

A. Continuous withdrawal from 00 to 48.

B. Single notch withdrawal from 00 to 48.

C. Single notch withdrawal from 00 to 36 and THEN continuous withdrawal to 48.

D. Continuous withdrawal to 04, single notch withdrawal from 04 to 36 and THEN continuous withdrawal to 48.

Answer: A ILT EXAM Page: 124 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 71 Details Question Type: Multiple Choice Topic: 71 - Generic.2.02 System ID: 24262 User ID: 24115 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 2 Point Value: 1.00 Cross Reference Number:

Num Field 1: 0.00 Num Field 2: 0.00 Text Field:

Comments: Objective: 29800LK017

Reference:

DGP 3-4, DGP 1-1 K/A: Generic.2.02 4.6 / 4.1 K/A: Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

Level: High Pedigree: Bank History: 2013 Cert Explanation: DGP 3-4 States "Do NOT use Notch Override Switch between positions 04 and 36 after SRMs have experienced three doublings (8 times the initial count rate) until the Unit is in a steaming condition (one bypass valve partially OPEN or the Unit on-line)." The notch override shall not be used when moving the rod less than 3 notches. High Cog due to the operator having to determine the number of doubling based on the information in the stem, then the procedural requirement.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 125 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 72 ID: 24229 Points: 1.00 Unit 2 was at rated power when a control power fuse blew inside a Control Room Panel. The Shift Manager has declared that the event did NOT create an emergency situation. A replacement fuse has been located and determined to be like-for like.

IAW CC-AA-206, Fuse Control, which of the following is correct?

A. The Operator may NOT install the fuse.

B. ONLY EMD may install the fuse with NO further engineering evaluation.

C. The Operator may install the fuse with NO further engineering evaluation.

D. The Operator may install the fuse ONLY after the fuse is evaluated by the Fuse Engineer.

Answer: C ILT EXAM Page: 126 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 72 Details Question Type: Multiple Choice Topic: 72 - Generic 2.14 System ID: 24229 User ID: 24229 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 29900LK081

Reference:

CC-AA-206 K/A: Generic 2.2.14 3.9/4.3 K/A: Knowledge of the process for controlling equipment configuration or status.

CFR: 41.10 PRA: No Level: Memory Pedigree: New History:

Comments: Since the plant was at rated power when a control fuse blew. The new fuse is like-for like with the old fuse. IAW the reference, the Operator may install the fuse and no further engineering evaluation.

a) is incorrect due to the fact that operators can install the fuse b) is incorrect due to the fact that operators can install fuses in both emergency and non-emergency situations c) is correct due to the fact that operators can install fuses in both emergency and non-emergency situations d) is incorrect due to the fact that the fuse has been determined to be like for like replacement, no further evaluation is required.

ILT EXAM Page: 127 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 73 ID: 24230 Points: 1.00 Consider the following two TIP system conditions:

Condition 1:

TIP scan is in progress with the TIP half-way in the core in AUTO.

Condition 2:

TIP insertion in progress with the TIP half-way in the core in MANUAL.

Which of the following describes the initial TIP response if reactor water level drops to +5 inches?

Condition 1 Condition 2 A. Reverses direction immediately Reverses direction immediately B. Continues inserting Continues inserting C. Continues inserting Reverses direction immediately D. Reverses direction immediately Continues inserting Answer: A ILT EXAM Page: 128 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 73 Details Question Type: Multiple Choice Topic: 73 - 215001.K4.01 System ID: 24230 User ID: 24230 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE215LN001.06

Reference:

DAN 902-5 E-5, DRE215LN001 K/A: 215001.K4.01 3.4 / 3.5 K/A: Knowledge of TRAVERSING IN-CORE PROBE design feature(s) and/or interlocks which provide for the following: Primary containment isolation:

Mark-I&II(Not-BWR1).

CFR: 41.7 Level: High Pedigree: Bank History: 2011 Cert Explanation: At RPV Level Low (Group II Initiation Signal +8 inches) the TIPS auto or manually withdraw and the Ball valve closes.

REQUIRED

REFERENCES:

None.

74 Points: 1.00 Unit 2 is operating at full power when the 2C RFP Flow transmitter begins failing down.

How will ACTUAL/APRM power respond prior to operator action and what actions are REQUIRED to gain control of RPV level?

A. Reactor Power will go up; take manual control of Low Flow FRV ONLY B. Reactor power will go up; take manual control of Main AND Low Flow FRVs C. Reactor power will go down; take manual control of Main FRVs ONLY D. Reactor power will go down; adjust FWLC setpoint to restore RPV level to desired band Answer: B ILT EXAM Page: 129 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 74 Details Question Type: Multiple Choice Topic: 74 - 259002 A1.03 System ID: 24231 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 259LN002.11

Reference:

DOA 0600-01 K/A: 259002 A1.03 3.8/3.8 K/A: Ability to predict and/or monitor changes in parameters associated with operating the Reactor Water Level Control controls including: Reactor Power CFR: 41.5 Safety Function: 2 PRA: Yes Level: High Pedigree: New History:

Comments:

A) Incorrect - Reactor Power will increase due to positive reactivity addition, however with LFRV already closed taking manual control will not reduce RPV water inventory.

B) Correct - Reactor Power will increase due to positive reactivity addition, taking Main and Low Flow FRVs to manual is required to discontinue the excess RPV water addition. Additional actions will be required to close the valves and match feed flow and steam flow to stabilize RPV level C) Incorrect - Reactor Power will increase due to positive reactivity addition. Main FRV and Low Flow FRV must be taken to manual to restore RPV level D) Incorrect - Reactor Power will increase due to positive reactivity addition. Main FRV and Low Flow FRV must be taken to manual to restore RPV level.

Adjusting setpoint may temporarily avert the RPV level rise.

ILT EXAM Page: 130 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 75 ID: 24232 Points: 1.00 A DBA LOCA has occurred on Unit 2 with the following plant conditions present:

• RPV level is -100 inches and rising slowly

• Torus water level is 8.0 feet and lowering slowly

• The torus leak is unisolable Given these conditions you would predict that the Core Spray pump discharge pressure would be

____________and the operator would throttle __________ the discharge valve.

A. Lowering, Close B. Lowering, Open C. Rising, Close D. Rising, Open Answer: A ILT EXAM Page: 131 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 75 Details Question Type: Multiple Choice Topic: 75 - 209001 A3.03 System ID: 24232 User ID: 24232 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 209LN001.06

Reference:

DOP 1400-02 K/A: 209001 A3.03 3.5/3.5 K/A: Ability to monitor automatic operations of the LPCS including: System Pressure CFR: 41.7 Safety Function: 2 PRA: No Level: High Pedigree: Bank History:

Comments:

As torus water level lowers, NPSH to CS pumps is reduced. Lowering flow is necessary to reduce vortexing/cavitation. As NPSH is reduced, system discharge pressure is reduced.

ILT EXAM Page: 132 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 1 ID: 24144 Points: 1.00 Given the following set of conditions on Unit 3:

• Single loop operation is in effect.

• 3A Recirc pump is secured.

• A leak develops causing Drywell pressure to rise to 3.3 psig, and it slowly continues to rise.

• LPCI loop select logic has just sent a trip signal to the 3B Recirc pump.

• RPV water level is currently 20 inches and slowly lowering.

• RPV pressure is currently 920 psig and slowly lowering.

Under these conditions, LPCI loop select logic will FIRST select a loop for injection when RPV (1) drops to (2) .

A. (1) pressure; (2) 350 psig B. (1) pressure; (2) 870 psig C. (1) water level; (2) +8 inches D. (1) water level; (2) -59 inches Answer: B ILT EXAM Page: 1 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 1 Details Question Type: Multiple Choice Topic: 01 - 295001.K2.05 System ID: 24144 User ID: 24144 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE203LN001.06

Reference:

12E-2437A, DAN 902-3 A-4 K/A: 295001.K2.05 3.2 / 3.6 K/A: Knowledge of the interrelations between Partial or Complete Loss of Forced Core Flow Circulation and the following: LPCI loop select logic: Plant-Specific CFR: 41.7 PRA: Yes Pedigree: Bank Level: High History: 06-1 CERT EXAM Explanation: With one pump running, a trip signal is sent to BOTH Recirc pumps immediately after loop select logic begins. To ensure accurate DP comparison is made between the two loops, the logic waits until RPV pressure drops below 900 psig to compare the loops. LPCI Loop select can be initiated due to either Drywell pressure or Reactor water level making all answers plausible. The question is higher order due to having to determine the impact of single loop operation on Loop Select logic.

REQUIRED

REFERENCE:

None.

ILT EXAM Page: 2 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 2 ID: 24145 Points: 1.00 Unit 2 was operating at near rated conditions, when the following occurred:

• Unit 2 experienced a Loss of Off-Site Power (LOOP).

• Unit 2 experiences a Reactor Scram

• Annunciator 902-8 E-4 2/3 DG OVERLOAD alarmed.

• Annunciator 902-8 D-4 2/3 DG GROUND FAULT alarmed.

• Annunciator 902-8 E-5 4KV BUS 24-1 OVERCURRENT alarmed.

• 2/3 DIESEL GENERATOR KILOWATT meter reads 2850 Kilowatts.

What action(s) is/are the NSO required to take?

A. Dispatch an EO to open 2/3 D/G to Bus 23-1 ACB.

B. Trip ALL loads connected to 2/3 DG, then close breakers one at a time to locate ground fault to prevent damage to the 2/3 EDG.

C. Trip ALL loads connected to 2/3 DG, then close breakers one at a time to locate ground fault to prevent damage to the load when Off-Site power restored.

D. Trip all UNNECESSARY loads connected to 2/3 DG, then close breakers one at a time to locate ground fault to prevent damage to the load when Off-Site power restored.

Answer: D ILT EXAM Page: 3 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 2 Details Question Type: Multiple Choice Topic: 02 - 295003.K3.04 System ID: 24145 User ID: 24145 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 3 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE264LN004.10

Reference:

DAN 902-8 D-4, DAN 902-8 E-4 K/A: 295003.K3.04 3.0 / 3.2 K/A: Knowledge of the reasons for the following responses as they apply to Partial or Complete Loss of AC: Ground isolation.

Level: High Pedigree: Bank History: 2007 NRC Explanation: The operator must determine which trips are bypassed with an automatic initiation signal vs a manual start. With the 2/3 EDG running via an AUTO start signal (LOOP), the actions required are to trip ALL unnecessary loads connected, then close breakers one at a time to locate ground fault to prevent damage to the load when Off-Site power restored.

REQUIRED

REFERENCES:

None.

3 Points: 1.00 Unit 3 was operating at near rated power, when Bus 33-1 tripped on overcurrent.

The 3A Pumpback compressor will have . . . . .

A. NO cooling water flow supplied to it.

B. FULL cooling water flow supplied to it.

C. partial cooling water flow supplied to it from 3A RBCCW Pump ONLY.

D. partial cooling water flow supplied to it from 3B RBCCW Pump ONLY.

Answer: B ILT EXAM Page: 4 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 3 Details Question Type: Multiple Choice Topic: 03 - 295018.K1.01 System ID: 24251 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 0.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 223LN001.03

Reference:

DOA 3700-01, DOP 1600-19 K/A: 295018.K1.01 3.5 / 3.6 K/A: Knowledge of the operational implications of the following concepts as they apply to Partial or Total Loss of CCW: Effects on component / system operations.

PRA: No CFR: 41.8 to 41.10 Level: Memory Pedigree: Bank History:

Explanation:

This question meets the K/A because a partial loss of CCW has occurred on Unit 3 however, the Unit 3 Pumpback air compressors are cooled by Unit 2 RBCCW which is not effected. This examines the knowledge of the effect (or lack thereof) on Unit 3 pumpback air compressor operations. If Unit 2 experienced a loss of RBCCW, Unit 2 and 3 pumpback air compressors would lose cooling.

This question also tests the differences between the Units at Dresden Station, as cooling water for the Unit 3 Pumpback air compressors can ONLY be supplied from UNIT 2 (not Unit 3).

When Bus 33-1 is de-energized, the 3A RBCCW pump would lose electrical power, but there is no loss of cooling to the Pumpbacks.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 5 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 4 ID: 24148 Points: 1.00 Given the following conditions:

• Unit 2 is at full power.

• 2A and 2B Instrument Air Compressors (IAC) are running.

• 2A IAC trips due to low lube oil pressure.

• Unit 2 Instrument Air pressure is 78 psig and dropping slowly.

• An operator has been dispatched to start and align 3C IAC to Unit 2.

The reason for this action is to prevent the __________.

A. FRVs from failing closed B. outboard MSIVs from drifting closed C. Target Rock from becoming inoperable in ERV mode D. Unit 2 Instrument Air to Unit 2 Service Air cross tie from opening Answer: B ILT EXAM Page: 6 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 4 Details Question Type: Multiple Choice Topic: 04 - 295019.K3.02 System ID: 24148 User ID: 24148 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 278LN001.12

Reference:

DOA 4700-01, LP DRE239LN001 K/A: 295019.AK3.02 3.5 / 3.4 K/A: Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR : Standby air compressor operation CFR: 41.5 Safety Function: 8 PRA: No Level: Memory Pedigree: Bank History:

Comments: High order due to having to determine the impact of loss of instrument air on the systems with U2 air not available and the flowpath for the use of U3 Instrument air.

a) Incorrect - The FRVs lock up on a loss of air pressure.

b) Correct - A reactor scram and manually closing the MSIVs is required on a loss of instrument air due to the potential of the MSIVs drifting closed.

c) Incorrect - The target rock would be inop in ERV mode with a loss of Drywell Pneumatics.

d) Incorrect - The Unit 2 IA to Unit 2 Service Air cross-tie would already be open (85 psig).

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 7 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 5 ID: 24153 Points: 1.00 Why is HPCI secured when the Torus level drops below 12 feet?

A. To prevent exceeding ECCS Vortex limit.

B. To prevent the suction from swapping to the Torus.

C. To prevent the HPCI exhaust line from being uncovered.

D. To conserve Torus water inventory for an ADS blowdown.

Answer: C Question 5 Details Question Type: Multiple Choice Topic: 05 - 295030.K2.01 System ID: 24153 User ID: 24153 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 2 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 29502LK01

Reference:

EPG B-7-51, TSG - 2, PSTG T/L-2.1 K/A: 295030.K2.01 3.8/3.9 K/A: Knowledge of the interrelations between LOW SUPPRESSION POOL WATER LEVEL and the following: HPCI: Plant-Specific.

CFR: 41.7 PRA: Yes Level: Memory Pedigree: Bank History: 2011 Cert Comments: DEOP 200-1 requires HPCI to be secured if you cannot hold torus level above 12 feet so that the HPCI exhaust remains underwater and does not exhaust steam to the Torus air space. ECCS Vortex limit is 10'4 inches for the conditions stated in the question.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 8 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 6 Points: 1.00 Which of the following describes the HIGHEST RPV pressure where the Low Pressure Coolant Injection (LPCI) system INJECTION flow is expected, following an auto initiation signal?

A. 300 psig B. 330 psig C. 360 psig D. 390 psig Answer: B Question 6 Details Question Type: Multiple Choice Topic: 06 - 295007.K2.03 System ID: 24154 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE206LN001.06

Reference:

DAN 902-3 A-4, DAN 902-3 H-16 K/A: 295007.K2.03 3.1 / 3.2 K/A: High Reactor Pressure: Knowledge of the interrelations between HIGH REACTOR PRESSURE and the following: RHR/LPCI Level: Memory Pedigree: Bank History: Clinton 2001 NRC, 2008 NRC Comments: LPCI and Core Spray systems will start upon an initiation signal, but the injection valves will not open until RPV pressure drops to <312.4 psig to 332.4psig. This makes 330 psig the highest pressure that injection will occur.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 9 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 7 ID: 24246 Points: 1.00 Unit 3 was operating at near rated power, with TIP traces being performed. The TIP is in the process of being driven to the full in-core position, in MANUAL.

Then the following occurs:

• A small leak develops inside the Drywell.

• Drywell pressure is 1.45 psig and steady.

Drywell Rad Monitors read as follows:

• 3-2419A: 15 R/hr

• 3-2419B: 15 R/hr Without Operator action, what is the expected response of the TIP system?

A. Detector will CONTINUE to CORE TOP position, then stop.

B. Detector will CONTINUE to CORE TOP position, then REVERSE direction and the ball valve remains open.

C. Detector will immediately REVERSE direction and ball valve will close when the detector is "in-shield".

D. Detector will CONTINUE to CORE TOP position, then REVERSE direction and the ball valve will close when the detector is "in-shield".

Answer: A ILT EXAM Page: 10 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 7 Details Question Type: Multiple Choice Topic: 07 - 295010.A2.03 System ID: 24246 User ID: 24246 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE223LN005.02

Reference:

DAN 902-5 E-5, DOP 0700-06 K/A: 295010.A2.03 3.3 / 3.6 K/A: Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE: Drywell radiation levels.

Level: Memory Pedigree: Bank History: 2006 NRC Explanation: While the Drywell pressure is an abnormal level (1.5 psig), it is not to the level to cause a Group II isolation (1.8 psig). TIPS will only withdraw to in-shield position, if a Group II was received (not received by Drywell pressure). Ball valves will close only if a Group II was received. The TIPS will not reverse direction given the conditions in the stem.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 11 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 8 ID: 24157 Points: 1.00 Unit 2 was operating at near rated power when a LOOP occurred, resulting in the following set of conditions:

• HPCI failed to inject.

• 2/3 EDG failed to start.

• Three (3) ADS valves are open.

• 2B Core Spray pump failed to start.

• RPV pressure is 275 psig and lowering.

• RPV water level is -110 inches and rising.

Core cooling is . . . . .

A. assured due to the core being submerged.

B. assured due to the steam cooling effects of the open SRVs.

C. NOT assured due to ONLY 3 ADS valves open.

D. NOT assured due to only two LPCI pumps injecting.

Answer: A ILT EXAM Page: 12 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 8 Details Question Type: Multiple Choice Topic: 08 - 203000.K5.02 System ID: 24157 User ID: 24157 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 3 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 299LN049-2

Reference:

TSG Attach L, DEOP 0010-00 K/A: 203000.K5.02 3.5 / 3.7 K/A: Knowledge of the operational implications of the following concepts as they apply to RHR/LPCI:

INJECTION MODE: Core cooling methods.

Level: High Pedigree: Bank History: 2009 Cert Explanation: With a LOOP, the Unit scrams. With the loss of HPCI, Bus 23-1 (2/3 EDG failure), and 2B Core Spray pump, the only possible injection source is C and D LPCI pumps. With RPV pressure <340, the LPCI pumps are allowed to inject. This injection is sufficient to provide core submergence. Top of active fuel is not reached until -143 inches (with RPV pressure less than 500 psig). Steam cooling would not come into effect unless RPV level was less than

-164 inches (with RPV pressure less than 500 psig).

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 13 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 9 Points: 1.00 Unit 2 was operating at near rated power and the Operating team is preparing to perform DOS 2300-03, HIGH PRESSURE COOLANT INJECTION SYSTEM OPERABILITY AND QUARTERLY IST VERIFICATION TEST.

Which of the following can be expected during the surveillance?

A Torus water . . . . .

A. level rise of 5 to 10 inches.

B. level drop of 5 to 10 inches.

C. temperature rise of 5 to 10°F.

D. temperature rise of 15 to 20°F.

Answer: C ILT EXAM Page: 14 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 9 Details Question Type: Multiple Choice Topic: 09 - 206000.A1.05 System ID: 24158 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE206LN001.02

Reference:

DOS 2300-03 K/A: 206000.A1.05 4.1 / 4.2 K/A: Ability to predict and/or monitor changes in parameters associated with operating the HIGH PRESSURE COOLANT INJECTION SYSTEM controls including: Suppression pool temperature.

Level: Memory Pedigree: Bank History: 2009 Cert Explanation: The answer can be found in the limitations and actions of the above procedure. When HPCI is run for a surveillance, its suction is from the Torus (not CSTs) and its discharge is to the Torus. HPCI does cause a small temperature increase (5 to 10 degrees),

but since the suction and discharge is the same, there is no significant change in Torus level.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 15 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 10 Points: 1.00 Unit 2 was operating at near rated power when an RPV water level transient occurred.

HPCI auto started and is being utilized for RPV water level control.

Several minutes later, annunciator 902-3 A-12, HPCI COND STG TK LVL LO LO alarmed.

What is the expected response of the HPCI system and what actions must the Operating team take to mitigate the consequences of the event?

A. The CST suction valve closes; Swap U2 HPCI suction to U3 Torus.

B. The U2 HPCI system loses suction but does NOT trip; Manually trip the U2 HPCI turbine.

C. Both U2 Torus suction valves open, THEN the CST suction valve closes; Place Makeup Demineralizer in service to raise CST water level, if available.

D. The CST suction valve remains open and both U2 Torus suction valves open; Place Makeup Demineralizer in service to raise CST water level, if available.

Answer: C ILT EXAM Page: 16 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 10 Details Question Type: Multiple Choice Topic: 10 - 206000.A2.09 System ID: 24159 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE206LN001.06

Reference:

DAN 902-3 A-12, A-11 K/A: 206000.A2.09 3.5 / 3.7 K/A: Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low condensate storage tank level:

BWR-2,3,4.

Level: Memory Pedigree: Bank History: 2009 NRC Explanation: With HPCI injecting, when the CST level low alarm comes in, the U2 Torus suction valves fully open THEN the CST suction valve closes (to maintain a suction path). Then the Operating team is directed by the procedure to refill the CSTs with the Makeup Demins, if available. With an auto start of the HPCI system the low suction pressure trip is bypassed as well as the 2301-8 will not close.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 17 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 11 ID: 24194 Points: 1.00 Given the following:

• A scram has occurred on U3.

• Rx level is +15 inches and dropping at 2 inches per minute.

• DW Pressure is 1.7 psig and rising 0.1 psig per minute.

Which DEOP 100 Entry condition will be reached FIRST, and which system will have automatic initiations/isolations when that entry condition is met?

ENTRY CONDITION SYSTEM AUTO ACTUATIONS AND/OR ISOLATIONS A. Rx Level SDC, RWCU B. Rx Level HPCI, RWCU C. DW Pressure HPCI, EDG's, RWCU D. DW Pressure HPCI, DW pneumatics, EDG's Answer: D ILT EXAM Page: 18 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 11 Details Question Type: Multiple Choice Topic: 11 - 295006.G4.02 System ID: 24194 User ID: 24194 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE209LN001.06

Reference:

DEOP 100, DAN 902(3)-5 D-11 K/A: 295006.G.4.02 SCRAM: Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions CFR:

Safety Function: 1 PRA: N/A Level: High Pedigree: New History: N/A Comments:

a) Is incorrect due to Rx level reaching the DEOP entry at 3.5 minutes b) Is incorrect due to Rx level reaching the DEOP entry at 3.5 minutes as well as HPCI does not initiate until

-59 inches c) Is incorrect due to RWCU's isolate on a group 3 for level but not on a 2 # signal d) Correct due to drywell pressure reaching 2# in 3 minutes causing HPCI to initiate, EDG's to start, and a GR II isolation causing loss of DW pneumatics REQUIRED

REFERENCES:

None.

ILT EXAM Page: 19 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 12 ID: 24203 Points: 1.00 Unit 2 was operating at 30% when a spurious turbine trip occurred.

Which of the following best describes the plant reactor pressure response with respect to this transient three minutes after the turbine tripped?

A. RPV pressure goes up and stabilizes at a higher than initial value B. RPV pressure goes down and stabilizes at a lower than initial value C. RPV pressure initially goes up then stabilizes at a lower than initial value.

D. RPV pressure initially goes down and stabilizes at a higher than initial value.

Answer: A ILT EXAM Page: 20 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 12 Details Question Type: Multiple Choice Topic: 12 - 295005 A02.04 System ID: 24203 User ID: 24203 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 245LN001.06.B

Reference:

UFSAR Figure 7.7-4a, DGP 2-3 K/A: 295005 A2.04 3.7/3.8 K/A: Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP:

Reactor Pressure CFR: 41.10 Safety Function: 3 PRA: No Level: High Pedigree: New History:

Comments: Pressure and power will initially go up due to loss of FW heating loss. After the plant stabilizes the pressure will be at a higher new value due to the positive bias and high value gate in the EHC logic.

A) Correct- RPV pressure will initially go up and then stabilize at a slightly higher value due to bypass valves being biased. This will cause the bypass valves to allow less steam flow from the RPV to the main condenser, therefore RPV pressure will be maintained slightly higher than the pre transient value.

B) Incorrect - RPV pressure will not go down initially.

Bypass valves will maintain RPV pressure slightly higher than the initial value.

C) Incorrect - RPV pressure will initially go up and then stabilize at a slightly higher value due to bypass valves being biased. This will cause the bypass valves to allow less steam flow from the RPV to the main condenser, therefore RPV pressure will be maintained slightly higher than the pre transient value.

D) Incorrect - RPV pressure initially go up with turbine stop and control valve closure. RPV pressure will not lower below the initial pre transient value during the time period specified.

ILT EXAM Page: 21 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 13 ID: 24265 Points: 1.00 The following alarms are received on the XL3 fire computer.

• 71-24 MAIN TRANSFORMER T3 SYSTEM FIRE

• 71-27 U-3 TRANSFORMERS DELUGE TROUBLE Upon arriving at the scene you would expect to find:

A. the local area temperature recorder reading 175 degrees ONLY.

B. a local high temperature alarm sounding on fire panel 2253-45 ONLY.

C. transformer 3 deluge system activated without a local alarm sounding on fire panel 2253-45.

D. transformer 3 deluge system activated, and local alarms sounding from system actuation and high temperature on fire panel 2253-45.

Answer: D Question 13 Details Question Type: Multiple Choice Topic: 13 -600000.G.1.19 System ID: 24266 User ID: 24265 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 286LN003.11

References:

DAN XL3 71-24 and 71-27 K/A: 600000.G.2.1.19 3.9/3.8 K/A: Plant Fire On Site: Ability to use plant computers to evaluate system or component status.

Level: High Pedigree: Bank History: N/A Comments: With both alarms in, a deluge condition on TR3 has occurred and not just a trouble alarm.

Therefor the actions of DAN SL-3, 71-24 are required to be verified: transformer 3 deluge system activated and local alarms sounding from system actuation and high temperature on fire panel 2253-45.

ILT EXAM Page: 22 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 14 ID: 24204 Points: 1.00 Unit 2 is operating at rated power when a transient occurred resulting in the following conditions:

? Drywell pressure is 6 psig

? All MSIVs are closed

? All rods are in

? RPV pressure is 600 psig and steady

? RPV level is trending down When is the EARLIEST an Emergency Depressurization can be performed and why?

A. When RPV level reaches -143" to maintain PCT < 1500F B. When RPV level reaches -170" to maintain PCT < 1500F C. When RPV level reaches -185" to maintain PCT < 1800F D. When RPV level reaches -204" to maintain PCT < 1800F Answer: B ILT EXAM Page: 23 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 14 Details Question Type: Multiple Choice Topic: 14 - 295031 K03.05 System ID: 24204 User ID: 24204 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 29501LK028

Reference:

EPG Appendix B Chapter 10, EPG Appendix B Chapter 17 K/A: 295031 K03.05 4.2/4.3 K/A: Knowledge of the reasons for the following responses as they apply to REACTOR LOW WATER LEVEL: Emergency Depressurization CFR: 41.5 Safety Function: 2 PRA: No Level: High Pedigree: New History:

Comments: While the bases for the blowdown is expected to be from memory, the candidate must work through the DEOP charts to determine when the blowdown is required.

A) Incorrect - With RPV pressure > 500 psig, TAF is

-170". ED due to RPV level prior to reaching TAF is not permitted by procedure B) Correct. With RPV pressure > 500 psig, TAF is

-170". Per EPGs, an ED may be performed when RPV level reaches TAF and MUST be performed prior to reaching MSCRWL (-164")

C) Incorrect - With injection sources available, Steam Cooling without injection is not permitted, therefore PCT limit of 1800F is not correct. Also, -185" is Minimum Zero Injection RPV Water Level when RPV Pressure is < 500 Psig D) Incorrect - With injection sources available, Steam Cooling without injection is not permitted, therefore PCT limit of 1800F is not correct. If Steam Cooling without injection were employed, the correct level to perform an ED would be -204".

ILT EXAM Page: 24 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 15 Points: 1.00 DOA 3300-02, Loss of Condenser Vacuum, actions are in progress due to lowering vacuum on Unit 2.

The Unit 2 NSO reports offgas system flow is HI.

Based on the offgas flow, what actions are directed by DOA 3300-02?

A. Bypass the filter building.

B. Secure hydrogen addition.

C. Swap cooler condenser trains.

D. Start all available condensate pumps.

Answer: A ILT EXAM Page: 25 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 15 Details Question Type: Multiple Choice Topic: 15 - 295002 A01.02 System ID: 24202 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 271LN001.11

Reference:

DOA 3300-02 K/A: 295002 A01.02 2.9/2.9 K/A: Ability to operate and/or monitor the following as they apply to LOSS OF MAIN CONDENSER VACUUM: Offgas System CFR: 41.7 Safety Function: 3 PRA: No Level: Memory Pedigree: New Comments:

A) Correct - Per DOA 3300-02, if offgas flow is HIGH, bypass the filter building.

B) Incorrect - Per DOA 3300-02 securing H2 addition would cause flow to increase flow by 20 scfm.

C) Incorrect - Condensate is the cooling for the Off Gas condenser but starting additional pumps would not help loss of vacuum.

D) Incorrect - DOA 3300-02 does not provide guidance for swap of cooler condenser trains.

ILT EXAM Page: 26 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 16 ID: 23505 Points: 1.00 The SPDS screen RADIATION RELEASE box will be _______ if the Liquid effluent radiation output signal is/are above the action setpoint.

A. RED B. BLUE C. CYAN D. YELLOW Answer: A Question 16 Details Question Type: Multiple Choice Topic: 16 - 295038.A.2.03 System ID: 23505 User ID: 23505 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 283LN002.03

Reference:

DOP 9950-17 K/A: 295038.A 2.03 3.5 / 4.3 K/A: High Off-Site Release Rate: Ability to determine and/or interpret the following as they apply to High Off-site Release Rate: Radiation levels.

Level: Memory Pedigree: Bank History: 2013 Cert Explanation: RED: SPDS parameter in Alarm condition.

BLUE: There are NOT a sufficient number of required instrumentation channels operable for monitoring a given SPDS parameter.

CYAN: SPDS parameter is invalid parameter.

YELLOW: Pre alarms (low and high).

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 27 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 17 ID: 331982 Points: 1.00 Which of the following statements describes how EDG will respond to a start signal if the Upper air start motor does NOT engage?

A. With only one of the two air start motors turning the engine, there is insufficient speed to start the engine.

B. Air will NOT be ported to the Air Start Relay valve to open the valve and allow the main air supply to drive the starting motors.

C. Without the Upper air start motor engaged, a vent path to atmosphere is NOT provided and the Lower air start motor will lock-up pneumatically.

D. The diesel generator will start normally. Two air start motors are provided for redundancy, but only one motor is needed to allow starting the engine.

Answer: B ILT EXAM Page: 28 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 17 Details Question Type: Multiple Choice Topic: 17 - 264000 K1.06 System ID: 24198 User ID: 331982 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Topic: 264000 K1.06 Objective: DRE264LN00.02

Reference:

DOS 6600-01 K/A: 264000 K1.06 3.2/3.2 K/A: EDGs: Knowledge of the physical connections and/or cause-effect relationships between EDGs and the following: Starting system.

CFR: 41.2 to 41.9 Safety Function: 6 PRA: Yes Level: Memory Pedigree: Bank History:

Comments:

When the D/G is started, the air start solenoid is powered, allowing air from the air receivers to pass through the solenoid valve to the pinion gear end of the lower start motor. This causes the pinion gear to move forward and engage the ring gear.

Movement of the pinion gear uncovers a port that allows air passage to the upper motor, engaging its pinion gear. Only when both pinion gears are engaged does air reach the air start relay valve that then opens the main air supply to drive each of the starting motors.

If the main air supply does NOT reach the air start motors in two seconds as sensed by the multiple start pressure switch, the air start solenoid will re-power to start the sequence again. This multiple start sequence will continue until the D/G reaches 200 RPM.

ILT EXAM Page: 29 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 18 ID: 323660 Points: 1.00 While performing the weekly battery checks of the Unit 2 250 Vdc safety related battery, which of the following values is an acceptable voltage if the battery charger is operation in the FLOAT mode?

A. 260.0 Vdc B. 262.0 Vdc C. 264.0 Vdc D. 266.0 Vdc Answer: C ILT EXAM Page: 30 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 18 Details Question Type: Multiple Choice Topic: 18 - 263000 G2.12 System ID: 24197 User ID: 323660 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Topic: 263000 G.2.12 Objective: 263LN001.14

Reference:

DOS 8300-07 K/A: 263000 G.2.12 3.7/4.1 K/A: DC Electrical Distribution; Knowledge of surveillance procedures.

CFR 41.10 Safety Function: 6 PRA: Yes Level: Memory Pedigree: Bank History: LGS NRC-05 Comments:

Per DOS 8300-07, Float voltage should be adjusted to within the range of 262.8 to 265.2 VDC.

a) incorrect below the lower limit of 262.8 VDC b) incorrect below the lower limit of 262.8 VDC c) correct above the lower limit of 262.8 VDC and below the upper limit of 265.2 VDC d) incorrect above the upper limit of 265.2 VDC ILT EXAM Page: 31 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 19 ID: 24258 Points: 1.00 Unit 2 and Unit 3 are operating at near rated power when Transmission Systems Operations (TSO) notifies the Control Room that the predicted post Unit trip with LOCA switchyard voltages are:

• Unit 2: 325 KV

• Unit 3: 350 KV What are the required actions from the Operating team AND the reason for these actions?

A. Adjust TR 32 Tap Changer; to restore system operability B. Adjust TR 32 Tap Changer; to reduce circulating currents C. Adjust TR 86 Tap Changer; to restore system operability D. Adjust TR 86 Tap Changer; to reduce circulating currents Answer: C ILT EXAM Page: 32 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 19 Details Question Type: Multiple Choice Topic: 19 - 700000.K1.03 System ID: 24258 User ID: 24258 Status: Active Always select on test: No Authorized for practice: No Difficulty: 0.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE262LN003.12

Reference:

DOA 6500-12 K/A: 700000.K1.03 3.3 / 3.4 K/A: Knowledge of the reasons for the following responses as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Actions contained in abnormal operating procedure for voltage and grid disturbances.

CFR: 41.10 Safety Function: 7 PRA: Yes Level: High Pedigree: Bank History: ILT 11-1 NRC Explanation: Given the voltages, only Unit 2 is below the procedural setpoint. TR-32 would be adjusted for Unit 3; TR-86 would be adjusted for Unit 2. The actions are to adjust the TR-86 Tap Changer (to position 31) to raise VOLTS (not VARs) to restore system operability.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 33 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 20 Points: 1.00 Which of the following sets of parameters are within the capacity of the Torus to accept a Blowdown?

Torus water level of ___(1)___ ft RPV pressure of ___(2)___ psig Torus bulk temperature of ___(3)___ oF A. (1) 16.5; (2) 500; (3) 180 B. (1) 16.5; (2) 600; (3) 175 C. (1) 17.5; (2) 350; (3) 170 D. (1) 17.5; (2) 400; (3) 150 Answer: D ILT EXAM Page: 34 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 20 Details Question Type: Multiple Choice Topic: 20 - 295026.G1.25 System ID: 24200 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE223LN001.12

Reference:

DEOP 200-01, TSG K/A: 295026.G1.25 3.9 / 4.2 K/A: SUPPRESSION POOL HIGH WATER TEMPERATURE: Ability to interpret reference materials, such as graphs, curves, tables, etc.

Level: High Pedigree: Bank History: 2010 NRC Explanation: The only above set of parameters that are NOT outside the capacity of the Torus to accept a Blowdown are a Torus Water level of 17.5 ft, with an RPV pressure of 400 psig and a Torus bulk temperature of 150oF. The Examinee will have to utilize both the Heat Capacity Limit curves to decide which set of parameters do NOT violate the curves.

REQUIRED

REFERENCES:

DEOP 200-1 figure M (Heat Capacity Limit) and TSG attachment G (Optimized Limit Curve).

ILT EXAM Page: 35 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 21 ID: 24196 Points: 1.00 U2 is operating at 90% Reactor Power when an inadvertant Group I occurs.

10 seconds later Rx water level will have_____ due to ______.

A. risen Iso Condenser initiation B. risen MSIV closure preventing inventory loss C. dropped ERV open actuation D. dropped Inventory shrink after the SCRAM Answer: D ILT EXAM Page: 36 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 21 Details Question Type: Multiple Choice Topic: 21 - 295020 K3.05 System ID: 24196 User ID: 24196 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 223LN005.12A

Reference:

UFSAR figure 15.2-2, UFSAR table 15.0-2 K/A: 295020 K3.05 K/A: Knowledge of the reasons for the following responses as they apply to Inadvertant Cont. Isolation:

Reactor water level response.

CFR: 41.5 Safety Function: 5 & 7 PRA: No Level: High Pedigree: New History:

Comments: Higher order due to having to evaluate system interrelationships and actuation time limits and the overall impact on reactor water level over time.

a) incorrect Iso condenser will not have initiated in the first 10 seconds b) incorrect MSIV will stop the loss of inventory, but level will still decrease due to shrinkage voids collapsing.

c) incorrect ERVs will not open with all rods in, with a group 1 at this power.

d) correct level will decrease due to shrink, and voids will collapse due to pressure spike.

ILT EXAM Page: 37 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 22 ID: 13188 Points: 1.00 Unit 3 was operating at 400 MWe, with the 3A CRD pump out of service for an oil change, when the following events occurred:

• Time 02:15:00 - Bus 34 experienced an overcurrent fault.

• Time 02:19:00 - CRD F-06 ACCUMULATOR TROUBLE light illuminated and is verified at position 28.

• Time 02:20:00 - CRD N-09 ACCUMULATOR TROUBLE light illuminated and is verified at position 32.

• Time 02:23:00 - EO reported CRD F-06 accumulator pressure was 900 psig.

• Time 02:24:00 - EO reported CRD N-09 accumulator pressure was 880 psig.

If the above conditions do NOT change, at time 02:45:00, what action(s) is/are required?

A. Place the Reactor Mode switch in SHUTDOWN and enter DGP 02-03.

B. Restore charging water header pressure to 940 psig by time 03:20:00.

C. Insert BOTH Control Rod F-06 AND N-09 with the Scram toggle switches.

D. Insert EITHER Control Rod F-06 OR N-09 with the Scram toggle switches.

Answer: A ILT EXAM Page: 38 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 22 Details Question Type: Multiple Choice Topic: 22 - 295022.K1.01 System ID: 24260 User ID: 13188 Status: Active Always select on test: No Authorized for practice: No Difficulty: 0.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE201LN001.12

Reference:

DOA 0300-01 K/A: 295022.K1.01 3.3 / 3.4 K/A: Knowledge of the operational implications of the following concepts as they apply to LOSS OF CRD PUMPS: Reactor pressure vs. rod insertion capability.

Level: High Pedigree: Bank History: 2008 NRC Comments: The candidate must understand with the reactor in mode 1 (indicated by full power) and a loss of all charging water pressure being lost for 20 minutes (indicated by 3A CRD pump out of service and 3B being lost when Bus 34 de-energizes) and a two or more CRD trouble alarms for low pressure, for CRDs not at position 00, the correct action is to place the mode switch in SHUTDOWN and enter DGP 02-03.

Restoring charging water pressure is not the action to take since the 20 minute procedural time has already expired.

Inserting any CRD with the scram toggle switch is not the appropriate action, since the reactor is NOT in mode 3, 4, or 5.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 39 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 23 ID: 24206 Points: 1.00 Unit 2 was operating at rated power when the following occurred:

? A SCRAM signal was received

? ALL rods did NOT fully insert

? ARI was initiated and was unsuccessful

? All APRMs indicate downscale

? Torus Temperature is 112F

? Drywell Pressure is 2.7 psig

? RPV level is being controlled at -40 inches If power was rising, when would the control room operators FIRST be required to TERMINATE and PREVENT INJECTION?

A. IRM reading 110 on range 8.

B. IRM reading 20 on range 9 C. IRM reading 60 on range 10 D. IRM reading 100 on range 10.

Answer: B ILT EXAM Page: 40 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 23 Details Question Type: Multiple Choice Topic: 23 - 295037 A1.06 System ID: 24206 User ID: 24206 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE215LN003.03

Reference:

As described in LP, DGP 1-1 K/A: 295037 A1.06 4.1/4.1 K/A: Ability to operate and/or monitor the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: Neutron monitoring system CFR: 41.7 Safety Function: 1 PRA:Yes Level: High Pedigree: New History:

Comments:

The operator must first determine the conditions necessary for a terminate and prevent order. Given in the stem all conditions with the exception of reactor power are given necessary to invoke the second override in the level control leg of DEOP 400-5. When Reactor power exceeds APRM downscale (6%,

177MWth), the requirements to terminate and prevent injection are met.

A) Incorrect - 110/125 on Range 8 equates to 110 MWth. APRM downscale is 177MWth B) Correct - 20/40 on Range 9 equates to 200 MWth.

APRM downscale is 177MWth C) Incorrect - 60/125 on Range 10 is 600MWth.

APRM downscale is 177MWth.

D) Incorrect - 100/125 on Range 10 is 1000MWth.

APRM downscale is 177MWth.

ILT EXAM Page: 41 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 24 ID: 24205 Points: 1.00 A steam leak has developed in the Unit 3 X-Area.

Which combination of temperature and trip channels will FIRST result in a PCIS actuation?

A. 180F sensed on channel A OR B B. 190F sensed on channel A OR B C. 210F sensed on channels A AND B D. 212F sensed on channels A AND B Answer: C ILT EXAM Page: 42 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 24 Details Question Type: Multiple Choice Topic: 24 - 295032 K01.03 System ID: 24205 User ID: 24205 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 223LN005.02 Ref: DAN 920(3)-5 D-9 K/A: 295032 K01.03 3.5/3.9 K/A: Knowledge of the operation implication of the following concepts as they apply to High Secondary Containment Area Temperature: Secondary Containment Leakage Detection CFR: 41.8 Safety Function: 5 PRA: No Level: Recall Pedigree: New History:

Comments: All distracters are plausible due to High Energy Line Break for the RWCU area and X-Area are actuated with a single channel high.

A) Incorrect - 180F is within the setpoint band for channel actuation, BOTH channels are required for PCIS actuation B) Incorrect - 190F is above the setpoint band for channel actuation however, BOTH channel are required for PCIS actuation C) Correct - Temperature is above setpoint and both channels will actuate resulting in a PCIS actuation D) Incorrect - Although conditions to actuate PCIS GRP I are met, this will occur after 210F therefore this answer is not the FIRST to occur.

ILT EXAM Page: 43 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 25 ID: 24201 Points: 1.00 Given the following conditions:

? Unit 2 startup in progress

? Rx Pressure is 950 psig

? Core flow is 30%

? Both recirc loops in operation A feedwater transient occurs on Unit 2.

Which one of the following violates a reactor core Safety Limit under these conditions?

A. MCPR at 1.08 B. Rx power rises to 30%

C. RPV level drops to -130 inches D. Steam dome pressure rises to 1300 psig Answer: A ILT EXAM Page: 44 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 25 Details Question Type: Multiple Choice Topic: 25 - 295014 G2.38 System ID: 24201 User ID: 24201 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 299LN001.03

Reference:

TS 2.0 K/A: 295014 G2.38 K/A: Inadvertent Reactivity Addition: Knowledge of conditions and limitations in the facility license.

Level: Memory Pedigree: New History:

Explanation: Per TS 2.1.1.2, MCPR is required to be

> 1.12 for 2 loop operation. The safety limit for level is TAF. Power must be < 25% if pressure is < 785 psig and core flow is > 10% rated core flow. Pressure safety limit is 1345 psig.

ILT EXAM Page: 45 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 26 Points: 1.00 Unit 2 was operating in MODE 3, with the following set of conditions:

• SDC in operation, with the 2B pump and heat exchanger in service.

• RBCCW in operation, with the 2B AND 2/3 pumps and heat exchangers in service.

The following annunciators are then received:

• Time 05:15:00; 902-4 A-23, SDC HX/FUEL POOL WTR TEMP HI.

• Time 05:25:00; 902-4 B-23, SDC PP TRIP.

Which of the following actions could have caused the SDC Pump to trip?

A. Loss of U2 250 VDC.

B. Bus 23-1 undervoltage.

C. Trip of the 2B RBCCW pump.

D. The 2B SDC pump discharge AOV drifting closed.

Answer: C ILT EXAM Page: 46 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 26 Details Question Type: Multiple Choice Topic: 26 - 295021.K2.04 System ID: 24149 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 3 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE205LN001.06

Reference:

DAN 902-4 B-23 K/A: 295021.K2.04 3.0 / 3.1 K/A: Knowledge of the interrelations between LOSS OF SHUTDOWN COOLING and the following: Component cooling water systems: Plant-Specific.

Level: High Pedigree: Bank History: 2008 NRC Comments: With the conditions given, only a trip of the 2B RBCCW pump would cause the SDC pump to trip.

This occurs because after the RBCCW pump trips, the SDC temperatures start to rise (as indicated by both annunciators). When the SDC temperature reaches 339oF at the suction of the pumps, this causes the SDC pump to trip. Loss of U2 250 VDC would not effect the system flows. U2 SDC cooling valves are fed from U3 250 VDC and would fail as is. Closing of the 2B SDC pump discharge valve is incorrect as it would cause SDC pump suction pressure to increase (which is the opposite of the SDC pump trip on LOW suction pressure). Bus 23-1 undervoltage is incorrect as the pumps listed as operating in the initial conditions are powered from Bus 24-1 (common misconception of power supplies since both the SDC and RBCCW systems have 3 pumps - with opposite power supplies from each other).

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 47 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 27 ID: 295023.K1.03 Points: 1.00 Unit 3 is in Mode 5 with fuel moves in progress. SRM counts begin to steadily go up and continue to go up over a 5 minute period in the quadrant containing the fuel moves.

How are fuel moves affected?

A. Stop ALL fuel moves. The grapple may be lowered, but NOT raised.

B. Stop ALL fuel moves. The grapple may be raised, but NOT lowered.

C. Stop ALL fuel moves. Do NOT attempt to raise or lower the grapple.

D. Fuel moves may continue. SRM response is normal for these conditions.

Answer: C ILT EXAM Page: 48 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 27 Details Question Type: Multiple Choice Topic: 27 - 295023.K1.03 System ID: 24256 User ID: 295023.K1.03 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE272LN002.06

Reference:

DOA 0800-03, DFP 800-1 K/A: 295023K1.03 3.7/4.0 K/A: Knowledge of the operational implications of the following concepts as they apply to REFUELING ACCIDENTS: Inadvertant criticality CFR: 41.8 to 41.10 PRA: Yes Level: High Pedigree: New History: None.

Explanation:

Per DOA 0800-03, conditions in the stem should be interpreted as inadvertant criticality. Immediate actions of DOA 0800-03 require operators to suspend fuel moves and NEITHER raise nor lower the grapple.

This question meets the high cognitive level criteria because it requires the candidate to determine inadvertant criticality has occurred and then determine the correct operational implications.

ILT EXAM Page: 49 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 28 ID: 295025.A2.04 Points: 1.00 A transient occurred on Unit 2 resulting in the following conditions:

Unit 2 125vDC Bus 2B-1 is tripped and will NOT reclose Reactor Pressure is 1050 psig and trending up The Unit Supervisor has directed you verify Torus level is within band for ERV operations.

How is Torus Level determined?

A. Wide Range Torus Level indication on 902-3 panel ONLY.

B. Narrow Range Torus Level indication on 902-3 panel ONLY.

C. BOTH Narrow and Wide Range Torus Level control room panel indications are available.

D. ALL control room panel indications for Torus Level are lost; an operator must be dispatched to verify Torus Level using the local sightglass.

Answer: A ILT EXAM Page: 50 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 28 Details Question Type: Multiple Choice Topic: 28 - 295025.A2.04 System ID: 24252 User ID: 295025.A2.04 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: 29501LK100 K/A: 295025.A2.04 3.9/3.9 K/A: Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE:

Suppression Pool Level

Reference:

DOP 6800-05, 12E-6822 Level: High PRA: No Pedigree: New History: None.

Comments:

This question examines the candidate's knowledge of the suppression pool capability to accept discharge from the ERVs as well as the control room indications available on a loss of power. 125vDC Bus 2B-1 feeds the DC portion of ATS Panel 2202-73B. Upon a loss of 125vDC Bus 2B-1, the narrow range torus level indication as well as HI and LO level annunciators are lost. Wide Range Torus level indications are still available on the 902-3 panel. Use of the local sight glass is an option, however, this distracter is not correct because control room indications of Torus Level are still available. Computer points for NR torus level are lost due to the DC power failure as well.

ILT EXAM Page: 51 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 29 Points: 1.00 Unit 2 was operating at near rated power, when a LOCA occurred. The following conditions exist:

• RPV pressure is 200 psig and lowering slowly.

• Indicated Wide Range RPV water level is 80 inches and rising slowly.

• Drywell pressure is 5.5 psig and rising slowly.

• Drywell temperature is 300oF and steady.

Wide Range RPV water level instrumentation is . . . . .

A. accurate and can be used for trending.

B. NOT accurate and CAN be used for trending, since WR level is above indicated usable level.

C. NOT accurate and CANNOT be used for trending, since WR level is below indicated usable level.

D. NOT accurate and CANNOT be used for trending since D/W temperature is above saturation temperature.

Answer: A ILT EXAM Page: 52 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 29 Details Question Type: Multiple Choice Topic: 29 - 295028.K1.01 System ID: 24152 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE216LN001.12

Reference:

DEOP 100 table 'A', EPG B-5-3 K/A: 295028.K1.01 3.5 / 3.7 K/A: Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL TEMPERATURE: Reactor water level measurement.

Level: High Pedigree: Bank History: 2009 Cert Comments: Utilizing DEOP 100 chart B, the parameters are below the line, so the instruments would be accurate in this situation, AND the instrument could be used to determine the level trend. Changes in instrument run temperatures can produce on-scale readings on some instruments even when the actual level is below their variable leg taps. Since DP is not affected by level changes below the variable leg tap, the indicated level would then no longer reflect changes in actual level (could not be used for trending).

REQUIRED

REFERENCES:

DEOP charts, with the entry conditions blanked out.

ILT EXAM Page: 53 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 30 ID: 24160 Points: 1.00 Unit 2 was operating at near rated power, when a LOCA occurred, resulting in the following set of conditions:

• Torus temperature is 109°F and steady.

• Drywell pressure is 10 psig and lowering slowly.

• Torus level is 15 ft.

• Off site power is available and grid voltage is stable.

• Core Spray flow is fluctuating between 2000 gpm to 4000 gpm.

• Core Spray discharge pressure is fluctuating between 150 psig and 325 psig.

What is the cause of the Core Spray indications?

A. Vortexing due to high ECCS flow.

B. ECCS suction strainers are plugging.

C. A loss of NPSH caused by Torus temperature.

D. Leak in the piping downstream of the PP DISCH VLV MO 2-1402-25A.

Answer: B ILT EXAM Page: 54 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 30 Details Question Type: Multiple Choice Topic: 30 - 209001.K5.01 System ID: 24160 User ID: 24160 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 4 Point Value: 1.00 Cross Reference Number:

Num Field 1: 0.00 Num Field 2: 0.00 Text Field:

Comments: Objective: DRE209LN001.08

Reference:

NRC Bulletin 93-02 K/A: 209001.K5.01 2.6 / 2.7 K/A: Knowledge of the operational implications of the following concepts as they apply to LOW PRESSURE CORE SPRAY SYSTEM: Indications of pump cavitation.

Level: High Pedigree: Bank History: 2007 NRC, 2011 Cert Explanation:

A) Torus parameters are within the operating curves to prevent vortexing from occurring B) With the fluctuations in pump flow and discharge pressure, it is an indication that the suction strainers are the failure mode.

C) Torus temperature is well within the band of ECCS operating curves at this Drywell pressure.

D) A leak downstream of the disch valve would cause an increase in flow and amps without fluctuations.

REQUIRED

REFERENCES:

DEOP Charts with entry conditions blanked out.

ILT EXAM Page: 55 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 31 ID: 24248 Points: 1.00 Unit 2 was operating at near rated power, when a fire caused an overcurrent condition on Bus 29.

Subsequently a feedwater transient caused the RPV to scram on RPV water level.

The SRO directs you to inject SBLC as an Alternate Injection System per DOP 1100-02, INJECTION OF SBLC Hard Card.

What would be the expected system response?

A. NEITHER Squib valve would fire B. 'A' Squib valve would fire ONLY C. 'B' Squib valve would fire ONLY D. BOTH Squib valves would fire Answer: B ILT EXAM Page: 56 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 31 Details Question Type: Multiple Choice Topic: 31 - 211000.A3.03 System ID: 24248 User ID: 24248 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 4 Point Value: 1.00 Cross Reference Number:

Num Field 1: 0.00 Num Field 2: 0.00 Text Field:

Comments: Objective: DRE211LN001.02

Reference:

M-33, DOP 6700-13 K/A: 211000.A3.03 3.8 / 3.8 K/A: Ability to monitor automatic operations of the SLC including: Explosive valves indicating lights Level: High Pedigree: Bank History: 2011 Cert Comments:

This question meets the K/A because it examines the candidate's ability to determine the status of the squib valves following a loss of power. The status of the squib valve will be determined through the change in light indications on the control panel.

b) With a loss of Bus 29, MCC 29-1 would be lost.

MCC 29-1 is the power supply to both the 'B' pump and squib valve, thus neither of them could become energized. 'A' pump and squib is powered from MCC 28-1, so when the control switch is taken to position "SYS 1 & 2" (per the hard card) they would become energized and operate as designed.

a) The candidate may choose neither if they did not understand the power supplies c) The candidate may choose 'B' if they didn't know that the hard card has the NSO take the control switch to SYS 1 & 2, as opposed to SYS 1 or SYS 2.

d) The candidate may chose both if they did not understand the power supplies.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 57 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 32 Points: 1.00 Unit 2 was operating at near rated power, when APRM 3 failed downscale.

A Half Scram will be generated on RPS ___(1)___ if IRM ___(2)___ becomes INOP.

A. (1) A; (2) 13 B. (1) B; (2) 13 C. (1) A; (2) 15 D. (1) B; (2) 15 Answer: A ILT EXAM Page: 58 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 32 Details Question Type: Multiple Choice Topic: 32 - 215003.K1.01 System ID: 24162 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE215LN003.06

Reference:

DOP 0700-02, DAN 902-5 C-6 K/A: 215003.K1.01 3.9 / 3.9 K/A: Knowledge of the physical connections and/or cause effect relationships between INTERMEDIATE RANGE MONITOR (IRM) SYSTEM and the following:

RPS.

Level: Memory Pedigree: Bank History: 2010 NRC Explanation: A Half Scram is generated if an APRM downscale is received concurrent with its companion IRM being INOP. In this case APRM 3 and the companion IRM 13, cause a half-scram on RPS "A" side.

REQUIRED

REFERENCES:

None.

33 ID: 24163 Points: 1.00 A fully withdrawn SRM detector transmits 300 pulses in one second.

100 of these pulses are cause by neutrons.

200 of the pulses are caused by gammas.

What is the expected reading on the 902-5 SRM LEVEL meter?

A. 100 cps B. 200 cps C. 300 cps D. 400 cps Answer: A ILT EXAM Page: 59 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 33 Details Question Type: Multiple Choice Topic: 33 - 215004.K4.03 System ID: 24163 User ID: 24163 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE215LN004.03

Reference:

LP DRE215LN004.03 K/A: 215004.K4.03 2.5 / 2.5 K/A: Knowledge of SOURCE RANGE MONITOR (SRM) SYSTEM design feature(s) and/or interlocks which provide for the following: Gamma compensation.

Level: Memory Pedigree: Bank History: 2011 Cert Comments: The purpose of the pulse height discriminator is to provide gamma compensation.

The PHD sets a threshold level. The neutron pulses are large enough to pass through the threshold level and are allowed to be counted. The gamma pulses are smaller than the threshold value and are not passed on to be counted, therefore they are eliminated.

The pulse pre-amplifier boosts the signal strength to separate out noise and get the pulses to the control room. SRMs count neutron pulses, not gamma pulses. The PHD only eliminates the smaller, gamma pulses.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 60 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 34 Points: 1.00 Unit 2 was operating at near rated power, when an ATWS occurred and the following conditions exist:

? Reactor power is 5%.

? ALL APRM downscale lights are illuminated.

? RPV level is -60 inches.

? Drywell pressure is 15 psig.

? Drywell AND Torus sprays have been initiated.

Given the above conditions, which of the following actions taken prior to timeout of the 120 second timer will PREVENT all automatic actuation of ADS?

A. Restore drywell pressure below 2 psig.

B. Maintaining RPV pressure below 150 psig.

C. Placing low pressure ECCS pumps in PTL.

D. Depressing AND releasing the TIMER RESET pushbutton.

Answer: C ILT EXAM Page: 61 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 34 Details Question Type: Multiple Choice Topic: 34 - 218000.K4.03 System ID: 24164 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 4 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE218LN001.06

Reference:

DAN 902-3 B-13 K/A: 218000.K4.03 3.8/4.0 K/A: Automatic Depressurization System: Knowledge of the physical connections and/or cause effect relationships between AUTOMATIC DEPRESSURIZATION SYSTEM and the following:

Low pressure core spray: Plant-Specific.

Level: High Pedigree: Bank History: 2008 NRC, 2011 Cert Comments: With RPV level lo-lo and/or Drywell pressure high AND any low pressure pump (LPCI or CS) running (discharge pressure greater than 100 psig) is a permissive to seal in the 120 sec ADS timer (DAN 902-3 B-13 references this as one of the conditions needed).

Once drywell pressure is above 2 psig, it seals in until reset (will not prevent actuation).

Reactor pressure is not an ADS permissive, but is a common misconception that the ADS will not open when RPV pressure is too low (150 psig).

Depressing and releasing the TIMER RESET pushbutton would only reset the timer and delay the ADS actuation (not prevent).

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 62 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 35 Points: 1.00 Unit 2 was operating at near rated power, when the following occurred sequentially:

• RPV pressure rose to 1085 psig for 30 seconds and then stabilized at 1005 psig.

• A fire in Unit 2 125 VDC Bus 2B-1 caused it to de-energize.

The effect this has on the plant is . . . . .

A. ALL Isolation Condenser isolation valves will close.

B. ONLY the Isolation Condenser VENT valves will close.

C. A loss of Control Room indications for components powered from Bus 23 AND Bus 24.

D. A loss of Control Room indications for components powered from Bus 23-1 AND Bus 24-1.

Answer: A ILT EXAM Page: 63 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 35 Details Question Type: Multiple Choice Topic: 35 - 223002.K6.05 System ID: 24165 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE207LN001.12

Reference:

DAN 902-3 H-2, 12E-2506 sheets 1-3 K/A: 223002.K6.05 3.0 / 3.3 K/A: Knowledge of the effect that a loss or malfunction of the following will have on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF: Containment instrumentation.

Level: High Pedigree: Bank History: 2010 Cert Explanation: With reactor pressure of 1085 psig, for 30 seconds, the Isolation Condenser will have actuated (1070 for 17 seconds). The power supplies for the Group 5 (Iso Cond) isolation instrumentation are 125VDC distribution panels 2A-1 & 2B-1. A Group 5 isolation is initiated whenever there is a loss of EITHER power supply circuits (de-energize to actuate). A Group 5 causes ALL isolation valves to close (NOT just the vent valves). Dist panel 2B-1 is normal control power to (and a loss of control room indication would only happen for) Bus 24 and Bus 24-1, and NOT Bus 23 (2A-1) OR Bus 23-1 (Rx Bldg Dist Pnl).

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 64 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 36 ID: 24166 Points: 1.00 Given the following plant conditions:

• Unit 3 is at 73% power.

• Torus bulk temperature is slowly rising.

• Div 2 torus water temperature Bay 1 is 95°F and slowly rising.

• DOA 0250-01, RELIEF VALVE FAILURE, has been entered for 3-203-3B ERV leaking by.

• Attempts to close the 3-203-3B ERV from the control room have failed.

The HVO has pulled the 3-203-3B ERV control power fuses.

All of the following indications can be used to verify the 3-203-3B ERV is closed EXCEPT:

A. Torus temperature recorder trend B. Control switch valve position indication lights C. Valve leak detection temperature recorder trend D. Acoustic monitor valve position indicating lights Answer: B ILT EXAM Page: 65 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 36 Details Question Type: Multiple Choice Topic: 36 - 239002 K5.04 System ID: 24166 User ID: 24166 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 239LN001.03

Reference:

DOA 0250-01; 12E-3461 & 3461A K/A: 239002 K5.04 3.3/3.5 Knowledge or the operational implications of the following concepts as they apply to SRV: Tail pipe temperature monitoring.

CFR:

Safety Function: 3 PRA: Yes Level: High Pedigree: Bank History: None Comments:

Options A,C, and D are all valid indications to confirm ERV closure. Option B is invalid due to ERV fuses being removed as indicated in the stem. Since the fuses are pulled, the CS indicating lights are extinguished.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 66 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 37 ID: 24249 Points: 1.00 U3 is operating at full power when a storm causes a loss of 345KV BUS 8.

What is the impact on the U3 4KV distribution system?

A. Bus 31 AND 33 trip then fast xfer to TR 31 B. Bus 32 AND 34 trip then fast xfer to TR 31 C. Bus 31 AND 33 trip then fast xfer to TR 32 D. Bus 32 AND 34 trip then fast xfer to TR 32 Answer: B Question 37 Details Question Type: Multiple Choice Topic: 37 - 262001.K6.02 System ID: 24249 User ID: 24249 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 262LN001.06

Reference:

DAN 903-8 E-2 K/A: 262001.K6.02 3.6/3.9 K/A: Knowledge of the effect that a loss or malfunction of the following will have on the A.C. Electrical Distribution: Off-Site Power.

Safety Function: 6 PRA: Yes Level: High Pedigree: New History:

Comments:

A) is incorrect, Bus 8 feeds the U3 division 2 buses.

B) is correct, Bus 8 feeds the U3 division 2 buses. On a trip a fast transfer occurs within 6 cycles.

C) is incorrect, Bus 8 feeds the U3 division 2 buses.

D) is incorrect, Bus 8 feeds the U3 division 2 buses, but TR 32 is dead with a loss of BUS 8 ILT EXAM Page: 67 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 38 Points: 1.00 Unit 3 was operating at near rated power, when Bus 37 experienced an overcurrent condition.

Which of the following Instrument Air Compressor(s) will lose its/their power supply?

A. 3A ONLY B. 3B ONLY C. 3C ONLY D. 3B and 3C ONLY Answer: D Question 38 Details Question Type: Multiple Choice Topic: 38 - 300000.K2.01 System ID: 24168 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE278LN001.02

Reference:

DOA 4700-01 K/A: 300000.K2.01 2.8 / 2.8 K/A: Knowledge of electrical power supplies to the following: Instrument air compressor.

Level: Memory Pedigree: Bank History: 2009 NRC Explanation: The power supplies are 3A - Bus 36, 3B -

Bus 37, and 3C - Bus 37.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 68 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 39 ID: 13452 Points: 1.00 Unit 2 was operating at near rated conditions, when the following occurred:

• 2A Recirc pump temperatures are rising rapidly.

• Annunciator 902-4 G-3 2A RECIRC PP SEAL CLG WTR FLOW LO alarms.

All other RBCCW parameters are normal.

The expected plant response is . . . . .

A. 2A Recirc pump will go to hold.

B. 2A Recirc pump seals and bearings could be damaged within one minute.

C. 2A Recirc pump seals will operate normally as long as CRD flow is maintained.

D. RWCU system could isolate since cooling is lost to the non-regenerative heat exchanger.

Answer: B ILT EXAM Page: 69 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 39 Details Question Type: Multiple Choice Topic: 39 - 400000.K3.01 System ID: 24255 User ID: 13452 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 3 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE202LN001.08

Reference:

DOA 3700-1, DAN 902-4 G-3, P+ID M-20 K/A: 400000.K3.01 2.9/3.3 K/A: Knowledge of the effect that a loss or malfunction of the CCWS will have on the following.

Level: High Pedigree: Bank History: 2005 NRC Comments: The conditions in the stem indicate a loss of RBCCW to the Recirc pump seals. All other RBCCW parameters are stable. Per the DOA if cooling flow is lost and cannot be restored within one minute the operator must trip the recirc pumps. In the discussion section of the DOA it is stated that loss of cooling flow resulting from failures in the RBCCW system will cause damage to plant equipment. If RBCCW flow cannot be restored to the Recirc pumps within one minute, damage may occur to the pump seal and bearings.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 70 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 40 ID: 2461 Points: 1.00 Unit 3 is conducting a special test with the Main Generator conditions as follows:

? Real load is 800 MWe

? Terminal Voltage is 17.1 kV

? Reactive Load is 0 MVAR

? Voltage Regulator Mode Switch is in MANUAL

? Generator hydrogen pressure is 30 psig If an operator placed the Voltage Regulator Mode Switch to AUTO, and the voltage regulator failed to its MINIMUM limit for the current voltage, which of the following indicates the final value of Main Generator reactive loading three minutes later (i.e. plant stable)?

(Assume terminal voltage remains constant.)

A. positive (+) 220 MVAR B. negative (-) 100 MVAR C. negative (-) 120 MVAR D. negative (-) 220 MVAR Answer: B ILT EXAM Page: 71 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 40 Details Question Type: Multiple Choice Topic: 40 - 245000.A1.08 System ID: 24261 User ID: 2461 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 245LN003.11

Reference:

DOP 6400-08 K/A: 245000.A1.08 2.5 / 2.7 K/A: Ability to predict and/or monitor changes in parameters associated with operating the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS controls including: Generator output voltage/reactive load CFR: 41.5 Safety Function: 6 PRA: No Level: High Pedigree: Bank History: ILT 11-1 NRC Comments:The examinee must identify the correct Minimum Excitation Limiter (MEL) curve from the supplied references. The MEL limits the excitation dependent on the current terminal voltage of the generator. The point on the graph will move straight down the 800MWE line until it reaches the 17.1 Kv limit Distracters indicates a misunderstanding of system operation or inability to read the graph.

REQUIRED

REFERENCES:

Figures 5, 6 & 7 from DOP 6400-08 ILT EXAM Page: 72 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 41 Points: 1.00 Unit 3 was in STARTUP, with the following conditions:

• Step 20 of the CRSP contains Control Rods H-8, F-10, H-6 and K-8 with a rod limit from position 08 to 12.

• Control Rod H-8 is withdrawn to position 12.

• Control Rod F-10 is withdrawn to position 10.

The NSO then selects Control Rod H-6, which is currently at position 08.

Prior to selecting the rod, what color will Control Rod H-6 be indicated on the RWM?

A. Red B. Cyan C. White D. Green Answer: D ILT EXAM Page: 73 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 41 Details Question Type: Multiple Choice Topic: 41 - 201006.A3.01 System ID: 24171 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1: 0.00 Num Field 2: 0.00 Text Field:

Comments: Objective: DRE201LN006.06

Reference:

DOP 0400-02 K/A: 201006.A3.01 3.2/3.1 K/A: Ability to monitor automatic operations of the RWM including: System window and light indications:

P-Spec(Not-BWR6).

Level: Memory Pedigree: Bank History: 2002 Quad NRC, 2009 NRC Explanation: Control rods are in red when they are out of sequence, green when they are in the current latched step or selected for rod exercising, white if they are not the rod selected for exercising or not part of the in-sequence step. H-6 should remain green the entire time. Control Rods are indicated in Cyan when they are taken O.O.S.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 74 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 42 ID: 24172 Points: 1.00 Unit 2 was operating at near rated power when Bus 29 experienced an overcurrent condition.

What affect does this have on the Unit 2 LPCI system?

A loss of the Div ___(x)___ ability to ___(y)___ , from the Main Control Room.

A. (x) 1 ONLY; (y) initiate Torus Cooling ONLY B. (x) 1 ONLY; (y) initiate Torus Cooling, spray the Drywell, AND spray the Torus C. (x) 2 ONLY; (y) initiate Torus Cooling ONLY D. (x) 2 ONLY; (y) spray the Drywell, AND spray the Torus Answer: D ILT EXAM Page: 75 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 42 Details Question Type: Multiple Choice Topic: 42 - 219000.K1.05 System ID: 24172 User ID: 24172 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE203LN001.02

Reference:

Valve label power supplies in C/R, load list in LP DRE 203LN001, DOS 1500-1 K/A: 219000.K1.05 3.5 / 3.6 K/A: Knowledge of the physical connections and/or cause effect relationships between RHR/LPCI:

TORUS/SUPPRESSION POOL COOLING MODE and the following: A.C. electrical power.

Level: High Pedigree: Bank History: 2013 Cert Explanation:

This question meets the K/A because it examines the candidate's understanding of Torus Cooling flow paths and the loss of ability to perform TORUS COOLING operation caused by a loss of A.C. electrical power.

Bus 29 powers MCC 29-1, which if lost removes power from the following: Torus Cooling valves (20 and 38),

Drywell spray valves (27 and 28), and Torus Spray valves (18 and 19) for Division II only are fed from MCC 29-4.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 76 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 43 Points: 1.00 Unit 2 was operating at near rated power when a loss of coolant resulted in a Reactor Scram.

The following conditions exist:

• Drywell pressure is 18 psig.

• RPV water level is 10 inches.

• 902-8 E-5, 4 KV BUS 24-1 OVERCURRENT annunciator illuminated.

• 10 minutes later, the US notices that the Division II CAM H2/O2 system is NOT working.

What action(s) is/are required to initiate the CAM system?

A. Reset the Bus 29 UV device ONLY.

B. Place the OFF-STANDBY-ANALYZE switch to ANALYZE.

C. X-tie Bus 28 to Bus 29 the Reset the Bus 29 UV device.

D. Close the feed breaker to MCC 29-1, then place the OFF-STANDBY-ANALYZE switch to ANALYZE.

Answer: C ILT EXAM Page: 77 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 43 Details Question Type: Multiple Choice Topic: 43 - 223001.K6.11 System ID: 24173 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1: 0.00 Num Field 2: 0.00 Text Field:

Comments: Objective: DRE223LN006.08

Reference:

DAN 902-8 H-3, DGA-12, DOP 2400-01, DOP 7000-07 K/A: 223001.K6.11 3.0 / 3.2 K/A: Knowledge of the effect that a loss or malfunction of the following will have on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES: A.C.

electrical distribution.

Level: High Pedigree: Bank History: 2008 NRC Comments: When Bus 24-1 goes overcurrent, Bus 24-1 and Bus 29 are de-energized and will load shed some equipment. During load shed conditions the breaker to the MCC 29-1 (which powers div 2 CAM) does not load shed. Once power is restored to Bus 29 (Xtie Bus 28 to Bus 29), the Bus 29 UV relay must be reset and then MCC 29-1 will be re-energized. The CAM feed breaker does NOT trip and with an ECCS signal still present, the system will start up automatically as soon as power is restored.

This meets the K/a because the examinee has to have knowledge of the effect of an OC trip on Bus 24 on the load shed of Bus 29.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 78 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 44 Points: 1.00 Unit 2 was operating at near rated power, when the following occurred:

• Offgas flow dropped approximately 100 scfm.

• Offgas Recombiner temperature dropped approximately 600oF.

The Unit Supervisor has directed entering DOP 5400-14, EXTINGUISHING AN OFF GAS FIRE.

Which of the following actions are performed prior to executing the procedure above?

A. Ensure adequate margin in the Instrument Air system, to extinguish the fire.

B. Initiate Station Fire Watches for the Offgas system, to identify potential insulation fires.

C. Start all available Circ Water pumps to limit Condensate temperature rise from reduced Condenser vacuum.

D. Drain loop seals upstream of the fire, to allow for intrusion of Instrument Air to extinguish the fire.

Answer: C ILT EXAM Page: 79 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 44 Details Question Type: Multiple Choice Topic: 44 - 271000.A2.11 System ID: 24174 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE271LN001.08

Reference:

DOP 5400-14 K/A: 271000.A2.11 2.8 / 2.9 K/A: Offgas System: Ability to (a) predict the impacts of the following on the OFFGAS SYSTEM: and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: OFFGAS SYSTEM LOW FLOW Level: High Pedigree: Bank History: 2009 NRC Explanation: All available Circ Water pumps should be started to limit Condensate temperature rise from reduced Condenser vacuum.

A fire watch would be an acceptable practice, but is not required.

Service Air is used to extinguish an Offgas fire (NOT Instrument Air).

Loop seals are to be ensured filled (not drained).

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 80 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 45 Points: 1.00 Unit 2 was operating at near rated power with MCC 28-2 out of service, when the following annunciators are received:

902-8 B-8, 120/240 ESS BUS VOLT LO.

902-8 E-10, 120/240 ESS BUS ON EMERG SPLY.

An impact of this transient is that the _______ rad monitor(s) become(s) de-energized.

A. Channel 'A' Off Gas B. Channel 'A' Refuel Floor C. 2B and 2D Main Steam Line (MSL)

D. Outboard channel 'B' Reactor Building and Fuel Pool Answer: C ILT EXAM Page: 81 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 45 Details Question Type: Multiple Choice Topic: 45 - 272000.K2.01 System ID: 24175 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE272LN002.02

Reference:

DOA 0500-05, DOA 6800-01, DANs 902-8 B-8 and E-10 K/A: 272000.K2.01 2.5 / 2.8 K/A: Radiation Monitoring System: Knowledge of electrical power supplies to the following: Main steamline radiation monitors.

Level: High Pedigree: Bank History: 2009 Cert Comments: With MCC 28-2 O.O.S, the RESERVE power supply to the U2 ESS bus is lost. The two alarms that are received indicate that the ESS Bus ABT has transferred (irregardless of the reserve power supply being energized or not). These events remove ALL power from the ESS bus, which is the power supply for the B and D MSL rad monitors.

Channel A Off Gas rad monitor and Channel A Refuel Floor rad monitor are powered from RPS Bus A, which is still energized (from MCC 29-2 via the B RPS MG Set - cross divisional power).

Outboard channel B RBX & fuel pool high rad aux relays are powered from the Inst Bus (which is still energized from MCC 25-2).

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 82 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 46 Points: 1.00 A hydraulic ATWS has occurred on Unit 2.

The Unit Supervisor has directed you to perform repeated scram resets per DEOP 0500-05.

Which of the following describes the MINIMUM electrical safety precautions required to perform this task?

All metal removed and ...

A. safety glasses B. safety glasses, long sleeve cotton shirt and rubber gloves C. safety glasses, electrical safety coat, face shield and rubber gloves D. safety glasses, long sleave cotton shirt, electrical safety coat and rubber gloves Answer: B ILT EXAM Page: 83 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 46 Details Question Type: Multiple Choice Topic: 46 - Generic.1.26 System ID: 24189 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 295L105

Reference:

SA-AA-129 K/A: Generic 2.1.26 3.4 / 3.6 K/A: Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

CFR: 41.10 PRA: No Level: Memory Pedigree: Bank History: ILT 11-1 NRC Comments: SA-AA-129 states that for the voltage in the area being worked in for DEOP 500-5 the minimum PPE is all metal removed, long sleeve cotton shirt, safety glasses and rubber gloves REQUIRED

REFERENCES:

None.

47 Points: 1.00 You are about to take the shift as a Unit 2 NSO. The last time you were on shift was seven (7) days ago.

To meet the requirements of OP-AA-112-101, What is the MINIMUM number of days of turnover logs that MUST be reviewed prior to making a relief?

A. 1 day.

B. 2 days.

C. 4 days.

D. 7 days.

Answer: C ILT EXAM Page: 84 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 47 Details Question Type: Multiple Choice Topic: 47 - Generic.1.03 System ID: 24190 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 29900LK022

Reference:

OP-AA-112-101 K/A: Generic.1.3 3.7 / 3.9 K/A: Knowledge of shift or short-term relief turnover practices.

Level: Memory Pedigree: Bank History: 2008 NRC Comments: OP-AA-112-101 requires Reactor Operator log review through the last previous date on shift, or the preceding four days, whichever is less. The distracters for 1 or 2 days are common misconceptions, based on days off during normal rotation. The 7 day distracter would be the choice (incorrect) based on not being on shift for the last 7 days.

REQUIRED

REFERENCES:

None.

48 ID: 24191 Points: 1.00 A locked throttle valve in a safety related system is to be positioned three turns CLOSED FROM FULL OPEN.

Per OP-AA-108-101-1001, COMPONENT POSITION DETERMINATION, which of the following verification techniques is required for the valve's position?

A. Peer Check B. Double Verification C. Concurrent Verification D. Independent Verification Answer: C ILT EXAM Page: 85 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 48 Details Question Type: Multiple Choice Topic: 48 - Generic.1.29 System ID: 24191 User ID: 24191 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 29900LK051

References:

OP-AA-108-101-1001, HU-AA-101 K/A: Generic.1.29 4.1 / 4.0 K/A: Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

Level: Memory Pedigree: Bank History: 2008 NRC Comments: Per OP-AA-108-101-1001 for component position determination, concurrent verification is required for throttle valve position.

REQUIRED

REFERENCES:

None.

49 Points: 1.00 Unit 2 and Unit 3 are operating at rated power.

IAW OP-AA-109-101, Clearance and Tagging, which of the following equipment isolations requires an EXCEPTIONAL clearance order if single point of isolation is used?

A. 2B TBCCW Pump.

B. RWCU Aux pump.

C. Waste Collector Pump.

D. Stator Cooling Hx tube side.

Answer: B ILT EXAM Page: 86 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 49 Details Question Type: Multiple Choice Topic: 49 - Generic.2.13 System ID: 24192 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 29900LK012

Reference:

OP-AA-109-101 K/A: Generic.2.13 4.1 / 4.3 K/A: Knowledge of tagging and clearance procedures.

Level: High Pedigree: New History: None.

Comments: Per OP-AA-109-101 attachment 2 the RWCU Aux Pump would meet the EXCEPTION of lack of dual valve isolation when isolation greater than 500psig or greater than 200 degrees fahrenheit.

REQUIRED

REFERENCES:

None.

50 Points: 1.00 A Unit 2 Drywell entry is required to be made.

Which of the following statements are correct, with regards to dose concerns, for the personnel making the Drywell entry?

A. Reactor MUST be shutdown.

B. Reactor power is 34% OR lower.

C. If in operation, the HPCI system MUST be secured.

D. If in operation, the RWCU system MUST be secured.

Answer: B ILT EXAM Page: 87 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 50 Details Question Type: Multiple Choice Topic: 50 - Generic.3.12 System ID: 24193 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 299LK0028

Reference:

DOP 1600-22 K/A: Generic.3.12 3.2/3.7 K/A: Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Level: Memory Pedigree: Bank History: 2007 NRC Explanation: Reactor power must be 34.2% or less for entry (not shutdown). The RWCU and HPCI systems should NOT be secured if running, since this would change conditions.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 88 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 51 Points: 1.00 Unit 2 was in STARTUP with only the 2C SDC pump in operation, when the 2C SDC pump tripped on high suction temperature.

One minute later, the U2 125 VDC Rx Bldg Distribution Panel de-energized, due to a fire.

Which picture below correctly identifies the proper indications for the above situation?

A. A B. B C. C D. D ILT EXAM Page: 89 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Answer: A Question 51 Details Question Type: Multiple Choice Topic: 51 - 205000.K6.02 System ID: 22570 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 3 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE205LN001.12

Reference:

DOA 6900-T1 K/A: 205000.K6.02 2.7 / 2.9 K/A: Knowledge fo the effect that a loss or malfunction of the following will have on the Shutdown Cooling:

D.C. electrical power.

Level: High Pedigree: Bank History: NRC, 2009 NRC Explanation: With a loss of the U2 125 VDC Rx Bldg Dist Panel, all control power is lost to Bus 23-1. The 2A and 2C SDC pumps are powered from Bus 23-1.

When control power is lost to Bus 23-1, all indicating lights for the 2A and 2C SDC pumps are lost. The 2B SDC pump will still have indicating lights, as it is powered from Bus 24-1, which receives its control power from 2B-1 Dist Panel. The 2B SDC pump does not auto start in this situation, so there will be no ON indicating light for it.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 90 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 52 Points: 1.00 Unit 2 was operating at near rated power when the following events occurred, sequentially:

? Drywell pressure increased to 3.0 psig.

? Annunciator 902-3 H-4, CORE SPRAY SYS B TIMERS NOT HOME is received.

? Bus 24 to 24-1 Feed and Main Feed Breakers trip.

With no further operation actions taken, when power is restored to Bus 24-1, the 2B Core Spray pump will . . . . .

A. start as soon as the Bus 24-1 undervoltage condition clears.

B. start 5 seconds after the Bus 24-1 undervoltage condition clears.

C. start 10 seconds after the Bus 24-1 undervoltage condition clears.

D. start 15 seconds after the Bus 24-1 undervoltage condition clears.

Answer: C ILT EXAM Page: 91 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 52 Details Question Type: Multiple Choice Topic: 52 - 262001 A3.04 System ID: 24208 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE262LN001.06

Reference:

DAN 902-3 H-4 K/A: 262001 A3.04 3.4 / 3.6 K/A: Ability to monitor automatic operations of the AC Electrical Distribution including: Load Sequencing.

Level: High Pedigree: New History:

Comments: A high DW pressure signal causes the Reactor to scram, Core Spray pumps start, and EDGs to start. A loss of power to Bus 24 causes the temporary loss of Bus 24-1. The U2 EDG will close on to Bus 24-1. The 2B Core Spray Pump will have lost power on the loss of 24-1. The 2B Core Spray pump breaker on Bus 24-1 opens and will reclose 10 seconds after the Bus 24-1 is re-energized by the U2 EDG due to load sequencing.

REQUIRED

REFERENCES:

None.

53 Points: 1.00 Which of the following plant electrical systems supplies power to the detector and electronic circuitry of the the Source Range Monitoring (SRM) System?

A. 24 VDC station batteries B. 120 V ESS Bus C. 120 V Instrument Bus D. 125 VDC station batteries Answer: A ILT EXAM Page: 92 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 53 Details Question Type: Multiple Choice Topic: 53 - 215004.K2.01 System ID: 24209 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE 215LN004.02

Reference:

UFSAR 8.3.2.3, DOA 6900-01 K/A: 215004.K2.01 2.6/2.8 K/A: Knowledge of electrical power supplies to the following: SRM channels/detectors.

Level: Memory Pedigree: Bank History:

Comment: Per FSAR section 8.3.2.3 24/48/V System is supplied from the 24/48 dc battery system. DOA 6900-01 also list the SRMs as a system supplied by 24/48 dc.

ILT EXAM Page: 93 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 54 Points: 1.00 Unit 2 was operating at near rated power, with the following conditions:

? The Unit 2A 125 VDC Battery Charger is supplying the Unit 2 125 VDC system.

? The Unit 2/3 250 VDC Battery Charger is supplying the Unit 2 250 VDC system.

Then a fire caused Bus 28 to de-energize.

(1) What effect will this have on the batteries AND (2) what actions can be taken to mitigate the transient?

A. (1) The Unit 2 125 VDC batteries ONLY will begin to discharge; (2) place the Unit 2 125 VDC Battery Charger in service.

B. (1) The Unit 2 250 VDC batteries ONLY will begin to discharge; (2) place the Unit 2 250 VDC Battery Charger in service.

C. (1) The Unit 2 125 AND 250 VDC batteries will begin to discharge; (2) place the Unit 2 125 AND Unit 2 250 VDC Battery Chargers in service.

D. (1) The Unit 2 125 AND 250 VDC batteries will begin to discharge; (2) place the Unit 2 125 Alternate Battery AND Unit 2 250 VDC Battery Charger in service.

Answer: A ILT EXAM Page: 94 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 54 Details Question Type: Multiple Choice Topic: 54 - 295004.A1.01 System ID: 24210 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE263LN001.02

Reference:

DOA 6900-04, DOA 6900-T1, DOA 6900-02 K/A: 295004.A1.01 3.3 / 3.4 K/A: Ability to operate and/or monitor the following as they apply to Partial or Total Loss of DC Pwr: D.C.

electrical distribution systems.

CFR: 41.7 Safety Function: 6 PRA: Yes Level: High Pedigree: Bank History: ILT 11-1 NRC Comments: Explanation: With the 2A charger (MCC 28-2) supplying the 125 VDC system and the 2/3 charger (MCC 29-2 or 39-2) supplying the 250 VDC system, a loss of Bus 28 will cause ONLY the 125 VDC 2A charger to lose power, which will cause the 125 VDC batteries to begin to discharge. Transferring the 125 VDC system to the Unit 2 125 VDC charger is the correct action.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 95 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 55 ID: 24250 Points: 1.00 Which one of the following describes the reason for placing the ISOL COND RX INLET VLV 2-1301 local selector switch on panel 2202-76 in VLV1 position?

A. To disconnect local control circuits from the valve.

B. To disconnect Control Room control circuits from the valve.

C. To isolate wire runs to meet divisional physical separation criteria.

D. To prevent overloading the associated DG during a design basis LOCA.

Answer: B Question 55 Details Question Type: Multiple Choice Topic: 55 - 295016.K2.02 System ID: 24250 User ID: 24250 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 29501LP083

Reference:

DSSP 0100-CR K/A: 295016.K2.02 4.0/4.1 K/A: Knowledge of the interrelations between Control Room Abandonment and the following: Local control stations: Plant-Specific.

Level: Memory Pedigree: New History:

Comments:

Placing the ISO COND '1' and '4' valves in the VLV1 position, removes the control circuit from the Main Control Room, in case of fire/evacuation. Operating this switch does not change the physical routing or location of equipment. This switch switches valve power from MCCs 28-1 to/from 38-1, which are both powered from the 2/3 EDG.

ILT EXAM Page: 96 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 56 ID: 24263 Points: 1.00 Unit 2 was operating at near rated power when a spike occurs resulting in annunciator 902-5 C-12, CHANNEL 1-3 APRM HI-HI / INOP illuminated.

An NSO reported that APRM 1 is pegged full scale.

What actions are required to return RPS to its pre-spike state and reset the alarms?

1) Depress the TRIP RESET pushbutton on the 902-37 panel.

2) Turn the SCRAM RESET switch to the GP 1-4 position 902-5 panel.

3) Turn the SCRAM RESET switch to the GP 2-3 position 902-5 panel.

4) Place the APRM BYPASS switch in the CH-1 position on the 902-5 panel.

A. 1, 2, 3, AND 4 B. 2 and 3 ONLY C. 2 and 4 ONLY D. 2, 3, and 4 ONLY Answer: D ILT EXAM Page: 97 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 56 Details Question Type: Multiple Choice Topic: 56 - 215005.K3.01 System ID: 24263 User ID: 24263 Status: Active Always select on test: No Authorized for practice: No Difficulty: 0.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE215LN005.08

Reference:

DAN 902-5 C-12, DOP 0500-07 K/A: 215005.K3.01 4.0/4.0 K/A: Knowledge of the effect that a loss or malfunction of the APRM/LPRM will have on following: RPS.

Level: Memory Pedigree: Bank History: 2013 Cert Explanation: The actions to reset the half scram is to first bypass the alarming APRM and then place the SCRAM RESET switch in BOTH positions.

Depressing the TRIP RESET pushbutton on the 902-37 panel only clears the Hi-Hi indicator light on that panel and is NOT required.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 98 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 57 Points: 1.00 Unit 2 was operating at rated power when 2-203-1D, D Inboard MSIV, failed shut. The following conditions are currently present:

• RPV level is being controlled at -40" in automatic

• RPV pressure is 1040 psig and being controlled with the IC

• All attempts to open the 2-4399-74, CLEAN DEMIN VLV have failed Per DOP 1300-03, Manual Operation of the Isolation Condenser, the preferred RPV pressure control method is:

A. ADS valve operation B. HPCI operation in the pressure control mode C. IC operation with contaminated demin make up D. IC operation with fire suppression system make up Answer: B ILT EXAM Page: 99 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 57 Details Question Type: Multiple Choice Topic: 57 - 207000.A2.07 System ID: 24214 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 207LN001.08

Reference:

DOP 1300-03 K/A: 207000 A2.07 3.5/3.5 K/A: Ability to (a) predict the impacts of the following on the Isolation (Emergency) Condenser; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Valve Closures-BWR 2,3 CFR: 41.5 Safety Function: 4 PRA: Yes Level: High Pedigree: New History:

Comments:

This question meets the K/A because it examines the candidate's ability to PREDICT the IC will require shell side make up and use DOP 1300-03 knowledge to determine necessary pressure control methodology.

With the conditions stated in the stem, a PCIS GRP I has occurred due to high steam flow. A reactor scram followed with a failure of all control rods to fully insert.

IC shell side makeup is required due to inventory loss.

With the failure of MO 2-4399-74 normal shell side makeup is unavailable. Per DOP 1300-03, clean demin is the preferred source with IC makeup pumps unavailable, however the flowpath for clean demin also requires the use of MO 2-4399-74 thereby making IC with clean demin an incorrect choice. Since RPV level is being maintained by FWLC in auto, HPCI is NOT needed for RPV level control and therefore available in the pressure control mode. Per DOP 1300-03, this is the preferred RPV pressure control method. ADS valve operations are available, but not preferred. IC operation with Fire suppression makeup is also available, however this option is pursued after ADS valve operation.

ILT EXAM Page: 100 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 58 Points: 1.00 Unit 2 was operating at rated power when a small LOCA occurred resulting in Drywell Pressure of 1.8 psig and increasing 0.1 psig/min.

The US has directed you to establish Torus Cooling using Division 1 LPCI. In order to establish flow through the LPCI heat exchanger, you must....

A. wait 30 seconds following LPCI initiation and then close the 2-1501-11A, Hx Bypass vlv.

B. wait 30 seconds following LPCI initiation and then close the 2-1501-11B, Hx Bypass vlv.

C. wait 5 minutes following LPCI initiation and then close the 2-1501-11A, Hx Bypass vlv.

D. wait 5 minutes following LPCI initiation and then close the 2-1501-11B, Hx Bypass vlv.

Answer: A ILT EXAM Page: 101 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 58 Details Question Type: Multiple Choice Topic: 58 - 295024.A.1.13 System ID: 24215 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 203LN001.06 Ref: UFSAR Figure 7.3-2B K/A: 295024 A1.13 3.6/3.6 K/A: Ability to operate and/or monitor the following as they apply to High Drywell Pressure: Suppression Pool Cooling CFR: 41.7 Safety Function: 5 PRA: Yes Level: Memory Pedigree: New History:

Comments:

A - Correct. 2-1501-11A is the LPCI/CCSW heat exchanger bypass for Division 1. This valve is interlocked open for 30 seconds following an initiation signal.

B - Incorrect. 2-1501-11B is the LPCI/CCSW heat exchanger bypass for Division 2. This valve is interlocked open for 30 seconds following an initiation signal.

C - Incorrect. 2-1501-11A is the LPCI/CCSW heat exchanger bypass for Division 1. This valve is interlocked open for 30 seconds following an initiation signal. 5 minutes is a plausible distracter based on additional LPCI interlocks.

D - Incorrect. 2-1501-11B is the LPCI/CCSW heat exchanger bypass for Division B. This valve is interlocked open for 30 seconds following an initiation signal. 5 minutes is a plausible distracter based on additional LPCI interlocks ILT EXAM Page: 102 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 59 Points: 1.00 An ATWS occurred on Unit 2 with the following conditions present:

• DEOP 400-2 has been executed due to being unable to hold RPV level above -164"

• 1 ERV failed to open

• RPV Pressure is above the Minimum Steam Cooling Pressure

• SBLC Pump discharge pressure is 400 psig

• SBLC switch is selected to System 1 Is SBLC injecting into the RPV and what is the status of the SBLC FLOW light on the 902-5 panel?

A. No. Flow light is illuminated.

B. No. Flow light is extinguished.

C. Yes. Flow light is illuminated.

D. Yes. Flow light is extinguished.

Answer: B ILT EXAM Page: 103 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 59 Details Question Type: Multiple Choice Topic: 59 - 211000.A4.05 System ID: 24216 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 211LN001.11

Reference:

M-33, DEOP 400-5 K/A: 211000 A04.05 4.1/4.0 K/A: Ability to manually operate and/or monitor in the control room: Flow Indication: Plant Specific CFR: 41.7 Safety Function: 1 PRA: Yes Level: High Pedigree: New Comments:

A - Incorrect - With RPV pressure above 420 psig (Minimum Steam Cooling Pressure with 4 ERVs open),

and SBLC discharge pressure of 400 psig, SBLC is NOT injecting. The SBLC relief valve has lifted and the flow transmitter is downstream of the relief valve, therefore no flow is indicated and the light will be extinguished.

B - Correct - With RPV pressure above 420 psig (Minimum Steam Cooling Pressure with 4 ERVs open),

and SBLC discharge pressure of 400 psig, SBLC is NOT injecting. The SBLC relief valve has lifted and the flow transmitter is downstream of the relief valve, therefore no flow is indicated and the light will be extinguished.

C - Incorrect - With RPV pressure above 420 psig (Minimum Steam Cooling Pressure with 4 ERVs open),

and SBLC discharge pressure of 400 psig, SBLC is NOT injecting. The SBLC relief valve has lifted and the flow transmitter is downstream of the relief valve, therefore no flow is indicated and the light will be extinguished.

D - Incorrect - With RPV pressure above 420 psig (Minimum Steam Cooling Pressure with 4 ERVs open),

and SBLC discharge pressure of 400 psig, SBLC is NOT injecting. The SBLC relief valve has lifted and the flow transmitter is downstream of the relief valve, therefore no flow is indicated and the light will be ILT EXAM Page: 104 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC extinguished.

60 ID: 24217 Points: 1.00 You are inspecting a Fire Extinguisher type that does NOT have a pressure gauge and discover that the seal is missing/broken. What action is required per DFPS 4114-15?

A. Reseal the extinguisher ONLY.

B. Verify alternate fire suppression is available.

C. Verify correct weight of the extinguisher and replace the seal.

D. Establish fire watch until approved extinguisher is in place.

Answer: C Question 60 Details Question Type: Multiple Choice Topic: 60 - Generic 4.25 System ID: 24217 User ID: 24217 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE286286LN001.14

Reference:

DFPS 4114-15 K/A: Generic 2.4.25 3.3/3.7 K/A: Knowledge of fire protection procedures.

CFR: 41.10 Level: Memory Pedigree: Bank History: LSG NRC 05 Comments:

Per DFPS 4114-15 Annual Fire Extinguisher Inspection, if you are performing extinguisher checks on an extinguisher type without a pressure gauge and discover that the seal is broken, then the correct action is to weigh the extinguisher and replace the seal per DFPP 4114-04. Replacing the extinguisher is not required. Only logging and continuing inspection is not the correct action. Verifying alternate fire suppression is not required by the procedure.

ILT EXAM Page: 105 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 61 Points: 1.00 You have been tasked as the Unit 2 NSO with transferring ESS bus power from MCC 28-2 to Bus 25.

Per DOP 6800-01, to prevent the RWCU system from isolating during the transfer you are REQUIRED to....

A. Place ONLY the RWCU INBD ISOL MN STEAM BYP SW to the Bypass position B. Place ONLY the RWCU OUTBD ISOL MN STEAM BYP SW to the Bypass position C. Place RWCU INBD ISOL MN STEAM BYP SW AND RWCU OUTBD ISOL MN STEAM BYP SW to the bypass positions D. Perform a controlled shutdown of the RWCU system per DOP 1200-03, RWCU SYSTEM OPERATION WITH THE REACTOR AT PRESSURE Answer: C ILT EXAM Page: 106 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 61 Details Question Type: Multiple Choice Topic: 61 - 262002.A4.01 System ID: 24218 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 204LN001.11

Reference:

DOP 6800-01 K/A: 262002 A4.01 2.8/3.1 K/A: Ability to manually operate and/or monitor in the control room: Transfer from alternative source to preferred source CFR: 41.7 Safety Function: 6 PRA: No Level: Memory Pedigree: New History:

Comments:

This question meets the K/A because it examines the candidate's ability to manually operate control room panels to accomplish ESS bus transfer from alternative to preferred source.

When transferring ESS Bus power supplies DOP 6800-01 requires the manipulation of both the inboard and outboard main steam bypass switches to the bypass position. The use of one switch is not permitted per DOP 6800-01. DOP 6800-01 provides no direction to perform an orderly shutdown of RWCU.

ILT EXAM Page: 107 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 62 Points: 1.00 An ATWS has occurred on Unit 3. The Unit Supervisor has directed you to pull RPS scram solenoid fuses per DEOP 0500-05.

Where are these fuses located and why is it important to remove them in the specified order?

A. 903-15 and 903-17 panels; To prevent core oscillations.

B. 903-16 and 903-17 panels; To prevent core oscillations.

C. 903-15 and 903-17 panels; To prevent a direct vent path from the RPV to the reactor building.

D. 903-16 and 903-17 panels; To prevent a direct vent path from the RPV to the reactor building.

Answer: C ILT EXAM Page: 108 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 62 Details Question Type: Multiple Choice Topic: 62 - 212000 G.1.30 System ID: 24219 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 29502LK094

Reference:

DEOP 0500-05 K/A: 212000.G.1.30 4.4/4.0 K/A: Ability to locate and operate components, including local controls CFR: 41.7 Safety Function: 1 PRA: No Level: Memory Pedigree: New History:

Comments:

DEOP 0500-05 directs removal of RPS scram fuses from the 902(3)-15 and 902(3)-17 panels. DEOP 0500-05 caution warns the operator that pulling the fuses in the incorrect sequence may result in a discharge path from the RPV to the reactor building via the scram discharge volume vents and drains.

Uncontrolled control rod insertion is incorrect because the operator is taking actions to insert the control rods, therefore this in NOT uncontrolled. 903-16 and 903-17 panels are valid distracters due to the proximity of the panels.

ILT EXAM Page: 109 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 63 ID: 24220 Points: 1.00 Unit 2 was at full power when a transient occurred causing an entry into an 'ALERT' EP classification.

You have been assigned the Operations Shift Communicator role.

Per EP-AA-112-100 F05 Whose permission is required(if any), to transfer ENS notification responsibility to the TSC/EOF?

A. TSC Director B. Shift Manager C. Unit Supervisor D. No permission required Answer: B Question 63 Details Question Type: Multiple Choice Topic: 63 - Generic 4.37 System ID: 24220 User ID: 24220 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: EP-G-105.2b

Reference:

EP-AA-112-100-F05 K/A: Generic 4.37 K/A: Knowledge of the lines of authority during implementation of the emergency plan.

CFR: 41.10 PRA: N/A Level: High Pedigree: New History:

Comments: Per EP-AA-112-100-F-05 step 2.2.D, when directed by the Shift Manager, then Contact the TSC/EOF ENS Communicator, using the ERF Telephone Directory to transfer ENS notification responsibilities.

ILT EXAM Page: 110 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 64 Points: 1.00 DOS 7500-02 is in progress for post maintenance testing for the 'A' SBGT, when 902-3 F-14, RX BLDG VENT CH A RAD HI-HI is received. The NSO reports both CH A and CH B Rx Bldg Vent monitors on the 902-10 panel indicate 5.8 mr/hr.

What procedural actions are required?

A. Place C/S for running SBGT train to PRI B. Place C/S for non-running SBGT train to PRI C. Verify ONLY U2 RB Vent damper isolation has occurred.

D. Verify PCIS GRP III has occurred and SBGT flow rate is within limits Answer: B ILT EXAM Page: 111 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 64 Details Question Type: Multiple Choice Topic: 64 - 261000.A2.13 System ID: 24221 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 261LN001.08

Reference:

DOP 7500-01, DOS 7500-02 K/A: 261000 A2.13 3.4/3.7 K/A: Ability to (a) predict the impacts of the following on the SGTS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High secondary containment ventilation exhaust radiation CFR: 41.5 Safety Function: 9 PRA: No Level: High Pedigree: New History:

Comments: The operator must determine that the set point for the alarm is also the setpoint for RB Vent trip and SBGT auto start. With the A Train already running the operator must understand that the non-running train must be placed in primary to allow for proper operation with all automatic functions activated.

A - Incorrect. With BOTH channels A and B of RB Vent Radiation monitors above 4 mr/hr SBGT receives an autostart signal. Per DOS 7500-02, if an autostart signal is received during post maintenance testing, the operator is directed to place the CS for the running train to STBY.

B - Correct. With BOTH channels A and B of RB Vent Radiation monitors above 4 mr/hr SBGT receives an autostart signal. Per DOS 7500-02, if an autostart signal is received during post maintenance testing, the operator is directed to place the CS for the non-running train to PRI.

C - Incorrect. DOS 7500-02 directs the operator in these conditions to verify the RB Vent isolation on the 923-4 panel vice the 923-5 panel D - Incorrect. The conditions in the stem represent conditions necessary to actuate PCIS GRP II. A PCIS ILT EXAM Page: 112 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC GRP III signal is not present.

65 ID: 24222 Points: 1.00 U2 was at full power when the following occurs:

• A scram signal is received

• Reactor power is 10%

• A steam leak is occurring making the Rx Building inaccessible Under these conditions, how will the crew raise CRD Drive Water pressure?

A. open the CRD 2-0302-8 valve B. close the CRD 2-0302-8 valve C. open the CRD 2-0301-25 valve D. close the CRD 2-0301-25 valve Answer: B ILT EXAM Page: 113 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 65 Details Question Type: Multiple Choice Topic: 65 - 201001.A4.04 System ID: 24222 User ID: 24222 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE 201LN001.06

Reference:

DGP 2-3 K/A: 201001.A4.04 3.1/3.0 K/A: Ability to manually operate and/or monitor in the control room: Drive water header pressure control valve Level: High History: New Comments: This question requires an understanding of the flow paths for the CRD hydraulic system.

a) opening the CRD 2-0302-8 valve will decrease drive water pressure b) closing the CRD 2-0302-8 valve is the correct answer. This will cause drive water pressure to increase and is guided by DGP 2-3 c) opening the CRD 2-0301-25 valve will allow flow through to the charging water header decreasing drive water pressure. The valve is located in the reactor building and not accessible due to the steam leak d) closing the CRD 2-0301-25 would isolate flow to the charging water header and increase flow to the drive water header. The valve is located in the reactor building and not accessible due to the steam leak ILT EXAM Page: 114 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 66 ID: 24223 Points: 1.00 Unit 3 is operating at near rated power, with a Control Rod selected for withdrawal, when APRMs 3 and 5 failed downscale simultaneously.

RBM(s) ___(x)___ auto bypassed AND the operator is required to bypass APRM(s) ___(y)___ to allow rod movement.

A. (x) 8 ONLY; (y) 3 ONLY B. (x) 8 ONLY; (y) 5 ONLY C. (x) 7 ONLY; (y) 3 AND 5 D. (x) 7 AND 8; (y) 3 AND 5 Answer: C ILT EXAM Page: 115 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 66 Details Question Type: Multiple Choice Topic: 66 - 215002.A2.03 System ID: 24223 User ID: 24223 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1: 0.00 Num Field 2: 0.00 Text Field:

Comments: Objective: 215L-S2-06

References:

DAN 902-5 C-6, UFSAR 7.6.1.5.3.2 K/A: 215002.A2.03 3.1 / 3.3 K/A: Ability to predict the impacts of the following on the RBM; and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel:

Level: Memory Pedigree: Bank History:

Explanation: RBMs are set up with a primary and alternate reference APRM. For channel 7, APRM 3 is the primary and APRM 2 is the alternate. For channel 8, APRM 4 is the primary and APRM 5 is the alternate.

When APRM 3 failed downscale a rod block occurs and APRM 7 is auto bypassed. Since APRM 4 did not fail then APRM 8 is unaffected. Both APRM 3 and APRM 5 must be bypassed to clear the rod block.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 116 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 67 ID: 24224 Points: 1.00 The Reactor Water Cleanup pump room was recently surveyed and the following radiological conditions exist:

? General area radiation of 200 mrem/hr.

? Smearable contamination of 90 dpm/100cm2 (beta-gamma)

How should the area be posted IAW RP-AA-376 Radiological Postings, Labeling, and Markings?

A. "Caution - High Radiation Area" only.

B. "Caution - Locked High Radiation Area" only.

C. "Caution - High Radiation Area" AND "Caution - Contaminated Area" D. "Caution - Locked High Radiation Area" AND "Caution - Contaminated Area" Answer: A ILT EXAM Page: 117 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 67 Details Question Type: Multiple Choice Topic: 67 - Generic 3.07 System ID: 24224 User ID: 24224 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective:

Reference:

RP-AA-376 K/A: Generic 2.3.7 3.5/3.6 K/A: Ability to comply with radiation work permit requirements during normal or abnormal conditions.

Level: Memory Pedigree: Bank CFR: 41.12 History: None Comments: Per RP-AA-376, a high radiation area is an area that could result in an individual receiving a deep dose equivalent rate in excess of 100 mrem/hr at 30 cm from the radiation source. A contaminated area contains contamination present at levels > 1000 dpm/100cm2 beta/gamma. Knowledge of radiation and contamination area markings is required to comply with RWPs.

ILT EXAM Page: 118 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 68 ID: 24225 Points: 1.00 With Unit 2 at 95% power, the following transient is observed:

• Rise in indicated core flow.

• Drop in core thermal power.

• Drop in Main Generator power.

• Drop in Core differential pressure.

Which of the following is causing the above operating anomaly?

A. Failure of a jet pump B. Partial opening of an ERV C. Loss of RWCU system due to HELB isolation D. Failure of a condensate demineralizer post strainer Answer: A ILT EXAM Page: 119 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 68 Details Question Type: Multiple Choice Topic: 68 - 202001.K5.02 System ID: 24225 User ID: 24225 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 20200LK016

Reference:

DOA 0201-01 K/A: 202001.K5.02 3.1 / 3.2 K/A: Knowledge of the operational implications of the following concepts as they apply to RECIRCULATION SYSTEM: Jet pump operation: BWR-3,4,5,6 CFR: 41.5 Safety Function: 1 & 4 PRA: No Level: High Pedigree: Bank History: ILT 11-1 NRC Comments: DOA 0201-01 states the symptoms of a failed Jet Pump are:Rise in indicated core flow, drop in core thermal power, drop in main generator power and drop in core D/P. None of the distracters would have all of the symptoms listed.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 120 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 69 ID: 23475 Points: 1.00 Given the following:

• A Scram has occurred on U2.

• DW pressure is 3.1 psig and slowly rising.

• The US has ordered Torus Sprays to be placed in service per the Hard Card.

When operating the control switches for Torus Spray, in the OPEN direction, the TORUS SPRAY VLV MO 2-1501-18A MUST be___(1)___ , and the TORUS SPRAY VLV MO 2-1501-19A MUST be ___(2)___ .

A. (1) given a momentary open signal; (2) given a momentary open signal B. (1) given a momentary open signal; (2) held in the open direction until the valve is FULL open C. (1) held in the open direction until the valve is FULL open; (2) given a momentary open signal D. (1) held in the open direction until the valve is FULL open; (2) held in the open direction until the valve is FULL open Answer: A ILT EXAM Page: 121 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 69 Details Question Type: Multiple Choice Topic: 69 - 230000.G1.23 System ID: 24226 User ID: 23475 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE203LN001.11

Reference:

12E-2441 sht 1+2 K/A: 230000.G1.23 3.8 / 3.6 K/A: RHR/LPCI: Torus/Pool Spray Mode: Ability to perform specific system and integrated plant procedures during all modes of plant operation CFR: 41.10 Level: Memory Pedigree: Bank History: 2013 Cert Explanation: Both valves are "Seal In" type control switches, in the open direction regardless of whether or not an initiation signal is present.

REQUIRED

REFERENCES:

None.

70 ID: 24227 Points: 1.00 Unit 2 was operating at 25% power when 2 out of 3 DEHC Pressure Controller Processors failed LOW.

What is the plant response to the above failures?

A. The Backup Pressure Regulator will take control and turbine load remains steady.

B. The Turbine trips, causing a Reactor Scram on load reject.

C. The Turbine Control and Bypass Valves close, causing a Reactor Scram on High Pressure.

D. Turbine throttle pressure drops, causing a Reactor Scram on MSIV closure.

Answer: C ILT EXAM Page: 122 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 70 Details Question Type: Multiple Choice Topic: 70 - 241000.K3.08 System ID: 24227 User ID: 24227 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE241LN001.12

Reference:

DOA 5650-02 K/A: 241000.K3.08 3.7 / 3.7 K/A: Knowledge of the effect that a loss or malfunction of the REACTOR/TURBINE PRESSURE REGULATING SYSTEM will have on following:

Control/governor valves.

Level: High Pedigree: Bank History: 2013 Cert Explanation: When 2 of the 3 DEHC Pressure Controller Processors fail LOW then the Turbine Control Valves and Turbine Bypass Valves close, causing a Reactor Scram on high pressure.

The backup pressure regulator will NOT be able to take control, since it is lost anytime 1 of the DEHC Pressure Controller Processors fail (high or low).

The turbine trip will NOT cause a scram, if Reactor power is < 38.5% power.

A scram on MSIV closure will NOT occur, since this happens only if the Pressure Control Processors fail HIGH (which would cause the Turbine Control Valves to open, causing Turbine throttle pressure to drop to <

827 psig [if the Mode Switch is in RUN], then the MSIVs close causing a Reactor Scram).

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 123 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 71 ID: 24115 Points: 1.00 Unit 3 was in STARTUP, with the following PRIOR TO STARTUP and CURRENT conditions:

PRIOR TO STARTUP CURRENT SRM 21 at 9 cps SRM 21 at 38 cps SRM 22 at 11 cps SRM 22 at 47 cps SRM 23 at 8 cps SRM 23 at 39 cps SRM 24 at 10 cps SRM 24 at 44 cps Moderator temp 148oF Moderator temp 149oF The Reactor is NOT critical.

The next sequence step is to move Control Rod F-05 from notch 00 to notch 48.

Which of the following methods is the FASTEST method allowed by DGP 3-4, CONTROL ROD MOVEMENT, to move Control Rod F-05?

A. Continuous withdrawal from 00 to 48.

B. Single notch withdrawal from 00 to 48.

C. Single notch withdrawal from 00 to 36 and THEN continuous withdrawal to 48.

D. Continuous withdrawal to 04, single notch withdrawal from 04 to 36 and THEN continuous withdrawal to 48.

Answer: A ILT EXAM Page: 124 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 71 Details Question Type: Multiple Choice Topic: 71 - Generic.2.02 System ID: 24262 User ID: 24115 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 2 Point Value: 1.00 Cross Reference Number:

Num Field 1: 0.00 Num Field 2: 0.00 Text Field:

Comments: Objective: 29800LK017

Reference:

DGP 3-4, DGP 1-1 K/A: Generic.2.02 4.6 / 4.1 K/A: Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

Level: High Pedigree: Bank History: 2013 Cert Explanation: DGP 3-4 States "Do NOT use Notch Override Switch between positions 04 and 36 after SRMs have experienced three doublings (8 times the initial count rate) until the Unit is in a steaming condition (one bypass valve partially OPEN or the Unit on-line)." The notch override shall not be used when moving the rod less than 3 notches. High Cog due to the operator having to determine the number of doubling based on the information in the stem, then the procedural requirement.

REQUIRED

REFERENCES:

None.

ILT EXAM Page: 125 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 72 ID: 24229 Points: 1.00 Unit 2 was at rated power when a control power fuse blew inside a Control Room Panel. The Shift Manager has declared that the event did NOT create an emergency situation. A replacement fuse has been located and determined to be like-for like.

IAW CC-AA-206, Fuse Control, which of the following is correct?

A. The Operator may NOT install the fuse.

B. ONLY EMD may install the fuse with NO further engineering evaluation.

C. The Operator may install the fuse with NO further engineering evaluation.

D. The Operator may install the fuse ONLY after the fuse is evaluated by the Fuse Engineer.

Answer: C ILT EXAM Page: 126 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 72 Details Question Type: Multiple Choice Topic: 72 - Generic 2.14 System ID: 24229 User ID: 24229 Status: Active Always select on test: No Authorized for practice: No Difficulty: 1.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 29900LK081

Reference:

CC-AA-206 K/A: Generic 2.2.14 3.9/4.3 K/A: Knowledge of the process for controlling equipment configuration or status.

CFR: 41.10 PRA: No Level: Memory Pedigree: New History:

Comments: Since the plant was at rated power when a control fuse blew. The new fuse is like-for like with the old fuse. IAW the reference, the Operator may install the fuse and no further engineering evaluation.

a) is incorrect due to the fact that operators can install the fuse b) is incorrect due to the fact that operators can install fuses in both emergency and non-emergency situations c) is correct due to the fact that operators can install fuses in both emergency and non-emergency situations d) is incorrect due to the fact that the fuse has been determined to be like for like replacement, no further evaluation is required.

ILT EXAM Page: 127 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 73 ID: 24230 Points: 1.00 Consider the following two TIP system conditions:

Condition 1:

TIP scan is in progress with the TIP half-way in the core in AUTO.

Condition 2:

TIP insertion in progress with the TIP half-way in the core in MANUAL.

Which of the following describes the initial TIP response if reactor water level drops to +5 inches?

Condition 1 Condition 2 A. Reverses direction immediately Reverses direction immediately B. Continues inserting Continues inserting C. Continues inserting Reverses direction immediately D. Reverses direction immediately Continues inserting Answer: A ILT EXAM Page: 128 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 73 Details Question Type: Multiple Choice Topic: 73 - 215001.K4.01 System ID: 24230 User ID: 24230 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: DRE215LN001.06

Reference:

DAN 902-5 E-5, DRE215LN001 K/A: 215001.K4.01 3.4 / 3.5 K/A: Knowledge of TRAVERSING IN-CORE PROBE design feature(s) and/or interlocks which provide for the following: Primary containment isolation:

Mark-I&II(Not-BWR1).

CFR: 41.7 Level: High Pedigree: Bank History: 2011 Cert Explanation: At RPV Level Low (Group II Initiation Signal +8 inches) the TIPS auto or manually withdraw and the Ball valve closes.

REQUIRED

REFERENCES:

None.

74 Points: 1.00 Unit 2 is operating at full power when the 2C RFP Flow transmitter begins failing down.

How will ACTUAL/APRM power respond prior to operator action and what actions are REQUIRED to gain control of RPV level?

A. Reactor Power will go up; take manual control of Low Flow FRV ONLY B. Reactor power will go up; take manual control of Main AND Low Flow FRVs C. Reactor power will go down; take manual control of Main FRVs ONLY D. Reactor power will go down; adjust FWLC setpoint to restore RPV level to desired band Answer: B ILT EXAM Page: 129 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 74 Details Question Type: Multiple Choice Topic: 74 - 259002 A1.03 System ID: 24231 User ID:

Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 259LN002.11

Reference:

DOA 0600-01 K/A: 259002 A1.03 3.8/3.8 K/A: Ability to predict and/or monitor changes in parameters associated with operating the Reactor Water Level Control controls including: Reactor Power CFR: 41.5 Safety Function: 2 PRA: Yes Level: High Pedigree: New History:

Comments:

A) Incorrect - Reactor Power will increase due to positive reactivity addition, however with LFRV already closed taking manual control will not reduce RPV water inventory.

B) Correct - Reactor Power will increase due to positive reactivity addition, taking Main and Low Flow FRVs to manual is required to discontinue the excess RPV water addition. Additional actions will be required to close the valves and match feed flow and steam flow to stabilize RPV level C) Incorrect - Reactor Power will increase due to positive reactivity addition. Main FRV and Low Flow FRV must be taken to manual to restore RPV level D) Incorrect - Reactor Power will increase due to positive reactivity addition. Main FRV and Low Flow FRV must be taken to manual to restore RPV level.

Adjusting setpoint may temporarily avert the RPV level rise.

ILT EXAM Page: 130 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC 75 ID: 24232 Points: 1.00 A DBA LOCA has occurred on Unit 2 with the following plant conditions present:

• RPV level is -100 inches and rising slowly

• Torus water level is 8.0 feet and lowering slowly

• The torus leak is unisolable Given these conditions you would predict that the Core Spray pump discharge pressure would be

____________and the operator would throttle __________ the discharge valve.

A. Lowering, Close B. Lowering, Open C. Rising, Close D. Rising, Open Answer: A ILT EXAM Page: 131 of 132 02/13/15

EXAMINATION ANSWER KEY ILT 14-1 RO NRC Question 75 Details Question Type: Multiple Choice Topic: 75 - 209001 A3.03 System ID: 24232 User ID: 24232 Status: Active Always select on test: No Authorized for practice: No Difficulty: 4.00 Time to Complete: 0 Point Value: 1.00 Cross Reference Number:

Num Field 1:

Num Field 2:

Text Field:

Comments: Objective: 209LN001.06

Reference:

DOP 1400-02 K/A: 209001 A3.03 3.5/3.5 K/A: Ability to monitor automatic operations of the LPCS including: System Pressure CFR: 41.7 Safety Function: 2 PRA: No Level: High Pedigree: Bank History:

Comments:

As torus water level lowers, NPSH to CS pumps is reduced. Lowering flow is necessary to reduce vortexing/cavitation. As NPSH is reduced, system discharge pressure is reduced.

ILT EXAM Page: 132 of 132 02/13/15