Text

Final - RO & SRO Written Examination with Answer Keys (Folder 3)
	ML071760138
Person / Time
Site:	Three Mile Island
Issue date:	04/19/2007
From:	; Division of Reactor Safety I
To:	; AmerGen Energy Co
	Sykes, Marvin D.
Shared Package
ML060800145	List: IR 05000289/2007301; ML071090575; ML071350626; ML071360136; ML071360144; ML071360151; ML071360155; ML071450423; ML071760022; ML071760030; ML071760031; ML071760138; ML071770540; ML071770553;
References
	IR-289/07-301
	Download: ML071760138 (183)
	v • d • e

ES-401 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: Facility/Unit: TMI Unit 1 Region: I Reactor Type: BW 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 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.

Applicants Signature Results Examination Value Points Applicants Score Points Applicants Grade Percent NUREG-1021, Revision 9

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator

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U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator

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U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Answer Key

1. B 26. C 51. C

2. C 27. C 52. A

3. D 28. B 53. B

4. A 29. D 54. D

5. C 30. A 55. A

6. A 31. C 56. D

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23. B 48. A 73. C

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25. B 50. C 75. A Page 3

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 001 Plant conditions:

Reactor Power 100%

Intermediate Closed Cooling Water Pump IC-P-1A OOS for maintenance

MU-P-1A providing makeup and seal injection

Seal injection flow 20 gpm due to RCP Seal Injection Valve MU-V-32 air leak Event:

Inadvertent B Train 30 psig ESAS Containment Isolation actuation occurs Which ONE (1) of the following events will occur?

A. IC-P-1B will trip.

B. All Reactor Coolant Pumps will trip.

C. RCP Seal Injection will be isolated.

D. Reactor Building Spray Pump 1B starts.

Page 4

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 002 Initial plant conditions:

Reactor at 100% power

Control Rod index 292%

A transient occurs yielding the following plant conditions:

Reactor power 100%

Both Thot instruments 599 °F and lowering

Control rod index 300%

Which ONE (1) of the following events would cause the above changes in plant conditions?

A. Tave instrument slowly fails high.

B. A Control Rod Drive Motor Fault has caused a continuous rod withdrawal.

C. Adding a batch to the Makeup Tank that has a higher boron concentration than expected.

D. Placing a Deborating Demineralizer in service with a lower than expected Decontamination Factor (DF).

Page 5

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 003 Which ONE (1) of the following events would prevent Simultaneous DHR and LPI/HPI Operation initiation in accordance with OP-TM-212-921, Simultaneous DHR and LPI/HPI Operation ,following an RCS LOCA?

A. Loss of Instrument Air.

B. Loss of Vital bus B (VBB).

C. All Reactor Coolant Pumps tripped.

D. Manual isolation of DH Removal Heat Exchanger B (DH-C-1B) due to RM-L-3 HI alarm.

Page 6

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 004 Plant conditions:

Reactor Coolant System unisolable LOCA in progress

Decay Heat Pump DH-P-1A flowrate 3150 gpm

Decay Heat Pump DH-P-1B flowrate 3240 gpm

MAP E-2-4 BWST Level LO alarm is illuminated

Reactor Building Flood level is 57 inches

OP-TM-EOP-010, Guide 21, RB Sump Recirc, has been initiated Event:

DH-V-6A, RB Sump To DH-P-1A Suct Hdr Isol Valve, will not open.

BWST Level continues to lower Which ONE (1) of the following is the required action?

A. Place DH-P-1A in Pull-to Lock.

B. Shutdown both Reactor Building Spray Pumps.

C. Initiate OP-TM-212-921, Simultaneous DHR and LPI/HPI Operation.

D. Open Decay Heat Removal Pump Suction cross-connect valve DH-V-12A.

Page 7

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 005 Plant conditions:

Reactor Coolant System fill in progress

The Pressurizer is vented to the Reactor Coolant Drain Tank

All Reactor Coolant Drain Tank manual vent valves are closed

The Reactor Vessel is vented to the Reactor Building via the CRDM vents

Hot Legs are vented to the Reactor Building via high point vents Event:

WDG-V-4, Containment Isolation RB Vent Header, fails closed If the fill evolution were to continue, which ONE of the following describes when Reactor Building Sump Level will begin to rise?

A. After the Pressurizer has filled, when the RC Drain Tank overflows through the relief valve.

B. After the Pressurizer has filled, when the RC Drain Tank rupture disk has failed.

C. Before Pressurizer level reaches 400 inches, when flow begins out the CRDM vents.

D. Before Pressurizer level reaches 400 inches, when flow begins out the Hot Leg vents.

Page 8

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 006 To prevent the formation of condensation in the Control Rod Drive (CRD) stator water jacket .

A. maintain Intermediate Closed Cooler outlet temperature >90°F.

B. backwash the Intermediate Closed coolers if differential pressure is >7 psig.

C. maintain Intermediate Closed Cooling Water filter differential pressure <12 psid.

D. do NOT operate with only one Intermediate Closed cooler in service for >24 hours.

Page 9

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 007 The reactor was manually tripped from 100% power due to lowering pressure caused by the Power Operated Relief Valve (PORV) failing open.

The following conditions exist;

Efforts to close the PORV Block Valve have failed

RCS pressure 1970 psig and lowering

Thot is 555 °F and slowly lowering

Tcold is 545 °F and stable

Pressurizer level indicates 375 inches and rising Which ONE (1) of the following actions is the NEXT to be taken?

A. Initiate, Control Building Ventilation System Radiological Event Operations, in accordance with OP-TM-826-901.

B. Bypass the 1600 PSIG ESAS signal prior to actuation in accordance with OP-TM-642-901, 1600 PSIG ESAS Actuation.

C. Push the 1600 PSIG ESAS Manual PBs to Initiate HPI in accordance with OP-TM-EOP-010, Rule 1, Loss of Subcooling Margin (SCM).

D. Place Normal Makeup Valve MU-V-17 in Hand and maintain Subcooling Margin

>70 °F in accordance with OP-TM-AOP-043, Loss of Pressurizer (Solid Ops Cooldown).

Page 10

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 008 The plant is operating at 100% power when the following is observed:

RC3-PR Hot Leg A Narrow Range Channel 1 fails to 2400 psig

MAP alarm H-3-2, SASS Mismatch is illuminated

Console Center Narrow Range Pressure SASS selector switch for RC3A-PT1 Hot Leg A Narrow Range Channel 1 has the red and white lights illuminated

Console Center Narrow Range Pressure SASS selector switch for RC3B PT1 Hot Leg B Narrow Range Channel has its red light illuminated Which ONE (1) of the following occurs?

A. The Pressurizer Spray Valve opens.

B. The Power Operated Relief Valve opens.

C. The Pressurizer Heaters energize. (Due to actual pressure).

D. No response. (SASS has transferred to an alternate channel).

Page 11

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 009 Plant conditions:

Reactor power at 100%

Reactor Protection System (RPS) Channel C tripped on a NI-7 detector failure and has been placed in Manual Bypass.

Event:

A malfunction within the RPS Channel D Shutdown Bypass bistable causes the channel to go into the Shutdown Bypass mode

MAP alarm G-3-2, RPS Shutdown Bypass is illuminated Which ONE (1) of the following will occur?

A. RPS Channel D trips on low pressure.

B. RPS Channel D trips on high pressure.

C. An automatic reactor trip on low pressure.

D. An automatic reactor trip on high pressure.

Page 12

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 010 Which ONE (1) of the choices correctly fills in the blank in the following statement?

Loss of the __________ will prevent the 1A Diesel Generator from supplying 1D 4160 Volt ES Bus if a Loss of Coolant Accident (LOCA) and coincidental Loss of Offsite Power (LOOP) were to occur.

A. VBA 120 Volt Vital Bus B. 1P 480 Volt Switchgear C. 1C 480 Volt ES Valves MCC D. 1A 250 Volt DC Distribution System Page 13

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 011 Plant conditions:

Reactor tripped due to a LOCA

1600 psig ESAS actuation has occurred

Decay Heat Pump 1A did not start automatically

Loss of offsite power (LOOP) occurred following the ESAS actuation

ESAS signals have NOT been cleared In the above situation..

A. ES selecting and starting Makeup Pump MU-P-1B on the 1E 4160V Bus could cause the bus to overload.

B. starting Decay Heat Removal Pump 1A on the 1D 4160V bus before block loading is complete will cause diesel generator damage.

C. clearing the disagreement lights before resetting the 27/86 Undervoltage Lockout Relays for busses P, S, R and T will prevent overloading the diesel generator.

D. pressing two out of three 1600 psig BYPASS pushbuttons while block loading is in progress is acceptable as long as no equipment positions are changed.

Page 14

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 012 Plant conditions:

Reactor tripped due to a large RCS Leak in containment (LOCA)

All RB Emergency Coolers are in operation, per OP-TM-534-901, RB Emergency Cooling Operations

RB Emergency Cooler A indicates 32 gpm leakage

RB Emergency Cooler pressure indicators RR-PI-224, RR-PI-225, RR-PI-226 read 52 psig

Individual RB Cooler outlet flows read as follows:

A cooler 2345 gpm

B cooler 2420 gpm

C cooler 2120 gpm Which ONE (1) of the following actions is required concerning continued operation of RB Emergency Coolers?

A. Throttle closed Reactor Building Emergency Cooling Coil Discharge Valve RR-V-6 locally.

B. Secure the 1A RB Emergency Cooling Fan and isolate the respective cooler.

C. Dispatch an operator to close RR-V-10A, RR-P-1A Recirculation Valve.

D. Throttle closed on RB Emergency Cooler B outlet valve RR-V-4B.

Page 15

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 013 Which ONE (1) of the following Reactor Protection System Trips is designed to prevent exceeding Minimum DNBR limitations of the core?

A. Nuclear Overpower B. Variable Low Pressure C. High RCS Temperature D. Loss of both Main FW Pumps Page 16

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 014 Plant conditions:

Reactor tripped due to a large RCS leak (LOCA)

ESAS actuations:

4 psig RB Pressure

1600 psig RCS Pressure ES signal failed to actuate.

Current RB pressure is 20 psig

No manual actuations were initiated

The 4 psig ES actuation has been placed in defeat.

No ES component positions have been changed.

Event:

The LOCA becomes larger resulting in RB pressure rising to 35 psig.

Which ONE (1) of the choices completes the following statement?

The Reactor Building Spray (BS) Pumps __________.

A. will start automatically, with normal flow B. will start automatically; however the discharge valves remain closed C. must be manually started using the BS Pump extension control switches D. must be started by pushing the MANUAL ES 30 psig actuation pushbuttons Page 17

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 015 Which ONE (1) of the following Reactor Building Emergency Cooler/Fan speed combinations meets accident analysis assumptions for post-accident Reactor Building emergency cooling if both Reactor Building Spray Pumps are out of service?

A. 2 Coolers with fans in SLOW speed.

B. 2 Coolers with fans in FAST speed.

C. 3 Coolers with fans in SLOW speed.

D. 3 Coolers with fans in FAST speed.

Page 18

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 016 Plant conditions:

Reactor at 100% power

Turbine Bypass Valves MS-V-3A, MS-V-3B and MS-V-3C are closed in HAND for ICS module replacement On a Reactor trip, OTSG ____ steam pressure will be _______than the normal post-trip value.

A. 1A/lower B. 1B/lower C. 1A/higher D. 1B/higher Page 19

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 017 Plant conditions:

Reactor power 100%

Loss of ICS Auto power occurred 10 minutes ago

Plant stability has been verified

Seal Injection Flow is 38 gpm

Makeup flow is normal

OP-TM-AOP-027, Loss of ATA or ICS Auto Power has been initiated Subsequent event:

Feedwater Pump FW-P-1B trips due to low oil pressure Which ONE (1) of the following conditions occurs and what is the required action to stabilize the plant?

A. FW-P-1B Discharge Valve will not receive an automatic close signal and must be closed manually in accordance with OP-TM-MAP-0107, FWP 1B TRIP.

B. Flow through FW-V-17A will be excessive. Demand must be reduced in accordance with OP-TM-421-451, Manual Control of Feed Flow to A OTSG.

C. Turbine control will be lost. A manual reactor trip is required in accordance with OP-TM-AOP-027, Loss of ATA or ICS Auto Power.

D. Feedwater flow will be less. FW-P-1A demand must be raised to maintain the required FW Valve P in accordance with OP-TM-401-472, Manual Control of FW-P-1A.

Page 20

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 018 Initial plant conditions:

Reactor power 100%

Condensate/Booster Pump String C (CO-P-1C and CO-P-2C) OOS for maintenance

All other equipment in a normal lineup Event:

1A Aux Transformer fault with failure of the 1A and 1B 4160 Volt Bus automatic transfers

Feedwater Pump 1A failed to trip and the CRO reduced speed to zero Which ONE (1) of the following identifies the response of the Emergency Feedwater System?

A. Only EF-P-1 and EF-P-2B start automatically. Level must be controlled manually in both OTSGs.

B. Only EF-P-1 and EF-P-2B start automatically. Level will be controlled automatically in both OTSGs.

C. All Emergency Feedwater Pumps start automatically. Level must be controlled manually both OTSGs.

D. All Emergency Feedwater Pumps start automatically. Level will be controlled automatically in both OTSGs.

Page 21

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 019 Plant conditions:

Emergency Feedwater Pump EF-P-1 OOS

OTSG B Tube Rupture occurs while at 100% power

Reactor tripped

Subcooling Margin was lost and OP-TM-EOP-010 Rule 1, Loss of Subcooling Margin (SCM) was initiated

Loss of offsite power (LOOP) with a failure of the EG-Y-1B Emergency Diesel to start

Emergency Feedwater Pump EF-P-2A is feeding both OTSGs as follows:

OTSG A - 312 gpm

OTSG B - 210 gpm In Accordance with OP-TM-EOP-010 Rule 4, FWC Feedwater Control, which ONE of the following actions is required?

A. Stop feeding OTSG B and throttle Emergency Feedwater Control Valve EF-V-30A to feed A OTSG at between 430 gpm and 515 gpm.

B. Stop feeding OTSG B and fully open Emergency Feedwater Control Valve EF-V-30A to feed OTSG A at the maximum available rate.

C. Throttle Emergency Feedwater Control Valves EF-V-30A and EF-V-30B to feed each OTSG at >215 gpm each.

D. Throttle Emergency Feedwater Control Valves EF-V-30A and EF-V-30B such that total emergency feedwater flow to both OTSGs is greater than 430 gpm.

Page 22

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 020 Maintenance requires 1P 480 volt bus to be fed from 1S 480 volt bus.

In accordance with OP-TM-731-550, Cross Tie of ES 480 Volt Bus Feeding 1P From 1S, current to the 1P 480 volt bus is monitored where, and by what means?

A. 4160 V Line to 1P Bus, by calculating.

B. 480 V Line to 1P Bus, by direct reading.

C. 4160 V Line to 1S Bus, by calculating.

D. 480 V Line to 1S Bus, by direct reading.

Page 23

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 021 For the 1A Station Battery to be considered operable.

A. Battery Charger 1E must be operable.

B. equalizing charge current must be < 2 amps.

C. Battery Room ventilation must be in operation while the reactor is critical.

D. terminal voltage must be between 129 and 131 VDC when not on an equalizing charge.

Page 24

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 022 Plant conditions:

Reactor power 100%

Emergency Diesel Generator EG-Y-1A monthly surveillance run is in progress

EG-Y-1A voltage control is in automatic

MVAR reading on the diesel is zero

Indicated 1D 4160 Volt ES Bus voltage is 4150 volts

EG-Y-1A manual voltage setting is at 4165 volts Transfer of EG-Y-1A Voltage Control to MANUAL in this situation will result in A. bus voltage rising.

B. bus voltage lowering.

C. reactive load on the diesel rising.

D. reactive load on the diesel lowering.

Page 25

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 023 Plant conditions:

The unit is at 100% power.

Event:

RM-L-1 HI, Primary Coolant Letdown Monitor, pegs full scale Which ONE (1) of the following identifies the alarm that will actuate and the action required to restore the normal flowpath in the affected system?

A. MAP C-1-1, RADIATION LEVEL HI, will actuate. The RM-L-1 HI FAIL RESET Pushbutton must be depressed to clear the interlock.

B. MAP C-1-1, RADIATION LEVEL HI, will actuate. The RM-L-1 HI Interlock Mode Switch must be placed in DEFEAT to clear the interlock.

C. MAP C-3-1, RAD MON SYSTEM TROUBLE, will actuate. The RM-L-1 HI FAIL RESET Pushbutton must be depressed to clear the interlock.

D. MAP C-3-1, RAD MON SYSTEM TROUBLE, will actuate. The RM-L-1 HI Interlock Mode Switch must be placed in DEFEAT to clear the interlock.

Page 26

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 024 Plant conditions:

A large break LOCA resulted in a reactor trip and ESAS actuation.

RCS and Reactor Building pressure have equalized at 40 psig.

Which ONE (1) of the choices completes the following statement?

The Reactor Coolant Pump seal injection flowpath is __________ and the seal return flowpath is __________.

A. open; open B. open; isolated C. isolated; open D. isolated; isolated Page 27

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 025 Which ONE (1) of the following Secondary Closed Cooling Water (SCCW) System alignments requires permission from the Director of Operations?

A. One SCCW Pump running with two SCCW Coolers in service.

B. Three SCCW Pumps running with four SCCW Coolers in service.

C. Two SCCW Coolers with closed side flow throttled utilizing closed side outlet valves.

D. Two SCCW Coolers in service with one having the river water outlet valve closed and river water inlet valve open.

Page 28

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 026 Which ONE (1) of the following describes the condition when Fire Service Water aligns to cool Instrument Air Compressors?

A. Low SCCW System pressure.

B. High SCCW System temperature.

C. Tripping of all 3 SCCW Pump breakers.

D. High Instrument Air Compressor temperature.

Page 29

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 027 Plant conditions:

100% power Which ONE (1) of the following requires action in accordance with Technical Specifications?

A. Reactor Building pressure is 0.5 psig vacuum.

B. Reactor Building Ventilation Fan AH-E-1C is tripped.

C. Reactor Building Purge Isolation AH-V-1A fails to close when a Reactor Building purge is secured.

D. Reactor Building Emergency Cooling System Cooler 1A has been secured and isolated to stop a cooling water a leak.

Page 30

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 028 Plant conditions:

Reactor tripped due to a loss of offsite power (LOOP)

Emergency Diesel Generator 1B did not start on the LOOP

A subsequent large RCS leak (LOCA) developed in the Reactor Building

Reactor Building pressure peaked at 34 psig

ESAS signals actuated as expected for the plant conditions

NS-V-15 Nuclear Services Supply Valve is verified closed

IC-V-4 to RB components Supply Valve is verified closed

IC-V-6 to CRD cooling Supply Valve is verified closed With respect to Intermediate Closed Cooling and Nuclear Services Closed Cooling, to satisfy containment integrity, ensure _________ are closed?

A. IC-V-2, ICCW From RB, and NS-V-35, RCP Motor Cooler Outlet Isolation.

B. IC-V-3, ICCW From RB, and NS-V-4, NS from RCP motor.

C. IC-V-2, ICCW From RB, and NS-V-4, NS from RCP motor.

D. IC-V-3, ICCW From RB, and NS-V-35, RCP Motor Cooler Outlet Isolation.

Page 31

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 029 Plant conditions:

Reactor Power 100% for 200 days.

Event:

One Control Rod in Group 6 drops to the fully inserted position.

ICS runback operates as expected to reduce power to approximately 455 MWe.

Initial attempts to recover the rod have failed.

To maintain power level at 55 % over the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , in order to compensate for Xenon it will be necessary to A. insert rods.

B. withdraw rods.

C. insert rods and then withdraw rods.

D. withdraw rods and then insert rods.

Page 32

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 030 Which ONE (1) of the choices correctly fills in the blanks of the following statement?

In accordance with OP-TM-220-000, REACTOR COOLANT SYSTEM, with reactor power at 100% and MU-V-17 in HAND, Pressurizer Level must be maintained while operating _______ in order to prevent _______.

A. 200 inches; indication from going off-scale low following a reactor trip B. 80 inches; heaters from de-energizing following a reactor trip C. 385 inches; pressurizer safety valves from passing water if the turbine trips without a reactor trip D. 260 inches; exceeding the Technical Specification pressurizer level limit following a turbine/reactor trip Page 33

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 031 Which one of the following identifies the reactor coolant temperature input to the Subcooling Margin Meter on PCL?

A. Narrow Range Thot.

B. Hottest In-Core Thermocouple.

C. Safety Grade Wide Range Thot.

D. Average of the 5 highest reading In-Core Thermocouples.

Page 34

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 032 Plant conditions:

100% power Event:

Loss of 1A ES MCC

DC input breaker on 1E inverter trips.

Which ONE (1) of the choices completes the following statement?

Power to ICS AUTO is from _________ and ICS HAND is _______.

A. TRA, from TRB B. TRA, Lost C. 1A DC via 1A inverter, from TRB D. 1A DC via 1A inverter, Lost Page 35

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 033 Plant conditions:

Reactor is in cold shutdown on August 10, outside air temperature 85°F.

Reactor Building personnel doors are open

Reactor Building Purge is in progress in accordance with OP-TM-823-408, RB Purge - RB Doors and/or Equipment Hatch Open

Both Purge Supply and both Purge Exhaust Fans are operating

Air flow is continuously out of the RB doors Which ONE (1) of the following procedural actions must be taken?

A. Close AH-V-1C and AH-V-1D Purge Supply Valves.

B. Adjust RB Purge Manual Loader Purge Rate (AH-D-8B-EX1).

C. Secure one of the Purge Exhaust fans (AH-E-7A or AH-E-7B).

D. Throttle open Purge Exhaust Valve (AH-V-1B) to the 90° position.

Page 36

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 034 Plant conditions:

Reactor Coolant System is in Refueling Shutdown condition.

The Fuel Transfer Canal has been filled.

Fuel Transfer Canal isolation Valves FH-V-1A and FH-V-1B are Closed.

Event and subsequent conditions.

Loss of Offsite Power (LOOP)

Spent Fuel Pool Temperature is 180 °F, rising slowly.

Spent Fuel Pool level is 342 and lowering.

Alarm PLB-2-9, Spent Fuel Pool A Level Lo, is illuminated.

Alarm PLB-2-10, Spent Fuel Pool B Level Lo, is illuminated.

Which ONE (1) of the following actions is required in accordance with OP-TM-AOP-035, Loss of Spent Fuel Cooling?

A. Place both trains of Spent Fuel Pool Cooling in service to increase cooling.

B. Open FH-V-1A and FH-V-1B to equalize level and temperature with the refueling cavity.

C. Commence makeup to the Spent Fuel Pool from the BWST to restore boron concentration.

D. Initiate Attachment 1 for makeup to the Spent Fuel Pool from Fire Service Water to restore level.

Page 37

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 035 Plant conditions:

The reactor is critical.

Operators are starting up the main turbine generator in accordance with OP-TM-301-102, MAIN TURBINE GENERATOR STANDBY MODE TO OPERATING MODE.

Which ONE (1) of the choices fills in the blank in the following statement?

In preparation for High Pressure Turbine Shell warming, the operator performs the step SELECT ON and Execute Command for Shell Warming. This step causes _______

to OPEN.

A. all Control Valves B. all Stop Valves C. all Intercept Control Valves D. all Intermediate Stop Valves Page 38

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 036 Plant conditions:

Makeup Tank venting is required to adjust gas concentration.

Which ONE (1) of the following is the required Waste Gas Compressor control alignment for the Makeup Tank venting evolution?

A. One Waste Gas Compressor must be in HAND.

B. Both Waste Gas Compressors must be in HAND.

C. One Waste Gas Compressor must be in AUTOMATIC.

D. Both Waste Gas Compressors must be in AUTOMATIC.

Page 39

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 037 Plant conditions:

Refueling is in progress.

Event:

RM-G-9, Fuel Handling Building (FHB), fails full scale.

Technicians have confirmed that it is an electronic component failure.

Repairs will take two hours.

Fuel movement was halted when the channel failed.

Which ONE (1) of the following describes the status of fuel handling operations with RM-G-9 failed?

A. Fuel handling activities can resume as long as RM-A-4, FHB Exhaust, remains operable.

B. Fuel handling activities can resume after RM-A-14, FHB ESF Ventilation, is verified in service.

C. Spent Fuel Bridge fuel handling and refueling operations are halted until portable instrumentation is substituted for RM-G-9.

D. Irradiated fuel movement into the FHB must remain suspended until RM-G-9 is restored to operability.

Page 40

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 038 Plant conditions:

100% power.

Event:

The Air Intake Tunnel North Tunnel (AIT) Halon unit has actuated.

Which ONE (1) of the following describes plant response?

A. All three deluge systems actuate and ONLY Fire Pumps FS-P-2 and FS-P-3 start on interlock with the actuation.

B. All three deluge systems actuate and ONLY Fire Pump FS-P-1 starts based on header pressure lowering to the setpoint.

C. The associated deluge system actuates and ONLY Fire Pump FS-P-1starts on interlock with the actuation.

D. The associated deluge system actuates and ONLY Fire Pumps FS-P-2 and FS-P-3 start based on header pressure lowering to the setpoint.

Page 41

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 039 The Diverse Scram System (DSS) provides backup protection for an ATWS (Abnormal Transient Without Scram) by ______________ the shunt trip coils on the

______________ 480V breakers.

A. energizing; CRD #10 and #11 B. de-energizing; CRD #10 and #11 C. de-energizing; 1L-2A and 1G-2A (CRD System Feeders)

D. energizing; 1L-2A and 1G-2A (CRD System Feeders)

Page 42

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 040 Plant conditions:

The reactor tripped due to a leak through Pressurizer Code Safety Valve RC-RV-1A.

The CRS initiated EOP-001, Reactor Trip, then EOP-002, Loss of Subcooling Margin (SCM), then EOP-006, LOCA Cooldown.

Incore Thermocouple Temperature is 522 °F.

RCS pressure is 975 psig.

Core cooldown rate is 42 °F/hr.

EOP-010, Rule 1, Loss of Subcooling Margin (SCM), has been completed.

EOP-010, Guide 6, OTSG Pressure Control, has been ordered initiated by the CRS.

Which ONE (1) of the following is the next action to be taken?

A. Reduce OTSG pressure to obtain a 100°F/hr cooldown rate.

B. Maintain OTSG pressure more than 100 psig below RCS Pressure.

C. Reduce OTSG pressure such that secondary Tsat is 40-60 °F lower than Incore Thermocouple Temperature.

D. Maintain OTSG pressure such that secondary Tsat is90-100 °F lower than Incore Thermocouple Temperature.

Page 43

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 041 Plant conditions:

A small break LOCA resulted in a reactor trip and 1600 psig ESAS actuation.

The operating crew is performing EOP-006, LOCA COOLDOWN.

Tave is 450 F.

Which ONE (1) of the following would require immediate operator action?

A. RCS cooldown rate is 40 F/hour with all Reactor Coolant Pumps stopped.

B. Pressurizer level has exceeded 80 inches with HPI in operation.

C. BWST level is 20 feet and lowering slowly.

D. RB pressure has exceeded 4 psig.

Page 44

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 042 Plant conditions:

35% reactor power and rising after a brief maintenance outage.

Reactor Coolant Pump RC-P-1A #1 Seal leakoff has been steadily lowering for the past hour and is now 0.7 gpm.

MAP F-1-3, RCP SEAL #1 LEAKOFF HI/LO, is actuated.

The Reactor Operator reports that RC-P-1A bearing water temperature has started to rise.

Which one (1) of the following is the required action?

A. Immediately trip the reactor; trip RC-P-1A; close MU-V-33A when RC-P-1A stops rotating.

B. Immediately trip RC-P-1A; close MU-V-33A when RC-P-1A stops rotating.

C. Within 5 minutes: Trip the reactor; trip RC-P-1A; place RC-P-1A in the standby mode.

D. Within 5 minutes: Trip RC-P-1A; place RC-P-1A in the standby mode.

Page 45

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 043 Plant conditions:

Reactor power 100%.

MU-P-1B is OOS for maintenance.

Event:

Reactor trip due to Loss of Offsite Power (LOOP).

EG-Y-1A and EG-Y-1B energize their 1D and 1E 4160 Volt ES busses respectively.

1P 480 Volt ES Bus de-energizes due to an electrical fault.

Makeup Tank level is in the restricted operating region of the curve.

Which one (1) of the following Makeup Pump - BWST suction valve combinations can be aligned to provide makeup flow?

A. Start MU-P-1A and open MU-V-14A.

B. Start MU-P-1A and open MU-V-14B.

C. Start MU-P-1C and open MU-V-14A.

D. Start MU-P-1C and open MU-V-14B.

Page 46

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 044 Plant conditions:

Cooldown in progress using the A Decay Heat Removal (DH) Train.

Decay Heat Return Temperature 185 °F.

Cooldown rate 12 °F/hr.

All Reactor Coolant Pumps are secured.

Event:

DH Pump 1A trips.

The B DH Removal train has been started in accordance with OP-TM-212-211, Shifting DHR Train B From DHR Standby To DHR Operating Mode.

Decay Heat Return Temperature rose to 189 °F during the transfer.

Decay Heat Return Temperature lowered from 189 °F to 174 °F when the B train was started.

Which ONE (1) of the following is the allowable action?

A. Hold RCS temperature constant for a minimum of 30 minutes using In-Core Thermocouple temperature indication.

B. Hold RCS temperature constant for a minimum of 30 minutes using Decay Heat Return Temperature Indicator DH-2-TI1.

C. The cooldown can continue to 159 °F within the next 30 minutes using In-Core Thermocouple temperature indication.

D. The cooldown can continue to 159 °F within the next 30 minutes using Decay Heat Return Temperature Indicator DH-2-TI1.

Page 47

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 045 Plant conditions:

The unit was at 100% power when a steam line break caused a reactor trip and ESAS actuation.

Which ONE (1) of the following is the reason for the procedural action to verify the trip and lock out the non-ES selected Nuclear Services River Water Pump?

A. to limit load on the 1R and 1T 480 Volt ES buses due to Decay Heat River Water Pump power requirements.

B. to limit load on the A and B Emergency Diesel Generators during a loss of offsite power (LOOP) with an ESAS signal present.

C. to prevent excessive cooling of the Nuclear Services Closed Cooling Water System during and ESAS condition since heat load is less than during normal operation.

D. to prevent pump damage if only two Nuclear Services Closed Coolers are in service when the ESAS signal is received.

Page 48

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 046 Plant conditions:

Reactor power 100%.

Event:

Both Main Feedwater Pumps trip.

The automatic reactor trip fails.

The automatic turbine trip fails.

Which ONE (1) of the choices completes the following statement describing the response of Tcold and nuclear instrumentation if the reactor continues untripped?

Tcold will ______ and Power Range Nuclear Instrumentation will indicate ________

than actual Core Thermal Power.

A. Lower, Higher B. Lower, Lower C. Rise, Higher D. Rise, Lower Page 49

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 047 Plant conditions:

100% power.

Overhead alarm MAP C-1-1, RADIATION LEVEL HI, just actuated.

The source of the alarm is RM-A-5 CONDENSER VACUUM PUMP EXHAUST.

Which ONE (1) of the choices completes the following statement?

The MAP-5 Sampler starts to sample the.

A. steam lines for iodine when RM-A-5 reaches the ALERT setpoint.

B. steam lines for iodine and tritium when RM-A-5 reaches the ALERT setpoint.

C. condenser offgas for iodine when RM-A-5 reaches the ALARM setpoint.

D. condenser offgas for iodine and tritium when RM-A-5 reaches the ALARM setpoint.

Page 50

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 048 Plant conditions:

Plant has tripped due to a Loss of Offsite Power (LOOP).

No equipment was out of service prior to the trip.

1D & 1E ES 4160V buses are powered by their respective Emergency Diesel Generator.

SCM is 47 °F, decreasing slowly

OTSGs are at 30% on operating range and lowering.

OTSG A/B pressure is 1010 psig and stable.

Incore Temperatures are rising.

Which ONE (1) of the following is the reason for placing the Emergency Feedwater Control Valves (EF-V-30s) in MANUAL?

A. To feed the OTSGs at the maximum available rate because incore temperatures are rising.

B. To allow feed rate to be adjusted to maintain OTSG levels at 25 in the STARTUP Range.

C. To lower feed rate to 215 gpm per OTSG since subcooling requirements are met.

D. To raise OTSG level to 75-85% in the OPERATING Range because no RCP is running.

Page 51

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 049 Plant conditions:

Turbine/Reactor trip from 100% power.

A loss of offsite power (LOOP) occurred.

Both Emergency Diesel Generators tripped while starting.

RCS pressure is 2065 psig.

The Incore thermocouple temperature is 555 °F rising slowly.

A Loop: Thot = 552 °F stable; Tcold = 495 °F lowering slowly.

B Loop: Thot = 552 °F stable; Tcold = 508 °F stable.

Both Atmospheric Dump Valves are closed.

Emergency Feedwater Pump EF-P-1 is running.

OTSG A level is at 35% and rising slowly.

OTSG B level is at 35% and rising slowly.

Both OTSGs 500 psig lowering slowly.

Which ONE (1) of the following correctly describes the status of Natural Circulation Cooling?

A. Natural Circulation flow is verified in both loops.

B. Natural Circulation flow is NOT verified in either loop.

C. Natural Circulation flow is verified in the A Loop ONLY.

D. Natural Circulation flow is verified in the B Loop ONLY.

Page 52

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 050 Plant event:

Reactor trip from 100% power due to a loss of offsite power (LOOP).

Both Emergency Diesel Generators have failed.

The operating crew is performing AOP-020, LOSS OF STATION POWER, Section 4.0 - STATION BLACKOUT.

Steam driven Emergency Feedwater Pump EF-P-1 is running.

The Transmission System Operator reports that it appears off-site power will not be restored for 24-48 hours.

RCS pressure is at 1815 psig.

In accordance with AOP-020, Loss of Station Power ,which ONE of the following identifies the minimum subcooling margin (SCM) and the means of control?

A. ZERO 25 F. Manually cycle the Pressurizer PORV to minimize SCM.

B. 25 F. Operate Pressurizer heaters to raise RCS pressure as temperature rises.

C. 30 F. Adjust MS-V-4A and MS-V-4B, as necessary to control temperature.

D. 70 F. Adjust EFW flow to maintain OTSG level at 75-85% to maximize SCM.

Page 53

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 051 Plant conditions:

Reactor power 100%.

Event:

MAP alarm A-1-6, Inverter Failed, illuminates.

MAP alarm A-1-8, Battery B Discharging, illuminates.

MAP alarm A-3-8, Inverter 1B/1D/1F Trouble, illuminates.

MAP alarm G-2-3, CRD DC BKR Open, illuminates.

4 psig RB Pressure Channel RB3B indicates actuated.

500 psig ESAS Channel RC6B indicates actuated.

1600 psig ESAS Channel RC3B indicates actuated.

30 psig RB Pressure ESAS Channel RB6B indicates actuated.

Reactor Protection Channel D has no lights illuminated.

The above conditions indicate..

A. Loss of B DC Distribution.

B. Loss of Regulated Bus TRB.

C. Loss of 120 Volt Vital Bus D.

D. Loss of 1B 480 Volt ES MCC.

Page 54

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 052 Plant conditions:

Reactor shutdown is in progress due to a cell short on A Battery that caused failure of a lead.

A Battery has been isolated.

The A and C Battery Chargers are supplying the A DC Bus.

The Turbine DC Lube Oil Pump LO-P-6 was subsequently started and caused the A Battery Charger to go into the current limiting condition. The A Battery charger going into current limiting will __________.

A. result in a voltage dip on the DC Bus B. cause the A Battery Charger to trip on overcurrent C. cause A Battery Charger to shift to the equalize mode D. prevent the C Battery Charger from going into the current limiting condition Page 55

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 053 Nuclear Services Closed Cooling Water (NSCCW) Containment Isolation Valves NS-V-4, NS-V-15 and NS-V-35 close on a Line Break Isolation actuation to prevent......

A. dilution of the Reactor Building Sump water due to a NSCCW system leak inside containment.

B. a radioactive release path in the event of a NSCCW break and an RCS break in containment.

C. loss of bearing cooling water to the Reactor Building Cooling Fans AH-E-1A/1B/1C during an emergency event.

D. loss of cooling water flow to essential components outside the RB in the event of a NSCCW leak inside containment.

Page 56

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 054 In EOP-002, LOSS OF 25 °F SUBCOOLED MARGIN, Step 4.1 reads IAAT HPI flow is ADEQUATE, then GO TO Step 3.9.

Which ONE (1) of the following meets the facility criteria for HPI flow is ADEQUATE?

A. Pressurizer level is rising.

B. HPI flow 200 gpm is verified.

C. In-core temperatures have stabilized.

D. All components in HPI Train A are in their ES actuation alignment.

Page 57

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 055 Plant conditions:

Reactor tripped due to steam leak from OTSG 1A in the Reactor Building

1600 psig and 4 psig ESAS actuations occurred and have been bypassed

RCS pressure 1620 psig

RCS Tave 522°F, steady

Pressurizer level 80 inches and rising

RB pressure 4.2 psig

Rule 3 isolation OTSG 1A has been completed

Rule 2, HPI/LPI Throttling is in progress Given the above conditions, which ONE of the following would be the reason for leaving MU-V-14A and MU-V-14B open when performing OP-TM-211-901, Emergency Injection (HPI/LPI), Attachment 7.3, Throttling HPI?

A. To maintain adequate shutdown margin with RCS temperature < 525°F.

B. To maintain minimum Makeup Pump flow requirements until HPI is secured.

C. To maintain adequate suction to the Makeup Pump until Pressurizer level recovers to level setpoint.

D. To raise RCS boron concentration in anticipation of the subsequent cooldown to cold shutdown conditions.

Page 58

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 056 Plant conditions:

Reactor trip from 100% power caused by a turbine trip.

All control rods are inserted.

All immediate actions are complete.

Which ONE (1) of the following requires an immediate transition out of EOP-001, REACTOR TRIP?

A. Loss of ICS AUTO Power.

B. E 4160 volt bus is powered from EG-Y-1B.

C. In-core temperatures 560 °F rising with only Emergency Feedwater Pump EF-P-1 running.

D. RM-A-5, CONDENSER VACUUM PUMP EXHAUST, in ALARM with Pressurizer level lowering at 1 inch per minute.

Page 59

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 057 Plant conditions:

The reactor was manually tripped

One rod in Group 3 failed to insert into the core.

OP-TM-EOP-005, OTSG TUBE LEAKAGE, was entered due to identified tube leakage.

RCS Tave is 528 °F and lowering slowly.

RCS Pressure is 1920 psig and lowering slowly.

Pressurizer level is 100 inches and stable.

Makeup Tank level is 88 inches.

Makeup Tank pressure is 25 psig.

Makeup flow is 8 gpm.

Seal Injection flow is 32 gpm.

Letdown flow is 45 gpm.

MU-V-14A is open.

Which ONE (1) of the following actions is required?

A. Adjust RCP seal injection flow to establish 42 gpm.

B. Initiate RCS bleed to RC Bleed Tank to lower makeup tank level.

C. Open MU-V-14B to ensure adequate NPSH to the Makeup Pump.

D. Raise letdown flow to 60 gpm to increase Emergency Boration Flow.

Page 60

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 058 Plant conditions:

A plant startup is in progress in accordance with 1102-2, Plant Startup.

Reactor power is 40%, on a hold.

Tave is 579 °F.

Turbine load is 342 MWe.

Event:

MAP Alarm N-1-6, MN COND VACUUM LO actuates.

Condenser vacuum is degrading slowly.

Assuming NO operator action, which ONE (1) of the following describes the current position of the control rods as compared to pre-degrading vacuum position?

A. LOWER due to a reduction in turbine efficiency.

B. LOWER due to crosslimits.

C. HIGHER due to a reduction in turbine efficiency.

D. HIGHER due to crosslimits.

Page 61

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 059 Plant conditions:

100% power

RC-2 MS Pressurizer Temperature Switch is selected to the TE-1 position.

RC-1 MS Pressurizer Level Selector Switch is selected to the RC-1 LT-1 position.

Which ONE (1) of the following sets of Pressurizer Level indications would require shifting RC-2 MS to the TE-2 position?

A. RC-1 LT-1 reads 220; RC-1 LT-3 reads 220; RC-LT-777A reads 150.

B. RC-1 LT-1 reads 220; RC-1 LT-3 reads 150; RC-LT-777A reads 150.

C. RC-1 LT-1 reads 150; RC-1 LT-3 reads 220; RC-LT-777A reads 220.

D. RC-1 LT-1 reads 150; RC-1 LT-3 reads 150; RC-LT-777A reads 220.

Page 62

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 060 Plant conditions:

The Control Room has just been evacuated due to a fire.

OP-TM-EOP-020, Cooldown From Outside the Control Room, Immediate Manual Actions were completed prior to leaving the Control Room.

All Remote Transfer switches have been operated.

Event:

A Loss of offsite power (LOOP) occurs.

With the above conditions.

A. A and B Emergency Diesels will start automatically and re-energize their respective bus.

B. A and B Emergency Diesels will start automatically but their respective breakers must be closed locally.

C. A Emergency Diesel must be started manually from the 1D 4160 Volt Bus and its breaker closed locally.

D. B Emergency Diesel will have to be started manually from the 1E 4160 Volt Bus and its breaker closed locally.

Page 63

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 061 Plant conditions:

Reactor power was 100% when a dropped rod in Group 3 occurred a few minutes ago.

Reactor power is currently 62% and stable.

Turbine load 532 MWe and stable.

MAP Alarm H-1-1, ICS RUNBACK, is illuminated.

MAP Alarm H-2-1, ICS IN TRACK, is illuminated.

MAP Alarm H-3-4, ULD HIGH LOAD LIMIT, is illuminated.

Given the above conditions the operator will have to.

A. reduce the ULD output until NI power is <55%.

B. reduce the ULD output until NI power is <60%.

C. take Hand control of the SG/RX Master and reduce NI power to <55%.

D. take Hand control of the Diamond and Feedwater stations to reduce power to

<60%.

Page 64

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 062 Which ONE (1) of the choices completes the following statement regarding operator action on Loss of ICS Hand Power?

The reactor must be tripped if reactor power is _______________.

A. < 75% and FW-V-17A is in HAND because a feedwater transient will occur.

B. < 75% and both FW-16A and FW-V-16B are in HAND because an RCS overcooling will occur.

C. > 75% and A Feedwater Pump is in HAND because an RCS heatup will occur.

D. > 75% and Turbine Bypass Valves are in HAND because reactor power will exceed 100% power.

Page 65

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 063 Plant conditions:

The plant is starting up.

Reactor power is 42%.

Tave is 579 °F.

Turbine load is 360 MWe.

Event:

Turbine trip, on stator coolant loss.

Which ONE (1) of the following is the required operator action?

A. Verify an automatic reactor trip on interlock with the turbine trip.

B. Ensure reactor power is reduced to within Turbine Bypass Valve capability.

C. Verify an ICS stator coolant runback is in progress to reduce power.

D. Initiate a MANUAL reactor trip if any Main Steam Safety Valves opens.

Page 66

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 064 Plant conditions:

Reactor was tripped due to a large RCS leak (LOCA).

EOP-001, Reactor Trip, was initiated.

Subcooling margin is 12 °F.

OP-TM-EOP-010 Rule 1, Loss of Subcooling Margin (SCM), has been initiated.

RC-P-1D was not tripped within one minute and is currently running.

Which ONE (1) of the following verified conditions allows RC-P-1D to be stopped?

A. Tclad > 1800 °F.

B. Adequate HPI flow.

C. A LPI Flow 1400 gpm, B LPI Flow 900 gpm.

D. Both OTSG levels are between 75 to 85% Operating Range Level.

Page 67

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 065 Plant conditions:

Reactor Tripped due to loss of offsite power (LOOP).

Both Emergency diesels started and are supplying their respective busses.

All three Emergency Feedwater Pumps have started.

Natural Circulation flow has been verified.

T cold is 520°F Which ONE (1) of the following describes the method of cooldown, the cooldown rate limit, and the reason for that limit?

A. Operate the Atmospheric Dump Valves to control cooldown rate 30 °F/hr to prevent voiding in the hot legs.

B. Operate the Atmospheric Dump Valves to control cooldown rate 50 °F/hr to prevent formation of a head bubble.

C. Operate the Turbine Bypass Valves to control cooldown rate 30 °F/hr to prevent voiding in the hot legs.

D. Operate the Turbine Bypass Valves to control cooldown rate 50 °F/hr to prevent formation of a head bubble.

Page 68

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 066 Which ONE (1) of the following is an acceptable communication during an emergency condition?

A. Announcing to control room personnel RM-A-5 and RM-A-15 are in alarm during the performance of reactor trip immediate manual actions.

B. Announcing on the plant page Fire in the Auxiliary Building, Elevation 305.

C. During an update the CRS announces Attention for a brief.

D. Giving an update to the crew control rods are at 290% and inserting and reactor power is at 101% and rising.

Page 69

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 067 A licensed reactor operator is returning to shift after being on vacation. His last watch before vacation was 0700-1900 on April 17, 2007. He is scheduled to be the Assistant Reactor Operator (ARO) for the 0700-1900 watch on April 26, 2007.

Which one (1) of the choices correctly fills in the blank in the following statement?

The reactor operator must review the Control Room Logs starting with __________ up to 0700, April 26, 2007, prior to assuming the scheduled ARO watch.

A. 0700, on April 25, 2007.

B. 1900, on April 25, 2007.

C. 0700, on April 22, 2007.

D. 1900, on April 17, 2007.

Page 70

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 068 Plant conditions:

The reactor tripped 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ago.

Core Burnup is 300 EFPD

An Estimated Critical Position calculation was completed with:

RC Tave = 532 °F

RC Pressure = 2155 psig Current conditions:

RC Tave = 531 °F

RC Pressure = 2120 psig Which ONE (1) of the choices completes the following statement?

During the startup, criticality as predicted by the 1/M Plot will be ______. Criticality will occur at a rod position ______than the ECP critical rod position.

A. accurate; lower B. accurate; higher C. inaccurate; lower D. inaccurate; higher Page 71

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 069 Which ONE (1) of the following describes a VIOLATION of refueling administrative requirements?

A. Fuel moves in Spent Fuel Pool are being supervised by an individual with an inactive SRO license.

B. An irradiated fuel assembly has been transferred to the Spent Fuel Pool with both trains of ESF Ventilation secured.

C. The fuel grapple FULL DOWN position has been determined by ZZ tape reading rather than by the Digital Fuel Elevation reading.

D. The Main Fuel Bridge has been left unattended with the fuel grapple at GRAPPLE UP DISENGAGED and the bridge de-energized.

Page 72

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 070 Conditions:

Work will be performed in an area that has a general radiation dose of 90 mRem/hr.

One worker can perform the job in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 15 minutes.

Two workers can perform the job in 45 minutes.

RadPro estimates that it will take two technicians 20 minutes each to install temporary shielding that will reduce the dose rate to 30 mRem/hr.

An engineering evaluation has been completed to allow shielding to remain if installed.

Which one (1) of the following methods of performing the job meets the facility criteria for RP-AA-400, ALARA PROGRAM?

A. One worker with temporary shielding.

B. One worker WITHOUT temporary shielding.

C. Two workers with temporary shielding.

D. Two workers WITHOUT temporary shielding.

Page 73

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 071 Plant conditions:

100% power.

RM-L-1, RC LETDOWN MONITOR, rapidly progressed to an ALERT alarm status and has now actuated on HI alarm.

Which ONE (1) of the following is the required action?

A. Place Control Tower on pressurized recirculation.

B. Ensure RC Sample Valves CA-V-1, 2, 3 or 13 closed on interlock.

C. Monitor RM-G-26 and 27, MAIN STEAM LINE Monitors, for rising counts.

D. Announce on Page: High Activity has been detected in letdown. All unnecessary personnel in the controlled area report to H.P. Checkpoint.

Page 74

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 072 Plant conditions:

A release is in progress from Waste Gas Decay Tank WDG-T-1A.

WDG-T-1B is in service.

The NLO on rounds reports that indicated pressure in WDG-T-1C has lowered 5 PSIG since the last set of readings.

Which ONE (1) of the following is the required action?

A. Close WDG-47, Waste Gas Release Control Valve.

B. Verify WDG-V-32, WDG-T-1C Outlet Isolation Valve, is locked closed.

C. Verify RM-A-7, WDG-T Discharge Monitor, has remained below the isolation setpoint.

D. Perform a valve lineup on WDG-T-1C to verify that it is NOT aligned to the vent header.

Page 75

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 073 When guidance from Rules, Guides or procedures conflict, the order of preference to be applied is.

A. EOP Rules, EOP steps, Other Procedures, EOP Guides.

B. EOP steps, EOP Rules, EOP Guides, Other Procedures.

C. EOP Rules, EOP steps, EOP Guides, Other Procedures.

D. EOP steps, EOP Rules, Other Procedures, EOP Guides.

Page 76

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 074 Plant conditions:

An OTSG tube rupture has resulted in a reactor trip and ESAS actuation.

The Shift Emergency Director initially classified the event as an ALERT 1115 hours0.0129 days 0.31 hours 0.00184 weeks 4.242575e-4 months .

Local notifications of the ALERT have been made.

The Shift Emergency Director upgraded the classification to SITE AREA EMERGENCY at 1148.

Which ONE (1) of the following identifies the latest time that the upgrade notification to required local agencies can be made and what action stops the clock?

A. 1203; after completion of the initial roll call.

B. 1203; after all required contacts have acknowledged the message.

C. 1248; after completion of the initial roll call.

D. 1248; after all required contacts have acknowledged the message.

Page 77

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Reactor Operator Question 075 Plant conditions:

An automatic reactor trip has actuated.

The operating crew is performing EOP-001, REACTOR TRIP.

Which ONE (1) of the following is permitted to be performed by a licensed reactor operator without concurrence from the Control Room Supervisor?

A. Reset the Pressurizer level control setpoint to the post-trip value.

B. Tripping MFW Pumps if OTSG A or B Operating Range level is > 97.5%.

C. An If at any time (IAAT) action after the step has been read and the condition is met.

D. Any alarm response procedure action step after the step ENSURE performance of an Alarm Review has been read.

Page 78

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date: Facility/Unit: TMI Unit 1 Region: I Reactor Type: BW 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 a 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.

Applicants Signature Results RO/SRO-Only/Total Examination Values / / Points Applicants Score / / Points Applicants Grade / / Percent Page 1

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator

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U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator

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U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator

1. B 26. C 51. C 76. D

2. C 27. C 52. A 77. D

3. D 28. B 53. B 78. A

4. A 29. D 54. D 79. B

5. C 30. A 55. A 80. C

6. A 31. C 56. D 81. D

7. D 32. C 57. D 82. B

8. A 33. B 58. C 83. B

9. B 34. D 59. D 84. B

10. D 35. A 60. D 85. C

11. C 36. A 61. C 86. C

12. A 37. C 62. A 87. A

13. B 38. A 63. B 88. Deleted

14. C 39. D 64. A 89. D

15. C 40. B 65. B 90. A

16. D 41. D 66. D 91. C

17. D 42. D 67. C 92. A

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21. D 46. C 71. D 96. D

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25. B 50. C 75. A 100. B Page 4

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 001 Plant conditions:

Reactor Power 100%

Intermediate Closed Cooling Water Pump IC-P-1A OOS for maintenance

MU-P-1A providing makeup and seal injection

Seal injection flow 20 gpm due to RCP Seal Injection Valve MU-V-32 air leak Event:

Inadvertent B Train 30 psig ESAS Containment Isolation actuation occurs Which ONE (1) of the following events will occur?

A. IC-P-1B will trip.

B. All Reactor Coolant Pumps will trip.

C. RCP Seal Injection will be isolated.

D. Reactor Building Spray Pump 1B starts.

Page 5

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 002 Initial plant conditions:

Reactor at 100% power

Control Rod index 292%

A transient occurs yielding the following plant conditions:

Reactor power 100%

Both Thot instruments 599 °F and lowering

Control rod index 300%

Which ONE (1) of the following events would cause the above changes in plant conditions?

A. Tave instrument slowly fails high.

B. A Control Rod Drive Motor Fault has caused a continuous rod withdrawal.

C. Adding a batch to the Makeup Tank that has a higher boron concentration than expected.

D. Placing a Deborating Demineralizer in service with a lower than expected Decontamination Factor (DF).

Page 6

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 003 Which ONE (1) of the following events would prevent Simultaneous DHR and LPI/HPI Operation initiation in accordance with OP-TM-212-921, Simultaneous DHR and LPI/HPI Operation ,following an RCS LOCA?

A. Loss of Instrument Air.

B. Loss of Vital bus B (VBB).

C. All Reactor Coolant Pumps tripped.

D. Manual isolation of DH Removal Heat Exchanger B (DH-C-1B) due to RM-L-3 HI alarm.

Page 7

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 004 Plant conditions:

Reactor Coolant System unisolable LOCA in progress

Decay Heat Pump DH-P-1A flowrate 3150 gpm

Decay Heat Pump DH-P-1B flowrate 3240 gpm

MAP E-2-4 BWST Level LO alarm is illuminated

Reactor Building Flood level is 57 inches

OP-TM-EOP-010, Guide 21, RB Sump Recirc, has been initiated Event:

DH-V-6A, RB Sump To DH-P-1A Suct Hdr Isol Valve, will not open.

BWST Level continues to lower Which ONE (1) of the following is the required action?

A. Place DH-P-1A in Pull-to Lock.

B. Shutdown both Reactor Building Spray Pumps.

C. Initiate OP-TM-212-921, Simultaneous DHR and LPI/HPI Operation.

D. Open Decay Heat Removal Pump Suction cross-connect valve DH-V-12A.

Page 8

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 005 Plant conditions:

Reactor Coolant System fill in progress

The Pressurizer is vented to the Reactor Coolant Drain Tank

All Reactor Coolant Drain Tank manual vent valves are closed

The Reactor Vessel is vented to the Reactor Building via the CRDM vents

Hot Legs are vented to the Reactor Building via high point vents Event:

WDG-V-4, Containment Isolation RB Vent Header, fails closed If the fill evolution were to continue, which ONE of the following describes when Reactor Building Sump Level will begin to rise?

A. After the Pressurizer has filled, when the RC Drain Tank overflows through the relief valve.

B. After the Pressurizer has filled, when the RC Drain Tank rupture disk has failed.

C. Before Pressurizer level reaches 400 inches, when flow begins out the CRDM vents.

D. Before Pressurizer level reaches 400 inches, when flow begins out the Hot Leg vents.

Page 9

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 006 To prevent the formation of condensation in the Control Rod Drive (CRD) stator water jacket .

A. maintain Intermediate Closed Cooler outlet temperature >90°F.

B. backwash the Intermediate Closed coolers if differential pressure is >7 psig.

C. maintain Intermediate Closed Cooling Water filter differential pressure <12 psid.

D. do NOT operate with only one Intermediate Closed cooler in service for >24 hours.

Page 10

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 007 The reactor was manually tripped from 100% power due to lowering pressure caused by the Power Operated Relief Valve (PORV) failing open.

The following conditions exist;

Efforts to close the PORV Block Valve have failed

RCS pressure 1970 psig and lowering

Thot is 555 °F and slowly lowering

Tcold is 545 °F and stable

Pressurizer level indicates 375 inches and rising Which ONE (1) of the following actions is the NEXT to be taken?

A. Initiate, Control Building Ventilation System Radiological Event Operations, in accordance with OP-TM-826-901.

B. Bypass the 1600 PSIG ESAS signal prior to actuation in accordance with OP-TM-642-901, 1600 PSIG ESAS Actuation.

C. Push the 1600 PSIG ESAS Manual PBs to Initiate HPI in accordance with OP-TM-EOP-010, Rule 1, Loss of Subcooling Margin (SCM).

D. Place Normal Makeup Valve MU-V-17 in Hand and maintain Subcooling Margin

>70 °F in accordance with OP-TM-AOP-043, Loss of Pressurizer (Solid Ops Cooldown).

Page 11

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 008 The plant is operating at 100% power when the following is observed:

RC3-PR Hot Leg A Narrow Range Channel 1 fails to 2400 psig

MAP alarm H-3-2, SASS Mismatch is illuminated

Console Center Narrow Range Pressure SASS selector switch for RC3A-PT1 Hot Leg A Narrow Range Channel 1 has the red and white lights illuminated

Console Center Narrow Range Pressure SASS selector switch for RC3B PT1 Hot Leg B Narrow Range Channel has its red light illuminated Which ONE (1) of the following occurs?

A. The Pressurizer Spray Valve opens.

B. The Power Operated Relief Valve opens.

C. The Pressurizer Heaters energize. (Due to actual pressure).

D. No response. (SASS has transferred to an alternate channel).

Page 12

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 009 Plant conditions:

Reactor power at 100%

Reactor Protection System (RPS) Channel C tripped on a NI-7 detector failure and has been placed in Manual Bypass.

Event:

A malfunction within the RPS Channel D Shutdown Bypass bistable causes the channel to go into the Shutdown Bypass mode

MAP alarm G-3-2, RPS Shutdown Bypass is illuminated Which ONE (1) of the following will occur?

A. RPS Channel D trips on low pressure.

B. RPS Channel D trips on high pressure.

C. An automatic reactor trip on low pressure.

D. An automatic reactor trip on high pressure.

Page 13

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 010 Which ONE (1) of the choices correctly fills in the blank in the following statement?

Loss of the __________ will prevent the 1A Diesel Generator from supplying 1D 4160 Volt ES Bus if a Loss of Coolant Accident (LOCA) and coincidental Loss of Offsite Power (LOOP) were to occur.

A. VBA 120 Volt Vital Bus B. 1P 480 Volt Switchgear C. 1C 480 Volt ES Valves MCC D. 1A 250 Volt DC Distribution System Page 14

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 011 Plant conditions:

Reactor tripped due to a LOCA

1600 psig ESAS actuation has occurred

Decay Heat Pump 1A did not start automatically

Loss of offsite power (LOOP) occurred following the ESAS actuation

ESAS signals have NOT been cleared In the above situation..

A. ES selecting and starting Makeup Pump MU-P-1B on the 1E 4160V Bus could cause the bus to overload.

B. starting Decay Heat Removal Pump 1A on the 1D 4160V bus before block loading is complete will cause diesel generator damage.

C. clearing the disagreement lights before resetting the 27/86 Undervoltage Lockout Relays for busses P, S, R and T will prevent overloading the diesel generator.

D. pressing two out of three 1600 psig BYPASS pushbuttons while block loading is in progress is acceptable as long as no equipment positions are changed.

Page 15

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 012 Plant conditions:

Reactor tripped due to a large RCS Leak in containment (LOCA)

All RB Emergency Coolers are in operation, per OP-TM-534-901, RB Emergency Cooling Operations

RB Emergency Cooler A indicates 32 gpm leakage

RB Emergency Cooler pressure indicators RR-PI-224, RR-PI-225, RR-PI-226 read 52 psig

Individual RB Cooler outlet flows read as follows:

A cooler 2345 gpm

B cooler 2420 gpm

C cooler 2120 gpm Which ONE (1) of the following actions is required concerning continued operation of RB Emergency Coolers?

A. Throttle closed Reactor Building Emergency Cooling Coil Discharge Valve RR-V-6 locally.

B. Secure the 1A RB Emergency Cooling Fan and isolate the respective cooler.

C. Dispatch an operator to close RR-V-10A, RR-P-1A Recirculation Valve.

D. Throttle closed on RB Emergency Cooler B outlet valve RR-V-4B.

Page 16

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 013 Which ONE (1) of the following Reactor Protection System Trips is designed to prevent exceeding Minimum DNBR limitations of the core?

A. Nuclear Overpower B. Variable Low Pressure C. High RCS Temperature D. Loss of both Main FW Pumps Page 17

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 014 Plant conditions:

Reactor tripped due to a large RCS leak (LOCA)

ESAS actuations:

4 psig RB Pressure

1600 psig RCS Pressure ES signal failed to actuate.

Current RB pressure is 20 psig

No manual actuations were initiated

The 4 psig ES actuation has been placed in defeat.

No ES component positions have been changed.

Event:

The LOCA becomes larger resulting in RB pressure rising to 35 psig.

Which ONE (1) of the choices completes the following statement?

The Reactor Building Spray (BS) Pumps __________.

A. will start automatically, with normal flow B. will start automatically; however the discharge valves remain closed C. must be manually started using the BS Pump extension control switches D. must be started by pushing the MANUAL ES 30 psig actuation pushbuttons Page 18

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 015 Which ONE (1) of the following Reactor Building Emergency Cooler/Fan speed combinations meets accident analysis assumptions for post-accident Reactor Building emergency cooling if both Reactor Building Spray Pumps are out of service?

A. 2 Coolers with fans in SLOW speed.

B. 2 Coolers with fans in FAST speed.

C. 3 Coolers with fans in SLOW speed.

D. 3 Coolers with fans in FAST speed.

Page 19

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 016 Plant conditions:

Reactor at 100% power

Turbine Bypass Valves MS-V-3A, MS-V-3B and MS-V-3C are closed in HAND for ICS module replacement On a Reactor trip, OTSG ____ steam pressure will be _______than the normal post-trip value.

A. 1A/lower B. 1B/lower C. 1A/higher D. 1B/higher Page 20

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 017 Plant conditions:

Reactor power 100%

Loss of ICS Auto power occurred 10 minutes ago

Plant stability has been verified

Seal Injection Flow is 38 gpm

Makeup flow is normal

OP-TM-AOP-027, Loss of ATA or ICS Auto Power has been initiated Subsequent event:

Feedwater Pump FW-P-1B trips due to low oil pressure Which ONE (1) of the following conditions occurs and what is the required action to stabilize the plant?

A. FW-P-1B Discharge Valve will not receive an automatic close signal and must be closed manually in accordance with OP-TM-MAP-0107, FWP 1B TRIP.

B. Flow through FW-V-17A will be excessive. Demand must be reduced in accordance with OP-TM-421-451, Manual Control of Feed Flow to A OTSG.

C. Turbine control will be lost. A manual reactor trip is required in accordance with OP-TM-AOP-027, Loss of ATA or ICS Auto Power.

D. Feedwater flow will be less. FW-P-1A demand must be raised to maintain the required FW Valve P in accordance with OP-TM-401-472, Manual Control of FW-P-1A.

Page 21

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 018 Initial plant conditions:

Reactor power 100%

Condensate/Booster Pump String C (CO-P-1C and CO-P-2C) OOS for maintenance

All other equipment in a normal lineup Event:

1A Aux Transformer fault with failure of the 1A and 1B 4160 Volt Bus automatic transfers

Feedwater Pump 1A failed to trip and the CRO reduced speed to zero Which ONE (1) of the following identifies the response of the Emergency Feedwater System?

A. Only EF-P-1 and EF-P-2B start automatically. Level must be controlled manually in both OTSGs.

B. Only EF-P-1 and EF-P-2B start automatically. Level will be controlled automatically in both OTSGs.

C. All Emergency Feedwater Pumps start automatically. Level must be controlled manually both OTSGs.

D. All Emergency Feedwater Pumps start automatically. Level will be controlled automatically in both OTSGs.

Page 22

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 019 Plant conditions:

Emergency Feedwater Pump EF-P-1 OOS

OTSG B Tube Rupture occurs while at 100% power

Reactor tripped

Subcooling Margin was lost and OP-TM-EOP-010 Rule 1, Loss of Subcooling Margin (SCM) was initiated

Loss of offsite power (LOOP) with a failure of the EG-Y-1B Emergency Diesel to start

Emergency Feedwater Pump EF-P-2A is feeding both OTSGs as follows:

OTSG A - 312 gpm

OTSG B - 210 gpm In Accordance with OP-TM-EOP-010 Rule 4, FWC Feedwater Control, which ONE of the following actions is required?

A. Stop feeding OTSG B and throttle Emergency Feedwater Control Valve EF-V-30A to feed A OTSG at between 430 gpm and 515 gpm.

B. Stop feeding OTSG B and fully open Emergency Feedwater Control Valve EF-V-30A to feed OTSG A at the maximum available rate.

C. Throttle Emergency Feedwater Control Valves EF-V-30A and EF-V-30B to feed each OTSG at >215 gpm each.

D. Throttle Emergency Feedwater Control Valves EF-V-30A and EF-V-30B such that total emergency feedwater flow to both OTSGs is greater than 430 gpm.

Page 23

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 020 Maintenance requires 1P 480 volt bus to be fed from 1S 480 volt bus.

In accordance with OP-TM-731-550, Cross Tie of ES 480 Volt Bus Feeding 1P From 1S, current to the 1P 480 volt bus is monitored where, and by what means?

A. 4160 V Line to 1P Bus, by calculating.

B. 480 V Line to 1P Bus, by direct reading.

C. 4160 V Line to 1S Bus, by calculating.

D. 480 V Line to 1S Bus, by direct reading.

Page 24

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 021 For the 1A Station Battery to be considered operable.

A. Battery Charger 1E must be operable.

B. equalizing charge current must be < 2 amps.

C. Battery Room ventilation must be in operation while the reactor is critical.

D. terminal voltage must be between 129 and 131 VDC when not on an equalizing charge.

Page 25

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 022 Plant conditions:

Reactor power 100%

Emergency Diesel Generator EG-Y-1A monthly surveillance run is in progress

EG-Y-1A voltage control is in automatic

MVAR reading on the diesel is zero

Indicated 1D 4160 Volt ES Bus voltage is 4150 volts

EG-Y-1A manual voltage setting is at 4165 volts Transfer of EG-Y-1A Voltage Control to MANUAL in this situation will result in A. bus voltage rising.

B. bus voltage lowering.

C. reactive load on the diesel rising.

D. reactive load on the diesel lowering.

Page 26

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 023 Plant conditions:

The unit is at 100% power.

Event:

RM-L-1 HI, Primary Coolant Letdown Monitor, pegs full scale Which ONE (1) of the following identifies the alarm that will actuate and the action required to restore the normal flowpath in the affected system?

A. MAP C-1-1, RADIATION LEVEL HI, will actuate. The RM-L-1 HI FAIL RESET Pushbutton must be depressed to clear the interlock.

B. MAP C-1-1, RADIATION LEVEL HI, will actuate. The RM-L-1 HI Interlock Mode Switch must be placed in DEFEAT to clear the interlock.

C. MAP C-3-1, RAD MON SYSTEM TROUBLE, will actuate. The RM-L-1 HI FAIL RESET Pushbutton must be depressed to clear the interlock.

D. MAP C-3-1, RAD MON SYSTEM TROUBLE, will actuate. The RM-L-1 HI Interlock Mode Switch must be placed in DEFEAT to clear the interlock.

Page 27

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 024 Plant conditions:

A large break LOCA resulted in a reactor trip and ESAS actuation.

RCS and Reactor Building pressure have equalized at 40 psig.

Which ONE (1) of the choices completes the following statement?

The Reactor Coolant Pump seal injection flowpath is __________ and the seal return flowpath is __________.

A. open; open B. open; isolated C. isolated; open D. isolated; isolated Page 28

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 025 Which ONE (1) of the following Secondary Closed Cooling Water (SCCW) System alignments requires permission from the Director of Operations?

A. One SCCW Pump running with two SCCW Coolers in service.

B. Three SCCW Pumps running with four SCCW Coolers in service.

C. Two SCCW Coolers with closed side flow throttled utilizing closed side outlet valves.

D. Two SCCW Coolers in service with one having the river water outlet valve closed and river water inlet valve open.

Page 29

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 026 Which ONE (1) of the following describes the condition when Fire Service Water aligns to cool Instrument Air Compressors?

A. Low SCCW System pressure.

B. High SCCW System temperature.

C. Tripping of all 3 SCCW Pump breakers.

D. High Instrument Air Compressor temperature.

Page 30

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 027 Plant conditions:

100% power Which ONE (1) of the following requires action in accordance with Technical Specifications?

A. Reactor Building pressure is 0.5 psig vacuum.

B. Reactor Building Ventilation Fan AH-E-1C is tripped.

C. Reactor Building Purge Isolation AH-V-1A fails to close when a Reactor Building purge is secured.

D. Reactor Building Emergency Cooling System Cooler 1A has been secured and isolated to stop a cooling water a leak.

Page 31

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 028 Plant conditions:

Reactor tripped due to a loss of offsite power (LOOP)

Emergency Diesel Generator 1B did not start on the LOOP

A subsequent large RCS leak (LOCA) developed in the Reactor Building

Reactor Building pressure peaked at 34 psig

ESAS signals actuated as expected for the plant conditions

NS-V-15 Nuclear Services Supply Valve is verified closed

IC-V-4 to RB components Supply Valve is verified closed

IC-V-6 to CRD cooling Supply Valve is verified closed With respect to Intermediate Closed Cooling and Nuclear Services Closed Cooling, to satisfy containment integrity, ensure _________ are closed?

A. IC-V-2, ICCW From RB, and NS-V-35, RCP Motor Cooler Outlet Isolation.

B. IC-V-3, ICCW From RB, and NS-V-4, NS from RCP motor.

C. IC-V-2, ICCW From RB, and NS-V-4, NS from RCP motor.

D. IC-V-3, ICCW From RB, and NS-V-35, RCP Motor Cooler Outlet Isolation.

Page 32

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 029 Plant conditions:

Reactor Power 100% for 200 days.

Event:

One Control Rod in Group 6 drops to the fully inserted position.

ICS runback operates as expected to reduce power to approximately 455 MWe.

Initial attempts to recover the rod have failed.

To maintain power level at 55 % over the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , in order to compensate for Xenon it will be necessary to A. insert rods.

B. withdraw rods.

C. insert rods and then withdraw rods.

D. withdraw rods and then insert rods.

Page 33

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 030 Which ONE (1) of the choices correctly fills in the blanks of the following statement?

In accordance with OP-TM-220-000, REACTOR COOLANT SYSTEM, with reactor power at 100% and MU-V-17 in HAND, Pressurizer Level must be maintained while operating _______ in order to prevent _______.

A. 200 inches; indication from going off-scale low following a reactor trip B. 80 inches; heaters from de-energizing following a reactor trip C. 385 inches; pressurizer safety valves from passing water if the turbine trips without a reactor trip D. 260 inches; exceeding the Technical Specification pressurizer level limit following a turbine/reactor trip Page 34

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 031 Which one of the following identifies the reactor coolant temperature input to the Subcooling Margin Meter on PCL?

A. Narrow Range Thot.

B. Hottest In-Core Thermocouple.

C. Safety Grade Wide Range Thot.

D. Average of the 5 highest reading In-Core Thermocouples.

Page 35

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 032 Plant conditions:

100% power Event:

Loss of 1A ES MCC

DC input breaker on 1E inverter trips.

Which ONE (1) of the choices completes the following statement?

Power to ICS AUTO is from _________ and ICS HAND is _______.

A. TRA, from TRB B. TRA, Lost C. 1A DC via 1A inverter, from TRB D. 1A DC via 1A inverter, Lost Page 36

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 033 Plant conditions:

Reactor is in cold shutdown on August 10, outside air temperature 85°F.

Reactor Building personnel doors are open

Reactor Building Purge is in progress in accordance with OP-TM-823-408, RB Purge - RB Doors and/or Equipment Hatch Open

Both Purge Supply and both Purge Exhaust Fans are operating

Air flow is continuously out of the RB doors Which ONE (1) of the following procedural actions must be taken?

A. Close AH-V-1C and AH-V-1D Purge Supply Valves.

B. Adjust RB Purge Manual Loader Purge Rate (AH-D-8B-EX1).

C. Secure one of the Purge Exhaust fans (AH-E-7A or AH-E-7B).

D. Throttle open Purge Exhaust Valve (AH-V-1B) to the 90° position.

Page 37

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 034 Plant conditions:

Reactor Coolant System is in Refueling Shutdown condition.

The Fuel Transfer Canal has been filled.

Fuel Transfer Canal isolation Valves FH-V-1A and FH-V-1B are Closed.

Event and subsequent conditions.

Loss of Offsite Power (LOOP)

Spent Fuel Pool Temperature is 180 °F, rising slowly.

Spent Fuel Pool level is 342 and lowering.

Alarm PLB-2-9, Spent Fuel Pool A Level Lo, is illuminated.

Alarm PLB-2-10, Spent Fuel Pool B Level Lo, is illuminated.

Which ONE (1) of the following actions is required in accordance with OP-TM-AOP-035, Loss of Spent Fuel Cooling?

A. Place both trains of Spent Fuel Pool Cooling in service to increase cooling.

B. Open FH-V-1A and FH-V-1B to equalize level and temperature with the refueling cavity.

C. Commence makeup to the Spent Fuel Pool from the BWST to restore boron concentration.

D. Initiate Attachment 1 for makeup to the Spent Fuel Pool from Fire Service Water to restore level.

Page 38

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 035 Plant conditions:

The reactor is critical.

Operators are starting up the main turbine generator in accordance with OP-TM-301-102, MAIN TURBINE GENERATOR STANDBY MODE TO OPERATING MODE.

Which ONE (1) of the choices fills in the blank in the following statement?

In preparation for High Pressure Turbine Shell warming, the operator performs the step SELECT ON and Execute Command for Shell Warming. This step causes _______

to OPEN.

A. all Control Valves B. all Stop Valves C. all Intercept Control Valves D. all Intermediate Stop Valves Page 39

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 036 Plant conditions:

Makeup Tank venting is required to adjust gas concentration.

Which ONE (1) of the following is the required Waste Gas Compressor control alignment for the Makeup Tank venting evolution?

A. One Waste Gas Compressor must be in HAND.

B. Both Waste Gas Compressors must be in HAND.

C. One Waste Gas Compressor must be in AUTOMATIC.

D. Both Waste Gas Compressors must be in AUTOMATIC.

Page 40

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 037 Plant conditions:

Refueling is in progress.

Event:

RM-G-9, Fuel Handling Building (FHB), fails full scale.

Technicians have confirmed that it is an electronic component failure.

Repairs will take two hours.

Fuel movement was halted when the channel failed.

Which ONE (1) of the following describes the status of fuel handling operations with RM-G-9 failed?

A. Fuel handling activities can resume as long as RM-A-4, FHB Exhaust, remains operable.

B. Fuel handling activities can resume after RM-A-14, FHB ESF Ventilation, is verified in service.

C. Spent Fuel Bridge fuel handling and refueling operations are halted until portable instrumentation is substituted for RM-G-9.

D. Irradiated fuel movement into the FHB must remain suspended until RM-G-9 is restored to operability.

Page 41

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 038 Plant conditions:

100% power.

Event:

The Air Intake Tunnel North Tunnel (AIT) Halon unit has actuated.

Which ONE (1) of the following describes plant response?

A. All three deluge systems actuate and ONLY Fire Pumps FS-P-2 and FS-P-3 start on interlock with the actuation.

B. All three deluge systems actuate and ONLY Fire Pump FS-P-1 starts based on header pressure lowering to the setpoint.

C. The associated deluge system actuates and ONLY Fire Pump FS-P-1starts on interlock with the actuation.

D. The associated deluge system actuates and ONLY Fire Pumps FS-P-2 and FS-P-3 start based on header pressure lowering to the setpoint.

Page 42

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 039 The Diverse Scram System (DSS) provides backup protection for an ATWS (Abnormal Transient Without Scram) by ______________ the shunt trip coils on the

______________ 480V breakers.

A. energizing; CRD #10 and #11 B. de-energizing; CRD #10 and #11 C. de-energizing; 1L-2A and 1G-2A (CRD System Feeders)

D. energizing; 1L-2A and 1G-2A (CRD System Feeders)

Page 43

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 040 Plant conditions:

The reactor tripped due to a leak through Pressurizer Code Safety Valve RC-RV-1A.

The CRS initiated EOP-001, Reactor Trip, then EOP-002, Loss of Subcooling Margin (SCM), then EOP-006, LOCA Cooldown.

Incore Thermocouple Temperature is 522 °F.

RCS pressure is 975 psig.

Core cooldown rate is 42 °F/hr.

EOP-010, Rule 1, Loss of Subcooling Margin (SCM), has been completed.

EOP-010, Guide 6, OTSG Pressure Control, has been ordered initiated by the CRS.

Which ONE (1) of the following is the next action to be taken?

A. Reduce OTSG pressure to obtain a 100°F/hr cooldown rate.

B. Maintain OTSG pressure more than 100 psig below RCS Pressure.

C. Reduce OTSG pressure such that secondary Tsat is 40-60 °F lower than Incore Thermocouple Temperature.

D. Maintain OTSG pressure such that secondary Tsat is90-100 °F lower than Incore Thermocouple Temperature.

Page 44

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 041 Plant conditions:

A small break LOCA resulted in a reactor trip and 1600 psig ESAS actuation.

The operating crew is performing EOP-006, LOCA COOLDOWN.

Tave is 450 F.

Which ONE (1) of the following would require immediate operator action?

A. RCS cooldown rate is 40 F/hour with all Reactor Coolant Pumps stopped.

B. Pressurizer level has exceeded 80 inches with HPI in operation.

C. BWST level is 20 feet and lowering slowly.

D. RB pressure has exceeded 4 psig.

Page 45

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 042 Plant conditions:

35% reactor power and rising after a brief maintenance outage.

Reactor Coolant Pump RC-P-1A #1 Seal leakoff has been steadily lowering for the past hour and is now 0.7 gpm.

MAP F-1-3, RCP SEAL #1 LEAKOFF HI/LO, is actuated.

The Reactor Operator reports that RC-P-1A bearing water temperature has started to rise.

Which one (1) of the following is the required action?

A. Immediately trip the reactor; trip RC-P-1A; close MU-V-33A when RC-P-1A stops rotating.

B. Immediately trip RC-P-1A; close MU-V-33A when RC-P-1A stops rotating.

C. Within 5 minutes: Trip the reactor; trip RC-P-1A; place RC-P-1A in the standby mode.

D. Within 5 minutes: Trip RC-P-1A; place RC-P-1A in the standby mode.

Page 46

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 043 Plant conditions:

Reactor power 100%.

MU-P-1B is OOS for maintenance.

Event:

Reactor trip due to Loss of Offsite Power (LOOP).

EG-Y-1A and EG-Y-1B energize their 1D and 1E 4160 Volt ES busses respectively.

1P 480 Volt ES Bus de-energizes due to an electrical fault.

Makeup Tank level is in the restricted operating region of the curve.

Which one (1) of the following Makeup Pump - BWST suction valve combinations can be aligned to provide makeup flow?

A. Start MU-P-1A and open MU-V-14A.

B. Start MU-P-1A and open MU-V-14B.

C. Start MU-P-1C and open MU-V-14A.

D. Start MU-P-1C and open MU-V-14B.

Page 47

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 044 Plant conditions:

Cooldown in progress using the A Decay Heat Removal (DH) Train.

Decay Heat Return Temperature 185 °F.

Cooldown rate 12 °F/hr.

All Reactor Coolant Pumps are secured.

Event:

DH Pump 1A trips.

The B DH Removal train has been started in accordance with OP-TM-212-211, Shifting DHR Train B From DHR Standby To DHR Operating Mode.

Decay Heat Return Temperature rose to 189 °F during the transfer.

Decay Heat Return Temperature lowered from 189 °F to 174 °F when the B train was started.

Which ONE (1) of the following is the allowable action?

A. Hold RCS temperature constant for a minimum of 30 minutes using In-Core Thermocouple temperature indication.

B. Hold RCS temperature constant for a minimum of 30 minutes using Decay Heat Return Temperature Indicator DH-2-TI1.

C. The cooldown can continue to 159 °F within the next 30 minutes using In-Core Thermocouple temperature indication.

D. The cooldown can continue to 159 °F within the next 30 minutes using Decay Heat Return Temperature Indicator DH-2-TI1.

Page 48

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 045 Plant conditions:

The unit was at 100% power when a steam line break caused a reactor trip and ESAS actuation.

Which ONE (1) of the following is the reason for the procedural action to verify the trip and lock out the non-ES selected Nuclear Services River Water Pump?

A. to limit load on the 1R and 1T 480 Volt ES buses due to Decay Heat River Water Pump power requirements.

B. to limit load on the A and B Emergency Diesel Generators during a loss of offsite power (LOOP) with an ESAS signal present.

C. to prevent excessive cooling of the Nuclear Services Closed Cooling Water System during and ESAS condition since heat load is less than during normal operation.

D. to prevent pump damage if only two Nuclear Services Closed Coolers are in service when the ESAS signal is received.

Page 49

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 046 Plant conditions:

Reactor power 100%.

Event:

Both Main Feedwater Pumps trip.

The automatic reactor trip fails.

The automatic turbine trip fails.

Which ONE (1) of the choices completes the following statement describing the response of Tcold and nuclear instrumentation if the reactor continues untripped?

Tcold will ______ and Power Range Nuclear Instrumentation will indicate ________

than actual Core Thermal Power.

A. Lower, Higher B. Lower, Lower C. Rise, Higher D. Rise, Lower Page 50

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 047 Plant conditions:

100% power.

Overhead alarm MAP C-1-1, RADIATION LEVEL HI, just actuated.

The source of the alarm is RM-A-5 CONDENSER VACUUM PUMP EXHAUST.

Which ONE (1) of the choices completes the following statement?

The MAP-5 Sampler starts to sample the.

A. steam lines for iodine when RM-A-5 reaches the ALERT setpoint.

B. steam lines for iodine and tritium when RM-A-5 reaches the ALERT setpoint.

C. condenser offgas for iodine when RM-A-5 reaches the ALARM setpoint.

D. condenser offgas for iodine and tritium when RM-A-5 reaches the ALARM setpoint.

Page 51

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 048 Plant conditions:

Plant has tripped due to a Loss of Offsite Power (LOOP).

No equipment was out of service prior to the trip.

1D & 1E ES 4160V buses are powered by their respective Emergency Diesel Generator.

SCM is 47 °F, decreasing slowly

OTSGs are at 30% on operating range and lowering.

OTSG A/B pressure is 1010 psig and stable.

Incore Temperatures are rising.

Which ONE (1) of the following is the reason for placing the Emergency Feedwater Control Valves (EF-V-30s) in MANUAL?

A. To feed the OTSGs at the maximum available rate because incore temperatures are rising.

B. To allow feed rate to be adjusted to maintain OTSG levels at 25 in the STARTUP Range.

C. To lower feed rate to 215 gpm per OTSG since subcooling requirements are met.

D. To raise OTSG level to 75-85% in the OPERATING Range because no RCP is running.

Page 52

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 049 Plant conditions:

Turbine/Reactor trip from 100% power.

A loss of offsite power (LOOP) occurred.

Both Emergency Diesel Generators tripped while starting.

RCS pressure is 2065 psig.

The Incore thermocouple temperature is 555 °F rising slowly.

A Loop: Thot = 552 °F stable; Tcold = 495 °F lowering slowly.

B Loop: Thot = 552 °F stable; Tcold = 508 °F stable.

Both Atmospheric Dump Valves are closed.

Emergency Feedwater Pump EF-P-1 is running.

OTSG A level is at 35% and rising slowly.

OTSG B level is at 35% and rising slowly.

Both OTSGs 500 psig lowering slowly.

Which ONE (1) of the following correctly describes the status of Natural Circulation Cooling?

A. Natural Circulation flow is verified in both loops.

B. Natural Circulation flow is NOT verified in either loop.

C. Natural Circulation flow is verified in the A Loop ONLY.

D. Natural Circulation flow is verified in the B Loop ONLY.

Page 53

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 050 Plant event:

Reactor trip from 100% power due to a loss of offsite power (LOOP).

Both Emergency Diesel Generators have failed.

The operating crew is performing AOP-020, LOSS OF STATION POWER, Section 4.0 - STATION BLACKOUT.

Steam driven Emergency Feedwater Pump EF-P-1 is running.

The Transmission System Operator reports that it appears off-site power will not be restored for 24-48 hours.

RCS pressure is at 1815 psig.

In accordance with AOP-020, Loss of Station Power ,which ONE of the following identifies the minimum subcooling margin (SCM) and the means of control?

A. ZERO 25 F. Manually cycle the Pressurizer PORV to minimize SCM.

B. 25 F. Operate Pressurizer heaters to raise RCS pressure as temperature rises.

C. 30 F. Adjust MS-V-4A and MS-V-4B, as necessary to control temperature.

D. 70 F. Adjust EFW flow to maintain OTSG level at 75-85% to maximize SCM.

Page 54

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 051 Plant conditions:

Reactor power 100%.

Event:

MAP alarm A-1-6, Inverter Failed, illuminates.

MAP alarm A-1-8, Battery B Discharging, illuminates.

MAP alarm A-3-8, Inverter 1B/1D/1F Trouble, illuminates.

MAP alarm G-2-3, CRD DC BKR Open, illuminates.

4 psig RB Pressure Channel RB3B indicates actuated.

500 psig ESAS Channel RC6B indicates actuated.

1600 psig ESAS Channel RC3B indicates actuated.

30 psig RB Pressure ESAS Channel RB6B indicates actuated.

Reactor Protection Channel D has no lights illuminated.

The above conditions indicate..

A. Loss of B DC Distribution.

B. Loss of Regulated Bus TRB.

C. Loss of 120 Volt Vital Bus D.

D. Loss of 1B 480 Volt ES MCC.

Page 55

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 052 Plant conditions:

Reactor shutdown is in progress due to a cell short on A Battery that caused failure of a lead.

A Battery has been isolated.

The A and C Battery Chargers are supplying the A DC Bus.

The Turbine DC Lube Oil Pump LO-P-6 was subsequently started and caused the A Battery Charger to go into the current limiting condition. The A Battery charger going into current limiting will __________.

A. result in a voltage dip on the DC Bus B. cause the A Battery Charger to trip on overcurrent C. cause A Battery Charger to shift to the equalize mode D. prevent the C Battery Charger from going into the current limiting condition Page 56

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 053 Nuclear Services Closed Cooling Water (NSCCW) Containment Isolation Valves NS-V-4, NS-V-15 and NS-V-35 close on a Line Break Isolation actuation to prevent......

A. dilution of the Reactor Building Sump water due to a NSCCW system leak inside containment.

B. a radioactive release path in the event of a NSCCW break and an RCS break in containment.

C. loss of bearing cooling water to the Reactor Building Cooling Fans AH-E-1A/1B/1C during an emergency event.

D. loss of cooling water flow to essential components outside the RB in the event of a NSCCW leak inside containment.

Page 57

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 054 In EOP-002, LOSS OF 25 °F SUBCOOLED MARGIN, Step 4.1 reads IAAT HPI flow is ADEQUATE, then GO TO Step 3.9.

Which ONE (1) of the following meets the facility criteria for HPI flow is ADEQUATE?

A. Pressurizer level is rising.

B. HPI flow 200 gpm is verified.

C. In-core temperatures have stabilized.

D. All components in HPI Train A are in their ES actuation alignment.

Page 58

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 055 Plant conditions:

Reactor tripped due to steam leak from OTSG 1A in the Reactor Building

1600 psig and 4 psig ESAS actuations occurred and have been bypassed

RCS pressure 1620 psig

RCS Tave 522°F, steady

Pressurizer level 80 inches and rising

RB pressure 4.2 psig

Rule 3 isolation OTSG 1A has been completed

Rule 2, HPI/LPI Throttling is in progress Given the above conditions, which ONE of the following would be the reason for leaving MU-V-14A and MU-V-14B open when performing OP-TM-211-901, Emergency Injection (HPI/LPI), Attachment 7.3, Throttling HPI?

A. To maintain adequate shutdown margin with RCS temperature < 525°F.

B. To maintain minimum Makeup Pump flow requirements until HPI is secured.

C. To maintain adequate suction to the Makeup Pump until Pressurizer level recovers to level setpoint.

D. To raise RCS boron concentration in anticipation of the subsequent cooldown to cold shutdown conditions.

Page 59

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 056 Plant conditions:

Reactor trip from 100% power caused by a turbine trip.

All control rods are inserted.

All immediate actions are complete.

Which ONE (1) of the following requires an immediate transition out of EOP-001, REACTOR TRIP?

A. Loss of ICS AUTO Power.

B. E 4160 volt bus is powered from EG-Y-1B.

C. In-core temperatures 560 °F rising with only Emergency Feedwater Pump EF-P-1 running.

D. RM-A-5, CONDENSER VACUUM PUMP EXHAUST, in ALARM with Pressurizer level lowering at 1 inch per minute.

Page 60

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 057 Plant conditions:

The reactor was manually tripped

One rod in Group 3 failed to insert into the core.

OP-TM-EOP-005, OTSG TUBE LEAKAGE, was entered due to identified tube leakage.

RCS Tave is 528 °F and lowering slowly.

RCS Pressure is 1920 psig and lowering slowly.

Pressurizer level is 100 inches and stable.

Makeup Tank level is 88 inches.

Makeup Tank pressure is 25 psig.

Makeup flow is 8 gpm.

Seal Injection flow is 32 gpm.

Letdown flow is 45 gpm.

MU-V-14A is open.

Which ONE (1) of the following actions is required?

A. Adjust RCP seal injection flow to establish 42 gpm.

B. Initiate RCS bleed to RC Bleed Tank to lower makeup tank level.

C. Open MU-V-14B to ensure adequate NPSH to the Makeup Pump.

D. Raise letdown flow to 60 gpm to increase Emergency Boration Flow.

Page 61

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 058 Plant conditions:

A plant startup is in progress in accordance with 1102-2, Plant Startup.

Reactor power is 40%, on a hold.

Tave is 579 °F.

Turbine load is 342 MWe.

Event:

MAP Alarm N-1-6, MN COND VACUUM LO actuates.

Condenser vacuum is degrading slowly.

Assuming NO operator action, which ONE (1) of the following describes the current position of the control rods as compared to pre-degrading vacuum position?

A. LOWER due to a reduction in turbine efficiency.

B. LOWER due to crosslimits.

C. HIGHER due to a reduction in turbine efficiency.

D. HIGHER due to crosslimits.

Page 62

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 059 Plant conditions:

100% power

RC-2 MS Pressurizer Temperature Switch is selected to the TE-1 position.

RC-1 MS Pressurizer Level Selector Switch is selected to the RC-1 LT-1 position.

Which ONE (1) of the following sets of Pressurizer Level indications would require shifting RC-2 MS to the TE-2 position?

A. RC-1 LT-1 reads 220; RC-1 LT-3 reads 220; RC-LT-777A reads 150.

B. RC-1 LT-1 reads 220; RC-1 LT-3 reads 150; RC-LT-777A reads 150.

C. RC-1 LT-1 reads 150; RC-1 LT-3 reads 220; RC-LT-777A reads 220.

D. RC-1 LT-1 reads 150; RC-1 LT-3 reads 150; RC-LT-777A reads 220.

Page 63

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 060 Plant conditions:

The Control Room has just been evacuated due to a fire.

OP-TM-EOP-020, Cooldown From Outside the Control Room, Immediate Manual Actions were completed prior to leaving the Control Room.

All Remote Transfer switches have been operated.

Event:

A Loss of offsite power (LOOP) occurs.

With the above conditions.

A. A and B Emergency Diesels will start automatically and re-energize their respective bus.

B. A and B Emergency Diesels will start automatically but their respective breakers must be closed locally.

C. A Emergency Diesel must be started manually from the 1D 4160 Volt Bus and its breaker closed locally.

D. B Emergency Diesel will have to be started manually from the 1E 4160 Volt Bus and its breaker closed locally.

Page 64

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 061 Plant conditions:

Reactor power was 100% when a dropped rod in Group 3 occurred a few minutes ago.

Reactor power is currently 62% and stable.

Turbine load 532 MWe and stable.

MAP Alarm H-1-1, ICS RUNBACK, is illuminated.

MAP Alarm H-2-1, ICS IN TRACK, is illuminated.

MAP Alarm H-3-4, ULD HIGH LOAD LIMIT, is illuminated.

Given the above conditions the operator will have to.

A. reduce the ULD output until NI power is <55%.

B. reduce the ULD output until NI power is <60%.

C. take Hand control of the SG/RX Master and reduce NI power to <55%.

D. take Hand control of the Diamond and Feedwater stations to reduce power to

<60%.

Page 65

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 062 Which ONE (1) of the choices completes the following statement regarding operator action on Loss of ICS Hand Power?

The reactor must be tripped if reactor power is _______________.

A. < 75% and FW-V-17A is in HAND because a feedwater transient will occur.

B. < 75% and both FW-16A and FW-V-16B are in HAND because an RCS overcooling will occur.

C. > 75% and A Feedwater Pump is in HAND because an RCS heatup will occur.

D. > 75% and Turbine Bypass Valves are in HAND because reactor power will exceed 100% power.

Page 66

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 063 Plant conditions:

The plant is starting up.

Reactor power is 42%.

Tave is 579 °F.

Turbine load is 360 MWe.

Event:

Turbine trip, on stator coolant loss.

Which ONE (1) of the following is the required operator action?

A. Verify an automatic reactor trip on interlock with the turbine trip.

B. Ensure reactor power is reduced to within Turbine Bypass Valve capability.

C. Verify an ICS stator coolant runback is in progress to reduce power.

D. Initiate a MANUAL reactor trip if any Main Steam Safety Valves opens.

Page 67

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 064 Plant conditions:

Reactor was tripped due to a large RCS leak (LOCA).

EOP-001, Reactor Trip, was initiated.

Subcooling margin is 12 °F.

OP-TM-EOP-010 Rule 1, Loss of Subcooling Margin (SCM), has been initiated.

RC-P-1D was not tripped within one minute and is currently running.

Which ONE (1) of the following verified conditions allows RC-P-1D to be stopped?

A. Tclad > 1800 °F.

B. Adequate HPI flow.

C. A LPI Flow 1400 gpm, B LPI Flow 900 gpm.

D. Both OTSG levels are between 75 to 85% Operating Range Level.

Page 68

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 065 Plant conditions:

Reactor Tripped due to loss of offsite power (LOOP).

Both Emergency diesels started and are supplying their respective busses.

All three Emergency Feedwater Pumps have started.

Natural Circulation flow has been verified.

T cold is 520°F Which ONE (1) of the following describes the method of cooldown, the cooldown rate limit, and the reason for that limit?

A. Operate the Atmospheric Dump Valves to control cooldown rate 30 °F/hr to prevent voiding in the hot legs.

B. Operate the Atmospheric Dump Valves to control cooldown rate 50 °F/hr to prevent formation of a head bubble.

C. Operate the Turbine Bypass Valves to control cooldown rate 30 °F/hr to prevent voiding in the hot legs.

D. Operate the Turbine Bypass Valves to control cooldown rate 50 °F/hr to prevent formation of a head bubble.

Page 69

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 066 Which ONE (1) of the following is an acceptable communication during an emergency condition?

A. Announcing to control room personnel RM-A-5 and RM-A-15 are in alarm during the performance of reactor trip immediate manual actions.

B. Announcing on the plant page Fire in the Auxiliary Building, Elevation 305.

C. During an update the CRS announces Attention for a brief.

D. Giving an update to the crew control rods are at 290% and inserting and reactor power is at 101% and rising.

Page 70

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 067 A licensed reactor operator is returning to shift after being on vacation. His last watch before vacation was 0700-1900 on April 17, 2007. He is scheduled to be the Assistant Reactor Operator (ARO) for the 0700-1900 watch on April 26, 2007.

Which one (1) of the choices correctly fills in the blank in the following statement?

The reactor operator must review the Control Room Logs starting with __________ up to 0700, April 26, 2007, prior to assuming the scheduled ARO watch.

A. 0700, on April 25, 2007.

B. 1900, on April 25, 2007.

C. 0700, on April 22, 2007.

D. 1900, on April 17, 2007.

Page 71

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 068 Plant conditions:

The reactor tripped 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ago.

Core Burnup is 300 EFPD

An Estimated Critical Position calculation was completed with:

RC Tave = 532 °F

RC Pressure = 2155 psig Current conditions:

RC Tave = 531 °F

RC Pressure = 2120 psig Which ONE (1) of the choices completes the following statement?

During the startup, criticality as predicted by the 1/M Plot will be ______. Criticality will occur at a rod position ______than the ECP critical rod position.

A. accurate; lower B. accurate; higher C. inaccurate; lower D. inaccurate; higher Page 72

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 069 Which ONE (1) of the following describes a VIOLATION of refueling administrative requirements?

A. Fuel moves in Spent Fuel Pool are being supervised by an individual with an inactive SRO license.

B. An irradiated fuel assembly has been transferred to the Spent Fuel Pool with both trains of ESF Ventilation secured.

C. The fuel grapple FULL DOWN position has been determined by ZZ tape reading rather than by the Digital Fuel Elevation reading.

D. The Main Fuel Bridge has been left unattended with the fuel grapple at GRAPPLE UP DISENGAGED and the bridge de-energized.

Page 73

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 070 Conditions:

Work will be performed in an area that has a general radiation dose of 90 mRem/hr.

One worker can perform the job in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 15 minutes.

Two workers can perform the job in 45 minutes.

RadPro estimates that it will take two technicians 20 minutes each to install temporary shielding that will reduce the dose rate to 30 mRem/hr.

An engineering evaluation has been completed to allow shielding to remain if installed.

Which one (1) of the following methods of performing the job meets the facility criteria for RP-AA-400, ALARA PROGRAM?

A. One worker with temporary shielding.

B. One worker WITHOUT temporary shielding.

C. Two workers with temporary shielding.

D. Two workers WITHOUT temporary shielding.

Page 74

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 071 Plant conditions:

100% power.

RM-L-1, RC LETDOWN MONITOR, rapidly progressed to an ALERT alarm status and has now actuated on HI alarm.

Which ONE (1) of the following is the required action?

A. Place Control Tower on pressurized recirculation.

B. Ensure RC Sample Valves CA-V-1, 2, 3 or 13 closed on interlock.

C. Monitor RM-G-26 and 27, MAIN STEAM LINE Monitors, for rising counts.

D. Announce on Page: High Activity has been detected in letdown. All unnecessary personnel in the controlled area report to H.P. Checkpoint.

Page 75

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 072 Plant conditions:

A release is in progress from Waste Gas Decay Tank WDG-T-1A.

WDG-T-1B is in service.

The NLO on rounds reports that indicated pressure in WDG-T-1C has lowered 5 PSIG since the last set of readings.

Which ONE (1) of the following is the required action?

A. Close WDG-47, Waste Gas Release Control Valve.

B. Verify WDG-V-32, WDG-T-1C Outlet Isolation Valve, is locked closed.

C. Verify RM-A-7, WDG-T Discharge Monitor, has remained below the isolation setpoint.

D. Perform a valve lineup on WDG-T-1C to verify that it is NOT aligned to the vent header.

Page 76

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 073 When guidance from Rules, Guides or procedures conflict, the order of preference to be applied is.

A. EOP Rules, EOP steps, Other Procedures, EOP Guides.

B. EOP steps, EOP Rules, EOP Guides, Other Procedures.

C. EOP Rules, EOP steps, EOP Guides, Other Procedures.

D. EOP steps, EOP Rules, Other Procedures, EOP Guides.

Page 77

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 074 Plant conditions:

An OTSG tube rupture has resulted in a reactor trip and ESAS actuation.

The Shift Emergency Director initially classified the event as an ALERT 1115 hours0.0129 days 0.31 hours 0.00184 weeks 4.242575e-4 months .

Local notifications of the ALERT have been made.

The Shift Emergency Director upgraded the classification to SITE AREA EMERGENCY at 1148.

Which ONE (1) of the following identifies the latest time that the upgrade notification to required local agencies can be made and what action stops the clock?

A. 1203; after completion of the initial roll call.

B. 1203; after all required contacts have acknowledged the message.

C. 1248; after completion of the initial roll call.

D. 1248; after all required contacts have acknowledged the message.

Page 78

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 075 Plant conditions:

An automatic reactor trip has actuated.

The operating crew is performing EOP-001, REACTOR TRIP.

Which ONE (1) of the following is permitted to be performed by a licensed reactor operator without concurrence from the Control Room Supervisor?

A. Reset the Pressurizer level control setpoint to the post-trip value.

B. Tripping MFW Pumps if OTSG A or B Operating Range level is > 97.5%.

C. An If at any time (IAAT) action after the step has been read and the condition is met.

D. Any alarm response procedure action step after the step ENSURE performance of an Alarm Review has been read.

Page 79

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 076 Plant conditions:

Plant startup in progress IAW 1102-2, Plant Startup.

Reactor Power 79%.

ICS is in full auto, except ULD.

Event:

Reactor Coolant Pump RC-P-1C ammeter falls to approximately 25%.

MAP Alarm F-3-2, RC LOOP B FLOW LO, illuminates.

RC-P-1C indication light is illuminated Red.

Reactor power is reducing.

MAP Alarm H-1-1, ICS RUNBACK, is illuminated.

MAP Alarm H-2-1, ICS IN TRACK, is illuminated.

Which ONE (1) of the following describes the event and the appropriate procedure to enter?

A. RC-P-1C locked rotor, trip the Reactor and go to EOP-001, Reactor Trip.

B. RC-P-1C locked rotor, secure RC-P-1C in accordance with OP-TM-226-153, Shutdown RC-P-1C.

C. RC-P-1C sheared shaft, trip the reactor and go to EOP-001, Reactor Trip.

D. RC-P-1C sheared shaft, secure RC-P-1C in accordance with OP-TM-226-153, Shutdown RC-P-1C.

Page 80

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 077 Plant conditions:

PORV Block Valve RC-V-2 is closed with power removed, due to the PORV RC-RV-2 failing open.

1102-11, Plant Cooldown, is in progress.

RCS temperature is 327°F.

To prevent severe over-pressurization of the RCS A. The plant must be in cold shutdown within 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months of PORV inoperability.

B. ES selected High Pressure Injection Pumps must be in Pull to Lock.

C. Restore power to the PORV Block Valve and open the PORV Block Valve.

D. MU-V-16A/B/C/D are closed with their breakers open, and MU-V-217 IS CLOSED.

Page 81

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 078 Plant conditions:

Reactor power is 40%

Turbine load is 340 MWe.

Main Feedwater Pump 1B (FW-P-1B) is tagged out of service.

All other equipment lineups are normal.

Event:

MAP Alarm M-1-1, FWP-1A TRIP, actuates.

Reactor power and turbine load are stable.

OTSG A and B levels are lowering.

Which ONE (1) of the following actions is required?

A. Initiate a MANUAL reactor trip and enter OP-TM-EOP-001, REACTOR TRIP.

B. Ensure MAP H-1-1, ICS RUNBACK, actuates and implement 1102-4, POWER OPERATIONS.

C. Rapidly reduce main turbine load until reactor power is less than 7% and implement GUIDE 15, EFW ACTUATION RESPONSE.

D. Initiate a MANUAL turbine trip and reduce reactor power to within turbine bypass valve capability in accordance with MAP K-1-1 TURBINE TRIP.

Page 82

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 079 Plant conditions:

Reactor is shutdown due to Steam Generator tube leak in OTSG 1A.

All four RCPs are operating.

OTSG 1A is isolated at a level of 87%.

OTSG 1B level is 25 inches.

OTSG 1A pressure 875 psig.

OTSG 1B pressure 727 psig.

BWST level is 54 ft.

No offsite dose increases have been noted by Radiological Assessment.

RCS Thot is 460°F.

RCS Tcold 455°F.

RCS Pressure is 965 psig.

RCS cooldown rate is 105°F/hr.

Which ONE (1) of the following actions must be taken?

A. Shutdown one Reactor Coolant Pump per loop in accordance with 1102-11, Plant Cooldown.

B. Minimize subcooling margin in accordance with OP-TM-EOP-010, Rule 6, Pressurized Thermal Shock (PTS).

C. Reduce Subcooling margin to 30 °F by opening the PORV in accordance with OP-TM-EOP-010, Guide 8 RCS Pressure Control.

D. Preferentially steam OTSG 1A to maintain level on scale in accordance with OP-TM-EOP-005, OTSG Tube Leakage.

Page 83

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 080 Plant conditions:

Reactor tripped due to a loss of offsite power (LOOP).

Natural Circulation flow has been verified.

The Atmospheric Dump Valves are in automatic.

Tave is 543 °F and lowering.

RCS Cooldown rate is 62 °F/hr.

OTSG 1A level 57%.

OTSG 1B level 61%.

OTSG 1A Pressure 905 psig and lowering.

OTSG 1B Pressure 900 psig and lowering.

All three Emergency Feedwater Pumps are running.

EFW Flow to OTSG 1A is 422 gpm.

EFW Flow to OTSG 1B is 477 gpm.

Which ONE (1) of the following actions must be taken?

A. Initiate OP-TM-EOP-010, Rule 3, Excessive Primary to Secondary Heat Transfer, to isolate B OTSG.

B. Close Emergency Feedwater Isolation Valves (EF-V-52s) in accordance with EOP-010, Guide 16.3, EFW Failure, to isolate the Emergency Feedwater Control Valves (EF-V-30s).

C. Close the Emergency Feedwater Control Valves in accordance with OP-TM-EOP-010, Guide 15, EFW Actuation Response, to stop the OTSG pressure reduction.

D. Take manual control of the Atmospheric Dump Valves and close them in accordance with OP-TM-411-451, Manual Control of TBVs/ADVs, to lower the cooldown rate.

Page 84

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 081 Plant conditions:

Reactor was manually tripped due to a loss of Instrument Air.

Secondary Instrument Air pressure is currently 45 psig.

Primary Instrument Air pressure is currently 51 psig.

Intermediate Closed Cooling Water Flow is 265 gpm.

RCP Seal Injection flow is 30 gpm.

MU-V-20, RCP Seal Injection Isolation Valve, is required to be blocked. . . .

A. CLOSED to ensure maximum HPI flow in the event of an automatic or manual ES actuation.

B. CLOSED to prevent the valve from opening and thereby inadvertently shocking the RCP seals when Instrument Air Pressure is restored.

C. OPEN to ensure maximum available makeup flow with the normal makeup flowpath isolated.

D. OPEN to ensure continued SI flow, with an operator assigned and available to close if containment isolation is required.

Page 85

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 082 Which ONE (1) of the following events would require four (4) hour report to the NRC Operations Center, in accordance with LS-AA-1020, Reportability Reference Manual?

A. Activation of ERDS, following declaration of an ALERT.

B. Initiating a plant shutdown for an OTSG tube leak of 0.5 gpm.

C. Completion of a cooldown to replace a leaking Code Safety Valve.

D. Cold shutdown loss of offsite power (LOOP), both diesel load onto buses.

Page 86

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 083 Plant conditions:

Reactor power is 100%.

Normal equipment lineups exist.

Waste Gas Decay Tank 1B is in service at 65 psig.

Waste Gas Decay Tank 1A is at 0 psig.

Waste Gas Decay Tank 1C is at 78 psig awaiting release paperwork.

Event:

A small leak has been discovered on the Waste Gas Delay Tank relief valve.

It has been determined that the Waste Gas Delay Tank must be isolated to replace the relief valve.

Given these conditions the CRS must .

A. initiate 1102-4, Power Operations, to place the unit in Hot Shutdown to allow isolation of the vent header.

B. initiate 1104-27, Waste Disposal - Gaseous, to isolate and bypass the Waste Gas Delay Tank to allow continued operation of the Waste Gas System.

C. initiate 1104-27, Waste Disposal - Gaseous, to shut down the Waste Gas System and isolate all WDL tanks on the header to terminate the leak.

D. initiate 6610-ADM-4250.11, Waste Gas Release Permit for Waste Gas Decay Tanks 1B and 1C, to allow depressurization of the Waste Gas System for repairs.

Page 87

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 084 If the Control Room must be evacuated due to a fire, Tech Specs requires the Remote Shutdown System to contain enough control and instrumentation functions to A. place and maintain the unit in Hot Standby.

B. place and maintain the unit in Hot Shutdown.

C. cooldown the unit to the Cold Shutdown condition.

D. cooldown the unit to the Refueling Shutdown condition.

Page 88

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 085 Plant conditions:

The reactor has tripped due to a loss of offsite power (LOOP).

Cooldown is in progress using the Atmospheric Dump Valves.

Neither OTSG has tube leakage.

Which ONE (1) of the choices fills in the blank of the following statement?

As a minimum, RCS pressure must be maintained above the ______ line of EOP-010, Figure 1, RCS PRESSURE-TEMPERATURE LIMITS.

A. SAT CURVE B. 25 °F SCM C. PREVENT HEAD BUBBLE D. 250 °F SCM Page 89

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 086 Plant conditions:

With the plant at 100% power Main Feedwater Pump FW-P-1A trips.

During the transient RCS Pressure peaks at 2245 psig and the 1B 4160 V bus trips.

Current plant conditions:

Reactor power has stabilized at 65%.

RCS pressure is 2030 psig and lowering slowly.

All available pressurizer heaters are energized.

RC Drain Tank pressure is <2 psig.

RC Drain Tank Temperature is stable.

Which ONE (1) of the following actions must be taken FIRST?

A. Transfer Group 9 Pressurizer Heaters to 1P 480V Bus in accordance with OP-TM-220-901, Emergency Power Supply For Pressurizer Heaters.

B. Trip the Reactor due to lowering RCS pressure to prevent an automatic trip and go to OP-TM-EOP-001, Reactor Trip.

C. Close the Pressurizer Spray Block Valve RC-V-3 to prevent a reactor trip in accordance with OP-TM-AOP-043, Loss of Pressurizer (Solid Ops Cooldown).

D. Close the PORV Block Valve RC-V-2 to prevent a reactor trip in accordance with OP-TM-MAP-G0308, RC Press Narrow RNG HI/LO.

Page 90

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 087 Which of the following describes a plant condition that has Technical Specification required action(s) and the bases for any action(s) that would be taken?

A. RPS Turbine Trip Anticipatory (ARTS) has NOT enabled by 55% power rising, Unnecessary challenges to the code safeties and PORV.

B. RPS Feedwater Pump Trip Anticipatory has NOT bypassed until 5% power lowering, Unnecessary challenges to the RPS when EFW available.

C. 15% power both Intermediate Range Instrument Amplifiers fail, Inability to verify one decade overlap with power range instruments.

D. 100% power, A RPS in Manual Bypass, Vital Bus B VBB power is lost, Zero degree of redundancy in RPS channels.

Page 91

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 088 (Question removed from exam, procedure change resulted in no correct answer)

Plant conditions:

An RCS LOCA results in reactor trip from 100% power.

OP-TM-EOP-010, Rule 1 - Loss of Subcooled Margin was completed.

ESAS equipment has operated except Decay Heat Pump1B, which tripped.

OP-TM-EOP-006, LOCA Cooldown has been initiated.

Decay Heat Removal crossconnect valves DH-V-38A and DH-V-38B are open.

Decay Heat Removal Pressurizer Spray Isolation Valve RC-V-4 is closed.

Guide 22 RB Sump Recirc has been initiated and Sump Recirc Valves DH-V-6A and DH-V-6B are open.

Decay Heat Removal Train A flow is 1415 gpm.

Decay Heat Removal Train B flow is 1355 gpm.

Reactor Building Spray Pump 1A Flow is 1450 gpm.

Reactor Building Spray Pump 1B Flow is 1100 gpm.

Reactor Building Sump Level is 90 inches.

Which ONE (1) of the following is the proper action:

A. Throttle DH-P-1A flow to <2700 total gpm to prevent pump runout in accordance with OP-TM-EOP-010, Guide 22 - RB Sump Recirculation.

B. Raise DH-P-1A flow to 3300 gpm to maximize reactor vessel cooling in accordance with OP-TM-EOP-010, Rule 2 - HPI-HPI/LPI Throttling.

C. Throttle Reactor Building Spray Pump 1A flow to < 1400 gpm to ensure pump NPSH in accordance with OP-TM-214-000, Building Spray System.

D. Raise Reactor Building Spray flow in both trains to 1700 gpm to maximize spray in accordance with OP-TM-214-901, RB Spray Operation.

Page 92

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 089 PLANT CONDITIONS:

Reactor power 50% following a loss of Feedwater Pump 1B.

VA-P-1B main vacuum pump is OOS for maintenance.

CO-P-1C condensate pump is OOS for maintenance.

CO-P-1A & CO-P-1B condensate pumps are operating.

CO-P-2A & CO-P-2C condensate booster pumps are operating.

Event:

1A 4160 Volt Bus trips.

Which ONE (1) of the following represents:

(1) The potential impact on the plant.

(2) The mitigation strategy.

A. (1) The reactor will trip due to loss of feedwater.

(2) Initiate Emergency Feedwater in accordance with OP-TM-EOP-010, Guide 15, Emergency Feedwater Actuation Response.

B. (1) Condensate Booster Pump CO-P-2B will auto-start.

(2) Reduce power to within the capability of the Condensate/Booster pumps in accordance with OP-TM-AOP-010, Loss of 1A 4160 Volt Bus.

C. (1) Overheating of the A Main Transformer due to loss of cooling.

(2) Reduce load in accordance with 1104-2, Power Operations, to maintain transformer temperatures within specifications.

D. (1) Vacuum will begin to degrade due to loss of power to the operable vacuum pumps.

(2) Provide power to start either operable Main Vacuum Pump in accordance with OP-TM-731-901, Energize 1C 480 Volt Bus Using 1N Bus Crosstie.

Page 93

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 090 Which ONE (1) of the following conditions exceeds a design assumption for Reactor Building (RB) performance during a design basis accident and the basis for the limit?

A. RB Pressure is 2.2 psig with the unit at 50% power; RB Pressure may exceed design limits.

B. RB Temperature above the 320 Elevation is 125 °F with the unit at 100% power; Temperature assumptions for equipment environmental qualification may be exceeded.

C. OTSG Sample valve CA-V-5A is failed closed and CA-V-4A is stuck open with the unit at 50% power; RB Isolation may not be established when actuated.

D. RB Equipment Hatch inner door is open for seal replacement with the unit at 100% power; The outer door may exceed P limits and fail.

Page 94

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 091 Plant conditions:

Reactor power is 100%.

Loss of ICS Auto power occurred 20 minutes ago.

Normal equipment lineups existed prior to the event.

OP-TM-AOP-027, Loss of ATA or ICS Auto Power, has been initiated.

As The Control Room Supervisor you must direct the CRO to A. trip the reactor in accordance with OP-TM-AOP-043, Loss of Pressurizer (Solid Ops Cooldown), when Pressurizer Level rises above 315 inches to prevent taking the plant solid.

B. commence a normal plant shutdown in accordance with OP 1102-4 Power Operations, to prevent exceeding 315 inches in the Pressurizer while critical.

C. take manual control of Normal Makeup Valve MU-V-17 in accordance with OP-TM-211-472, Manual Pressurizer Level Control, to maintain level between 80 and 385 inches.

D. reduce Seal Injection flow to 22 gpm in accordance with OP-TM-211-476, Seal Injection Control - Console Operations, to prevent the need for a plant shutdown or a reactor trip.

Page 95

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 092 Plant conditions:

100% power.

An approved release is in progress from Waste Gas Decay Tank (WDG-T-1A).

Event:

Power is lost to RM-A-7, Gaseous Waste Discharge Tank Monitor.

Which ONE (1) of the following describes the correct action and the subsequent release of WDG-T-1A?

A. Ensure WDG-V-47 closes to isolate the release. Place RM-A-7 in DEFEAT in accordance with MAP C-3-1, Rad Mon System Trouble. Release may resume as long as RM-A-8 is operable.

B. Ensure WDG-V-47 closes to isolate the release. Place RM-A-7 in DEFEAT in accordance with MAP C-3-1, Rad Mon System Trouble. RM-A-7 must be restored to operable before resuming the release.

C. WDG-V-47 remains open. Continue the release in accordance with 1104-27, Waste Disposal - Gaseous, as long as RM-A-8 is operable.

D. WDG-V-47 remains open. Manually terminate the release in accordance with 1104-27, Waste Disposal - Gaseous until RM-A-7 is restored to operable.

Page 96

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 093 Plant conditions:

Reactor is in Hot Shutdown.

Normal equipment lineups exist.

Event:

PLF-1-1 Reactor BLDG fire, alarm is received.

Temperatures in the Reactor Building are approximately 98 °F rising slowly.

An NLO reports the panel fire alarm is for RB-FZ-1A, Reactor Building 281 North Outside D ring.

As Control Room Supervisor, which ONE (1) of the following procedural actions will be directed from AOP-001, FIRE?

A. Initiate OP-TM-811-901, Containment Fire Service, to place the containment fire service system in service.

B. Initiate OP 1102-11, Plant Cooldown, to commence a plant cooldown.

C. Initiate OP-TM-534-901, RB Emergency Cooling Operations, to start the RB Emergency Cooling System.

D. Initiate OP-MA-001-007, Fire Protection System Impairment Control, to remove alarm RB-FZ-1A, allowing other zones to actuate an alarm if the fire spreads.

Page 97

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 094 Plant conditions:

The reactor was at 100% power when a grid disturbance caused Core Thermal Power (C1708) to stabilize at 2587 MWt.

Which ONE (1) of the choices completes the following statement regarding the required action?

Immediately reduce core thermal power to less than __________.

A. 2581 and hold until the One Hour Average Core Thermal Power (C3560) is <

2581 MWt B. 2581 and hold until the Four Hour Average Core Thermal Power (C3553) is <

2581 MWt C. 2568 and hold until the One Hour Average Core Thermal Power (C3560) is <

2568 MWt D. 2568 and hold until the Four Hour Average Core Thermal Power (C3553) is <

2568 MWt Page 98

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 095 Plant conditions:

An automatic reactor trip occurred after 200 days of operation at full power.

The crew is performing a reactor startup in accordance with 1103-8, APPROACH TO CRITICALITY.

ECP Data:

Estimated critical rod position is 90% withdrawn on CRG 6.

Minimum withdrawal limit is 40% withdrawn on CRG 6.

Maximum withdrawal limit is 50% withdrawn on CRG 7.

Current conditions:

50% withdrawn on CRG 7

CRO reports and STA confirms that the 1/M predicts criticality at 65% withdrawn on CRG 7.

As CRS, which ONE (1) of the following actions must be directed?

A. Commence emergency boration and contact Reactor Engineering.

B. Insert regulating rods to achieve at least a 1% K/K subcritical condition.

C. Insert the rods to 90% withdrawn on CRG 6 and deborate to achieve criticality.

D. Leave the rods at 50% withdrawn on CRG 7, continue monitoring the NIs and re-evaluate the ECP.

Page 99

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 096 Plant conditions:

A refueling outage is in progress.

You are the SRO Fuel Handling Supervisor.

An assembly has been withdrawn and the bridge is starting to move away from the core.

RMS alarm RM-A-2, REACTOR BUILDING, has actuated in the control room.

The Shift Manager has informed you that it appears RM-A-2 is failed but, as a precautionary measure, all personnel will be directed to exit the Reactor Building.

In accordance with 1505-1, REFUELING PROCEDURE, which ONE of the choices completes the following statement regarding required actions prior to exiting the Reactor Building?

Return to the core and insert the assembly into ___________________________.

A. any available core location then move the bridge away from the core B. any available core location; leaving the grapple engaged C. an approved location then move the bridge away from the core D. an approved location; leaving the grapple engaged Page 100

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 097 Plant conditions:

The unit is in cold shutdown.

CRD maintenance required patch point reconnection.

As a result, OP-TM-622-221, CONTROL ROD PROGRAM SPECIAL CHECK, must be performed.

Which ONE (1) of the following identifies the position that must approve unlocking the Patch Panel(s)?

A. Control Room Supervisor.

B. Shift Manager.

C. Operations Director.

D. Plant Manager.

Page 101

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 098 Plant conditions:

A large break LOCA including fuel damage has occurred.

Both trains of LPI are in service.

Decay Heat Removal Pump DH-P-1A needs oil to be added to ensure continued operability.

Significant radiation levels are anticipated in the area of the pump.

Adding oil to the Decay Heat Removal Pump has been classified as Protecting Valuable Property.

Which ONE (1) of the following is the maximum TEDE dose limit for this operation?

A. 2 Rem.

B. 5 Rem.

C. 10 Rem.

D. 25 Rem.

Page 102

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 099 Plant conditions:

The unit is at 100% power.

Two NLOs must enter a Level 2 Locked High Radiation Area to verify the position of a manual valve that is not documented in the proper position.

The job is expected to take only 1-2 minutes and total exposure for each person is expected to be < 100 mrem.

Which ONE (1) of the following positions must provide approval prior to the entry?

A. Shift Manager.

B. Duty RadCon Technician.

C. Radiation Protection Manager.

D. Plant Manager or Site Vice President.

Page 103

U.S.N.R.C. Site-Specific Written Examination Three Mile Island Senior Reactor Operator Question 100 Plant conditions:

The operating crew has just initiated a plant shutdown due to OTSG A tube leakage of 1.5 gpm.

The Shift Manager has validated a report from NRC that a Boeing 737 was hijacked in Chicago. The FAA informed the NRC that the hijacker has directed the pilot to fly to Harrisburg International Airport for refueling and further instructions.

The NRC notified TMI that it considers this to be a direct threat to TMI until further notice.

The plane is in the air and 22 minutes from Harrisburg.

Which ONE (1) of the following is the correct Emergency Action Level (EAL) for this event?

A. UNUSUAL EVENT.

B. ALERT.

C. SITE AREA EMERGENCY.

D. GENERAL EMERGENCY.

Page 104

ML071760138

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