Text

Draft Written Exam (Folder 2)
	ML13066A305
Person / Time
Site:	Indian Point
Issue date:	02/27/2013
From:	D'Antonio J; NRC Region 1
To:	; Entergy Nuclear Operations
	Jackson D
References
	TAC U01866
	Download: ML13066A305 (178)
	v • d • e

U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:

Date: Facility/Unit: IPEC Unit 3 Region: I II 0 III IVO Reactor Type: W~ CE BW GE I~Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after the examination begins.

Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicant's Signature Results Examination Value Points Applicant's Score Points

Applicant's Grade Percent

UNIT 32013 Exam Date 02/1112013 Question: 1 Operators suspect a vapor space leak through either a Pressurizer Safety or PORV. What indication combinations are available to help the operator determine which valve is faulted?

ACOUSTIC MONITOR TAILPIPE TEMPERATURE A. each safety each safety each PORV common PORV line B. common safety line common safety line each PORV each PORV

c. each safety each safety common PORV line common PORV line D. common safety each safety line common PORV line each PORV Page 1 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 2 Given the following conditions:

A Small Break LOCA has occurred.

The crew is performing the actions of ES-1.2, "POST LOCA COOLDOWN AND DEPRESSURIZATION".

All SI pumps are running.

All RCPs are running.

RCS cooldown via High Pressure Steam Dumps is ongoing.

RCS Tave is 510°F and lowering at a rate of 90°F/Hr.

RCS pressure is 1350 psig and stable.

PZR level indicates 38% and slowly rising.

Which of the following describes the next major action to be implemented in the EOP to mitigate the current conditions?

A. Depressurize the RCS using normal spray to collapse voids and refill the PZR.

B. Transition to ES-1.1, "SI TERMINATION", to immediately stop all SI pumps.

C. Stop all but 34 RCP and begin the SI flow reduction process by stopping ECCS pumps.

D. Stop the cooldown. Energize all PZR heaters to collapse voids and stabilize PZR level.

Page 2 of 100 12/1212012

UNIT 32013 Exam Date 0211112013 Question: 3 Given the following:

A large break LOCA has occurred.

The 31 spray pump is out of service.

All other ESF equipment started on demand.

The crew has entered ES-1.3, Transfer to Cold Leg Recirculation.

Which of the following correctly describes the containment spray pump operation when recirc switch 1 is placed to on during this transfer?

A. Spray pump 32 will continue to operate and must be manually tripped when RWST level reaches 1.5 feet.

B. Spray pump 32 will trip when recirc switch 1 is placed to on. The pump must be restarted and must be manually tripped when RWST level reaches 1.5 feet.

C. Spray pump 32 will continue to operate and will automatically trip when RWST level reaches 1.5 feet.

D. Spray pump 32 will trip when recirc switch 1 is placed to on. The pump must be restarted and will automatically trip when RWST level reaches 1.5 feet.

Page 3 of 100 12/12/2012

UNIT 32013 Exam Date 02111/2013 Question: 4 The plant is at 25% power, on chemistry hold for secondary cation concentration, Action Level 1.

A loss of offsite power occurs. The plant remains on-line and all equipment operates as designed.

What is the configuration of the AFW system?

A. 32 and 33 AFW pumps are running, supplying auxiliary feedwater to all steam generators.

B. 31 and 32 AFW pumps are running, only 31 and 32 Steam Generators are being supplied auxiliary feedwater.

C. 32 and 33 AFW pumps are running, only 33 and 34 Steam Generators are being supplied auxiliary feedwater.

D. 31, 32 and 33 AFW pumps are running, supplying auxiliary feedwater to all steam generators.

Page 4 of 100 12/1212012

UNIT 32013 Exam Date 02/1112013 Question: 5 Which of the following identifies the first pump checked, and if necessary started, in 3-AOP 480V-1, Loss of Normal Power to Any 480V Bus and why this pump is addressed first?

A A charging pump to ensure RCS inventory is adequate to prevent letdown isolation B. A charging pump to ensure RCP Seal cooling if CCW to thermal barrier also lost C. A Service Water Pump to ensure cooling is maintained to Hydrogen Seal Oil Coolers D. A Service Water Pump to ensure cooling to Emergency Diesel Generators Page 5 of 100 12/12/2012

UNIT 32013 Exam Date 02111/2013 Question: 6 Given the following conditions:

RHR is in service at Reduced Inventory conditions at 65 feet.

AOP-RHR-1, Loss of RHR, has been entered.

Which ONE of the following indications in the Control Room are used to determine if cavitation is occurring.

A. RHR flow high coincident with RVLlS Full Range level low.

B. RHR flow and pump amps increasing as RCS inventory is raised.

C. RHR flow and Associated 480 volt bus amp oscillations.

D. RHR pump flow and RVLlS Full Range level oscillations.

Page 6 of 100 12112/2012

UNIT 32013 Exam Date 02111/2013 Question: 7 Given the following:

Unit is at 100% power.

CCW SURGE TANK #311#32 LEVEL alarms are lit

A Low level condition is present.

CCW surge tanks level are DECREASING.

The makeup valve is OPEN.

There is NO indication of relief valve leakage in any CCW-cooled components Which ONE of the following is the location of the leak?

A. RCS sample coolers during sampling B. Non-Regenerative heat exchanger C. Thermal barrier heat exchanger D. Seal return heat exchanger Page 7 of 100 12112/2012

UNIT 32013 Exam Date 0211112013 Question: 8 With the plant initially at 100% power and rod control in manual, a short duration spurious runback occurs Current conditions are as follows:

Power has stabilized at 80%.

Tave has increased to 593°F.

Pressurizer level has risen to 80%.

Pressurizer pressure is currently 2350 psig.

PORV 455C indicates OPEN.

PORV 456 indicates CLOSED.

PRT pressure and level are increasing.

All Pressurizer backup heaters are energized.

In accordance with EN-OP-115 Conduct of Operations, what action is required to be taken by the operators?

A. Trip the reactor and enter E-O, since an automatic reactor trip should have occurred.

B. Open PORV 456, since it should already be OPEN.

C. Close PORV 455C, since it should have already CLOSED.

D. Turn all pressurizer backup heaters to OFF, since they should not have energized.

Page 8 of 100 12/12/2012

UNIT 32013 Exam Date 02111/2013 Question: 9 Reactor Trip and Bypass Breakers have been aligned to support testing of Reactor Protection Train A when an inadvertent Safety Injection signal is generated on Safety Injection Train A.

Which of the following describes the Reactor Protection System response?

A. An ATWS occurs because Reactor Trip Breaker A and Reactor Trip Bypass Breaker B remain closed.

B. An ATWS occurs because Reactor Trip Breaker B and Reactor Trip Bypass Breaker A remain closed.

C. The Reactor trips. Reactor Trip Breaker A, Reactor Trip Breaker B, and Reactor Trip Bypass Breaker A are open. Reactor Trip Bypass Breaker B is locked open.

D. The Reactor trips. Reactor Trip Breaker A, Reactor Trip Breaker B, and Reactor Trip Bypass Breaker B are open. Reactor Trip Bypass Breaker A is locked open.

Page 9 0[100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 10 Given:

The Unit was operating at 100% power.

A Steam Generator Tube Ruptured occurred in 34 SG.

Off-site power was lost coincident with the reactor trip.

Which of the following describes how the E-3 Cooldown will be controlled?

A. Limited to 0.4 E6 Ibm/hr to prevent false Integrity Status Tree Entry.

B. Maximum achievable rate using all intact SG atmospheric dump valves.

C. Limited to ensure final temperature will remain above 320°F D. Maximum achievable rate using available condenser steam dumps.

Page 10 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 11 Given the following plant conditions:

Plant is operating at 81% power

No equipment is out of service

31 and 32 Condensate Pumps operating

31 Condensate Pumps trips due to a winding short Which of the below statements describes the required operator actions to mitigate the transient?

A Reduce turbine load as necessary to maintain MBFP suction pressure greater than 265 psig.

B. Verify 31 and 33 AFW Pumps automatically start; verify MBFP suction pressure greater than 265 psig.

C. Start 33 Condensate Pump, reduce turbine load as necessary to maintain MBFP suction pressure greater than 265 psig.

D. Trip the Reactor, Go To E-O, Reactor Trip or Safety Injection.

Page 11 of 100 12112/2012

UNIT 32013 Exam Date 0211112013 Question: 12 Unit 3 is in Mode 5 on RHR with 31 and 33 CCW Pumps in service. Automatic safety injection was disabled shortly after entering Mode 5. All 3 EDGs are operable. Maintenance wants to perform an activity that will disable the auto start of 31 CCW Pump. Which of the following would you expect regarding this activity?

A. The activity will be allowed since auto starts of CCW pumps during a station blackout are already disabled when automatic safety injection is disabled.

B. The activity will be allowed since auto starts of 31 CCW pump would not occur during a station blackout since 31 CCW is already in service.

C. The activity will not be allowed. 31 CCW is required to be operable since RHR is in service. Loss of auto start capability will render 31 CCW pump inoperable.

D. The activity may be allowed after assessing for risk impact of having to manually restart 31 CCW during a station blackout.

Page 12 of 100 12/12/2012

UNIT 32013 Exam Date 0211112013 Question: 13 The plant is at normal 100% power lineup with Channel B selected for feed flow and steam flow control. Which set of actions will be required per 3-AOP-IB-1, Loss of Power to an Instrument Bus, for a loss of 31 and 31A Instrument Busses?

I - Swap feed flow and steam flow to the A channel II - Place MBFPs in Manual control III - Place MFRVs in Manual control A. I and II B. I and III C. II and III D. I, II, and III Page 13 of 100 1211212012

UNIT 32013 Exam Date 02/1112013 Question: 14 Given the following plant conditions:

The Unit is at 20% power

A loss of ALL normal Service Water Pumps has occurred due large amount of debris on the screens

No Circ Water Pumps are available due to the debris Which of the following describes the required operator action for the above condition?

A. Trip the Reactor, do NOT SHUT the MSIVs and initiate E-O, Reactor Trip or Safety injection.

B. Trip the Reactor, SHUT the MSIVs and initiate E-O, Reactor Trip or Safety injection.

C. Immediately align Backup Service Water Pumps, 37, 38 and 39 to the essential service water header.

D. Commence a rapid plant shutdown as long as temperatures remain below the trip setpoint.

Page 14 of 100 12/1212012

UNIT 3 2013 Exam Date 02/1112013 Question: 15 Unitt 3 is in a normal 100% power lineup when the "480 VOLT SAFEGUARD BUS.

UNDERVOLTAGE" alarm annunciates and immediately clears. The cause is a grid disturbance that affected 138 KV Feeder 95331. Which of the following describes the direction specified in ARP-005, Panel SBF SAFEGUARDS?

A. Per AOP-138KV-1, Loss of Power to 6.9 KV Bus 5 and/or 6, check status of SFP pumps because historically the standby pump has started due to grid disturbances.

B. Per AOP-138KV-1, Loss of Power to 6.9 KV Bus 5 and/or 6, check status of SFP pumps because historically the running pump has tripped due to grid disturbances.

C. Per a checklist in SOP-EL-5, Operation of On-Site Power Sources, check status of SFP pumps because historically the standby pump has started due to grid disturbances.

D. Per a checklist in SOP-EL-5, Operation of On-Site Power Sources, check status of SFP pumps because historically the running pump has tripped due to grid disturbances.

Page 15 of 100 12/12/2012

UNIT 32013 Exam Date 0211112013 Question: 16 The crew has completed the actions of ECA-1.2, LOCA Outside Containment.

Pressurizer level is 35% and stable.

Steam Generator narrow range levels are 30%.

Subcooling is 35°F.

RCS pressure is 1400 psig and slowly lowering.

Which ONE (1) of the following procedures will be performed next?

A. ES-1.1, SI Termination.

B. E-O, Reactor Trip or Safety Injection.

C. ECA-1.1, Loss of Emergency Coolant Recirculation.

D. E-1, Loss of Reactor or Secondary Coolant.

Page 16 of 100 12/12/2012

UNIT 32013 Exam Date 02/11/2013 Question: 17 The plant is in an emergency condition, and the control room operators are responding to a loss of secondary heat sink. RCS bleed-and-feed is in progress, and RCS temperatures are stable. The operators restore a feedwater source and prepare to feed the S/Gs, which are hot and dry. The SM directs them to re-establish FW flow to only one S/G rather than to all of the S/Gs.

The primary reason for feeding only one S/G under these conditions is to:

A. Prevent a rapid cooldown of the RCS that could lead to a pressurized thermal shock condition.

B. Ensure that if S/G failure occurs due to excessive stresses, the failure is isolated to one S/G.

C. Ensure pump runout conditions will not occur for the FW source until adequate heat sink established D. Determine if one S/G is capable of maintaining adequate heat sink so that RCS bleed and-feed can be terminated.

Page 17 of 100 12/12/2012

UNIT 32013 Exam Date 0211112013 Question: 18 Given:

A LOCA has occurred.

Operators were performing ECA-1.1, Loss of Emergency Coolant Recirculation when Containment pressure is noted to be 22.3 psig.

The decision of whether to remain in ECA-1.1 or transition to another procedure was properly made.

Which of the following describes how the Containment Spray system will be operated, and why?

The Containment Spray System is operated as directed in...

A. ECA-1.1 because it establishes minimum required containment spray flow and conserves RWST inventory.

B. FR-Z.1, Response to High Containment Pressure, since restoration of the critical safety function takes precedence.

C. ECA-1.1 since FRPs (Functional Restoration Procedures) are NOT implemented during the performance of ECA-1.1.

D. FR-Z.1 because containment is the last fission product barrier actions are the same as SAMGs (Severe Accident Management Guidelines)

Page 18 of 100 12112/2012

UNIT 3 2013 Exam Date 02/1112013 Question: 19 Given the following:

The plant was initially at 95% power.

The reactor tripped 20 minutes ago.

INTERMEDIATE RANGE NO.1 LOSS OF COMPENSATE VOLTAGE alarm is annunciated.

Which ONE (1) of the following describes the response of Intermediate Range N-35 to the loss of compensating voltage and what actions are given for this condition?

A. Indicates LOW; Press appropriate Intermediate Range Permissive Defeat Button to re energize Source Range Channel N31 B. Indicates HIGH; Press both Source Range AlB Logic Trip Block Buttons to re-energize both Source Range Channels C. Indicates LOW; Press Source Range A Logic Trip Block Button to re-energize Source Range Channel N31 D. Indicates HIGH; Press both Intermediate Range Permissive Defeat Buttons to re energize both Source Range Channels Page 19 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 20 Given the following conditions:

Plant is in refueling performing a core reload

Transfer tube gate valve is opened

An irradiated assembly has just removed from the Containment Upender and is in the mast

The following occurs: Reactor pit sump pump indicates ON

High level Reactor Pit alarm annunciates

Containment and Recirculation sump levels are rising slowly

R-2 and R-7 are in alarm and indications are rising Which one of the following actions would be directed by AOP-FH-1 "Fuel Damage OR Loss of SFP/Refueling Cavity Level"?

Place the Fuel Assembly A. In the upender and lower to horizontal position B. directly west of the RCC Change Fixture and unlatch the assembly from the gripper C. in any accessible spent fuel pit location D. in the RCC Change Fixture Page 20 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 21 Which of the following describes the Reactor Operator's task for safe shutdown outside the control room and reason for this task?

A. Establish charging within 30 minutes of the event initiation to ensure pressurizer level remains in the indicating range.

B. Establish charging with 60 minutes of the event initiation to ensure adequate shutdown margin is maintained.

C. Establish AFW flow within 30 minutes of the event initiation to ensure steam generators do not dry out.

D. Establish AFW flow within 60 minutes of the event initiation to ensure RCS pressure does not exceed PORV setpoints.

Page 21 of 100 12112/2012

UNIT 3 2013 Exam Date 02/11/2013 Question: 22 The operating team has entered AOP-HIACT-1, High RCS Activity, due to elevated RCS activity as noted by Chemistry. Which of the following is true regarding R-63 (Gross Failed Fuel Detector) readings per AOP-HIACT-1?

A. If R-63 is in alarm, verify that RCS sample isolation valves has automatically closed.

B. If R-63 is in alarm, verify that letdown has automatically diverted through the standby mixed bed.

C. If activity on R-63 is > 50 !-ICi/cc, then no samples of the RCS are to be taken.

D. If activity on R-63 is> 50 !-ICi/cc , then consideration should be given to using the Post Accident Sampling System.

Page 22 of 100 12/12/2012

UNIT 3 2013 Exam Date 02/11/2013 Question: 23 Given:

The team is performing the actions of ES-1.1, "SI Termination"

At Step 4 of ES-1.1, The team secured all SI and RHR Pumps

At step 8 of ES-1.1, the team secured all but one charging pump

RCS Pressure and Pressurizer Level begin to lower after the charging pumps are secured Which one of the following describes the required operator actions in accordance with ES-1.1?

A. Monitor RCS Pressure and Pressurizer Level, if pressure and level continue to lower, restart SI pumps and return to procedure previously in effect.

B. Manually re-initiate SI and Transition to E-O, "Reactor Trip or Safety Injection" step 1.

C. Adjust charging flow and if Pressurizer Level cannot be maintained, then restart SI pumps as required and transition to E-1, "Loss of Reactor or Secondary Coolant".

D. Restart one charging pump and if Pressurizer Level cannot be maintained transition to E-1. "Loss of Reactor or Secondary Coolant."

Page 23 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 24 Given the following Plant conditions;

The plant is operating at 100% power, steady state.

The Pressurizer Level Defeat switch is in the Defeat 3 position The operator notes the following indications 3 minutes after a failure occurred:

All Pressurizer heaters are on.

Letdown isolation valve LCV-459 is open.

Charging pump speed slowly lowering.

Which ONE of the following describes a cause for these indications?

A. Pressurizer level channel 1 detector, LT-459, failed high.

B. Pressurizer level channel 2 detector, LT-460, failed high.

C. Pressurizer level channel 1 detector, LT-459, failed low.

D. Pressurizer level channel 2 detector, LT -460, failed low.

Page 24 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 25 An INADEQUATE CORE COOLING condition is present during a small break loss of coolant accident. The following conditions are noted:

No safety injection pumps are available

Both RHR pumps are running

No RCPs are running

Both motor driven AFW pumps are operating

RCS pressure is 1100 psig

CETs are 765°F and rising slowly

RVLlS is 31% and lowering slowly

Steam generator pressure is 1050 psig Which of the following is true regarding recovery actions?

A. A secondary depressurization will cause enough heat rejection to the steam generators that safety injection system flow will no longer be required to combat the event.

B. A secondary depressurization will lower reactor coolant system pressure, allowing safety injection accumulators to recover the core.

C. Opening power-operated relief valves (PORVs) will take the reactor coolant system to saturation, allowing latent heat removal to bring down core temperature.

D. Opening power-operated relief valves (PORVs) will depressurize the reactor coolant system low enough to allow the RHR system to cool the core.

Page 25 of 100 12/12/2012

UNIT 32013 Exam Date 0211112013 Question: 26 Given the following conditions:

The reactor is tripped

A Safety Injection signal has been generated

All RCPs are running

Average CETs indicate 515°F

RCS Pressure is 1800 psig and stable

CNMT Pressure is 24 psjg and slowly increasing

Pressurizer level is off scale low

All ESF/ECCS equipment operated as designed Which ONE of the following describes why the RCPs should or should not be tripped?

A. RCP trip foldout page criteria are met The RCPs should be tripped Prevent exceeding peak clad temperature limits B. RCP trip foldout page criteria are met The RCPs should continue to run Provide forced cooling.

C. RCP trip foldout page criteria are NOT met The RCPs should be tripped Prevent damage to pumps D. RCP trip foldout page criteria are NOT met The RCPs should remain running Ensure adequate core cooling Page 26 of 100 12/12/2012

UNIT 32013 Exam Date 0211112013 Question: 27 FR-Z.2, "Response to Containment Flooding", addresses flooding in Containment as an ORANGE path. Which one of the following statements describes why this condition is considered a severe challenge to a critical safety function?

A. The highly corrosive nature of salt water may cause internal component failure during recirculation phase of an accident.

B. Critical components necessary for plant recovery may fail if submerged.

C. pH in the sump may be too low to ensure effective iodine removal and minimize corrosion.

D. RCS activity in the sump may cause the off-site dose limits to be exceeded if the water is transferred outside containment, Page 27 of 100 12/12/2012

UNIT 32013 Exam Date 02111/2013 Question: 28 GIVEN:

The unit experienced a reactor trip coincident with a loss of off site power.

The crew entered 3-ES-0.2, natural Circulation Cooldown

Lift oil pump is running

RCS pressure is 350 psig

Seal Injection flow is 8 gpm to each RCP

Seal Leakoff flow is 0.15 gpm from each RCP

Number 1 sealleakoff temperature is 100°F

All bearing temperatures are less than 150°F

VCT pressure is 50 psig

Both Spray valves are in AUTO and closed

138kV power is available from Buchanan Switchyard

The crew is making preparations to start RCP 34 Which of the following actions should the CRS direct the operator to perform?

A. Direct the operator to start RCP 34, all conditions are satisified.

B. Direct the operator to start RCP 34, all conditions are not satisified but are not required.

C. Direct the operator to decrease VCT pressure to increase seal leakoff flow, then RCP 34 may be started.

D. Direct the operator to open RCP No.1 Seal Bypass Valve, 246 to increase sealleakoff flow, then RCP 34 may be started.

Page 28 of 100 12/12/2012

UNIT 3 2013 Exam Date 02/1112013 Question: 29 Unit 3 is at 100% power when a CCW leak is found on AC-TCV-130, Non-Regenerative Heat Exchanger CCW Outlet Temperature Control Valve. Repairs are expected to only take a few hours, but will require isolating CCW to AC-TCV-130. Which of the following is the likely action that will be taken for dealing with this issue?

A. The plant will have to proceed to Mode 5 to make repairs since isolation of this leak will cause a loss of cooling to letdown and RCP seal return.

B. The plant will have to proceed to placing RHR in service before isolation can occur because isolation will require removing all of CCW Loop 2 from service.

C. Repairs can occur on line, but letdown and all charging will be isolated. OM permission will be required to operate with thermal barrier cooling as the only means of cooling RCP seals.

D. Repairs can occur on line. Excess letdown will be placed in service with normal letdown secured to allow isolation of AC-TCV-130.

Page 29 of 100 12112/2012

UNIT 32013 Exam Date 02/11/2013 Question: 30 One hour after the RHR system was placed in service to provide shutdown cooling, a tube in

31 RHR heat exchanger fails. Which of the following indications would the operator expect to see?

A. CCW surge tank level would decrease and ReS inventory would increase B. CCW surge tank level would decrease and RHR boron concentration would decrease C. CCW surge tank level would increase and CCW radiation levels would increase D. CCW surge tank level would increase and 822A, RHR HX CCW Shutoff Valve would auto close.

Page 30 of 100 12/12/2012

UNIT 32013 Exam Date 0211112013 Question: 31 Unit 3 is on RHR with 34 RCP running and AC-MOV-730 and AC-MOV-731 energized. A loss of offsite power occurs and 31 EDG fails to start. 32 and 33 EDGs start and automatically power their 480V busses. During the loss of offsite power, RCS wide range pressure increased to 600 psi on both channels and remains at this pressure. Without operator action, what is the status of 730 and 731 after the 480V busses re-energize?

A. 730 and 731 are both closed or going closed.

B. 730 and 731 are both open and not going closed.

C. 730 is open and not going closed, 731 is closed or going closed.

D. 731 is open and not going closed, 730 is closed or going closed.

Page 31 of 100 1211212012

UNIT 32013 Exam Date 02/1112013 Question: 32 The plant experienced a LOCA coincident with loss of off-site power. RCS pressure remains above the shutoff head of the RHR pumps; however the conditions necessary to secure the pumps are not satisfied (Le., RCS pressure continues to slowly decrease).

Which of the following describes the RHR pump operations for this condition?

A. Auxiliary Component Cooling Water Pumps will circulate CCW through RHR pump seal and thermal barrier heat exchangers. Pumps can continue to operate indefinitely.

B. With no Component Cooling Water to the RHR pumps, the pumps can operate for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months together followed by a single pump for an additional 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

C. Shaft driven pumps will circulate CCW through RHR pump seal and thermal barrier heat exchangers. Pumps can continue to operate indefinitely.

D. With no Component Cooling Water to the RHR pumps, the pumps can operate for 45 minutes together followed by a single pump for an additional 45 minutes.

Page 32 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 33 Unit 3 experienced a LOCA and has transferred to cold leg recirculation when it is determined that inadequate low head flow exists due to high RCS pressure. The team transitions to the attachment to establish HHSI recirculation. Which of the following actions will be taken per this attachment?

A. Both Recirc Pumps will be operated to ensure adequate suction flow to the HHSI Pumps while maintaining recirc spray flow.

B. Only one Recirc Pump will be operated to ensure that no Recirc Pump is operating with its discharge check valve closed by flow from the other pump.

C. All HHSI Pumps will be operated to ensure adequate core recirculation flow is established.

D. Only One HHSI Pump (31 or 33) will be operated.

Page 33 of 100 12112/2012

UNIT 32013 Exam Date 0211112013 Question: 34 How are the discharge lines from the Pressurizer code safety valves and PORVs connected to the PRT?

A. The code safety valves and PORVs share a single common discharge line that connects to the PRT.

B. The code safety valves share a common discharge line to the PRT and the PORVs share a common discharge line to the PRT.

C. Each code safety valve has an individual discharge line to the PRT and the PORVs share a common discharge line to the PRT.

D. Each code safety valve and each PORV has an individual discharge line to the PRT.

Page 34 of 100 12112/2012

UNIT 32013 Exam Date 02111/2013 Question: 35 Given the following plant conditions:

Reactor Coolant System temperature is 185°F.

Reactor Coolant System pressure is 100 psig.

RHR cooldown operations have been established with both RHR pumps and heat exchangers in service.

The Shift Manager has directed the crew to establish a cooldown.

Which of the following describes how this is accomplished?

A. Opening AC-820 AlB is not limited. These valves provide coarse temperature control.

Opening SWN-35-1/2 is limited to 27.5° and 2r respectively. These valves provide fine temperature control.

B. Opening AC-820 AlB is limited to 27.5° and 27° respectively. These valves provide coarse temperature control.

Opening SWN-35-1/2 is not limited. These valves provide fine temperature control.

C. Opening AC-820 AlB is not limited. These valves provide fine temperature control.

Opening SWN-35-1/2 is not limited. These valves provide coarse temperature control.

D. Opening AC-820 AlB is limited to 27.5° and 27° respectively. These valves provide coarse temperature control.

Opening SWN-35-1/2 is not limited. These valves provide fine temperature control.

Page 35 of 100 12112/2012

UNIT 32013 Exam Date 0211112013 Question: 36 The controlling pressurizer pressure channel PT-455 has failed low. Which of the following describes plant response to heaters automatically energizing? (Assume No Operator Action)

A. Pressure increase will be limited by pressurizer sprays.

B. Plant pressure will be controlled by ONE PORV cycling.

c. Plant pressure will be controlled by BOTH PORVs cycling.

D. Pressure increases until the plant trips on high pressure.

Page 36 of 100 12/12/2012

UNIT 32013 Exam Date 02111/2013 Question: 37 A rapid load reduction has just been completed. You observe the following:

pressurizer sprays partially open

modulating heaters full off

backup heaters on Which of the following would cause these indications?

A. Controlling pressurizer pressure channel failed high B. Pressurizer level insurge from the downpower C. Controlling pressurizer level channel failed low D. Pressurizer program level decrease from the downpower Page 37 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 38 Given the following plant conditions:

Unit 3 is at 80% power with all systems aligned normal.

PT-412A, Turbine First Stage Pressure, fails high.

For the above conditions, the control rods will be continuously (1) . If the rods continue to move after controls are shifted to MANUAL the operator will initiate a reactor trip.

and then confirm that the reactor is tripped by observing the (2)

(1) (2)

A. Inserting Reactor Trip Breakers GREEN lights LIT, and the Bypass Breaker indicating lights DARK.

B. Inserting GREEN lights LIT on both the Reactor Trip Breakers and Bypass Breakers.

c. Withdrawing Reactor Trip Breakers GREEN lights LIT, and the Bypass Breaker indicating lights DARK.

D. Withdrawing GREEN lights LIT on both the Reactor Trip Breakers and Bypass Breakers.

Page 38 of 100 12/1212012

UNIT 3 2013 Exam Date 02111120 l3 Question: 39 Which of the following describes the automatic actions and basis for these actions if an under frequency condition exists on 6.9 KV Busses 1-4 with Unit 3 at 100% power?

A. 6.9 KV Busses 1-4 de-energize. This causes a reactor trip to ensure that KWIft limits are not violated.

B. 6.9 KV Busses 1-4 de-energize. This causes a reactor trip prior to reaching conditions that could lead to lifting a pressurizer safety on a trip.

C. Trips the RCPs on busses with low frequency. This prevents damage to RCPs to ensure they are available if needed for a loss of cooling event.

D. All RCPs trip. This causes a reactor trip to ensure that DNBR limits are not violated.

Page 39 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 40 A Safety Injection Signal occurred on both Trains A and B due to I&C testing. The operating crew reset the SI signal in accordance with emergency operating procedures. Non-SI Blackout Logic Defeat has not been reset. All components functioned as designed. Subsequently, 6.9 KV bus 5 normal feed breaker tripped on overcurrent. What is the status of CCW Pumps?

A. All CCW Pumps are secured B. 31 and 32 CCW Pumps are running 33 CCW Pump is secured.

C. All CCW Pumps are running D. 31 and 32 CCW Pumps are secured, 33 CCW pump is running.

Page 40 of 100 12112/2012

UNIT 32013 Exam Date 02/11/2013 Question: 41 Due to a catastrophic failure of the instrument air system in the aux boiler feed pump building, all air and backup nitrogen pressure has been lost.

Which of the following describes the impact on 32 Auxiliary Boiler Feed Pump and what actions are necessary.

A. Both PCV-1139 and HCV-1118 fail open on loss of air. Local manual control of valves is necessary to control pump speed.

B. Both PCV-1139 and HCV-1118 fail closed on loss of air. Local manual control of valves is necessary to control pump speed.

C. PCV-1139 fails closed and HCV-1118 fails open. Only local manual control of PCV 1139 is necessary to control speed.

D. PCV-1139 fails open and HCV-1118 fails closed. Only local manual control of HCV 1118 is necessary to control speed.

Page 41 of 100 12/1212012

UNIT 32013 Exam Date 02/1112013 Question: 42 Consider the following possible actions for SWN-TCV-1104/1105:

1. Fail OPEN on a loss of air to ensure adequate containment cooling is available in during an accident.

2. Fail CLOSED on a loss of.air to ensure runout of ESW pump(s) does not occur on a loss of instrument air.

3. Get open signal SI circuit

4. Get open signal from High Containment Pressure circuit

5. Throttle to maintain temperature following SI reset From the above list, which of the following contains actions that are correct for SWN-TCV 1104/1105?

A. 1,4,5 B. 2,4 C. 1,3 D. 2,3,5 Page 42 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 43 The following plant conditions exist:

Fan Cooler #32 is tagged out for maintenance.

A Large Break Loss of Coolant Accident occurred coincident with a Los of Off Site Power

Emergency Diesel # 33 fails to start

Local efforts to start the diesel by the NPO were unsuccessful Based only on the actions taken above, what containment cooling equipment is expected to be running when the crew exits E-O?

A. #31, #33 and #34 Fan Cooler Units, #32 Spray Pump B. #33, #34,and #35 Fan Cooler Units, #31 Spray Pump C. #34 and #35 Fan Cooler Units, #31 Spray pump D. #34 and #35 Fan Cooler Units, #32 Spray Pump Page 43 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 44 The Unit is operating at 80% power with all systems in automatic. One Group of condenser steam dump valves fails full OPEN. Assuming that NO operator action occurs. what will be the resulting Rx power level?

A. 0%

B. 70%

C. 80%

D. 90%

Page 44 of 100 12112/2012

UNIT 32013 Exam Date 02/11/2013 Question: 45 3-AOP-FW-1, Loss of Feedwater, requires tripping the reactor if both MBFPs are not operating when reactor power is above a specified value. Select the statement below that best describes the basis for this step.

The reactor is tripped if power is >_ _ _% because a single MBFP can only sustain SG level at power level no higher than %.

A. 70,70 B. 80, 70 C. 80,80 D. 70,80 Page 45 of 100 12/12/2012

UNIT 32013 Exam Date 02/11/2013 Question: 46 The plant is shutting down for a refueling outage and is currently at 250 MWe about to perform a planned Reactor Trip. All Main Feedwater equipment is available and all steps of POP-2.1 and POP-3.1 have been satisfied at this point in the shutdown. Which of the following is the expected configuration of Main Feedwater prior to the trip?

A. Both MBFPs are in service Low Flow Bypass Feed Regulation Valves are in service B. One MBFPs is in service, One MBFP is in Standby Low Flow Bypass Feed Regulation Valves are in service C. Both MBFPs are in service Main Feed Regulation Valves in service D. One MBFPs is in service, One MBFP is in Standby Main Feed Regulation Valves in service Page 46 of 100 12/1212012

llNIT 3 2013 Exam Date 02111/2013 Question: 47 During the startup of 31 Auxiliary Boiler Feedwater pump as part of a plant shutdown, the operator inadvertently places the recirculation valve control switch in close instead of automatic. What affect will this have on the Auxiliary Boiler Feedwater pump?

A. The low flow trip is disabled; the pump will overheat if flow decreases too low.

B. The low follow trip remains enabled, the pump will trip if flow drops below 40 gpm for

>15 seconds.

C. The low flow alarm only is disabled, but the pump will still trip if flow remains below 130 gpm for >15 seconds.

D. The low flow alarm is enabled; an orificed line to the CST will maintain minimum flow.

Page 47 of 100 12112/2012

UNIT 32013 Exam Date 0211112013 Question: 48 A grid disturbance in the Buchanan Switchyard resulted in a unit trip and loss of off site power.

The BOP identifies buses 5A and 6A are energized from their respective diesel generators.

Of the following conditions, which will prevent the automatic closure of the 31 Emergency Diesel Generator breaker (52/EG-1)?

A. Fault on 480 VAC Bus 3A B. Normal feed breaker for Bus 2A (52/2A) closed C. Bus 2A-3A tie breaker is closed.

D. Normal feed breaker for Bus 3A (52/3A) closed Page 48 of 100 1211212012

UNIT 32013 Exam Date 02/11/2013 Question: 49 Given:

The plant experienced a steam break in the turbine building.

All equipment functioned as designed.

All required procedural actions were completed

When the crew entered ES-1.1, SI Termination, off-site power was temporarily lost.

Which of the following describes actions (if any) related to the electrical lineup?

A. MCCs with battery chargers must be aligned and reset within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

B. MCCs with battery chargers must be aligned and reset within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

C. MCCs with battery chargers do not strip for Blackout, no alignment is necessary.

D. MCCs previously reset will remain energized; no further action necessary.

Page 49 of 100 12/12/2012

UNIT 3 2013 Exam Date 02/1112013 Question: 50 The fire main in the 480V Switchgear room ruptured resulting in a loss of all 480V AC buses.

The crew entered ECA-O.O, Loss of All AC Power and started the Appendix R Diesel Generator. Bus 312 is energized and all Appendix R equipment is available.

Which of the following properly states the post-accident instrumentation available with power from the Appendix R Diesel Generator?

A. 31, 32, 33 SG Narrow Range Level Pressurizer Level Pressurizer Pressure CST Level R-27 Core Exit Thermocouples B. 31, 32, 33 SG WR Level Pressurizer Level Pressurizer Pressure 31 Loop WR Thot 31 Loop WR Tcold N-38 C. 31, 32, 33 SG Narrow Range Level Pressurizer Level Pressurizer Pressure CST Level R-27 31 Loop WR Tcold D. 31,32,33 SG WR Level Pressurizer Level Containment Pressure 31 Loop WR Thot RWST Level N-38 Page 50 of 100 12/1212012

UNIT 3 2013 Exam Date 02/1112013 Question: 51 R-19 (SG Blowdown Activity) is in alarm and has caused an auto-closure of SG sample isolation valves. Unit 3 remains on line. Which of the following actions will be necessary to re open these valves to sample SGs?

A. Acknowledge R-19 alarm on RM-23 panel to re-open valves.

B. Purge R-19 or raise alarm setpoint to re-open valves.

C. Place individual SG sample isolation valves in Rad Bypass position.

D. Press individual valve reset buttons on Panel SMF.

Page 51 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 52 A large leak has developed on the Essential Service Water Header causing SW Header pressure to drop to 40 psig. All available SW Pumps are operating and component temperatures are elevated but stable below alarm setpoints. The plant is currently at 25%

power.

Which of the following describes the required operator action for the above condition?

A. Immediately commence a rapid plant shutdown, main turbine bearing temperatures are expected to rise rapidly.

B. Maintain present power level unless turbine generator bearing oil drain temperatures cannot be maintained below 180°F then trip the turbine.

C. Maintain present power level unless oil temperature from the MBFP bearings cannot be maintained below 190°F then trip the affect MBFP{s).

D. Initiate a plant shutdown to Mode 3 using POP-3.1, Plant Shutdown from 45% Power as long as adequate cooling can be maintained.

Page 52 of 100 12112/2012

UNIT 32013 Exam Date 02/11/2013 Question: 53 Given the following:

The plant is at 100% power

32, 33, 36 Service Water Pumps are running

31,34 and 35 Service Water Pumps are in AUTO

The Service Water Pump Mode Selector Switch is in the 4-5-6 position

The tie breaker between 2A and 3A (2AT3A) is OOS for maintenance.

Assuming no operator action, which one of the following describes the status of the SW Pumps after a Reactor Trip coincident with a Loss of Off-site power occurs?

A. 32, 34, and 36 SW Pumps will be running B. 35 and 36 SW Pumps will be running C. 34, 35, and 36 SW Pumps will be running D. 34 and 36 SW Pumps will be running Page 53 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 54 Unit 3 is at 100% power with 31 Instrument Air Compressor (lAC) in HAND and 32 lAC in AUTO. SOV-1142, Station Air Makeup to Instrument Air is initially closed when a rupture occurs somewhere in the Instrument Air System. What indications do you expect to see in the Control Room for this event?

A. At 105 psig a red light for 32 lAC and at 100 psig a red lightfor SOV-1142 B. At 100 psig a red light for 32 lAC and at 95 psig a red light for SOV-1142 C. At 95 psig a red light for 32 lAC and at 90 psig a red light for SOV-1142 D. At 90 psig a red light for 32 lAC and at 85 psig a red light for SOV-1142 Page 54 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 55 Unit 3 is in a forced maintenance outage with RCS temperature being maintained at 300°F while repairs are being made to 32 AFW Pump. Material is being brought into containment through the 95 ft Airlock, when the inner door is damaged. The door cannot be closed. No other equipment was damaged. What is the operational impact of this event?

A. There is no impact in the current mode. Repairs will be necessary prior to entering a higher mode.

B. If the outer door is verified closed within one hour and locked closed within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , operation can continue in the current mode.

C. The airlock is inoperable. The airlock must be declared operable within one hour or the plant will have to be in Mode 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

D. The containment system is inoperable. The system must be declared operable within one hour or the plant will have to be in Mode 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Page 55 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 56 Given:

The unit is at 100% power

31 EDG is OOS for a breaker PM

A fault occurred in the Buchanan switchyard resulting in a loss of 138KV power.

What is the immediate impact on the plant?

A. The reactor will trip due to loss of both Rod Drive MG Sets when bus 138kV power is lost.

B. 31 Rod Drive MG set was previously secured; the reactor trips when bus 138kV power is lost.

C. The reactor will remain at approximately100% power with only 31 Rod Drive MG set energized.

D. The reactor will remain at approximately1 00% power with both Rod Drive MG Sets energized.

Page 56 of 100 12/1212012

UNIT 32013 Exam Date 02/1112013 Question: 57 Control Room operators are responding to a loss of secondary heat sink. Attempts to restore feedwater flow to the steam generators have been unsuccessful, so the operators are attempting to provide "Bleed and Feed Cooling" to the RCS. Only two Charging Pumps have been started. During performance of these actions there is a delay in starting SI Pumps and the STA recommends opening the PZR PORVs while waiting for SI flow to be established.

Which of the following is your assessment of the STA's recommendation?

A. Agree. With two Charging Pumps running it is acceptable to open the PORVs while continuing with the steps necessary to establish SI flow.

B. Agree. The procedure Caution states that due to a loss of secondary heat sink, the steps to implement bleed and feed should be immediately initiated.

C. Disagree. The correct action would be to start the third Charging Pump then open both PORVs while waiting for SI flow to be established.

D. Disagree. Opening the PORV before SI Pumps are operating could result in uncovery and severe damage to the core.

Page 57 of 100 1211212012

UNIT 32013 Exam Date 02/1112013 Question: 58 Given the following conditions:

The unit was operating at 100% power

A malfunction has caused a Pressurizer Safety Valve to open and stick open

A Reactor Trip and Safety Injection occurred

The RCS rapidly depressurized to saturation conditions

Pressurizer level initially dropped and then began to increase rapidly What is the relationship between pressurizer level and RCS inventory under these conditions?

A. Level is not an accurate indication of inventory, because the pressurizer level channel reference legs will flash causing an indicated increase in level B. Level is not an accurate indication of inventory, because RCS voiding may result in a rapidly increasing pressurizer level.

C. Level is an accurate indication of level, because hydraulic pressure would force any voids into the pressurizer steam space and out the safety valve.

D. Level is an accurate indication of inventory, because voiding would occur in the pressurizer prior to reaching saturation conditions in the RCS.

Page 58 of 100 1211212012

UNIT 32013 Exam Date 0211112013 Question: 59 With the plant operating at 90% power, the following alarms have annunciated:

NIS POWER RANGE OVER POWER ROD STOP

NIS POWER RANGE SINGLE CHANNEL HIGH RANGE TRIP

NIS POWER RANGE LOSS OF DETECTOR VOLTAGE

NIS POWER RANGE DROPPED ROD ROD STOP All Power Range Channels are indicating 90% power. Which of the following are correct, with no operator action?

A. Instrument power fuse has blown, Control rods will not move B. Instrument power fuse has blown, Control rods can only be inserted C. Control power fuse has blown, Control rods will not move D. Control power fuse has blown, Control rods can only be inserted Page 59 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 60 Select the answer which describes when an RCP would be restarted while performing FR-C.1, "RESPONSE TO INADEQUATE CORE COOLING".

A. Blowdown of the Steam Generators to Atmospheric pressure has been unable to reduce CET (Core Exit Thermocouple) temperatures below 1200°F.

B. All three HHSI pumps have failed to start and CET temperatures are above 1200°F.

C. Opening of PORVs has been unsuccessful in reducing CET temperatures below 1200°F.

D. RCPs must be started any time CET temperatures exceed 1200"F.

Page 60 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 61 What is the purpose of the Sodium Tetraborate baskets in the Vapor Containment Building 46' elevation?

A. Establish an alkaline pH to maintain Iodine in solution.

B. Establish an alkaline pH to maintain Hydrogen in solution.

C. Establish a neutral pH to reduce Iodine concentration in solution.

D. Establish a neutral pH to reduce Hydrogen concentration in solution.

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UNIT 32013 Exam Date 0211112013 Question: 62 Given the following plant conditions on Unit 3:

The unit is in Mode 6 with refueling activities in progress.

Containment purge is in service.

A fuel element accidentally dropped into the cavity.

R-11, R-12 and R-14 have a HIGH alarm.

R-25 and R-26, VC High Range Area Monitors, have a HIGH alarm.

Which ONE of the following actions would occur, assuming that operators follow the required actions of 3-AOP-FH-1, "Fuel Damage or Loss Of SFP/Refueling Cavity Level", and all equipment responds as designed?

A. Containment evacuation alarm sounds automatically. Containment purge stops automatically.

B. Containment evacuation alarm is manually actuated by the control room operator.

Containment purge stops automatically.

C. Containment evacuation alarm sounds automatically. Containment purge is stopped manually by the control room operator.

D. Containment evacuation alarm is manually actuated by the control room operator.

Containment purge is stopped manually by the control room operator.

Page 62 of 100 12112/2012

UNIT 32013 Exam Date 02111/2013 Question: 63 Given the following conditions:

Fuel handling is in progress in Containment and the Spent Fuel Pool (SFP).

FSB FSB Fans are operating in NORMAL mode.

Radiation Monitor R 5 SPENT FUEL POOL AREA MONITOR fails LOW.

All other radiation monitors are operable.

What is the impact of this failure?

A. Only recently irradiated fuel assembly movement in the FSB must be suspended.

B. All fuel assembly movement in the FSB AND Containment must be suspended.

C. All fuel assembly movement in the FSB must be suspended.

D. Fuel assembly movement may continue in the FSB and Containment provided R-14, Plant Vent Gas Activity and R-27, Wide Range Plant Vent Gas Activity, monitors are operable.

Page 63 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 64 Which one of the following correctly describes the automatic operation of the main generator voltage controller?

A. Main generator output is compared to the base adjuster setpoint and the comparison could result in the adjustment of generator excitation.

B. Main generator output is compared to the automatic rheostat setpoint which is set by the operator. If there is a difference, the controller bucks or boosts the base adjuster output.

C. Main generator output is compared to the base adjuster rheostat setpoint which is set by the operator. If there is a difference, the controller bucks or boosts the base adjuster output.

D. Main generator output is compared with exciter output. If there is an error, the automatic controller bucks or boosts the base adjuster output.

Page 64 of 100 1211212012

UNIT 32013 Exam Date 02/1112013 Question: 65 Given the following:

The unit is at 100% power

Fire Protection header pressure is lowering Which one of the following has the alternate pumps listed in the proper sequence of automatic start?

A. Standby Jockey Pump at 115 psig, Motor Driven Fire Pump at 110 psig; Diesel Fire Pump at 105 psig B. Standby Jockey Pump at 110 psig; Motor Driven Fire Pump at 105 psig; Diesel Fire Pump at 95 psig C. Standby Jockey Pump at 115 psig; Motor Driven Fire Pump at 110 psig; Diesel Fire Pump when <105 psig for more than 10 seconds D. Standby Jockey Pump at 110 psig; Motor Driven Fire Pump at 105 psig; Diesel Fire Pump when <95 psig for more than 10 seconds Page 65 of 100 12/12/2012

UNIT 3 2013 Exam Date 02/1112013 Question: 66 Unit 3 is in a refueling outage with fuel movement in progress. Per EN-OP-115, Conduct of Operations, what is the minimum Unit 3 on-duty control room compliment for this condition?

(Assume Fire Brigade Leader is staffed by Unit 2 individual and a Unit 3 SRO is staffed as Refueling SRO)

A. ONE Shift Manager, ONE Control Room Supervisor, TWO Reactor Operators, ONE Shift Technical Advisor.

B. ONE Shift Manager, ONE Control Room Supervisor, TWO Reactor Operators.

C. ONE Shift Manager, TWO Reactor Operators, ONE Shift Technical Advisor D. ONE Shift Manager, ONE Control Room Supervisor, ONE Reactor Operators.

Page 66 of 100 12112/2012

UNIT 32013 Exam Date 02/11/2013 Question: 67 The plant is at 100% power with all systems in automatic when both heater drain pumps trip.

Which of the following actions will the operator take in order to stabilize the plant?

A. Immediately run the turbine back to 70% power to prevent a main feed pump trip.

B. Reduce turbine load as needed to match steam flow and feed flow while maintaining MBFP suction pressure above 265 psig.

C. Reduce turbine load to 900 MW and ensure MBFP suction pressure remains greater than 265 psig at the new load.

D. If MBFP suction pressure decreases to 265 psig, reduce turbine load until suction pressure is greater than 265 psig.

Page 67 of 100 1211212012

UNIT 32013 Exam Date 02111/2013 Question: 68 The plant had been operating at 100% power for the last 100 days, when a reactor trip occurred 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months ago.

Conditions prior to the trip were:

Core burnup is 10,000 MWD/MTU (MOL)

Boron concentration was 700 ppm

Control Bank D was at 230 steps The estimated critical position is Control Bank D at 120 steps. The operators have just completed pulling the shutdown banks. The source range counts (in CPS) while withdrawing the shutdown banks are:

SR# Initial CPM SB"A" SB"B" SB"C" SB"D" 31 165 180 210 230 250 32 180 210 240 260 280 Which action below should crew take?

A. Suspend rod withdrawal, re-evaluate all inputs and mathematics used in the ECP, and direct Chemistry to obtain an RCS boron sample.

B. Fully insert all CONTROL RODS, and re-evaluate all inputs and mathematics used in the ECP.

C. Obtain new baseline counts for both source range channels and commence pulling CONTROL BANKS. Criticality is expected at about the 5th doubling.

D. Calculate the amount and borate so that criticality will occur at 120 steps on Control Bank D and resume CONTROL RODS to go critical. Criticality is expected at about the 5th doubling.

Page 68 of 100 12/12/2012

UNIT 32013 Exam Date 02/11/2013 Question: 69 Given the following conditions:

A reactor startup is in progress.

A malfunction of the Rod Control Bank Overlap Unit has caused Control Bank 0 Rods to begin withdrawing 20 steps earlier than designed.

Which ONE (1) of the following describes the impact of this malfunction if it were allowed to continue during the power increase?

A. QPTR limits may be challenged.

B. Shutdown margin may be reduced if a reactor trip occurs.

C. Power Peaking factors may rise to unacceptable values.

D. The Safety Analysis for ejected rod worth may be invalid.

Page 69 of 100 1211212012

UNIT 32013 Exam Date 02111/2013 Question: 70 Per POP-1.1, Plant Heatup from Cold Shutdown Condition, when are the Over Pressure System (OPS) states links required to be OPENED?

A. Prior to closing the final RCS vent path.

B. Prior to starting the first RCP.

C. Prior to exceeding 200°F.

D. Prior to exceeding 350°F.

Page 70 of 100 12/1212012

UNIT 32013 Exam Date 0211112013 Question: 71 The following plant conditions exist:

100 % power

32 EDG is out of service for preventative maintenance The maintenance supervisor requests a work permit for 31 AFW pump to be worked now due to man power availability. The estimated completion time for the work is 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Should 31 AFW pump be taken out of service? Select the proper action to be taken with the justification for your choice.

A. Yes. Technical Specifications allow for one MDAFW pump to be out of service, provided it is returned to service within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and the remaining pumps are demonstrated operable.

B. Yes. Technical Specifications allows for one MDAFW pump to be out of service, for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months provided the remaining pumps are demonstrated operable.

C. No. Technical Specifications requires all 3 AFW pumps with their associated piping and valves to be operable if any EDG is inoperable.

D. No. Technical Specifications state that if one EDG is out of service then the other 2 EDG's and their associated safeguards equipment should be maintained operable.

Page 71 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 72 The following conditions exist:

The PAB Sump Tank Room is posted as a "Locked High Radiation Area".

The area is at the MINIMUM required radiation level for the posting in all posted areas.

Your present annual exposure is 500 mRem.

You are required to perform a retest within the posted area.

What would be your maximum calculated stay time in this area be in order to avoid exceeding the Entergy Routine Annual Limit for radiation exposure per EN-RP-201, Dosimetry Administration?

A. 30 minutes B. 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months C. 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months D. 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Page 72 of 100 12/1212012

UNIT 3 2013 Exam Date 0211112013 Question: 73 Unit 3 is at power and CH-LCV-459, Letdown Isolation, has failed closed. Maintenance believes the reason the valve failed closed is due to a problem with a solenoid on the valve that can be repaired in 5 minutes. Dose rates are 2000 mR/hr at the job site. Which of the following describes the requirements per OAP-007, Containment Entry and Egress, that need to be satisfied to make this repair?

(Assume all other procedural requirements for the repair and entry are met and workers will not exceed annual exposure limits from this job.)

A. Reactor power must be lowered until dose rates are less than 1000 mR/hr at the job site prior to allowing work to begin.

B. Since the expected dose is less than 1000 mRem, only normal OAP-007 SM authorization is required prior to allowing job to begin.

C. Unit AOM and RP Manager approvals are required prior to allowing job to begin.

D. Since the valve is outside the crane wall, only normal OAP-007 SM authorization is required prior to allowing job to begin.

Page 73 of 100 12/1212012

UNIT 32013 Exam Date 02111/2013 Question: 74 An AOP is being implemented when it is determined that a reactor trip and SI are required. Per OAP-015, AOP and ONOP User's Guide, when can the CRS direct that actions in the AOP be resumed (assuming these actions will not detract from performance of the EOP)?

A. Only when called for by the EOP in use.

B. When E-O has been exited.

C. When SI is reset.

D. After completion of step 4 of E-O.

Page 74 of 100 12/12/2012

UNIT 32013 Exam Date 02/11/2013 Question: 75 Security has just confirmed that a Security CODE RED exists. Armed intruders have gained entry into the protected area.

Which one of the following actions should be taken?

A. Trip the reactor, ensure AFW pumps start, perform E-O in parallel with AOP-SEC-1 B. Start AFW Pumps, trip the reactor, perform E-O in parallel with AOP-SEC-1 C. Perform a normal plant shutdown in parallel with AOP-SEC-1 D. Maintain plant in a stable condition while performing AOP-SEC-1 Page 75 of 100 12112/2012

ES~401 Site~Specific SRO Written Examination Form ES401~8 Cover Sheet u.s. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date: Facility/Unit: IPEe Unit 3 Region: I I8.11 III IV Reactor Type: w~eE BW GED Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to complete the combined examination, and 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months if you are only taking the SRO portion.

Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicant's Signature Results RO/SRO-OnlylTotal Examination Values I -- I -- Points Applicant's Scores / -- / -- Points Applicant's Grade /

-- / -- Percent

UNIT 3 2013 Exam Date 02/11/2013 Question: 1 Operators suspect a vapor space leak through either a Pressurizer Safety or PORV. What indication combinations are available to help the operator determine which valve is faulted?

ACOUSTIC MONITOR TAILPIPE TEMPERATURE A. each safety each safety each PORV common PORV line B. common safety line common safety line each PORV each PORV C. each safety each safety common PORV line common PORV line D. common safety each safety line common PORV line each PORV Page 1 of 100 1211212012

UNIT 32013 Exam Date 02/1112013 Question: 2 Given the following conditions:

A Small Break LOCA has occurred.

The crew is performing the actions of ES-1.2, "POST LOCA COOLDOWN AND DEPRESSURIZATION".

All SI pumps are running.

All RCPs are running.

RCS cooldown via High Pressure Steam Dumps is ongoing.

RCS Tave is 510°F and lowering at a rate of 90°F/Hr.

RCS pressure is 1350 psig and stable.

PZR level indicates 38% and slowly rising.

Which of the following describes the next major action to be implemented in the EOP to mitigate the current conditions?

A. Depressurize the RCS using normal spray to collapse voids and refill the PZR.

B. Transition to ES-1.1, "SI TERMINATION", to immediately stop all SI pumps.

C. Stop all but 34 RCP and begin the SI flow reduction process by stopping ECCS pumps.

D. Stop the cooldown. Energize all PZR heaters to collapse voids and stabilize PZR level.

Page 2 of 100 12/1212012

UNIT 32013 Exam Date 0211112013 Question: 3 Given the following:

A large break LOCA has occurred.

The 31 spray pump is out of service.

All other ESF equipment started on demand.

The crew has entered ES-1.3, Transfer to Cold Leg Recirculation.

Which of the following correctly describes the containment spray pump operation when recirc switch 1 is placed to on during this transfer?

A. Spray pump 32 will continue to operate and must be manually tripped when RWST level reaches 1.5 feet.

B. Spray pump 32 will trip when recirc switch 1 is placed to on. The pump must be restarted and must be manually tripped when RWST level reaches 1.5 feet.

C. Spray pump 32 will continue to operate and will automatically trip when RWST level reaches 1.5 feet.

D. Spray pump 32 will trip when recirc switch 1 is placed to on. The pump must be restarted and will automatically trip when RWST level reaches 1.5 feet.

Page 3 of 100 12112/2012

UNIT 32013 Exam Date 02/11/2013 Question: 4 The plant is at 25% power, on chemistry hold for secondary cation concentration, Action Level 1.

A loss of offsite power occurs. The plant remains on-line and all equipment operates as designed.

What is the configuration of the AFW system?

A. 32 and 33 AFW pumps are running, supplying auxiliary feedwater to all steam generators.

B. 31 and 32 AFW pumps are running, only 31 and 32 Steam Generators are being supplied auxiliary feedwater.

C. 32 and 33 AFW pumps are running, only 33 and 34 Steam Generators are being supplied auxiliary feedwater.

D. 31,32 and 33 AFW pumps are running, supplying auxiliary feedwater to all steam generators.

Page 4 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 5 Which of the following identifies the first pump checked, and if necessary started, in 3-AOP 480V-1, Loss of Normal Power to Any 480V Bus and why this pump is addressed first?

A. A charging pump to ensure RCS inventory is adequate to prevent letdown isolation B. A charging pump to ensure RCP Seal cooling if CCW to thermal barrier also lost C. A Service Water Pump to ensure cooling is maintained to Hydrogen Seal Oil Coolers D. A Service Water Pump to ensure cooling to Emergency Diesel Generators Page 5 0[100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 6 Given the following conditions:

RHR is in service at Reduced Inventory conditions at 65 feet.

AOP-RHR-1, Loss of RHR, has been entered.

Which ONE of the following indications in the Control Room are used to determine if cavitation is occurring.

A. RHR flow high coincident with RVLlS Full Range level low.

B. RHR flow and pump amps increasing as RCS inventory is raised.

C. RHR flow and Associated 480 volt bus amp oscillations.

D. RHR pump flow and RVLlS Full Range level oscillations.

Page 6 of 100 12112/2012

UNIT 32013 Exam Date 0211112013 Question: 7 Given the following:

Unit is at 100% power.

CCW SURGE TANK #31/#32 LEVEL alarms are lit

A Low level condition is present.

CCW surge tanks level are DECREASING.

The makeup valve is OPEN.

There is NO indication of relief valve leakage in any CCW-cooled components Which ONE of the following is the location of the leak?

A. RCS sample coolers during sampling B. Non-Regenerative heat exchanger C. Thermal barrier heat exchanger D. Seal return heat exchanger Page 7 of 100 12/12/2012

UNIT 32013 Exam Date 02/11/2013 Question: 8 With the plant initially at 100% power and rod control in manual, a short duration spurious runback occurs Current conditions are as follows:

Power has stabilized at 80%.

Tave has increased to 593°F.

Pressurizer level has risen to 80%.

Pressurizer pressure is currently 2350 psig.

PORV 455C indicates OPEN.

PORV 456 indicates CLOSED.

PRT pressure and level are increasing.

All Pressurizer backup heaters are energized.

In accordance with EN-OP-115 Conduct of Operations, what action is required to be taken by the operators?

A. Trip the reactor and enter E-O, since an automatic reactor trip should have occurred.

B. Open PORV 456, since it should already be OPEN.

C. Close PORV 455C, since it should have already CLOSED.

D. Turn all pressurizer backup heaters to OFF, since they should not have energized.

Page 8 of 100 12/12/2012

UNIT 32013 Exam Date 0211112013 Question: 9 Reactor Trip and Bypass Breakers have been aligned to support testing of Reactor Protection Train A when an inadvertent Safety Injection signal is generated on Safety Injection Train A.

Which of the following describes the Reactor Protection System response?

A. An A TWS occurs because Reactor Trip Breaker A and Reactor Trip Bypass Breaker B remain closed.

B. An ATWS occurs because Reactor Trip Breaker B and Reactor Trip Bypass Breaker A remain closed.

C. The Reactor trips. Reactor Trip Breaker A, Reactor Trip Breaker 8 , and Reactor Trip Bypass Breaker A are open. Reactor Trip Bypass Breaker B is locked open.

D. The Reactor trips. Reactor Trip Breaker A, Reactor Trip Breaker 8 , and Reactor Trip Bypass Breaker B are open. Reactor Trip Bypass Breaker A is locked open.

Page 9 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 10 Given:

The Unit was operating at 100% power.

A Steam Generator Tube Ruptured occurred in 34 SG.

Off-site power was lost coincident with the reactor trip.

Which of the following describes how the E-3 Cooldown will be controlled?

A. Limited to 0.4 E6 Ibm/hr to prevent false Integrity Status Tree Entry.

B. Maximum achievable rate using all intact SG atmospheric dump valves.

C. Limited to ensure final temperature will remain above 320°F D. Maximum achievable rate using available condenser steam dumps.

Page 10 of 100 12112/2012

UNIT 32013 Exam Date 02111/2013 Question: 11 Given the following plant conditions:

Plant is operating at 81 % power

No equipment is out of service

31 and 32 Condensate Pumps operating

31 Condensate Pumps trips due to a winding short Which of the below statements describes the required operator actions to mitigate the transient?

A. Reduce turbine load as necessary to maintain MBFP suction pressure greater than 265 psig.

B. Verify 31 and 33 AFW Pumps automatically start; verify MBFP suction pressure greater than 265 psig.

C. Start 33 Condensate Pump, reduce turbine load as necessary to maintain MBFP suction pressure greater than 265 psig.

D. Trip the Reactor, Go To E-O, Reactor Trip or Safety Injection.

Page 11 of 100 12112/2012

UNIT 3 2013 Exam Date 02/11/2013 Question: 12 Unit 3 is in Mode 5 on RHR with 31 and 33 CCW Pumps in service. Automatic safety injection was disabled shortly after entering Mode 5. All 3 EDGs are operable. Maintenance wants to perform an activity that will disable the auto start of 31 CCW Pump. Which of the following would you expect regarding this activity?

A. The activity will be allowed since auto starts of CCW pumps during a station blackout are already disabled when automatic safety injection is disabled.

B. The activity will be allowed since auto starts of 31 CCW pump would not occur during a station blackout since 31 CCW is already in service.

C. The activity will not be allowed. 31 CCW is required to be operable since RHR is in service. Loss of auto start capability will render 31 CCW pump inoperable.

D. The activity may be allowed after assessing for risk impact of having to manually restart 31 CCW during a station blackout.

Page 12 of 100 12/12/2012

UNIT 32013 Exam Date 02111/2013 Question: 13 The plant is at normal 100% power lineup with Channel B selected for feed flow and steam flow control. Which set of actions will be required per 3-AOP-IB-1, Loss of Power to an Instrument Bus, for a loss of 31 and 31A Instrument Busses?

I - Swap feed flow and steam flow to the A channel II - Place MBFPs in Manual control III - Place MFRVs in Manual control A. I and II B. land III C. II and III D. I, II, and III Page 13 of! 00 12112/2012

UNIT 32013 Exam Date 0211112013 Question: 14 Given the following plant conditions:

The Unit is at 20% power

A loss of ALL normal Service Water Pumps has occurred due large amount of debris on the screens

No Circ Water Pumps are available due to the debris Which of the following describes the required operator action for the above condition?

A. Trip the Reactor, do NOT SHUT the MSIVs and initiate E-O, Reactor Trip or Safety injection.

B. Trip the Reactor, SHUT the MSIVs and initiate E-O, Reactor Trip or Safety injection.

C. Immediately align Backup Service Water Pumps, 37, 38 and 39 to the essential service water header.

D. Commence a rapid plant shutdown as long as temperatures remain below the trip setpoint.

Page 14 of 100 1211212012

UNIT 32013 Exam Date 02/11/2013 Question: 15 Unitt 3 is in a normal 100% power lineup when the "480 VOLT SAFEGUARD BUS.

UNDERVOLTAGE" alarm annunciates and immediately clears. The cause is a grid disturbance that affected 138 KV Feeder 95331. Which of the following describes the direction specified in ARP-005, Panel SBF SAFEGUARDS? .

A. Per AOP-138KV-1, Loss of Power to 6.9 KV Bus 5 and/or 6, check status of SFP pumps because historically the standby pump has started due to grid disturbances.

B. Per AOP-138KV-1, Loss of Power to 6.9 KV Bus 5 and/or 6, check status of SFP pumps because historically the running pump has tripped due to grid disturbances.

C. Per a checklist in SOP-EL-5, Operation of On-Site Power Sources, check status of SFP pumps because historically the standby pump has started due to grid disturbances.

D. Per a checklist in SOP-EL-5, Operation of On-Site Power Sources, check status of SFP pumps because historically the running pump has tripped due to grid disturbances.

Page 15 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 16 The crew has completed the actions of ECA-1.2, LOCA Outside Containment.

Pressurizer level is 35% and stable.

Steam Generator narrow range levels are 30%.

Subcooling is 35°F.

RCS pressure is 1400 psig and slowly lowering.

Which ONE (1) of the following procedures will be performed next?

A. ES-1.1, SI Termination.

B. E-O, Reactor Trip or Safety Injection.

C. ECA-1.1, Loss of Emergency Coolant Recirculation.

D. E-1, Loss of Reactor or Secondary Coolant.

Page 16 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 17 The plant is in an emergency condition, and the control room operators are responding to a loss of secondary heat sink. RCS bleed-and-feed is in progress, and RCS temperatures are stable. The operators restore a feedwater source and prepare to feed the S/Gs, which are hot and dry. The SM directs them to re-establish FW flow to only one S/G rather than to all of the S/Gs.

The primary reason for feeding only one S/G under these conditions is to:

A. Prevent a rapid cooldown of the RCS that could lead to a pressurized thermal shock condition.

B. Ensure that if S/G failure occurs due to excessive stresses, the failure is isolated to one S/G.

C. Ensure pump runout conditions will not occur for the FW source until adequate heat sink established D. Determine if one S/G is capable of maintaining adequate heat sink so that RCS bleed and-feed can be terminated.

Page 17 of 100 12112/2012

UNIT 32013 Exam Date 0211112013 Question: 18 Given:

A LOCA has occurred.

Operators were performing ECA-1.1, Loss of Emergency Coolant Recirculation when Containment pressure is noted to be 22.3 psig.

The decision of whether to remain in ECA-1.1 or transition to another procedure was properly made.

Which of the following describes how the Containment Spray system will be operated, and why?

The Containment Spray System is operated as directed in...

A. ECA-1.1 because it establishes minimum required containment spray flow and conserves RWST inventory.

B. FR-Z.1, Response to High Containment Pressure, since restoration of the critical safety function takes precedence.

C. ECA-1.1 since FRPs (Functional Restoration Procedures) are NOT implemented during the performance of ECA-1.1.

D. FR-Z.1 because containment is the last fission product barrier actions are the same as SAMGs (Severe Accident Management Guidelines)

Page 18 of 100 12112/2012

UNIT 32013 Exam Date 02111/2013 Question: 19 Given the following:

The plant was initially at 95% power.

The reactor tripped 20 minutes ago.

INTERMEDIATE RANGE NO.1 LOSS OF COMPENSATE VOLTAGE alarm is annunciated.

Which ONE (1) of the following describes the response of Intermediate Range N-35 to the loss of compensating voltage and what actions are given for this condition?

A. Indicates LOW; Press appropriate Intermediate Range Permissive Defeat Button to re energize Source Range Channel N31 B. Indicates HIGH; Press both Source Range AlB Logic Trip Block Buttons to re-energize both Source Range Channels C. Indicates LOW; Press Source Range A Logic Trip Block Button to re-energize Source Range Channel N31 D. Indicates HIGH; Press both Intermediate Range Permissive Defeat Buttons to re energize both Source Range Channels Page 19 of 100 12/12/2012

UNIT 3 2013 Exam Date 02/1112013 Question: 20 Given the following conditions:

Plant is in refueling performing a core reload

Transfer tube gate valve is opened

An irradiated assembly has just removed from the Containment Upender and is in the mast

The following occurs: Reactor pit sump pump indicates ON

High level Reactor Pit alarm annunciates

Containment and Recirculation sump levels are rising slowly

R-2 and R-7 are in alarm and indications are rising Which one of the following actions would be directed by AOP-FH-1 "Fuel Damage OR Loss of SFP/Refueling Cavity Level"?

Place the Fuel Assembly A. In the upender and lower to horizontal position B. directly west of the RCC Change Fixture and unlatch the assembly from the gripper C. in any accessible spent fuel pit location D. in the RCC Change Fixture Page 20 of 100 12/12/2012

UNIT 32013 Exam Date 0211112013 Question: 21 Which of the following describes the Reactor Operator's task for safe shutdown outside the control room and reason for this task?

A. Establish charging within 30 minutes of the event initiation to ensure pressurizer level remains in the indicating range.

B. Establish charging with 60 minutes of the event initiation to ensure adequate shutdown margin is maintained.

C. Establish AFW flow within 30 minutes of the event initiation to ensure steam generators do not dry out.

D. Establish AFW flow within 60 minutes of the event initiation to ensure RCS pressure does not exceed PORV setpoints.

Page 21 of 100 12112/2012

UNIT 32013 Exam Date 02/11/2013 Question: 22 The operating team has entered AOP-HIACT-1, High RCS Activity, due to elevated RCS activity as noted by Chemistry. Which of the following is true regarding R-63 (Gross Failed Fuel Detector) readings per AOP-HIACT-1?

A. If R-63 is in alarm, verify that RCS sample isolation valves has automatically closed.

B. If R-63 is in alarm, verify that letdown has automatically diverted through the standby mixed bed.

C. If activity on R-63 is > 50 !lCi/cc, then no samples of the RCS are to be taken.

D. If activity on R-63 is > 50 !lCi/cc, then consideration should be given to using the Post Accident Sampling System.

Page 22 of 100 12112/2012

UNIT 32013 Exam Date 02111/2013 Question: 23 Given:

The team is performing the actions of ES-1.1, "SI Termination"

At Step 4 of ES-1.1, The team secured all SI and RHR Pumps

At step 8 of ES-1.1, the team secured all but one charging pump

RCS Pressure and Pressurizer Level begin to lower after the charging pumps are secured Which one of the following describes the required operator actions in accordance with ES-1.1?

A. Monitor RCS Pressure and Pressurizer Level, if pressure and level continue to lower, restart SI pumps and return to procedure previously in effect.

B. Manually re-initiate SI and Transition to E-O, "Reactor Trip or Safety Injection" step 1.

C. Adjust charging flow and if Pressurizer Level cannot be maintained, then restart SI pumps as required and transition to E-1, "Loss of Reactor or Secondary Coolant".

D. Restart one charging pump and if Pressurizer Level cannot be maintained transition to E-1, "Loss of Reactor or Secondary Coolant."

Page 23 of 100 12112/2012

UNIT 32013 Exam Date 0211112013 Question: 24 Given the following Plant conditions;

The plant is operating at 100% power, steady state.

The Pressurizer Level Defeat switch is in the Defeat 3 position The operator notes the following indications 3 minutes after a failure occurred:

All Pressurizer heaters are on.

Letdown isolation valve LCV-459 is open.

Charging pump speed slowly lowering.

Which ONE of the following describes a cause for these indications?

A. Pressurizer level channel 1 detector, LT-459, failed high.

B. Pressurizer level channel 2 detector, LT -460, failed high.

C. Pressurizer level channel 1 detector, LT-459, failed low.

D. Pressurizer level channel 2 detector, LT-460, failed low.

Page 24 of 100 1211212012

UNIT 32013 Exam Date 02111/2013 Question: 25 An INADEQUATE CORE COOLING condition is present during a small break loss of coolant accident. The following conditions are noted:

No safety injection pumps are available

Both RHR pumps are running

No RCPs are running

Both motor driven AFW pumps are operating

RCS pressure is 1100 psig

CETs are 765°F and rising slowly

RVLlS is 31% and lowering slowly

Steam generator pressure is 1050 psig Which of the following is true regarding recovery actions?

A. A secondary depressurization will cause enough heat rejection to the steam generators that safety injection system flow will no longer be required to combat the event.

B. A secondary depressurization will lower reactor coolant system pressure, allowing safety injection accumulators to recover the core.

C. Opening power-operated relief valves (PORVs) will take the reactor coolant system to saturation, allowing latent heat removal to bring down core temperature.

D. Opening power-operated relief valves (PORVs) will depressurize the reactor coolant system low enough to allow the RHR system to cool the core.

Page 25 of 100 12112/2012

UNIT 32013 Exam Date 02111/2013 Question: 26 Given the following conditions:

The reactor is tripped

A Safety Injection sjgnal has been generated

All RCPs are running

Average CETs indicate 515°F

RCS Pressure is 1800 psig and stable

CNMT Pressure is 24 psig and slowly increasing

Pressurizer level is off scale low

All ESF/ECCS equipment operated as designed Which ONE of the following describes why the RCPs should or should not be tripped?

A. RCP trip foldout page criteria are met The RCPs should be tripped Prevent exceeding peak clad temperature limits B. RCP trip foldout page criteria are met The RCPs should continue to run Provide forced cooling.

C. RCP trip foldout page criteria are NOT met The RCPs should be tripped Prevent damage to pumps D. RCP trip foldout page criteria are NOT met The RCPs should remain running Ensure adequate core cooling Page 26 of 100 12112/2012

UNIT 3 2013 Exam Date 02/1112013 Question: 27 FR-Z.2, "Response to Containment Flooding", addresses flooding in Containment as an ORANGE path. Which one of the following statements describes why this condition is considered a severe challenge to a critical safety function?

A. The highly corrosive nature of salt water may cause internal component failure during recirculation phase of an accident.

B. Critical components necessary for plant recovery may fail if submerged.

C. pH in the sump may be too low to ensure effective iodine removal and minimize corrosion.

D. RCS activity in the sump may cause the off-site dose limits to be exceeded if the water is transferred outside containment, Page 27 of 100 12/12/2012

UNIT 32013 Exam Date 0211112013 Question: 28 GIVEN:

The unit experienced a reactor trip coincident with a loss of off site power.

The crew entered 3-ES-0.2, natural Circulation Cooldown

Lift oil pump is running

RCS pressure is 350 psig

Seal Injection flow is 8 gpm to each RCP

Seal Leakoff flow is 0.15 gpm from each RCP

Number 1 seal leakoff temperature is 100°F

All bearing temperatures are less than 150°F

VCT pressure is 50 psig

Both Spray valves are in AUTO and closed

138kV power is available from Buchanan Switchyard

The crew is making preparations to start RCP 34 Which of the following actions should the CRS direct the operator to perform?

A. Direct the operator to start RCP 34, all conditions are salisified.

B. Direct the operator to start RCP 34, all conditions are not satisified but are not required.

C. Direct the operator to decrease VCT pressure to increase sealleakoff flow, then RCP 34 may be started.

D. Direct the operator to open RCP No.1 Seal Bypass Valve, 246 to increase sealleakoff flow, then RCP 34 may be started.

Page 28 of 100 12112/2012

UNIT 32013 Exam Date 0211112013 Question: 29 Unit 3 is at 100% power when a CCW leak is found on AC-TCV-130, Non-Regenerative Heat Exchanger CCW Outlet Temperature Control Valve. Repairs are expected to only take a few hours, but will require isolating CCW to AC-TCV-130. Which of the following is the likely action that will be taken for dealing with this issue?

A. The plant will have to proceed to Mode 5 to make repairs since isolation of this leak will cause a loss of cooling to letdown and RCP seal return.

B. The plant will have to proceed to placing RHR in service before isolation can occur because isolation will require removing all of CCW Loop 2 from service.

C. Repairs can occur on line, but letdown and all charging will be isolated. OM permission will be required to operate with thermal barrier cooling as the only means of cooling RCP seals.

D. Repairs can occur on line. Excess letdown will be placed in service with normal letdown secured to allow isolation of AC-TCV-130.

Page 29 of 100 12112/2012

UNIT 32013 Exam Date 02111/2013 Question: 30 One hour after the RHR system was placed in service to provide shutdown cooling, a tube in

31 RHR heat exchanger fails. Which of the following indications would the operator expect to see?

A. eew surge tank level would decrease and ReS inventory would increase B. eew surge tank level would decrease and RHR boron concentration would decrease

e. eew surge tank level would increase and eew radiation levels would increase D. CCW surge tank level would increase and 822A, RHR HX CCW Shutoff Valve would auto close.

Page 30 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 31 Unit 3 is on RHR with 34 RCP running and AC-MOV-730 and AC-MOV-731 energized. A loss of offsite power occurs and 31 EDG fails to start. 32 and 33 EDGs start and automatically power their 480V busses. During the loss of offsite power, RCS wide range pressure increased to 600 psi on both channels and remains at this pressure. Without operator action, what is the status of 730 and 731 after the 480V busses re-energize?

A. 730 and 731 are both closed or going closed.

B. 730 and 731 are both open and not going closed.

C. 730 is open and not going closed, 731 is closed or going closed.

D. 731 is open and not going closed, 730 is closed or going closed.

Page 31 of 100 12112/2012

UNIT 32013 Exam Date 0211112013 Question: 32 The plant experienced a LOCA coincident with loss of off-site power. RCS pressure remains above the shutoff head of the RHR pumps; however the conditions necessary to secure the pumps are not satisfied (Le., RCS pressure continues to slowly decrease).

Which of the following describes the RHR pump operations for this condition?

A. Auxiliary Component Cooling Water Pumps will circulate CCW through RHR pump seal and thermal barrier heat exchangers. Pumps can continue to operate indefinitely.

B. With no Component Cooling Water to the RHR pumps, the pumps can operate for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months together followed by a single pump for an additional 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

C. Shaft driven pumps will circulate CCW through RHR pump seal and thermal barrier heat exchangers. Pumps can continue to operate indefinitely.

D. With no Component Cooling Water to the RHR pumps, the pumps can operate for 45 minutes together followed by a single pump for an additional 45 minutes.

Page 32 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 33 Unit 3 experienced a LOCA and has transferred to cold leg recirculation when it is determined that inadequate low head flow exists due to high RCS pressure. The team transitions to the attachment to establish HHSI recirculation. Which of the following actions wi" be taken per this attachment?

A. Both Recirc Pumps will be operated to ensure adequate suction flow to the HHSI Pumps while maintaining recirc spray flow.

B. Only one Recirc Pump will be operated to ensure that no Recirc Pump is operating with its discharge check valve closed by flow from the other pump.

C. A" HHSI Pumps will be operated to ensure adequate core recirculation flow is established.

D. Only One HHSI Pump (31 or 33) will be operated.

Page 33 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 34 How are the discharge lines from the Pressurizer code safety valves and PORVs connected to the PRT?

A. The code safety valves and PORVs share a single common discharge line that connects to the PRT.

B. The code safety valves share a common discharge line to the PRT and the PORVs share a common discharge line to the PRT.

C. Each code safety valve has an individual discharge line to the PRT and the PORVs share a common discharge line to the PRT.

D. Each code safety valve and each PORV has an individual discharge line to the PRT.

Page 34 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 35 Given the following plant conditions:

Reactor Coolant System temperature is 185°F.

Reactor Coolant System pressure is 100 psig.

RHR cooldown operations have been established with both RHR pumps and heat exchangers in service.

The Shift Manager has directed the crew to establish a cooldown.

Which of the following describes how this is accomplished?

A. Opening AC-820 AlB is not limited. These valves provide coarse temperature control.

Opening SWN-35-1/2 is limited to 27.5° and 2]0 respectively. These valves provide fine temperature control.

B. Opening AC-820 AlB is limited to 27.5° and 27° respectively. These valves provide coarse temperature control.

Opening SWN-35-1/2 is not limited. These valves provide fine temperature control.

C. Opening AC-820 AlB is not limited. These valves provide fine temperature control.

Opening SWN-35-1/2 is not limited. These valves provide coarse temperature control.

D. Opening AC-820 AlB is limited to 27.5° and 2]0 respectively. These valves provide coarse temperature control.

Opening SWN-35-1/2 is not limited. These valves provide fine temperature control.

Page 35 of 100 12112/2012

UNIT 32013 Exam Date 0211112013 Question: 36 The controlling pressurizer pressure channel PT-455 has failed low. Which of the following describes plant response to heaters automatically energizing? (Assume No Operator Action)

A. Pressure increase will be limited by pressurizer sprays.

B. Plant pressure will be controlled by ONE PORV cycling.

C. Plant pressure will be controlled by BOTH PORVs cycling.

D. Pressure increases until the plant trips on high pressure.

Page 36 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 37 A rapid load reduction has just been completed. You observe the following:

pressurizer sprays partially open

modulating heaters full off

backup heaters on Which of the following would cause these indications?

A. Controlling pressurizer pressure channel failed high B. Pressurizer level insurge from the downpower C. Controlling pressurizer level channel failed low D. Pressurizer program level decrease from the downpower Page 37 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 38 Given the following plant conditions:

Unit 3 is at 80% power with all systems aligned normal.

PT-412A, Turbine First Stage Pressure, fails high.

For the above conditions, the control rods will be continuously (1) . If the rods continue to move after controls are shifted to MANUAL the operator will initiate a reactor trip, and then confirm that the reactor is tripped by observing the (2)

(1 ) (2)

A. Inserting Reactor Trip Breakers GREEN lights LIT, and the Bypass Breaker indicating lights DARK.

B. Inserting GREEN lights LIT on both the Reactor Trip Breakers and Bypass Breakers.

c. Withdrawing Reactor Trip Breakers GREEN lights LIT, and the Bypass Breaker indicating lights DARK.

D. Withdrawing GREEN lights LIT on both the Reactor Trip Breakers and Bypass Breakers.

Page 38 of 100 12/12/2012

UNIT 32013 Exam Date 02111/2013 Question: 39 Which of the following describes the automatic actions and basis for these actions if an under frequency condition exists on 6.9 KV Busses 1-4 with Unit 3 at 100% power?

A. 6.9 KV Busses 1-4 de-energize. This causes a reactor trip to ensure that KW/ft limits are not violated.

B. 6.9 KV Busses 1-4 de-energize. This causes a reactor trip prior to reaching conditions that could lead to lifting a pressurizer safety on a trip.

C. Trips the RCPs on busses with low frequency. This prevents damage to RCPs to ensure they are available if needed for a loss of cooling event.

D. All Reps trip. This causes a reactor trip to ensure that DNBR limits are not violated.

Page 39 of 100 12/12/2012

UNIT 32013 Exam Date 02/11/2013 Question: 40 A Safety Injection Signal occurred on both Trains A and B due to I&C testing. The operating crew reset the SI signal in accordance with emergency operating procedures. Non-SI Blackout Logic Defeat has not been reset. All components functioned as designed. Subsequently, 6.9 KV bus 5 normal feed breaker tripped on overcurrent. What is the status of CCW Pumps?

A. All CCW Pumps are secured B. 31 and 32 CCW Pumps are running 33 CCW Pump is secured.

C. All CCW Pumps are running D. 31 and 32 CCW Pumps are secured, 33 CCW pump is running.

Page 40 of 100 12112/2012

UNIT 3 2013 Exam Date 0211112013 Question: 41 Due to a catastrophic failure of the instrument air system in the aux boiler feed pump building, all air and backup nitrogen pressure has been lost.

Which of the following describes the impact on 32 Auxiliary Boiler Feed Pump and what actions are necessary.

A. Both PCV-1139 and HCV-1118 fail open on loss of air. Local manual control of valves is necessary to control pump speed.

B. Both PCV-1139 and HCV-1118 fail closed on loss of air. Local manual control of valves is necessary to control pump speed.

C. PCV-1139 fails closed and HCV-1118 fails open. Only local manual control of PCV 1139 is necessary to control speed.

D. PCV-1139 fails open and HCV-1118 fails closed. Only local manual control of HCV 1118 is necessary to control speed.

Page 41 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 42 Consider the following possible actions for SWN-TCV-1104/1105:

1. Fail OPEN on a loss of air to ensure adequate containment cooling is available in during an accident.

2. Fail CLOSED on a loss of air to ensure runout of ESW pump(s) does not occur on a loss of instrument air.

3. Get open signal SI circuit

4. Get open signal from High Containment Pressure circuit

5. Throttle to maintain temperature following SI reset From the above list, which of the following contains actions that are correct for SWN-TCV 1104/1105?

A. 1,4,5 B. 2,4 C. 1,3 D. 2,3,5 Page 42 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 43 The following plant conditions exist:

Fan Cooler #32 is tagged out for maintenance.

A Large Break Loss of Coolant Accident occurred coincident with a Los of Off Site Power

Emergency Diesel # 33 fails to start

Local efforts to start the diesel by the NPO were unsuccessful Based only on the actions taken above, what containment cooling equipment is expected to be running when the crew exits E-O?

A. #31, #33 and #34 Fan Cooler Units, #32 Spray Pump B. #33, #34,and #35 Fan Cooler Units, #31 Spray Pump C. #34 and #35 Fan Cooler Units, #31 Spray pump D. #34 and #35 Fan Cooler Units, #32 Spray Pump Page 43 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 44 The Unit is operating at 80% power with all systems in automatic. One Group of condenser steam dump valves fails full OPEN. Assuming that NO operator action occurs, what will be the resulting Rx power level?

A. 0%

B. 70%

C. 80%

D. 90%

Page 44 of 100 12/1212012

UNIT 32013 Exam Date 02/1112013 Question: 45 3-AOP-FW-1, Loss of Feedwater, requires tripping the reactor if both MBFPs are not operating when reactor power is above a specified value. Select the statement below that best describes the basis for this step.

The reactor is tripped if power is >___ % because a single MBFP can only sustain SG level at power level no higher than %.

A. 70,70 B. 80,70 C. 80,80 D. 70,80 Page 45 of 100 12112/2012

UNIT 32013 Exam Date 0211112013 Question: 46 The plant is shutting down for a refueling outage and is currently at 250 MWe about to perform a planned Reactor Trip. All Main Feedwater equipment is available and all steps of POP-2.1 and POP-3.1 have been satisfied at this point in the shutdown. Which of the following is the expected configuration of Main Feedwater prior to the trip?

A. Both MBFPs are in service Low Flow Bypass Feed Regulation Valves are in service B. One MBFPs is in service, One MBFP is in Standby Low Flow Bypass Feed Regulation Valves are in service C. Both MBFPs are in service Main Feed Regulation Valves in service D. One MBFPs is in service, One MBFP is in Standby Main Feed Regulation Valves in service Page 46 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 47 During the startup of 31 Auxiliary Boiler Feedwater pump as part of a plant shutdown, the operator inadvertently places the recirculation valve control switch in close instead of automatic. What affect will this have on the Auxiliary Boiler Feedwater pump?

A. The low flow trip is disabled; the pump will overheat if flow decreases too low.

B. The low follow trip remains enabled, the pump will trip if flow drops below 40 gpm for

>15 seconds.

C. The low flow alarm only is disabled, but the pump will still trip if flow remains below 130 gpm for >15 seconds.

D. The low flow alarm is enabled; an orificed line to the CST will maintain minimum flow.

Page 47 of 100 12/12/2012

UNIT 32013 Exam Date 02111/2013 Question: 48 A grid disturbance in the Buchanan Switchyard resulted in a unit trip and loss of off site power.

The BOP identifies buses SA and 6A are energized from their respective diesel generators.

Of the following conditions, which will prevent the automatic closure of the 31 Emergency Diesel Generator breaker (S2/EG-1)?

A. Fault on 480 VAC Bus 3A B. Normal feed breaker for Bus 2A (S2/2A) closed C. Bus 2A-3A tie breaker is closed.

D. Normal feed breaker for Bus 3A (S2/3A) closed Page 48 of 100 12112/2012

UNIT 32013 Exam Date 0211112013 Question: 49 Given:

The plant experienced a steam break in the turbine building.

All equipment functioned as designed.

All required procedural actions were completed

When the crew entered ES-1.1, 51 Termination, off-site power was temporarily lost.

Which of the following describes actions (if any) related to the electrical lineup?

A. MCCs with battery chargers must be aligned and reset within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

B. MCCs with battery chargers must be aligned and reset within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

C. MCCs with battery chargers do not strip for Blackout, no alignment is necessary.

D. MCCs previously reset will remain energized; no further action necessary.

Page 49 of 100 12/12/2012

UNIT 32013 Exam Date 02/11/2013 Question: 50 The fire main in the 480V Switchgear room ruptured resulting in a loss of all 480V AC buses.

The crew entered ECA-O.O, Loss of All AC Power and started the Appendix R Diesel Generator. Bus 312 is energized and all Appendix R equipment is available.

Which of the following properly states the post-accident instrumentation available with power from the Appendix R Diesel Generator?

A 31, 32, 33 SG Narrow Range Level Pressurizer Level Pressurizer Pressure CST Level R-27 Core Exit Thermocouples B. 31,32,33 SG WR Level Pressurizer Level Pressurizer Pressure 31 Loop WR Thot 31 Loop WR Tcold N-38 C. 31,32,33 SG Narrow Range Level Pressurizer Level Pressurizer Pressure CST Level R-27 31 Loop WR Tcold D. 31,32,33 SG WR Level Pressurizer Level Containment Pressure 31 Loop WR Thot RWST Level N-38 Page 50 of 100 12/12/2012

UNIT 32013 Exam Date 0211112013 Question: 51 R-19 (SG Blowdown Activity) is in alarm and has caused an auto-closure of SG sample isolation valves. Unit 3 remains on line. Which of the following actions will be necessary to re open these valves to sample SGs?

A. Acknowledge R-19 alarm on RM-23 panel to re-open valves.

B. Purge R-19 or raise alarm setpoint to re-open valves.

C. Place individual SG sample isolation valves in Rad Bypass position.

D. Press individual valve reset buttons on Panel SMF.

Page 51 of 100 12/12/2012

UNIT 32013 Exam Date 02111/2013 Question: 52 A large leak has developed on the Essential Service Water Header causing SW Header pressure to drop to 40 psig. All available SW Pumps are operating and component temperatures are elevated but stable below alarm setpoints. The plant is currently at 25%

power.

Which of the following describes the required operator action for the above condition?

A. Immediately commence a rapid plant shutdown, main turbine bearing temperatures are expected to rise rapidly.

B. Maintain present power level unless turbine generator bearing oil drain temperatures cannot be maintained below 180°F then trip the turbine.

C. Maintain present power level unless oil temperature from the MBFP bearings cannot be maintained below 190°F then trip the affect MBFP(s).

D. Initiate a plant shutdown to Mode 3 using POP-3.1, Plant Shutdown from 45% Power as long as adequate cooling can be maintained.

Page 52 of 100 12112/2012

UNIT 32013 Exam Date 02/11/2013 Question: 53 Given the following:

The plant is at 100% power

32, 33, 36 Service Water Pumps are running

31,34 and 35 Service Water Pumps are in AUTO

The Service Water Pump Mode Selector Switch is in the 4-5-6 position

The tie breaker between 2A and 3A (2AT3A) is OOS for maintenance.

Assuming no operator action, which one of the following describes the status of the SW Pumps after a Reactor Trip coincident with a Loss of Off-site power occurs?

A. 32, 34, and 36 SW Pumps will be running B. 35 and 36 SW Pumps will be running C. 34, 35, and 36 SW Pumps will be running D. 34 and 36 SW Pumps will be running Page 53 of 100 12112/2012

UNIT 32013 Exam Date 02/11/2013 Question: 54 Unit 3 is at 100% power with 31 Instrument Air Compressor (lAC) in HAND and 32 lAC in AUTO. SOV-1142, Station Air Makeup to Instrument Air is initially closed when a rupture occurs somewhere in the Instrument Air System. What indications do you expect to see in the Control Room for this event?

A. At 105 psig a red lightfor 32 lAC and at 100 psig a red light for SOV-1142 B. At 100 psig a red light for 32 lAC and at 95 psig a red light for SOV-1142 C. At 95 psig a red light for 32 lAC and at 90 psig a red light for SOV-1142 D. At 90 psig a red light for 32 lAC and at 85 psig a red light for SOV-1142 Page 54 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 55 Unit 3 is in a forced maintenance outage with RCS temperature being maintained at 300°F while repairs are being made to 32 AFW Pump. Material is being brought into containment through the 95 ft Airlock, when the inner door is damaged. The door cannot be closed. No other equipment was damaged. What is the operational impact of this event?

A. There is no impact in the current mode. Repairs will be necessary prior to entering a higher mode.

B. If the outer door is veri'fied closed within one hour and locked closed within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , operation can continue in the current mode.

C. The airlock is inoperable. The airlock must be declared operable within one hour or the plant will have to be in Mode 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

D. The containment system is inoperable. The system must be declared operable within one hour or the plant will have to be in Mode 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Page 55 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 56 Given:

The unit is at 100% power

31 EDG is OOS for a breaker PM

A fault occurred in the Buchanan switchyard resulting in a loss of 138KV power.

What is the immediate impact on the plant?

A. The reactor will trip due to loss of both Rod Drive MG Sets when bus 138kV power is lost.

B. 31 Rod Drive MG set was previously secured; the reactor trips when bus 138kV power is lost.

C. The reactor will remain at approximately1 00% power with only 31 Rod Drive MG set energized.

D. The reactor will remain at approximately100% power with both Rod Drive MG Sets energized.

Page 56 of 100 12112/2012

UNIT 32013 Exam Date 0211112013 Question: 57 Control Room operators are responding to a loss of secondary heat sink. Attempts to restore feedwater flow to the steam generators have been unsuccessful, so the operators are attempting to provide "Bleed and Feed Cooling" to the RCS. Only two Charging Pumps have been started. During performance of these actions there is a delay in starting SI Pumps and the STA recommends opening the PZR PORVs while waiting for SI flow to be established.

Which of the following is your assessment of the STA's recommendation?

A. Agree. With two Charging Pumps running it is acceptable to open the PORVs while continuing with the steps necessary to establish SI flow.

B. Agree. The procedure Caution states that due to a loss of secondary heat sink, the steps to implement bleed and feed should be immediately initiated.

C. Disagree. The correct action would be to start the third Charging Pump then open both PORVs while waiting for SI flow to be established.

D. Disagree. Opening the PORV before SI Pumps are operating could result in uncovery and severe damage to the core.

Page 57 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 58 Given the following conditions:

The unit was operating at 100% power

A malfunction has caused a Pressurizer Safety Valve to open and stick open

A Reactor Trip and Safety Injection occurred

The RCS rapidly depressurized to saturation conditions

Pressurizer level initially dropped and then began to increase rapidly What is the relationship between pressurizer level and RCS inventory under these conditions?

A. Level is not an accurate indication of inventory, because the pressurizer level channel reference legs will flash causing an indicated increase in level B. Level is not an accurate indication of inventory, because RCS voiding may result in a rapidly increasing pressurizer level.

C. Level is an accurate indication of level, because hydraulic pressure would force any voids into the pressurizer steam space and out the safety valve.

D. Level is an accurate indication of inventory, because voiding would occur in the pressurizer prior to reaching saturation conditions in the RCS.

Page 58 of 100 12112/2012

UNIT 32013 Exam Date 02/11/2013 Question: 59 With the plant operating at 90% power, the following alarms have annunciated:

NIS POWER RANGE OVER POWER ROD STOP

NIS POWER RANGE SINGLE CHANNEL HIGH RANGE TRIP

NIS POWER RANGE LOSS OF DETECTOR VOLTAGE

NIS POWER RANGE DROPPED ROD ROD STOP All Power Range Channels are indicating 90% power. Which of the following are correct, with no operator action?

A. Instrument power fuse has blown, Control rods will not move B. Instrument power fuse has blown, Control rods can only be inserted C. Control power fuse has blown, Control rods will not move D. Control power fuse has blown, Control rods can only be inserted Page 59 of 100 12/1212012

UNIT 3 2013 Exam Date 02/1112013 Question: 60 Select the answer which describes when an RCP would be restarted while performing FR-C.1, IIRESPONSE TO INADEQUATE CORE COOLING".

A. Blowdown of the Steam Generators to Atmospheric pressure has been unable to reduce CET (Core Exit Thermocouple) temperatures below 1200°F.

B. All three HHSI pumps have failed to start and CET temperatures are above 1200°F.

C. Opening of PORVs has been unsuccessful in reducing CET temperatures below 1200°F.

D. RCPs must be started any time CET temperatures exceed 1200°F.

Page 60 of 100 12112/2012

UNIT 3 2013 Exam Date 02/1112013 Question: 61 What is the purpose of the Sodium Tetraborate baskets in the Vapor Containment Building 46' elevation?

A. Establish an alkaline pH to maintain Iodine in solution.

B. Establish an alkaline pH to maintain Hydrogen in solution.

C. Establish a neutral pH to reduce Iodine concentration in solution.

D. Establish a neutral pH to reduce Hydrogen concentration in solution.

Page 61 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 62 Given the following plant conditions on Unit 3:

The unit is in Mode 6 with refueling activities in progress.

Containment purge is in service.

A fuel element accidentally dropped into the cavity.

R-11, R-12 and R-14 have a HIGH alarm.

R-25 and R-26, VC High Range Area Monitors, have a HIGH alarm.

Which ONE of the following actions would occur, assuming that operators follow the required actions of 3-AOP-FH-1, "Fuel Damage or Loss Of SFP/Refueling Cavity Level", and all equipment responds as designed?

A. Containment evacuation alarm sounds automatically. Containment purge stops automatically.

B. Containment evacuation alarm is manually actuated by the control room operator.

Containment purge stops automatically.

C. Containment evacuation alarm sounds automatically. Containment purge is stopped manually by the control room operator.

D. Containment evacuation alarm is manually actuated by the control room operator.

Containment purge is stopped manually by the control room operator.

Page 62 of 100 1211212012

UNIT 3 2013 Exam Date 02/1112013 Question: 63 Given the following conditions:

Fuel handling is in progress in Containment and the Spent Fuel Pool (SFP).

FSB FSB Fans are operating in NORMAL mode.

Radiation Monitor R 5 SPENT FUEL POOL AREA MONITOR fails LOW.

All other radiation monitors are operable.

What is the impact of this failure?

A Only recently irradiated fuel assembly movement in the FSB must be suspended.

B. All fuel assembly movement in the FSB AND Containment must be suspended.

C. All fuel assembly movement in the FSB must be suspended.

D. Fuel assembly movement may continue in the FSB and Containment provided R-14, Plant Vent Gas Activity and R-27, Wide Range Plant Vent Gas Activity, monitors are operable.

Page 63 of 100 12/12/2012

UNIT 32013 Exam Date 02111/2013 Question: 64 Which one of the following correctly describes the automatic operation of the main generator voltage controller?

A. Main generator output is compared to the base adjuster setpoint and the comparison could result in the adjustment of generator excitation.

B. Main generator output is compared to the automatic rheostat setpoint which is set by the operator. If there is a difference, the controller bucks or boosts the base adjuster output.

C. Main generator output is compared to the base adjuster rheostat setpoint which is set by the operator. If there is a difference, the controller bucks or boosts the base adjuster output.

D. Main generator output is compared with exciter output. If there is an error, the automatic controller bucks or boosts the base adjuster output.

Page 64 of 100 12112/2012

UNIT 32013 Exam Date 0211112013 Question: 65 Given the following:

The unit is at 100% power

Fire Protection header pressure is lowering Which one of the following has the alternate pumps listed in the proper sequence of automatic start?

A. Standby Jockey Pump at 115 psig, Motor Driven Fire Pump at 110 psig; Diesel Fire Pump at 105 psig B. Standby Jockey Pump at 110 psig; Motor Driven Fire Pump at 105 psig; Diesel Fire Pump at 95 psig C. Standby Jockey Pump at 115 psig; Motor Driven Fire Pump at 110 psig; Diesel Fire Pump when <105 psig for more than 10 seconds D. Standby Jockey Pump at 110 psig; Motor Driven Fire Pump at 105 psig; Diesel Fire Pump when <95 psig for more than 10 seconds Page 65 of 100 1211212012

UNIT 32013 Exam Date 02/11/2013 Question: 66 Unit 3 is in a refueling out~ge with fuel movement in progress. Per EN-OP-115, Conduct of Operations, what is the minimum Unit 3 on-duty control room compliment for this condition?

(Assume Fire Brigade Leader is staffed by Unit 2 individual and a Unit 3 SRO is staffed as Refueling SRO)

A. ONE Shift Manager, ONE Control Room Supervisor, TWO Reactor Operators, ONE Shift Technical Advisor.

B. ONE Shift Manager, ONE Control Room Supervisor, TWO Reactor Operators.

C. ONE Shift Manager, TWO Reactor Operators, ONE Shift Technical Advisor D. ONE Shift Manager, ONE Control Room Supervisor, ONE Reactor Operators.

Page 66 of 100 1211212012

UNIT 32013 Exam Date 0211112013 Question: 67 The plant is at 100% power with all systems in automatic when both heater drain pumps trip.

Which of the following actions will the operator take in order to stabilize the plant?

A. Immediately run the turbine back to 70% power to prevent a main feed pump trip.

B. Reduce turbine load as needed to match steam flow and feed flow while maintaining MBFP suction pressure above 265 psig.

c. Reduce turbine load to 900 MW and ensure MBFP suction pressure remains greater than 265 psig at the new load.

D. If MBFP suction pressure decreases to 265 psig, reduce turbine load until suction pressure is greater than 265 psig.

Page 67 of 100 1211212012

UNIT 32013 Exam Date 02/11/2013 Question: 68 The plant had been operating at 100% power for the last 100 days, when a reactor trip occurred 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months ago.

Conditions prior to the trip were:

Core burnup is 10,000 MWD/MTU (MOL)

Boron concentration was 700 ppm

Control Bank D was at 230 steps The estimated critical position is Control Bank D at 120 steps. The operators have just completed pulling the shutdown banks. The source range counts (in CPS) while withdrawing the shutdown banks are:

SR# Initial CPM SB"A" SB"B" SB"C" SB"D" 31 165 180 210 230 250 32 180 210 240 260 280 Which action below should crew take?

A. Suspend rod withdrawal, re-evaluate all inputs and mathematics used in the ECP, and direct Chemistry to obtain an RCS boron sample.

B. Fully insert all CONTROL RODS, and re-evaluate all inputs and mathematics used in the ECP.

C. Obtain new baseline counts for both source range channels and commence pulling CONTROL BANKS. Criticality is expected at about the 5th doubling.

D. Calculate the amount and borate so that criticality will occur at 120 steps on Control Bank D and resume CONTROL RODS to go critical. Criticality is expected at about the 5th doubling.

Page 68 of 100 12112/2012

UNIT 32013 Exam Date 02/11/2013 Question: 69 Given the following conditions:

A reactor startup is in progress.

A malfunction of the Rod Control Bank Overlap Unit has caused Control Bank 0 Rods to begin withdrawing 20 steps earlier than designed.

Which ONE (1) of the following describes the impact of this malfunction if it were allowed to continue during the power increase?

A. QPTR limits may be challenged.

B. Shutdown margin may be reduced if a reactor trip occurs.

C. Power Peaking factors may rise to unacceptable values.

D. The Safety Analysis for ejected rod worth may be invalid.

Page 69 of 100 12/12/2012

UNIT 32013 Exam Date 02/11/2013 Question: 70 Per POP-1.1, Plant Heatup from Cold Shutdown Condition, when are the Over Pressure System (OPS) states links required to be OPENED?

A. Prior to closing the final RCS vent path.

B. Prior to starting the first RCP.

C. Prior to exceeding 200°F.

D. Prior to exceeding 350°F.

Page 70 of 100 12/12/2012

UNIT 32013 Exam Date 02/11/2013 Question: 71 The following plant conditions exist:

100 % power

32 EDG is out of service for preventative maintenance The maintenance supervisor requests a work permit for 31 AFW pump to be worked now due to man power availability. The estimated completion time for the work is 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Should 31 AFW pump be taken out of service? Select the proper action to be taken with the justification for your choice.

A. Yes. Technical Specifications allow for one MDAFW pump to be out of service, provided it is returned to service within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and the remaining pumps are demonstrated operable.

B. Yes. Technical Specifications allows for one MDAFW pump to be out of service, for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months provided the remaining pumps are demonstrated operable.

C. No. Technical Specifications requires all 3 AFW pumps with their associated piping and valves to be operable if any EDG is inoperable.

D. No. Technical Specifications state that if one EDG is out of service then the other 2 EDG's and their associated safeguards equipment should be maintained operable.

Page 71 of 100 1211212012

UNIT 32013 Exam Date 0211112013 Question: 72 The following conditions exist:

The PAB Sump Tank Room is posted as a "Locked High Radiation Area".

The area is at the MINIMUM required radiation level for the posting in all posted areas.

Your present annual exposure is 500 mRem.

You are required to perform a retest within the posted area.

What would be your maximum calculated stay time in this area be in order to avoid exceeding the Entergy Routine Annual Limit for radiation exposure per EN-RP-201, Dosimetry Administration?

A. 30 minutes B. 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months C. 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months D. 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Page 72 of 100 12112/2012

UNIT 32013 Exam Date 0211112013 Question: 73 Unit 3 is at power and CH-LCV-459, Letdown Isolation, has failed closed. Maintenance believes the reason the valve failed closed is due to a problem with a solenoid on the valve that can be repaired in 5 minutes. Dose rates are 2000 mR/hr at the job site. Which of the following describes the requirements per OAP-007, Containment Entry and Egress, that need to be satisfied to make this repair?

(Assume all other procedural requirements for the repair and entry are met and workers will not exceed annual exposure limits from this job.)

A. Reactor power must be lowered until dose rates are less than 1000 mRlhr at the job site prior to allowing work to begin.

B. Since the expected dose is less than 1000 mRem, only normal OAP-007 SM authorization is required prior to allowing job to begin.

C. Unit AOM and RP Manager approvals are required prior to allowing job to begin.

D. Since the valve is outside the crane wall, only normal OAP-007 SM authorization is required prior to allowing job to begin.

Page 73 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 74 An AOP is being implemented when it is determined that a reactor trip and SI are required. Per OAP-015, AOP and ONOP User's Guide, when can the CRS direct that actions in the AOP be resumed (assuming these actions will not detract from performance of the EOP)?

A. Only when called for by the EOP in use.

B. When E-O has been exited.

C. When SI is reset.

D. After completion of step 4 of E-O.

Page 74 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 75 Security has just confirmed that a Security CODE RED exists. Armed intruders have gained entry into the protected area.

Which one of the following actions should be taken?

A. Trip the reactor, ensure AFW pumps start, perform E-O in parallel with AOP-SEC-1 B. Start AFW Pumps, trip the reactor, perform E-O in parallel with AOP-SEC-1 C. Perform a normal plant shutdown in parallel with AOP-SEC-1 D. Maintain plant in a stable condition while performing AOP-SEC-1 Page 75 of 100 12/12/2012

UNIT 32013 Exam Date 0211112013 Question: 76 Given:

The plant is operating at 100% power

34 RCP Shaft Vibration is 16 mils and oscillating +/- 0.6 mils.

34 RCP Upper Bearing temperature is 185° and increasing at approximately 1°/hr for the last 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months

The cause of the vibration and temperature increases is under investjgation

The team has initiated a plant shutdown Which of the following describes the operating strategy for 3-AOP-RCP-1 for the above conditions?

A. Perform a normal POP shutdown and secure 34 RCP prior to reaching high vibrations limit B. Perform a rapid (ONOP-TG-3) shutdown and secure 34 RCP prior to reaching high vibration limit.

C. Perform a normal POP shutdown and secure 34 RCP prior to reaching high bearing temperature limit.

D. Perform a rapid (ONOP-TG-3) shutdown and secure 34 RCP prior to reaching high bearing temperature limit Page 76 of 100 12/12/2012

UNIT 32013 Exam Date 0211112013 Question: 77 The plant is in a normal 100% alignment with 31 Charging Pump out of service for a major overhaul. While expanding the tagging boundaries, a mistake occurred which rendered the suction path to all charging pumps unavailable due to a gas buildup. Operators responded by securing charging and letdown and entered AOP-CVCS-1, Chemical and Volume Control System Malfunctions. Restoration of the suction path is expected to take two hours.

Based on these conditions, what will the mitigating strategy of AOP-CVCS-1 be?

A. Pressurizer level will lower to less than allowed for heater operation in the time that repairs are expected to take. Therefore, the AOP directs a normal shutdown for this condition.

B. Pressurizer level will lower to less than allowed for heater operation in the time that repairs are expected to take. Therefore, the AOP directs a shutdown using ONOP-TG 3, Rapid Shutdown.

C. Pressurizer level will NOT lower to less than allowed for heater operation in the time that repairs are expected to take. However, the AOP directs a shutdown using ONOP TG-3, Rapid Shutdown whenever charging flow cannot be immediately re-established.

D. Pressurizer level will NOT lower to less than allowed for heater operation in the time that repairs are expected to take. Therefore, the AOP allows for continued operation until charging is re-established.

Page 77 of 100 12112/2012

UNIT 32013 Exam Date 0211112013 Question: 78 Given the following:

The crew is responding to an ATWS.

FR-S.1, Response to Nuclear Power Generation/ATWS has been entered and the Immediate Actions are complete.

The reactor is tripped and all control rods are inserted.

Neutron flux is decreasing in the Intermediate Range.

Safety Injection is NOT actuated.

Which of the following identifies the condition concerning boration as addressed in FR-S.1 based on the above indications?

A. With the reactor tripped and neutron flux decreasing, boration is NOT initiated in FR S.1; additional boration may be required by subsequent procedure in effect.

B. Boration must be initiated in FR-S.1, but may be terminated in FR-S.1 once the sources of positive reactivity addition to the RCS have been eliminated.

C. Boration must be initiated in FR-S.1, and the Cold Shutdown boron concentration is NOT required to exit FR-S.1 D. Boration must be initiated in FR-S.1, and the Cold Shutdown boron concentration IS required to exit FR-S.1.

Page 78 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 79 Given:

A steam line break occurred in the turbine building.

The reactor was tripped and MSIVs closed

SI did NOT actuate

The crew is currently in ES-O.1, Reactor Trip Response

RCS Temperature is 532°F

IRPI indication:

o C-9 25 Steps o M-12 10 Steps o E-13 228 Steps Which of the following describes the emergency boration time requirements for the above plant conditions?

A. Emergency borate for temperature < 540 with ~1 stuck rod then emergency borate for 1 stuck rod B. Emergency borate for 2 stuck rods only C. Emergency borate for temperature < 540 with >1 stuck rod then emergency borate for 3 stuck rods D. Emergency borate for 1 stuck rod only Page 79 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 80 The plant is in a 100% normal lineup when 480V Bus 5A is lost due to a short that causes severe bus damage. Which of the following statements describes how DC loads will be addressed for this event?

A. Alternate power options to 31 DC Power Panel are not allowed for this condition prior to the plant being placed in Mode 5. During the shutdown/cooldown, 31 DC Power Panel will be lost when 31 Battery depletes, however 31 Instrument Bus will remain energized.

B. Alternate power options to 31 DC Power Panel are not allowed for this condition prior to the plant being placed in Mode 5. During the shutdown/cooldown, 31 DC Power Panel and 31 Instrument Bus will be lost when 31 Battery depletes.

C. 3-AOP-DC-1, Loss of Power to a 125V DC Panel, will cross connect 31 and 32 DC Power Panels to maintain power to 31 DC Power Panel during the shutdown/cooldown.

D. 3-AOP-DC-1, Loss of Power to a 125V DC Panel, will align 35 Battery Charger to maintain power to 31 DC Power Panel during the shutdown/cooldown.

Page 80 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 81 INITIAL PLANT CONDITIONS:

Plant is in MODE 5 on the 31 Train of RHR

480V Bus 6A Electrical Distribution Train is de-energized for maintenance, and cannot be immediately restored

Vacuum refill of the RCS has been completed.

RCS temperature is 180°F

RCS pressure is 175 psi

All Steam Generators are in Wet-Layup

No RCPs are running 31 RHR Pump fails due to a motor bearing failure.

Which of the following actions are required?

A. Establish conditions for natural circulation and open the steam generator atmospheric dump valves.

B. Open both PORVs, fill the RCS using one SI Pump from the RWST.

C. Open both PORVs, fill the RCS using one Charging Pump from the RWST.

D. Start one Reactor Coolant Pump, and open the steam generator atmospheric dump valves.

Page 81 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 82 Given the following plant conditions:

One Shutdown Sank-A Group 2 Rod has dropped into the core.

The crew is recovering the dropped rod.

ROD CONTROL URGENT FAILURE, alarm is received.

Which ONE (1) of the following describes the reason for the alarm and the expected response?

A. The alarm is NOT expected for the recovery of a shutdown bank rod. Actions will be initiated per the ARP prior to proceeding with rod recovery.

S. The alarm is NOT expected for the recovery of a shutdown bank rod. Actions will be initiated per the contingency attachment of AOP-ROD-1 prior to proceeding with rod recovery.

C. The alarm is expected due to Shutdown Sank-A Group 1 rods not moving. Prior to proceeding, the AOP requires verifying the alarm at the appropriate power cabinet.

D. The alarm is expected due to Shutdown Bank-A Group 1 rods not moving. Alarm is anticipated by AOP and recovery may continue with no further action.

Page 82 of 100 1211212012

UNIT 32013 Exam Date 02111/2013 Question: 83 The plant is being cooled down following a SGTR using blowdown. Given the following plant conditions:

Pressurizer Level is 53% and increasing

Ruptured SG NR Level is 35% and decreasing

No other event is in progress

Shutdown margin is adequate What should be done to stabilize Pressurizer and Ruptured SG levels?

A. Increase RCS Makeup Flow B. Turn ON Pressurizer Heaters C. Depressurize the RCS using normal spray D. Maintain RCS pressure slightly higher than ruptured SG pressures Page 83 of 100 1211212012

UNIT 3 2013 Exam Date 02/1112013 Question: 84 IPEC Unit 3 was at 100% power with 33 EDG tagged out for maintenance when a small break loss of coolant accident occurred coincident with a loss of offsite power. The team is in ES-1.2, Post LOCA Cooldown and Depressurization, and has just secured one HHSI pump. Which of the following describes how accumulators will be addressed?

A. Accumulators will be left in service until all HHSI pumps are secured.

B. All accumulators will be vented.

C. SI-MOV-894B and SI-MOV-894D will be closed, 31 and 33 Accumulators will be vented.

D. SI-MOV-894A and SI-MOV-894C will be closed, 32 and 34 Accumulators will be vented.

Page 84 of 100 12/12/2012

UNIT 32013 Exam Date 02111/2013 Question: 85 Given the following conditions:

A reactor trip has occurred concurrent with a loss of offsite power.

The Team is performing actions of ES-0.2, "Natural Circulation Cooldown".

Train "A" of RVLlS is out of service.

The Team has commenced RCS cooldown and depressurization.

ReS pressure is 1380 psig and trending DOWN.

Qualified eETs are 468°F and trending DOWN.

Pressurizer level is 38% and trending UP slowly.

Due to secondary inventory concerns, RCS cooldown rate MUST be performed at approximately 40°F/Hr.

Which one of the following actions will be required?

A. Repressurize the RCS to minimize void growth in accordance with ES-0.2.

B. Stop the depressurization to reestablish subcooling in accordance with ES-0.2.

C. Transition to ES-0.3, "Natural Circulation Cooldown With Steam Void In Vessel (With RVLlS)".

D. Transition to ES-O.4, "Natural Circulation Cooldown With Steam Void In Vessel (Without RVLlS)".

Page 85 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 86 Given:

The plant is at 50% power

N2 MAKE UP INST. AIR LOW PRESS. AUX. B.F.P. ROOM has annunciated

Nitrogen Pressure is 1837 psig.

The ARP directs a dedicated operator be stationed immediately. What is the reason for stationing a dedicated operator?

A. The operator is stationed near the SG Atmospherics. Backup nitrogen must be lined up to the Atmospheric Steam Dumps in the event of a loss of instrument air.

B. The operator is stationed near 131 OAIB. Backup nitrogen bottles must be lined up to 1310AlB to maintain the valves open in the event of a loss of instrument air.

C. The operator is stationed near the MSIVs. Local manual action is required to maintain the MSIVs open in the event of a loss of instrument air.

D. The operator is stationed near the Aux Boiler Feed Pumps. Local manual action is required to prevent a pump runout condition in the event of a loss of instrument air.

Page 86 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 87 The plant is cooling down in preparation for refueling. RCS Temperature is 250°F and lowering as per the cooldown schedule with all systems in the expected configuration. All actions to make the Low Temperature Over Pressure System (LTOPS) operable were completed when directed by the POP. Personnel performing work on top of the pressurizer inadvertently damage the nitrogen line for PORV PCV-455C rendering it inoperable. Which of the following describes the required action regarding LTOPS?

A. No action is required since ONLY one PORV is needed to satisfy the LTOPS LCO.

B. Restore PCV-455C to operable status or place the plant in a condition that does not require LTOPS within 7 days.

C. Immediately place ALL HHSI pump switches to trip-pull-out.

D. Immediately close and de-energize ALL accumulator isolation valves.

Page 87 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 88 Given:

A Large Break LOCA has occurred.

Reactor Trip Breaker A failed to open and could not be locally opened by the NPO.

All other equipment functioned as designed.

During the performance of RO-1, BOP Operator Actions During the Performance of EOPs, the BOP depresses both SI Reset Pushbuttons.

Which of the following describes the plant response and procedural requirements?

A. Neither Train of SI will reset.

Place the SI Block Key Switches to "Defeat" After 2 minutes has elapsed, depress the SI Reset Pushbuttons again.

B. Train A of SI will not reset Place SI Block Key Switches to "Defeat" Press Pin Resets on SI Master Relays in G racks C. Neither Train of SI will reset.

Place the SI Block Key Switches to "Defeat'

Press Pin Resets on SI Master Relays in G racks D. Train A of SI will not reset Place Train A SI Block Unblock switch to "Block" After 2 minutes has elapsed, depress the SI Reset Pushbuttons again Page 88 of 100 12/12/2012

UNIT 32013 Exam Date 0211112013 Question: 89 The plant is operating at 100% power with a normal electrical plant alignment and all TS equipment OPERABLE.

A drop in offsite system voltage causes 480V Bus SA voltage to drop to 418V causing the "480 VOLT SAFEGUARD BUS UNDERVOLTAGE" alarm to annunciate. System voltage is subsequently restored to normal one minute later.

Which of the following describes the effect on Bus SA and the actions required?

A. Load breakers on SA for non-essential equipment open, but the bus stays energized.

When voltage returns to normal, loads are restored using an AOP.

B. Load breakers on SA for non-essential equipment open, but the bus stays energized.

When voltage returns to normal, loads are restored using SOPs.

C. The normal supply breaker to Bus SA opens, load breakers for non-essential equipment open, and power to the bus is supplied by 33 EDG. When voltage returns to normal, normal power and loads are restored using an AOP.

D. The normal supply breaker to Bus SA opens, load breakers for non-essential equipment open, and power to the bus is supplied by 33 EDG. When voltage returns to normal, normal power and loads are restored using SOPs.

Page 89 of 100 12/12/2012

UNIT 32013 Exam Date 02111/2013 Question: 90 Given the following conditions:

The plant is operating at 100% power with all systems in normal alignments.

A liquid release of 31 Monitor Tank is in progress.

The following annunciators are received in the Control Room o CHANNEL FAILURE-o R-18 LlQ. EFF."

R-18, Liquid Waste Effluent monitor is alarming with the indication showing off-scale low.

The liquid release remains in progress.

Which ONE (1) of the following describes effect on the plant and the actions required?

A. The radiation monitor has failed. Request that HP recheck calculations and provide recommendations on action to be taken.

B. The radiation monitor has failed. The release may continue provided 2 independent samples are taken and the activity is verified to be below ODCM limits.

C. The discharge should have automatically stopped. Stop the discharge, direct Chemistry to sample the tank and refer to the ODCM for further actions.

D The discharge should have automatically stopped. Stop the discharge. The release CANNOT be continued until R-18 is operable.

Page 90 of 100 12/1212012

UNIT 3 2013 Exam Date 02111/2013 Question: 91 Given:

The plant was at 95% power with all control systems in automatic.

Control Bank 0 rods were at 220 steps.

PT-412A First Stage Pressure Transmitter failed high

Step counters for Control Bank 0 indicated 236 steps when Rod Control was placed in manual.

The ATC immediately inserted rods until CBO step counters indicated 220 step.

Which of the following describes the current status of the rod control system and what actions are required to correct this condition?

A. Actual rod position is lower than indicated on the step counters 3-S0P-RC-001 Full Length Rod Control and RPI System Operation will properly restore rod alignment and sequence.

B. Actual rod position is lower than indicated on the IRPls.

3-AOP-ROO-1, Rod Control and Indication System Malfunctions will realign the rods and reset the PIA converter.

C. Actual rod position is higher than indicated on the step counters.

Rods are properly aligned and sequenced, only the Rod Control Logic needs to be reset per 3-S0P-RC-001 Full Length Rod Control and RPI System Operation o Actual rod position is higher than indicated on the IRPls.

3-AOP-ROO-1, Rod Control and Indication System Malfunctions will realign the rods and reset the Bank Overlap Unit.

Page 91 of 100 12112/2012

UNIT 32013 Exam Date 0211112013 Question: 92 Given the following conditions:

Unit 3 is in a refueling outage

Core unload is in progress

The fuel transfer cart is in containment

RWST Level is 1 ft

Mansell Level Indication begins lowering rapidly

Reactor Sump Level begins increasing rapidly Which one of the following statements describes the mitigating actions for this event per AOP FH-1, Fuel Damage of Loss of SFP/Refueling Cavity Level?

A. Ensure the fuel transfer gate valve is closed to isolate the SFP from the Reactor Cavity.

Align RHR to take suction on the Recirc Sump Level when level is above 48' 2".

B. Ensure the fuel transfer gate valve is closed to isolate the SFP from the Reactor Cavity.

Align a Recirc Pump to take suction on the Recirc Sump Level when level is above 48' 2".

C. Ensure the fuel transfer gate valve is open to provide increased inventory while establishing recirculation flow. Align RHR to take suction on the Recirc Sump Level when level is above 48' 2".

D. Ensure the fuel transfer gate valve is open to provide increased inventory while establishing recirculation flow. Align a Recirc Pump to take suction on the Recirc Sump Level when level is above 48' 2".

Page 92 of 100 12/12/2012

UNIT 32013 Exam Date 02/1112013 Question: 93 Core off-load is in progress when you are notified by the Fuel Handling Supervisor that an irradiated fuel assembly was dropped in the spent fuel pool. The assembly fell into the correct pool location. R-5 and R-27 readings are increasing. R-5 is in ALARM.

Based on these conditions, what actions are required after suspending fuel handling operations in the FSB by 3-AOP-FH-1, Fuel Damage or Loss of SFP/Refueling Cavity Level?

A. Evacuate ONLY non-essential personnel from the FSB, place FSB ventilation in service and monitor R27.

B. Evacuate ONLY non-essential personnel from the FSB, secure FSB ventilation and monitor R27.

C. Evacuate ALL personnel from the FSB, dispatch an operator to close ALL FSB doors and monitor R27.

D. Evacuate ALL personnel from the FSB and dispatch an operator to independently verify proper fuel bundle location and monitor R27.

Page 93 of 100 12112/2012

UNIT 32013 Exam Date 0211112013 Question: 94 The following conditions exist at Unit 3:

Core offload is in progress.

Nuclear Source Range N-31 is selected as the input for the Audio Count Rate Drawer.

N-38 and N-39 are out of service due to outage electrical work, but are expected to be returned to service in 30 minutes.

N-31 has just become inoperable.

Which ONE of the following describes the proper action for this condition?

A. Core alterations may continue for up to one hour provided the Audio Count Rate Drawer is switched to N-32 within this time.

B. Immediately stop any core alterations. Core alterations may continue when N-38 or N 39 is placed in service and the Audio Count Rate Drawer is switched to an operable channel.

C. Immediately stop any core alterations. Core alterations may continue when N-31 is restored to operable status. N-38 or N-39 cannot be used to satisfy requirements for core alterations.

D. Core alterations may continue for up to one hour provided N-38 or N-39 is placed in service and the Audio Count Rate Drawer is switched to an operable channel within this time.

Page 94 of 100 12112/2012

UNIT 32013 Exam Date 02/1112013 Question: 95 While transferring 31 Static Inverter from Reverse Transfer to Forward Transfer following a surveillance test, 31 Main Boiler Feed Pump Speed Control Trouble alarm annunciated. The flight panel indications for 31 and 32 MBFPs are:

Indication 31 MBFP 32 MBFP Turbine RPM 4726 4706 Percent Startup 94.8 94 Percent Feedwater 67.9 65.2 Percent Hold 66 Blank Failure Hold LED ON OFF The I&C technician states the cause of the alarm was due to a momentary voltage spike on 31 Instrument Bus.

How is the voltage spike theory confirmed, and what actions are required?

A. %FW signal for 31 MBFP is within 4% of %FW for 32 MBFP, Press Reset button on Flight Panel per ARP for 31 MBFP Speed Control Trouble B. %FW for 31 MBFP is within 4% of % Hold Signal, Press Reset button on Flight Panel per AOP-FW-1 Loss of Feedwater C. %FW signal for 31 MBFP is within 4% of %FW for 32 MBFP, Press Reset button on Flight Panel per AOP-FW-1 Loss of Feedwater D. If %FW for 31 MBFP is within 4% of % Hold signal, Press Reset button on Flight Panel per ARP for 31 MBFP Speed Control Trouble Page 95 of 100 12112/2012

UNIT 32013 Exam Date 02/11/2013 Question: 96 On 8124112 at 0800, the plant commenced a reduction in power from 100% to just below the C 20 (AMSAC) setpoint due to AMSAC being inoperable and its LCO condition expiring. Reactor power was below 50% at 1100 and the load reduction was completed at 1230. During and after the load reduction, there were roblems kee in dl in the tar et band.

Out of In Out of In Quadran Band Band Band Band t

41 1210 42 1105 43 1050 1130 1230 44 1135 Time Line:

41 r*....*..*****r..** ..*.. _*T* ..*....**..**i..*............r.............., ..............,...........................

42 i i [ I I ! !

43! i I!! ~~-"""--f---i---!

44

~

i ! ~

Ii!

I~too I*~--f"----k.----r--........)....---i Assuming AMSAC gets fixed, at what time can reactor power be raised above 50%?

A. 1110 on 8/25/12 B. 1035 on 8/25/12 C. 1030 on 8/25/12 D. 1020 on 8/25/12 Page 96 of 100 1211212012

UNIT 32013 Exam Date 02/1112013 Question: 97 What is the basis for requiring a minimum of 360,000 gallons of water in the Condensate Storage Tank?

Ensures adequate volume to:

A. maintain Hot Zero Power for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and then cooldown to MODE 4 <350°F.

B. maintain MODE 4 for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months with at minimum of 2 SGs greater than 9% NR level.

C. Cooldown from Trip concurrent with loss of off-site power to MODE 4 <350°F on RHR.

D. remove decay heat while in MODE 3 for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following a reactor trip from 102%

RTP.

Page 97 of 100 12/12/2012

UNIT 32013 Exam Date 0211112013 Question: 98 The plant is operating at 100% power. A tube leak has been detected on 32 SG and primary to-secondary leak rate is being estimated using RCS activity per Attachment 1 of 3-AOP-SG-1 ,

Steam Generator Tube Leak.

Using Attachment 1 (attached) for estimating leak rate via RCS activity, what is the MINIMUM reading on R-15 listed that would translate into a value requiring shutdown to Mode 3 within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months per 3-AOP-SG-1 ?

Condenser Air In-Leakage: 20.0 scfm

RCS activity: 5.00 E-2 j..ICi/cc A. 3.50 E-4 j..ICi/cc B. 3.50 E-5 j..ICi/cc C. 1.75 E-5 j..ICi/cc D. 1.25 E-6 j..ICi/cc Page 98 of 100 1211212012

UNIT 32013 Exam Date 02/1112013 Question: 99 The STA has advised the CRS that an ORANGE path exists for CORE COOLING and no other higher ORANGE or RED paths exist.

While depressurizing the SGs to 175 psig lAW 3-FR-C.2, "Response To Degraded Core Cooling",

the STA reports that you are now in a RED path on the INTEGRITY CSF.

Which of the following describe the appropriate action to be taken?

A. Complete the depressurization of all SGs to 175 psig, then transition to FR-P.1, "Response to Imminent Pressurized Thermal Shock".

B. Immediately transition to FR-P .1, "Response to Imminent Pressurized Thermal Shock".

C. Complete FR-C.2, "Response to Degraded Core Cooling", then transition to FR-P.1, "Response To Imminent Pressurized Thermal Shock".

D. Continue with FR-C.2, "Response To Degraded Core Cooling", and concurrently perform actions in in FR-P.1, "Response To Imminent Pressurized Thermal Shock", that do not conflict with FR-C.2 Page 99 of 100 12112/2012

UNIT 3 2013 Exam Date 0211112013 Question: 100 The plant is responding to a large break LOCA. The operators have just transitioned to ES-1.3, "Transfer to Cold Leg Recirculation" on RWST Low-Low level. SI has been reset.

While aligning the plant for cold leg recirculation, containment pressure is noted to be 14 psig and rising slowly.

If pressure continues to rise to 22 psig, the team should ...

A. Exit ES-1.3 at step in progress and transition to FR-Z.1, "Response to Containment High Pressure".

B. Complete ALL steps in ES-1.3 prior to transitioning to FR-Z.1, "Response to Containment High Pressure".

C. Complete steps in ES-1.3 to establish cold leg recirculation prior to transitioning to FR-Z.1, "Response to Containment High Pressure".

D. Remain in ES-1.3. Functional Restoration Procedures are not implemented once ES-1.3 has been entered.

Page 100 of 100 12/12/2012

IPEC Unit 3 NRC Written Exam Answer Key February 1, 2013 1 A - C 51 C 76 C 2 C 27 B 52 0 77 0 3 A 28 C 53 0 78 C 4 C 29 0 54 C 79 A 5 B 30 C 55 B 80 A 6 C 31 A 56 C 81 A 7 0 32 0 57 0 82 0 8 B 33 I B 58 B 8 B 9

10 C

~

35 59 60 0 84 85 C

B A A C 11 C 36 B 61 A 86 0 12 I 0 37 B 62 A 87 B

=i+/-~

38 0 63 C 88 B 39 0 64 B 89 C 15 0 40 0 65 B 90 C 16 C 41 A 66 B 91 .

17 B 42 C 67 B 92 B 18 A 43 0 68 C 93 C I 19 0 44 0 69 C 94 B 20 A 45 B 70 0 95 B 21 C 46 0 71 0 96 B 22 0 47 A 72 B 97 0 23 C 48 B 73 C 98 C 24 B 49 A 74 0 99 C 25 B 50 B 75 B 100 C

v t e Letter Sequence Draft Other
TAC:U01866, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML13066A337, ML13066A354, ML13066A461, ML13066A514, ML13109A406
MONTHYEAR2013-02-27 [Table View]

ML13066A305

Text

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