ML090980403

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Initial Exam 2009-301 Final RO Written Examination
ML090980403
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 03/18/2009
From:
NRC/RGN-II
To:
References
50-250/09-301, 50-251/09-301, ES-401-7
Download: ML090980403 (79)
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Text

ES-401 , Rev. 9 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet u.s. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:

Date: 3/18/09 Facility/Unit: Turkey Point 3 & 4 Region:1 IIX III IV Reactor Type: WX CE BW GE 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. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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

TURKEY POINT NRC EXAM - 03/12/09 Q#1 Reactor and turbine power are stable at 20%.

Operators have positioned the Reactor Trip and Bypass breakers to test Train "A" reactor protection logic in accordance with 4-0SP-049.1, "Reactor Protection System Logic Test."

  • Turbine thrust bearing oil pressure increases to 80 psig.

The RO observes the following on the console:

  • Bypass Breaker "A": Red Light
  • Bypass Breaker "B": No Light The reactor is _ _ _ and the RO _ _ _ required to manually trip the reactor.

A. NOT tripped is B. NOT tripped is NOT

c. tripped is D. tripped is NOT Page 1

TURKEY POINT NRC EXAM - 03/12/09 0#2 Unit 4 is in Mode 1 when Pressurizer Pressure Transmitter, PT-4-445, fails high.

Following manual closure of the Pressurizer PORV, PCV-4-456, the RO noted the following indications:

  • RCS pressure is 2100 psig and decreasing.
  • Charging pump speed is increasing slowly.
  • The PORV indicating lights on the console are green.
  • The associated PORV block valve, MOV-4-535, indicating lights are NOT lit.

Which ONE of the following correctly describes the reason the pressure is decreasing and the action(s) directed by 4-0NOP-041.5, "Pressurizer Pressure Control Malfunction" that will stop this pressure reduction?

A. Pressurizer PORV, PCV-4-456, is leaking.

Take manual control of Pressurizer Pressure Controller, PC-4-444J to fully close PCV-4-456.

B. A Pressurizer Spray valve is leaking.

Take manual control of Pressurizer Pressure Controller, PC-4-444J to fully close the Pressurizer spray valves.

C. Pressurizer PORV, PCV-4-456, is leaking.

Reclose the breaker for MOV-4-535 and then close Pressurizer PORV Block Valve, MOV-4-535.

D. A Pressurizer Spray valve is leaking.

Place both individual spray valves' controllers in manual and close the Pressurizer spray valves.

Page 3

TURKEY POINT NRC EXAM - 03/12/09 Q#3 Unit 3 is at 100% power.

  • 3A Charging Pump is running.
  • 3C Charging Pump is tagged out of service.

A 150 gpm leak occurs on 3A RCS Loop.

  • The RO isolates letdown and maximizes charging flow.
  • FI 122A charging line flow indicates 130 gpm.
  • ERDADS indicates the following:
  • RCP A seal injection flow 7.5 gpm
  • RCP B seal injection flow 8.0 gpm
  • RCP C seal injection flow 8.5 gpm Pressurizer level will _ _ _ and the operators will _ __

A. stabilize.

continue to respond to the leakage using 3-0NOP-041.3, "Excessive Reactor Coolant Leakage".

B. stabilize.

perform 3-GOP-103, "Power Operation to Hot Standby".

C. continue to decrease.

continue to respond to the leakage using 3-0NOP-041.3, "Excessive Reactor Coolant Leakage."

D. continue to decrease.

transition to 3-EOP-E-0, "Reactor Trip or Safety Injection".

Page 5

TURKEY POINT NRC EXAM - 03/12/09 Q#4 Unit 3 is in Mode 1.

The following RCP temperatures are observed during performance of 3-0NOP-041.1, "Reactor Coolant Pump Off-Normal":

Motor Bearing Temp Motor Stator Temp 3A RCP 3B RCP 3C RCP In accordance with the limits in 3-0NOP-041.1, which ONE of the following identifies the RCP(s) that need to be stopped as a result of high temperature(s)?

A. Only 3A RCP B. Only 3B RCP C. Only 3A and 3B RCPs D. Only 3A and 3C RCPs Page 7

TURKEY POINT NRC EXAM - 03/12/09 0#5 Unit 3 is at 100% power with all systems in normal alignment.

  • The charging flow header shears at the inlet to the Regenerative Heat Exchanger.

Which ONE of the following correctly describes the effect of this break on charging pump speed and seal injection flow?

A. Charging pump speed will remain constant.

Seal injection flow will decrease and can only be controlled locally in the pipe and valve room.

B. Charging pump speed will remain constant.

Seal injection flow will decrease until restored by closing Charging Flow to Regen Heat Exchanger valve, HCV-3-121.

C. Charging pump speed will automatically increase.

Seal injection flow will decrease and can only be controlled locally in the pipe and valve room.

D. Charging pump speed will automatically increase.

Seal injection flow will decrease until restored by closing Charging Flow to Regen Heat Exchanger valve, HCV-3-121.

Page 9

TURKEY POINT NRC EXAM - 03/12/09 Q#6 Unit 3 is in Mode 5 with the RCS in a water-solid condition.

The following annunciators alarm:

A 3/2 OMS HI PRESS ALERT A 3/3 OMS CONTROL ACTIVATED A 4/1 PORV/SAFETY VALVE OPEN A 9/6 RHR MOV-750n51 LETDOWN ISOLATION H 6/2 RHR HX HI/LO FLOW Which ONE of the following describes the event that caused these alarms?

RCS Loop Pressure Transmitter:

A. PT-3-403 failed high resulting in opening of Pressurizer PORV, PCV-3-455C.

B. PT-3-405 failed high resulting in opening of Pressurizer PORV, PCV-3-456.

C. PT-3-403 failed high resulting in closing of Loop 3C RHR Suction Stop valve, MOV-3-750.

D. PT-3-405 failed high resulting in closing of Loop 3C RHR Suction Stop valve, MOV-3-750.

Page 11

TURKEY POINT NRC EXAM - 03/12/09 Q#7 Unit 3 is at 100% power.

  • A complete loss of CCW flow occurs.

In accordance with 3-0NOP-030, "Component Cooling Water Malfunction", which ONE of the following describes why operators are directed to establish one charging pump running at maximum speed?

A. Operating a charging pump at normal speed without CCW cooling may result in excessive coupling oil temperatures within 20 seconds.

B. Maximum charging flow is required to provide adequate cooling to the RCP seal packages during a loss of all CCW.

C. Maximum charging flow will result in pressurizer level rising above program to allow for RCS shrinkage during a subsequent natural circulation cooldown.

D. Operating a charging pump at maximum speed is needed to restore pressurizer level to program after the RO trips the reactor.

Page 13

TURKEY POINT NRC EXAM - 03/12/09 Q#8 Unit 3 is at 100% power.

  • An RCS leak occurs.
  • Pressurizer pressure is 1975 psig and decreasing.
  • Pressurizer level is 10% and decreasing.
  • Step 1 of 3-EOP-E-O, "Reactor Trip or Safety Injection", is in progress.
  • Efforts to manually trip the reactor are unsuccessful.

Which ONE of the following describes the correct operator response?

A. Continue with Step 2 of 3-EOP-E-O, and manually initiate SI.

B. Transition to 3-EOP-FR-S.1, "Response to Nuclear Power Generation/ATWS", and manually initiate SI.

C. Continue with Step 2 of 3-EOP-E-0 and DO NOT manually initiate SI.

D. Transition to 3-EOP-FR-S.1, "Response to Nuclear Power Generation/ATWS", and DO NOT manually initiate SI.

Page 15

TURKEY POINT NRC EXAM - 03/12/09 0#9 With both units initially in Mode 1 the switchyard de-energizes.

Unit 4 operators are responding to an uncontrolled depressurization of all SGs.

  • RCS Cold Leg temperatures have decreased from 54rF to 400°F in the past 15 minutes.
  • The RO is preparing to reinitiate feed flow to the SGs.

In accordance with 4-EOP-ECA-2.1, "Uncontrolled Depressurization of All Steam Generators", which ONE of the following describes how much feed flow will be established to the Unit 4 SGs and the basis for these actions?

Initially establish:

A. 25 gpm flow to each SG.

Feed flow is required to be initiated slowly to avoid unacceptable thermal stress on the reactor vessel and SGs.

B. 100 gpm flow to each SGs.

Feed flow is required to be initiated slowly to avoid unacceptable thermal stress on the reactor vessel and SGs.

C. 25 gpm flow to each SG.

Minimum safeguards AFW flow required for heat removal plus normal channel inaccuracy.

D. 100 gpm flow to each SGs.

Minimum safeguards AFW flow required for heat removal plus normal channel inaccuracy.

Page 17

TURKEY POINT NRC EXAM - 03/12/09 Q #10 Unit 3 was at 100% power when it experienced a Loss of All Main Feedwater Event.

  • All SGs have blown dry.
  • "A" AFW pump has been reset and is ready for operation.

In accordance with 3-EOP-FR-H.1, "Response to Loss of Secondary Heat Sink",

which ONE of the following correctly describes limits (if any) on the re-introduction of AFW flow to the dry SGs and the reason for those limits?

A. Do not re-initiate AFW flow to any SG until Bleed and Feed is established.

Flow introduction into dry SGs may result in unacceptable stresses to SG components.

B. Limit AFW flow to each SG to 100 gpm until wide-range level reaches 10%.

AFW flow greater than 100 gpm per SG may result in excessive RCS cooldown.

C. Limit total AFW flow to 345 gpm until wide-range levels reaches 10%.

AFW flow greater than 345 gpm may result in excessive RCS cooldown.

D. Establish maximum AFW flow within the capabilities of the "A" AFW pump.

RCS cooling must be established immediately to prevent an Inadequate Core Cooling situation.

Page 19

TURKEY POINT NRC EXAM - 03/12/09 Q #11 Both units are at 100% power.

The Turkey Point switchyard de-energizes.

  • Both 3A and 3B EDGs lockout and cannot be restarted.
  • All other equipment operated per design.

In accordance with 3-EOP-ECA-0.0, "Loss of All AC Power", which ONE of the following describes the correct operator response regarding operation of HHSI pumps?

Unit 3 Operators will:

A. maintain all four HHSI pumps control switches in AUTO.

B. place all four HHSI pumps control switches in Pull-To-Lock.

C. place Unit 3 HHSI pumps control switches in Pull-To-Lock and will maintain Unit 4 HHSI pumps control switches in AUTO.

D. maintain Unit 3 HHSI pumps control switches in AUTO and will place Unit 4 HHSI pumps control switches in Pull-To-Lock.

Page 21

TURKEY POINT NRC EXAM - 03/12/09 Q #12

  • Unit 4 is at 100% power with the Unit 4 Startup transformer out of service.

Which ONE of the following describes the effect on the Main Steam Isolation Valves (MSIVs) and required operator response in accordance with 4-EOP-ES-O.1?

The MSIVs will:

A. remain open.

If a cooldown due to excessive steam flow occurs, place the Steam Dump Mode Selector Switch to MAN.

B. remain open.

If a cooldown due to excessive steam flow occurs, place all MSIV control switches to CLOSE.

C. automatically close.

Verify the Steam Dump to Atmosphere controllers are in AUTO.

D. automatically close.

Place all MSIV control switches to CLOSE.

Page 23

TURKEY POINT NRC EXAM - 03/12/09 Q #13 Unit 3 is at 50% power.

  • The Pressurizer Level Control Transfer Switch on VPA is in Position 1.
  • Power is lost to 120V Vital Instrument Panel 3P07.

Which ONE of the following identifies the required operator action in accordance with 3-0NOP-003.7, "Loss of 120V Vital Instrument PaneI.3P07", and the reasons for that action?

Place the Pressurizer Level Control Transfer Switch in:

A. Position 2 to allow letdown to be reestablished and pressurizer heaters to be reenergized.

B. Position 2 to allow letdown to be reestablished and to allow automatic charging pump operation.

C. Position 3 to allow letdown to be reestablished and pressurizer heaters to be reenergized.

D. Position 3 to allow letdown to be reestablished and to allow automatic charging pump operation.

Page 25

TURKEY POINT NRC EXAM - 03/12/09 Q #14 Unit 3 is in Mode 1 and Unit 4 is in Mode 6.

  • 40 MCC is out of service.
  • Vital DC Bus 3001 de-energizes.
  • Following plant stabilization, the Shift Manager has given permission to re-energize 3D01.

Which ONE of the following describes how power will be restored to 3001 in accordance with 3-0NOP-003.4, "Loss of Bus 3001 and 3D01A (3A)"?

Strip the loads from 3001, place:

A. 3A2 Battery Charger in service, then place the 3A Battery in service.

B. 3A 1 Battery Charger in service, then place the 3A Battery in service.

C. 3A Battery in service, then place 3A2 Battery Charger in service.

O. 3A Battery in service, then place 3A 1 Battery Charger in service.

Page 27

TURKEY POINT NRC EXAM - 03/12/09 Q #15 Unit 3 is at 100% power with all systems operable and in normal alignment.

  • 3A and 3C ICW pumps are running.
  • 3A EDG locks out.

Which ONE of the following describes the automatic response of the ICW pumps and what is the minimum number of ICW pumps required to provide post-accident heat removal capability?

3A and 3C ICW pumps trip. Then:

A. Both 3B and 3C ICW pumps will automatically start.

Two ICW pumps are required to provide post-accident heat removal capability.

B. Both 3B and 3C ICW pumps will automatically start.

Only one ICW pump is required to provide post-accident heat removal capability.

C. Only 3B ICW pump will automatically start.

Two ICW pumps are required to provide post-accident heat removal capability.

D. Only 3B ICW pump will automatically start.

Only one ICW pump is required to provide adequate post-accident heat removal capability.

Page 29

TURKEY POINT NRC EXAM - 03/12/09 Q #16 Which one of the following is the concern when cross-tie valves (IAS-3-012 and IAS-4-012) downstream of the instrument air particulate filters are open during instrument air dryer maintenance?

A. Problems with pneumatic controllers due to unfiltered air being supplied to the system.

B. If one of the filters plugged, this could result in reduced air pressure on both Units 3 and 4.

C. This defeats the alternate shutdown requirements of the Instrument Air System if Control Room evacuation is required.

D. Low air pressure protection provided by header pressure control valves CV-3-1605 and CV-4-1605 are bypassed.

Page 31

TURKEY POINT NRC EXAM - 03/12/09 Q #17 Unit 3 is on-line at 8% power.

Unit 4 is on-line at 40% power.

  • Both units' Generator Hertz meters peg low below 58 hertz.

Which ONE of the following describes the effect on the plant if grid frequency drops to 54 hertz and remains less than 55 hertz?

A. Only Unit 4 reactor will trip due to RCP breaker-open logic and both units' GCB(s) will open 12 seconds later.

B. Only Unit 4 reactor will trip due to RCP breaker-open logic and only Unit 4's GCB(s) will open 12 seconds later.

C. Both Unit 3 and Unit 4 reactors will trip due to RCP breaker-open logic and both units' GCB(s) will open 12 seconds later.

D. Both Unit 3 and Unit 4 reactors will trip due to RCP breaker-open logic and only Unit 4's GCB(s) will open 12 seconds later.

Page 33

TURKEY POINT NRC EXAM - 03/12/09 Q #18 Which ONE of the following identifies a containment sump recirculation isolation valve configuration that wi" cause a loss of Emergency Coolant Recirculation due to backflow from the RWST to the Containment Sump?

A. Both MOV-862A and MOV-862B are open while both MOV-860A and MOV-861A are open B. Both MOV-862A and MOV-862B are open while both MOV-860A and MOV-860B are open C. Either MOV-862A or MOV-862B is open while both MOV-860A and MOV-861A are open D. Both MOV-862A and MOV-862B are open while either MOV-860A or MOV-860B is open Page 35

TURKEY POINT NRC EXAM - 03/12/09 Q #19 Unit 3 is at 95% power.

  • "0" Bank control rods are all at 190 steps when they begin to withdraw.
  • The RO places rods in MANUAL after "0" Bank has withdrawn 6 steps.
  • Rod H8 did not move and is still at 190 steps.
  • Reactor Engineering determines Rod H8 did not move because of excessive friction.

Which ONE of the following describes the effect of this event on control rod operability and the correct operator response in accordance with 3-0NOP-028, "Reactor Control System Malfunction"?

Rod H-8 is:

A. operable.

Maintain rods in MANUAL at the present rod height.

B. operable.

Insert the other "0" Bank control rods to 190 steps to match Tavg with Tref.

C. inoperable.

Insert the other "0" Bank control rods to 190 steps to comply with Tech Spec 3.1.3.1, "Movable Control Assemblies - Group Height".

O. inoperable.

Comply with Tech Spec 3.1.1.1, "Shutdown Margin" Action Statement.

Page 37

TURKEY POINT NRC EXAM - 03/12/09 Q#20 Unit 3 Reactor power is 80%.

  • The Shift Manager has directed the crew to realign Rod H8.
  • Annunciator B 9/4, ROD CONTROL URGENT FAILURE, alarms when the rod realignment begins.

Which ONE of the following identifies which lift coil disconnect switches were disconnected and the source of the B 9/4 alarm?

A. All "0" bank switches except Rod H-8 were disconnected.

Group 1 is the source of the B 9/4 alarm.

B. Only "0" bank Group 2 switches except Rod H-8 were disconnected.

Group 1 is the source of the B 9/4 alarm.

C. All "0" bank switches except Rod H-8 were disconnected.

Group 2 is the source of the B 9/4 alarm.

D. Only "0" bank Group 2 switches except Rod H-8 were disconnected.

Group 2 is the source of the B 9/4 alarm.

Page 39

TURKEY POINT NRC EXAM - 03/12/09 Q #21 The Unit 4 RO is Emergency Borating.

  • Emergency Boration valve, MOV-4-350, is placed to OPEN.
  • Both red and green lights for MOV-4-350 came on and then went out.
  • Emergency Borate Flow indicator, FI-4-110, displays 20 gpm flow.

NOTE valve titles:

FCV-4-113A: Boric Acid to Blender Valve FCV-4-113B: Blender Flow to Charging Pump Valve 4-356: Manual Emergency Boration Valve In accordance with 4-0NOP-046.1, "Emergency Boration", which ONE of the following identifies the required operator actions that will establish adequate emergency boration flow?

A. Start an additional charging pump and increase its speed to maximum.

B. Direct the field operator to locally open MOV-4-350.

C. Open FCV-4-113A OR FCV-4-113B .

. Locally open 4-356. When 4-356 is open, close FCV-4-113B if opened.

D. Open FCV-4-113A AND FCV-4-113B.

Locally open 4-356. When 4-356 is open, close FCV-4-113B.

Page 41

TURKEY POINT NRC EXAM - 03/12/09 0#22 Which ONE of the following lists the MINIMUM required conditions (Interlocks) that must be met before the fuel transfer carriage can be moved from containment to the spent fuel pit?

A. Transfer tube valve oper;1, containment side frame in the DOWN position, spent fuel pit side frame in the UP position.

B. Manipulator crane grippers UP or UP disengaged, containment side frame in the DOWN position, spent fuel pit side frame in the UP position.

c. Manipulator crane grippers UP or UP disengaged both containment and spent fuel pit frames in the DOWN position.

D. Transfer tube valve open, both containment and spent fuel pit frames in the DOWN position.

Page 43

TURKEY POINT NRC EXAM - 03/12/09 0#23 Unit 4 is at 100% power.

  • Unit 4 fuel clad defects and Iodine concentrations are at the levels assumed in the FSAR.

Which one of the following identifies the order in which process radiation monitor(s) will alarm following the tube rupture and describes the FSAR predicted doses as compared to the 10CFR20 limit for a worker at the site boundary?

NOTE: R-15 is the Condenser Air Ejector Gas Monitor R-19 is the Steam Generator Liquid Sample Monitor A. R-15 will alarm before R-19.

The Thyroid and Wholebody doses will be less than 10CFR20 limits.

B. R-15 will alarm before R-19.

The Thyroid and Wholebody doses will be greater than 10CFR20 limits.

C. R-15 will alarm after R-19.

The Thyroid and Wholebody doses will be less than 10CFR20 limits.

D. R-15 will alarm after R-19.

The Thyroid and Wholebody doses will be greater than 10CFR20 limits.

Page 45

TURKEY POINT NRC EXAM - 03/12/09 0#24 80th Units are initially at 100% power.

  • A fire has erupted in the Cable Spreading Room.
  • The Shift Manager has ordered a control room evacuation.

In accordance with 0-ONOP-1 05, "Control Room Evacuation", which ONE of the following correctly describes an immediate action the Unit 3 RO should perform prior to evacuating the control room?

A. Place the control switches for the pressurizer PORVs, PCV-3-455C and PCV-3-456, to CLOSE.

8. Place the control switch for the High Press LID Isol Valve, LCV-3-460, to CLOSE C. Verify the 38 Charging pump is tripped.

D. Verify the "8" Standby SG Feedwater Pump is tripped.

Page 47

TURKEY POINT NRC EXAM - 03/12/09 0#25 Operators have entered 3-EOP-FR-P.1, "Response to Imminent Pressurized Thermal Shock Condition" due to a main steam line break outside containment.

  • The RO is preparing to depressurize the RCS to decrease RCS subcooling.

Based on these conditions and in accordance with 3-EOP-FR-P.1, which ONE of the following correctly identifies the required method to be used to depressurize the RCS and a correct criterion for stopping the depressurization.

Depressurize the RCS using a(n):

A. auxiliary pressurizer spray valve.

Stop Depressurizing when pressurizer level reaches 30%.

B. pressurizer PORV.

Stop Depressurizing when pressurizer level reaches 30%.

C. auxiliary pressurizer spray valve.

Stop Depressurizing when RCS CET subcooling is less than 40°F D. pressurizer PORV.

Stop Depressurizing when RCS CET subcooling is less than 40°F Page 49

TURKEY POINT NRC EXAM - 03/12/09 Q#26 Operators are performing a natural circulation cooldown on Unit 3.

  • Auxiliary spray is being used to depressurize the RCS.
  • As pressure is decreased through 900 psig, Pressurizer level rapidly increases.
  • Charging and letdown are in manual and are matched.

Which ONE of the following describes the correct action required to mitigate this event in accordance with 3-EOP-ES-0.2, "Natural Circulation Cooldown"?

A. Increase the cooldown rate to the maximum allowed rate of 25°F/hour.

Continue performing 3-EOP-ES-0.2.

B. Increase the cooldown rate to the maximum allowed rate of 100°F/hour.

Transition to 3-EOP-ES-0.3, "Natural Circulation Cooldown with Steam Void in Vessel".

C. Repressurize the RCS to collapse any steam voids.

Continue performing 3-EOP-ES-0.2.

D. Repressurize the RCS to collapse any steam voids.

Transition to 3-EOP-ES-0.3, "Natural Circulation Cooldown with Steam Void in Vessel".

Page 51

TURKEY POINT NRC EXAM - 03/12/09 0#27 Operators are performing 4-EOP-FR-Z.1, "Response to High Containment Pressure."

Which ONE of the following describes the operation of Reactor Coolant Pumps (RCPs) per 4-EOP-FR-Z.1 and the position of the MSIVs.

A. All RCPs should be stopped to minimize energy input into the containment.

MSIVs are open.

B. All RCPs should be stopped to prevent them from being damaged due to cooling water isolation.

MSIVs are closed.

C. All RCPs can remain running provided seal injection can be established.

MSIVs are open.

D. All RCPs can remain running provided seal injection can be established.

MSIVs are closed.

Page 53

TURKEY POINT NRC EXAM - 03/12/09 Q #28 Which ONE of the following correctly describes the PUrj:.l e of the RCP Oil Lift pump and how it is required to be operated in accor ce with 3-0P-041.1, "Reactor Coolant Pump", during a normal RCP st ?

The RCP Oil Lift pump prevents metal to m al contact for the RCP:

A. thrust bearing during RCP sta p.

The RCP Oil Lift Pump ope tion must be limited to 20 minutes.

B. thrust bearing during P startup.

The RCP Oil Lift P P should be run at least 3 minutes prior to starting the RCP.

C. radial bear" gs during RCP startup.

The RC Oil Lift Pump operation must be limited to 20 minutes.

D. ra 'al bearings during RCP startup.

he RCP Oil Lift Pump should be run at least 3 minutes prior to starting the RCP.

Page 55

TURKEY POINT NRC EXAM - 03/12/09 Q#29 Unit 3 is at 100% power when SI actuates.

Which ONE of the following describes the effect of this SI actuation on the RCPs?

A. Seal injection flow to the RCPs will be isolated.

B. CCW flow to and from the RCPs motor bearing coolers will be isolated.

C. CCW flow to and from the RCPs thermal barrier will be isolated.

D. #1 seal backpressure will increase causing a decrease in #1 seal leak-off flow.

Page 57

TURKEY POINT NRC EXAM - 03/12/09 Q#30 Unit 4 operators are performing 4-EOP-ECA-1.1, "Loss of Emergency Coolant Recirculation".

  • Unit 4 RWST level is at 30,000 gallons and decreasing.

Based on these conditions which ONE of the following describes the effect on Unit 4 charging pump operation and required operator action(s) in accordance with 4-EOP-ECA-1.1 ?

The running charging pump is:

A. in immediate danger of gas binding.

Stop the running charging pump.

B. still capable of delivering flow.

Add makeup to the Unit 4 RWST.

C. in immediate danger of gas binding.

Isolate the charging flowpath and maintain minimum seal injection flow.

D. still capable of delivering flow.

Isolate the seal injection flowpath and maintain charging flow.

Page 59

TURKEY POINT NRC EXAM - 03/12/09 Q #31 Unit 3 is on RHR cooling in Mode 4.

  • RCS loop temperatures are 340°F.
  • All plant systems are operable and in normal Mode 4 alignment.
  • A tube leak occurs in the 3A RHR Heat Exchanger.
  • Operators isolate the 3A RHR Heat Exchanger.

NOTE: Tech Spec 3.4.1.3,"Reactor Coolant System - Hot Shutdown" Limiting Condition for Operation (LCO).

Which ONE of the following describes the effect of the 3A RHR Heat Exchanger isolation on the RHR system and the status of compliance with Tech spec 3.4.1.3?

The RHR System is:

A. still capable of removing core decay heat.

Tech Spec 3.4.1.3 LCO is satisfied.

B. still capable of removing core decay heat.

Tech Spec 3.4.1.3 LCO is NOT satisfied.

C. NOT capable of removing core decay heat.

Tech Spec 3.4.1.3 LCO is satisfied.

D. NOT capable of removing core decay heat.

Tech Spec 3.4.1.3 LCO is NOT satisfied.

Page 61

TURKEY POINT NRC EXAM - 03/12/09 Q#32 Which ONE of the following identifies a situation that can cause damage to ECCS components and the procedural method that will prevent this occurrence?

A. RHR system over-pressure caused by starting an RHR Pump with discharge valves closed.

Open RHR Hx Bypass Flow Valve, FCV-3-605, prior to starting the first RHR pump in accordance with 3-0P-050, "Residual Heat Removal System".

B. RHR system over-pressure caused by starting an RHR Pump with discharge valves closed.

Open RHR Hx Outlet Flow Valve, HCV-3-758, prior to starting the first RHR pump in accordance with 3-0P-050, "Residual Heat Removal System".

C. A water hammer event caused by nitrogen intrusion into RHR piping.

Periodically vent RHR piping and equipment in accordance with 3-0SP-202.2, "RHR Pump and Piping Venting".

D. A water hammer event caused by nitrogen intrusion into RHR piping.

Periodically sample for nitrogen in the RHR system in accordance with 0-NCZP-050, "Obtaining a Residual Heat Removal (RHR) Sample".

Page 63

TURKEY POINT NRC EXAM - 03/12/09 Q#33 Unit 3 is at 100% power with all controls in automatic and all tank levels within normal limits.

  • Pressurizer Safety, RV-3-551 B, begins to leak causing VCT level to decrease at a steady rate of 1% every minute.

Which ONE of the following describes the expected rate of change in pressurizer level and pressurizer relief tank (PRT) level for this constant leak rate?

Pressurizer level will:

A. remain constant.

PRT level will increase at a rate of approximately 1% every minute.

B. remain constant.

PRT level will increase at a rate of approximately 1% every 7 minutes.

C. decrease at a rate of approximately 1% every 3 minutes.

PRT level will increase at a rate of approximately 1% every minute.

D. decrease at a rate of approximately 1% every 3 minutes.

PRT level will increase at a rate of approximately 1% every 7 minutes.

Page 65

TURKEY POINT NRC EXAM - 03/12/09 Q#34 Unit 3 is at 100% power.

  • RCS and containment pressure are approximately 23 psig and lowering.

Which ONE of the following describes the relationship between initial and final 3A and 38 CCW Header Flow Indicators, FI-3-613A18?

CCW flow in the:

A. "3A" and "38" headers will increase to approximately 2000 gpm.

8. "3A" and "38" headers will increase to approximately 6000 gpm.

C. "3A" header will increase from approximately 200 gpm to 2000 gpm and "38" header will remain approximately 6000 gpm D. "3A" header will remain approximately 6000 gpm and "38" header will increase from approximately 200 gpm to 2000 gpm.

Page 67

TURKEY POINT NRC EXAM - 03/12/09 0#35 Unit 4 is at 100% power.

  • Operators start a second Component Cooling Water pump.
  • A 1/1, RCP THERMAL BARR COOLING WATER HI FLOW, alarms and clears.
  • A 1/3, RCP THERMAL BARR COOLING WATER La FLOW, alarms and locks in.

Based on these conditions, which ONE of the following describes the effect on RCP operation and the required operator response in accordance with 4-ARP-097.CR A 1/3, "RCP THERMAL BARR COOLING WATER La FLOW"?

A. RCP Thermal Barrier cooling is lost.

Re-open RCP THERMAL BARR OUTLET valve, MOV-4-626.

B. RCP Thermal Barrier cooling is lost.

Trip the reactor and trip the RCPs.

C. All RCP seal cooling has been lost.

Re-open RCP THERMAL BARR OUTLET valve, MOV-4-626.

D. All RCP seal cooling has been lost.

Trip the reactor and trip the RCPs.

Page 69

TURKEY POINT NRC EXAM - 03/12/09 Q#36

  • 3-GOP-305, "Hot Standby to Cold Shutdown" is in progress on Unit 3.
  • Conditions have been established to block SI for the second time.

Which ONE of the following identifies the SI signal that is being blocked at this point, and what other block occurs at this time?

A. Low Pressurizer Pressure SI Automatic opening of Pressurizer PORVs will be blocked.

B; High Steamline Flow with Low Tavg SI Automatic opening of Pressurizer PORVs will be blocked.

C. Low Pressurizer Pressure SI Automatic closing of the MSIVs will be blocked.

D. High Steamline Flow with Low Tavg SI Automatic closing of the MSIVs will be blocked.

Page 71

TURKEY POINT NRC EXAM - 03/12/09 0#37 Operators are responding to a Main Steam Line Break on Unit 3.

  • During the event the Pressurizer completely emptied.
  • Pressurizer level is 60%.
  • Pressurizer steam space temperature is 600°F.
  • Pressurizer water space temperature is 560°F.
  • RCS hot leg temperatures are 54rF.
  • RCS cold leg temperatures are 528°F
  • Operators are restoring normal letdown.

As pressurizer level decreases, which ONE of the following identifies the lowest value RCS pressure may reach as a result of restoring letdown?

A. 856 psig B. 1005 psig C. 1119psig D. 1528 psig NOTE: Steam Tables Provided Page 73

TURKEY POINT NRC EXAM - 03/12/09 Q#38 Unit 3 is at 5% power.

  • AC Vital Panel 3P06's main input breaker, 3P06-MAIN, trips open.

Which ONE of the following describes the response of the reactor protection system?

A. Only SR N-31 causes a reactor trip.

B. Only IR N-35 causes a reactor trip.

C. Both IR N-35 and PR N-41 cause a reactor trip.

D. NO reactor trip results from N-31, N-35 or N-41.

Page 75

TURKEY POINT NRC EXAM - 03/12/09 Q#39 Unit 4 is Mode 1 @ 100%.

The following conditions exist:

  • 4C CCW Pump is running for an oil sample.
  • 4D 4Kv bus is aligned to the 4A 4Kv bus.
  • 4A and 4B Component Cooling Water (CCW) pumps are in standby.

A Loss Of Offsite Power (LOOP) occurs on Unit 4.

Which ONE of the following correctly describes the status of the CCW pumps and their power source when sequencing is complete?

A. 4A CCW pump running powered via the 4A EDG and 4B CCW pump running powered from the 4B EDG.

B. 4C CCW pump running powered via the 4A EDG and 4B CCW pump running powered from the 4B EDG.

C. Only the 4A CCW pump running from the 4A EDG.

D. Only the 4B CCW pump running from the 4B EDG.

Page 77

TURKEY POINT NRC EXAM - 03/12/09 0#40 Operators are responding to a Safety Injection (SI) actuation on Unit 3.

  • Containment pressure peaked @ 18 psig.
  • Containment temperature is currently 185 degrees and lowering.

Which ONE of the following describes the current status of the containment isolation valves and Emergency Containment Coolers (ECCs)?

Phase "8" valves ECCs RUNNING A. CLOSED 3A&38

8. OPEN 3A&3C C. CLOSED 3A& 3C D. OPEN 3A& 38 Page 79

TURKEY POINT NRC EXAM - 03/12/09 Q #41 Unit 3 experienced a large break LOCA.

Operators have responded with the EOP network.

The following conditions exist on Unit 3:

  • U3 RWST level is 57,000 gallons
  • U3 Containment Sump level is 431"
  • Containment temperature is 140°F and slowly lowering.

Which ONE of the following describes the correct Containment Spray Pump (CSP) alignment when the operators exit ES-1.3, "Transfer to Cold Leg Recirculation"?

A. All CSPs placed in Pull to Lock.

B. 1 CSP running with its suction aligned from the RHR pump discharge.

C. 1 CSP running with its suction aligned directly from U3 RWST.

D. 1 CSP running with its suction aligned directly from U4 RWST.

Page 81

TURKEY POINT NRC EXAM - 03/12/09 Q #42 Operators are responding to a LOCA on Unit 3

  • Safety Injection (SI) is reset 3 minutes after SI actuation
  • Containment pressure increases to 20 psig one minute after SI is reset.

Which ONE of the following correctly describes the effect of this event on the Containment Spray flow and the required operator response in accordance with 3-EOP-E-O, "Reactor Trip or Safety Injection"?

A. Containment spray flow is established.

Verify both CSPs automatically started and both CSP discharge MOVs automatically opened.

B. Containment spray flow is NOT established.

Verify both CSPs automatically started and manually open both CSP discharge MOVs.

C. Containment spray flow is NOT established.

Manually start both CSPs and manually open both CSP discharge MOVs.

D. Containment spray flow is NOT established.

Manually start both CSPs and verify the CSP discharge MOVs automatically opened.

Page 83

TURKEY POINT NRC EXAM - 03/12/09 Q #43 Operators are performing a reactor startup on Unit 4.

  • The 4A Steam Oump to Atmosphere (SOTA) valve is 10% open and its controller is being operated in automatic when its setpoint begins to continuously drift below 1000 psig.

Which ONE of the following describes the effect of this setpoint drift?

The 4A SOTA valve will:

A. OPEN, dumping more steam and lowering Tavg. If uncorrected, the 541°F minimum temperature for criticality Tech Spec limit may be violated.

8. OPEN, dumping more steam and lowering Tavg. If uncorrected, the 543°F minimum temperature for criticality Tech Spec limit may be violated.

C. CLOSE and stop dumping steam. 48 and 4C SOTA valves will open to relieve more steam and maintain Tavg within acceptable limits.

O. CLOSE and stop dumping steam. 48 and 4C SOTA valves will not respond and Tavg will increase above the limit of 549°F.

Page 85

TURKEY POINT NRC EXAM - 03/12/09 0#44 Unit 3 is at 70% power with all controls in automatic.

Which ONE of the following predicts how the 3A SG level will initially respond and the required operator actions in accordance with 3-ARP-097.CR, "Control Room Annunciator Response"?

A. 3A SG level will increase above program.

Place 3A SG Feedwater controller in MAN and decrease feed flow to bring level back to program.

B. 3A SG level will increase above program.

Select feed flow transmitter FT-3-477 for control and verify 3A SG level automatically returns to programmed level.

C. 3A SG level will decrease below program.

Place 3A SG Feedwater controller in MAN and increase feed flow to bring level back to program.

D. 3A SG level will decrease below program.

Select feed flow transmitter FT-3-477 for control and verify 3A SG level automatically returns to programmed level.

Page 87

TURKEY POINT NRC EXAM - 03/12/09 Q#45 Unit 3 is in Mode 3.

  • The 3B 4KV Bus Startup Transformer breaker, 3AB05, trips open.

Which ONE of the following describes the direct effect of this event on the AFW system?

Only Steam Supply to Aux Feedwater Pumps valves:

A. MOV-3-1403 and MOV-3-1404 will automatically open providing main steam to Train 2 AFW pump(s) only.

B. MOV-3-1403 and MOV-3-1404 will automatically open providing main steam to all AFW pumps C. MOV-3-1404 and MOV-3-1405 will automatically open providing main steam to Train 1 AFW pump(s) only.

D. MOV-3-1404 and MOV-3-1405 will automatically open providing main steam to all AFW pumps Page 89

TURKEY POINT NRC EXAM - 03/12/09 Q#46 The Auxiliary Feedwater (AFW) system receives an auto-start signal while Unit 3 is in Mode 3.

  • "A" AFW pump trips on over-speed.

Which ONE of the following describes the effect of this event on Train 1 AFW flow control valves?

The Train 1 AFW flow control valves will:

A. NOT auto-open.

B. auto-open and remain fully open.

c. auto-open but will close after the AFW pump trips.

D. auto-open and then throttle back to maintain 130 gpm flow.

Page 91

TURKEY POINT NRC EXAM - 03/12/09 Q#47 Unit 4 is in Mode 6.

  • The 4A 4KV Bus and its associated 480V Load Centers are out of service.
  • The DC input breaker to 4A Inverter trips open and cannot be reclosed.

Which ONE of the following describes the effect on the plant and the correct operator response?

Vital AC Bus 4P07 will:

A. automatically be powered from the AS Inverter.

Operators will manually transfer 4P07 from the AS Inverter to the CVT.

B. automatically be powered from its back-up CVT Operators will manually transfer 4P07 from the CVT to the AS Inverter.

C. de-energize.

Operators will manually transfer 4P07 to the AS Inverter.

D. de-energize.

Operators will manually transfer 4P07 to its back-up CVT.

Page 93

TURKEY POINT NRC EXAM - 03/12/09 Q#48 Which ONE of the following identifies the major DC loads that are affected with a loss of 3D01?

A. 3B EDG, AFW Train 2, Containment Air Monitors R-11 and R-12, C AFW Pump Control B. 4A EDG, AFW Train 2, Containment Air Monitors R-11 and R-12, Control Room Annunciators C. 3A EDG, AFW Train 1, Blender Flow to CHP Suction Header valve FCV-113B, Control Room Annunciators D. 4B EDG, AFW Train 1, Blender Flow to CHP Suction Header valve FCV-113B, C AFW Pump Control Page 95

TURKEY POINT NRC EXAM - 03/12/09 0#49 Both Units are at 100% power.

  • Unit 3 Startup transformer is out of service.
  • ANN - F - 8/2 "EDG A Trouble Alarm" is in alarm.
  • ANPO reports to the control room that 3A EDG starting air receivers pressure are 150 PSIG as read on both PI-3-3690A and PI-3-3693A.

Which ONE of the following describes the effect on EDG operability and the reportability requirements to the NRC in accordance with Tech Specs Section 3.8.1 "AC Sources - Operating"?

NOTE: NRCOC: Nuclear Regulatory Commission Operations Center The 3A EDG is:

A. OPERABLE.

Notification to the NRC is NOT required.

B. OPERABLE.

Only the NRC Resident needs to be notified.

C. INOPERABLE.

Only the NRC Resident needs to be notified.

D. INOPERABLE.

This event shall be reported to the NRCOC.

Page 97

TURKEY POINT NRC EXAM - 03/12/09 Q #50 Unit 3 is in Mode 1 when a LOCA occurs.

  • 38 EDG locks out and cannot be restarted.

Which ONE of the following describes the required operator actions in accordance with 3-EOP-E-0,"Reactor Trip or Safety Injection"?

Operators will:

A stop both Unit 4 HHSI pumps and maintain Unit 4 HHSI pumps suction aligned to the Unit 4 RWST.

8 stop one Unit 4 HHSI pump and realign the Unit 4 HHSI pumps suction to the Unit 3 RWST.

C maintain all available HHSI pumps running and realign the Unit 4 HHSI pumps suction to the Unit 3 RWST.

o stop both Unit 4 HHSI pumps and realign the Unit 4 HHSI pumps suction to the Unit 3 RWST, then restart one Unit 4 HHSI pump.

Page 99

TURKEY POINT NRC EXAM - 03/12/09 Q #51 Which ONE of the following describes the Reactor Coolant Letdown Line Radioactivity Monitor, R-20 and the design feature that compensates for Nitrogen 16 (N-16) gamma radiation?

R-20 is a:

A. Geiger-Mueller detector.

N-16 gamma is compensated by the long transit time from the reactor to the detector.

B. Scintillation detector.

N-16 gamma is compensated by the long transit time from the reactor to the detector.

C. Geiger-Mueller detector.

N-16 gamma is compensated by the shielding provided by the steel pipe wall of the letdown line.

D. Scintillation detector.

N-16 gamma is compensated by the shielding provided by the steel pipe wall of the letdown line.

Page 101

TURKEY POINT NRC EXAM - 03/12/09 Q#52 Unit 3 is at 100% power in normal system alignment with the following exceptions:

  • 3A Intake Cooling Water (ICW) Pump is tagged out for Maintenance.
  • 3C Component Cooling Water (CCW) Hx is tagged out for cleaning.

The 38 ICW Pump trips on overcurrent.

The SNPO reports the following ICW/CCW Hx flows:

3A 8500 gpm 38 8000 gpm 3C DOS The Unit 3 Turbine Operator reports the following ICWITPCW Hx flows:

3A 3500 gpm 38 2500 gpm 3C ODS In accordance with 3-0NOP-019, "Intake Cooling Water Malfunction", which ONE of the following is the maximum allowed flow for one pump operation and the required operator action?

A. 19,000 gpm; throttle ICW flow to the TPCW Hxs and / or CCW Hxs.

8. 21,000 gpm; throttle ICW flow to the TPCW Hxs and / or CCW Hxs.

C. 19,000 gpm; isolate ICW flow to the 38 CCW Hx.

D. 21,000 gpm; isolate ICW flow to the 38 TPCW Hx.

Page 103

TURKEY POINT NRC EXAM - 03/12/09 Q #53 Which ONE of the following identifies the normal Intake Cooling Water (ICW) system alignment as it relates to train separation?

The ICW headers to the Component Cooling Water (CCW) Heat Exchangers are

___ and ICW pumps are always powered from separate trains.

A. separated "A" and "8"

8. separated "8" and "c" C. cross-connected "A" and "8" D. cross-connected "8" and "c" Page 105

TURKEY POINT NRC EXAM - 03/12/09 0#54 Operators are responding to a large Instrument Air (IA) leak.

  • The RO dispatches the field operator to identify the source of the leak.
  • The field operator reports the Distribution Header Pressure Control Valves' status:

o CV-3-1605 is closed o CV-4-1605 is in mid position.

Which ONE of the following identifies the source of the leak and the lowest instrument air pressure expected to occur on the unit with the intact instrument air system?

A. The leak is on Unit 3.

Unit 4's instrument air pressure will go no lower than 88 psig.

B. The leak is on Unit 3.

Unit 4's instrument air pressure will go no lower than 75 psig.

C. The leak is on Unit 4.

Unit 3's instrument air pressure will go no lower than 88 psig.

D. The leak is on Unit 4.

Unit 3's instrument air pressure will go no lower than 75 psig.

Page 107

TURKEY POINT NRC EXAM - 03/12/09 Q#55 Unit 3 is in Mode 4.

Maintenance has requested to remove power from Excess Letdown and RCP Seal Return Valve, MOV-3-381, and maintain the valve fully open while work is performed on the valve motor.

This request should:

A. NOT be granted because maintaining MOV-3-381 fully open would result in exceeding the thermal limits of the Seal Water HX.

B. NOT be granted because it would place the unit in non-compliance with the Containment Integrity Limiting Condition for Operation.

C. be granted because Unit 3 is in Mode 4 and the Containment Integrity Limiting Condition for Operation is NOT applicable.

D. be granted because RCP Seal Return is a non-safety related flow path and the Containment Integrity Limiting Condition for Operation is NOT applicable.

Page 109

TURKEY POINT NRC EXAM - 03/12/09 Q#56 Unit 3 is at 100% power.

The Tavg signal to the Pressurizer level control program rapidly fails low.

Which ONE of the following describes the effect on Pressurizer level and the Pressurizer heaters (Assume no Operator Action)?

Pressurizer level will:

A. increase.

Backup Heaters "An & "B" will automatically turn on and stay on.

B. decrease.

Backup Heaters "A" & "B" will automatically turn on and stay on.

c. increase.

Backup Heaters "An & "B" will automatically turn on and subsequently automatically turn off.

D. decrease.

Backup Heaters "An & "B" will automatically turn on and subsequently automatically turn off.

Page 111

TURKEY POINT NRC EXAM - 03/12/09 Q #57 Unit 3 is at 100% power with all systems in normal operation with the following exception, 3A Boric Acid Transfer Pump (BATP) which is tagged out for maintenance.

The unit 3 Reactor trips and while operators are performing steps in 3-EOP-ES-O.1, "Reactor Trip Response," the following conditions exist:

  • 3B BATP breaker control board lights are extinguished.
  • H-8 RPI indicates 152 steps and M-8 RPI indicates 112 steps and their associated rod bottom lights are out.

Which ONE of the following describes the required operator action in accordance with 3-EOP-ES-0.1 and the subsequent effect of the operator's local action?

The RO will dispatch the plant operator to:

A. check the breakers to the RPI Inverter.

Control Room RPI indication will be subsequently restored.

B check the trouble indicating lamps on the Rod Control Logic Cabinet.

Control Room RPI indication will be subsequently restored.

C. close the breaker for the 3B BATP.

Emergency boration will be subsequently established from the BASTs.

D. open the breaker for VCT Outlet Valve, LCV-3-115C.

Emergency boration will be subsequently established from the RWST.

Page 113

TURKEY POINT NRC EXAM - 03/12/09 Q #58 Unit 4 is at 100% power with all systems operable and in normal alignment.

  • Turbine first stage pressure transmitter PT-4-447 fails high.

Which ONE of the following correctly describes the effect of this failure on Unit 4 and the operator response required by 4-0NOP-049.1, "Deviation or Failure of Safety Related or Reactor Protection Channels"?

High steam flow bistables for Safety Injection logic have:

A. tripped.

Bistable switches will have to be placed in the tripped position.

B. tripped.

Bistable switches will NOT have to be placed in the tripped position.

C. NOT tripped.

Bistable switches will have to be placed in the tripped position.

D. NOT tripped.

Bistable switches will NOT have to be placed in the tripped position.

Page 115

TURKEY POINT NRC EXAM - 03/12/09 0#59 Which ONE of the following describes the upper range for the GET system and also identifies the temperature that corresponds to the onset of the lirc-Water reaction?

GETs are capable of indicating accurately up to _ _

_ _ is the threshold temperature that indicates the onset of lirc-Water reaction.

A. 2300°F 12000F B. 2750 0F 1000°F G. 2300 0F 1000°F D. 2750°F 1200°F Page 117

TURKEY POINT NRC EXAM - 03/12/09 Q #60 Operators are responding to a Small Break LOCA on Unit 3.

  • Containment pressure peaked at 12 psig.
  • Containment temperature is 160 degrees and slowly lowering.
  • One hour after event initiation the 3C ECF fan fails.
  • The RO observes dual light indication (Both red and green lights on) for the 3C ECF Spray valves.

Which ONE of the following describes the 3C ECF spray valves response and the effect on 3C ECF charcoal bed temperatures?

A. Both ECF spray valves are full open.

3C ECF charcoal temperatures will decrease.

B. Both ECF spray valves are full open.

3C ECF charcoal temperatures will increase.

C. Only one ECF spray valve is full open.

3C ECF charcoal temperatures will decrease.

D. Only one ECF spray valve is full open.

3C ECF charcoal temperatures will increase.

Page 119

TURKEY POINT NRC EXAM - 03/12/09' Q #61 Operators are performing a plant start up on Unit 4.

  • 4A SG narrow range level is 47% and stable.
  • 4A SG level controller is placed in AUTO.
  • Subsequently, the pressure compensation input to the 4A SG level control system fails high.

Which ONE of the following describes the initial and subsequent operation of the 4A feed reg va Ive?

When the controller is initially placed in AUTO, the 4A feed reg valve will (1) _ _

When the pressure compensation fails high, the 4A feed reg valve will (2) to match feed flow with steam flow.

A. (1) maintain feed flow matched with steam flow.

(2) open B. (1) maintain feed flow matched with steam flow.

(2) close C. (1) open to control SG level at 50%.

(2) open D. (1) open to control SG level at 50%.

(2) close Page 121

TURKEY POINT NRC EXAM - 03/12/09 Q#62 Unit 4 is in Mode 3.

Operators are preparing to cool down using the Steam Oump to Condenser (SOTC) system.

Which ONE of the following correctly describes conditions or interlocks that must be satisfied to allow operators to use the SOTC system for this purpose?

A. The Mode Selector Switch must be in AUTO.

Condenser vacuum must remain above 20"HG.

B. The Mode Selector Switch must be in AUTO.

The low Tavg interlock must be bypassed before Tavg decreases to 543°F.

C. The Mode Selector Switch must be in MANUAL.

Condenser vacuum must remain above 20"HG.

O. The Mode Selector Switch must be in MANUAL.

The low Tavg interlock must be bypassed before Tavg decreases to 543°F.

Page 123

TURKEY POINT NRC EXAM - 03/12/09 Q#63 Operators are rolling the Unit 3 turbine to normal operating spee

  • Turbine speed is approaching 1400 rpm when turbine 275 rpm/minute.

In accordance with 3-0P-089, "Main Turbine", w' ONE of the following describes the correct operator response?

Lower the:

A. Load Limit controller until cceleration is less than the maximum allowed value of 250 rpm/min B. Governor contr er until acceleration is less than the maximum allowed value of 25 pm/minute.

C. Load Imit controller until acceleration is less than the maximum allowed e of 150 rpm/minute.

Governor controller until acceleration is less than the maximum allowed value of 150 rpm/minute.

Page 125

TURKEY POINT NRC EXAM - 03/12/09 Q#64 A leaking fuel element is causing radiation levels in the Spent Fuel Pit (SFP) to increase.

Which ONE of the following identifies the requirements of 4-0P-033, "Spent Fuel Pit Cooling System," as it relates to the operation of the SFP purification loop?

1) Maximum allowable flow through the SFP Demineralizer is _ __
2) Maximum allowable SFP Demineralizer inlet water temperature is _ __

A. 1) 100 gpm

2) 140°F B. 1) 120 gpm
2) 140°F C. 1) 100 gpm
2) 130°F D. 1) 120 gpm
2) 130°F Page 127

TURKEY POINT NRC EXAM - 03/12/09 Q#65 Operators have just completed the release of a Gas Decay Tank (GOT) that had both Hydrogen and Oxygen concentrations in excess of 5%.

  • Chemistry has resampled the GOT after release and reports the following concentrations:

Hydrogen: 4.1 %

Oxygen: 2.3%

Which ONE of the following describes the required operator action (if any) and the reason for that action?

The GOT:

A. must be pressurized and released again based only on high Oxygen concentration.

B. must be pressurized and released again based on both high Hydrogen and Oxygen concentrations.

C. does NOT have to be released again because both the Hydrogen and Oxygen concentrations are within limits.

O. does NOT have to be released again because the Oxygen concentration is within limits.

Page 129

TURKEY POINT NRC EXAM - 03/12/09 0#66 The Reactor Operator reports an event that happened on a previous shift that should be entered into the Operations Department Logbook Program (NOMS).

In accordance with O-ADM-204, "Operations Narrative Logbooks," which ONE of the following describes the correct person and all steps needed to make this entry?

The log entry should be made by the:

A. responsible Reactor Operator.

Enter the date and time the event occurred and then the entry.

B. responsible Reactor Operator.

Enter "Late Entry", followed by the date/time the event occurred and then the entry.

C. Shift Manager.

Enter the date and time the event occurred and then the entry.

D. Shift Manager.

Enter liLate Entry", followed by the date/time the event occurred and then the entry.

Page 131

TURKEY POINT NRC EXAM - 03/12/09 Q #67 Unit 3 is at 70% power in a normal electrical alignment when the following events occur:

  • 3B SGFP's red light is on and its amperage has gone to zero.

Which ONE of the following describes a control room indication that is consistent with this event?

A. Megawatts are decreasing at 200% per minute.

B. Control Rods are inserting at 72 steps per minute.

C. 3B Bus Supply breaker, 3AB02, shows green light indication.

D. 3C Bus Supply breaker, 3AC16, shows green light indication.

Page 133

TURKEY POINT NRC EXAM - 03/12/09 Q#68 Unit 4 has been cooled down in preparation for refueling.

  • RCS Tavg is 135°F.
  • Maintenance is preparing to detension the Reactor Vessel head.

Which ONE of the following describes the Tech Spec Operational Mode the unit is presently in and the reason why?

A. Mode 5 because the Reactor Vessel head has not yet been detensioned.

B. Mode 5 because Tavg is higher than the Mode 6 temperature threshold.

C. Mode 6 because Tavg is lower than the Mode 6 temperature threshold.

D. Mode 6 because Shutdown Margin exceeds 5%.

Page 135

TURKEY POINT NRC EXAM - 03/12/09 Q#69 Unit 3 is at 90% power.

  • The Quadrant Power Tilt Ratio is 1.11 as a result of misalignment of a control rod.

Which ONE of the following describes the minimum actions required by Tech Specs?

Reduce reactor power to less than or equal to:

A. 57% within 30 minutes.

B. 67% within 30 minutes.

C. 57% within 60 minutes.

D. 67% within 60 minutes.

Page 137

TURKEY POINT NRC EXAM - 03/12/09 Q #70 Which ONE of the following describes an operational concern associated with initiating a Containment purge on Unit 3?

An uncontrolled radioactive release can occur if the Containment Purge:

A. Exhaust fan is started before the Containment Purge Supply fan.

B. Exhaust fan is started without the Unit 3 equipment hatch, emergency hatch, and at least one personnel door closed.

C. Supply fan is started without the Unit 3 equipment hatch, emergency hatch, and at least one personnel door closed.

D. Exhaust valves, POV-3-2602 and POV-3-2603, are opened before the Containment Purge Supply valves, POV-3-2600 and POV-3-2601, are opened.

Page 139

TURKEY POINT NRC EXAM - 03/12/09 Q #71

  • A core off-load is in progress on Unit 3.
  • Operators are performing 3-0NOP-033.2, "Refueling Cavity Seal Failure."

Which ONE of the following identifies a hazard and the required actions in accordance with 3-0NOP-033.2 to mitigate this hazard?

A. Airborne contamination levels in Containment will increase.

Start at least one Emergency Containment Filter fan.

B. Radiation levels in Containment will increase.

Place the assembly latched on the manipulator into the upender and leave the fuel assembly latched.

C. Radiation levels in the Spent Fuel Pit will increase.

Move the fuel transfer cart to the containment and close the transfer tube gate valve.

D. Fuel elements in the Spent Fuel Pit Region 1 racks will be uncovered.

Move the fuel transfer cart to the Spent Fuel Pit and close the transfer tube gate valve.

Page 141

TURKEY POINT NRC EXAM - 03/12/09 Q #72 An operator's cumulative documented dose for the year is 0.50 rem.

During a subsequent emergency response, the operator:

  • performed actions that decreased the severity of the event and
  • received an additional total dose (TEDE) of 4.75 rem.

Which ONE of the following identifies how this event affects the operator?

A. The operator did NOT exceed either the yearly limit for occupational workers or the emergency worker exposure limit.

The operator may receive more occupational dose this year.

B. The operator exceeded the yearly limit for occupational workers but did NOT exceed the emergency worker exposure limit.

The operator may NOT receive more occupational dose this year.

c. The operator did NOT exceed the yearly limit for occupational workers but did exceed the emergency worker exposure limit.

The operator may receive more occupational dose this year.

D. The operator exceeded both the yearly limit for occupational workers and the emergency worker exposure limit.

The operator may NOT receive more occupational dose this year.

Page 143

TURKEY POINT NRC EXAM - 03/12/09 Q#73 Operators have completed aligning Unit 3 for hot leg recirculation in accordance with 3-EOP-ES-1.4, "Transfer to Hot Leg Recirculation."

  • Plant conditions are stable.
  • The RO has relieved the STA in monitoring Critical Safety Functions (CSFs).
  • All CSF paths are green except for a yellow path on Inventory.

Based on these conditions, which ONE of the following describes the direction given in 3-EOP-F-0, "Critical Safety Function Status Trees" regarding CSFs monitoring?

The RO:

A. is required to continuously monitor the CSFs.

B. is required to monitor the CSFs every 10 to 20 minutes.

C. may discontinue monitoring the CSFs after one pass through 3-EOP-F-0.

D. is no longer required to monitor the CSFs under these conditions.

Page 145

TURKEY POINT NRC EXAM - 03/12/09 Q#74 Operators are performing 3-EOP-ES-1.3,"Transfer to Cold Leg Recirculation."

  • The Containment Recirculation Sump MOVs are being opened.
  • The Shift Technical Advisor reports a Red Path on Core Cooling.

Which ONE of the following describes the correct operator response and the reason?

A. Transition to 3-EOP-FR-C.1 ,"Response to Inadequate Core Cooling."

The core cooling Red Path FRP has priority and occurred because the actions of 3-EOP-ES-1.3 were not implemented in a timely manner B. Transition to 3-EOP-FR-C.1, "Response to Inadequate Core Cooling."

The core cooling Red Path FRP has priority and will provide corrective actions that will mitigate the inadequate core cooling condition.

C. Continue to implement 3-EOP-ES-1.3.

3-EOP-ES-1.3 actions must be completed through step 34 before implementing any FRPs because 3-EOP-ES-1.3 steps relate to the maintenance of core cooling.

D. Continue to implement 3-EOP-ES-1.3.

3-EOP-ES-1.3 actions must be completed through step 34 before implementing any FRPs, except 3-EOP-FR-S.1, "Response to Nuclear Power Generation/ATWS" because 3-EOP-ES-1.3 steps relate to the maintenance of core cooling.

Page 147

TURKEY POINT NRC EXAM - 03/12/09 Q#75 An Unusual Event has just been declared due to a hurricane approaching Turkey Point.

  • The Communicator has contacted the State Warning Point via the Hot Ring Down (HRD) phone and is ready to relay the information.
  • Miami-Dade County is on the line.
  • The Monroe County contact failed.

Which ONE of the following describes the required action by the Communicator in accordance with O-EPIP-20134, "Off Site Notifications and Protective Action Recommendations" .

The Communicator is required to A. communicate the information to Monroe County during the next hourly update or if the initial classification is going to be escalated or down graded.

B. follow up with the state to ensure that Monroe County has the information or contact Monroe County directly to convey the message.

C. delay the notification to the State Warning Point and Miami-Dade County until Monroe County is present to receive the message.

D. contact the NRCOC to ensure Monroe County is notified.

Page 149

Turkey Point 2009-301 Initial Written Examination Reference List For RO and SRO Written Examinations Steam Tables

Turkey Point 2009-301 Written Examination Key:

RO PORTION OF EXAM 1 A 2 C 3 D 4 B 5 D 6 C 7 A 8 D 9 A 10 B 11 C 12 B 13 A 14 D 15 D 16 D 17 A 18 A 19 D 20 A 21 D 22 D 23 A 24 C 25 D 26 C 27 B 28 DELETED 29 D 30 B 31 A 32 C 33 B 34 C 35 A 36 A 37 C 38 B 39 A 40 B 41 B 42 D 43 A 44 C 45 A 46 B 47 C 48 C 49 D 50 B

51 A 52 A 53 C 54 B 55 B 56 D 57 D 58 C 59 A 60 C 61 C 62 C 63 DELETED 64 A 65 B 66 D 67 D 68 A 69 B 70 C 71 A 72 B 73 B 74 C 75 B

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