ML081410443

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Proposed Written Exam for the Fermi 2 Initial Examination - January 2008
ML081410443
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 03/25/2008
From: Hironori Peterson
Operations Branch III
To: Jennifer Davis
Detroit Edison
References
50-341/08-301
Download: ML081410443 (102)
v • d • e


Text

Fermi 2 - 2008 NRC RO License Exam QUESTION 1 Following a Loss of Coolant Accident, plant conditions are as follows:

  • RPV Water Level is -25 inches.
  • Reactor Pressure is 50 psig.
  • The Reactor Building is NOT accessible due to High Radiation Levels.

Which ONE of the following paths can be used to inject from the Condensate Storage Tank (CST) into the reactor, using ONLY Main Control Room manipulations?

The CST can be injected by using the:

_____ A. Residual Heat Removal System with suction aligned from the Torus.

_____ B. Standby Liquid Control System with suction aligned from the Test Tank.

_____ C. Core Spray System with suction aligned from the Condensate Storage Tank.

_____ D. High Pressure Coolant Injection System with suction aligned from the Condensate Storage Tank.

Fermi 2 - 2008 NRC RO License Exam QUESTION 2 The plant is in MODE 4, COLD SHUTDOWN, conditions are as follows:

  • RPV Water Level is 230 inches.
  • E1150-F003B, Div 2 RHR Hx Outlet Vlv is THROTTLED OPEN 60 SECONDS.
  • E1150-F048B, Div 2 RHR Hx Bypass Vlv is OPEN.

Which ONE of the following will REDUCE cooldown rate?

_____ A. FULLY OPEN E1150-F003B, Div 2 RHR Hx Outlet Valve.

_____ B. FULLY SHUT E1150-F048B, Div 2 RHR Hx Bypass Valve.

_____ C. THROTTLE SHUT E1150-F048B, Div 2 RHR Hx Bypass Valve.

_____ D. THROTTLE CLOSED E1150-F003B, Div 2 RHR Hx Outlet Valve.

Fermi 2 - 2008 NRC RO License Exam QUESTION 3 Following a transient, HPCI is being used to maintain RPV Water Level per 29.100.01 Sheet 1, RPV Control. Alarm 2D54, HPCI INVERTER CIRCUIT FAILURE actuates with the following indications failing DOWNSCALE:

  • E41-R609, HPCI Pump Suction/Discharge Pressure.
  • E41-R608, HPCI Turbine Steam Inlet/Exhaust Pressure.
  • E41-R613, HPCI Pump Flow Indicator.
  • E41-K615, HPCI Flow Controller.

With these indications, which ONE of the following caused the loss of the HPCI Inverter and what actions are required?

Loss of the HPCI Inverter was produced by a LOSS of:

_____ A. Division 1 130 VDC power to the inverter, it is required to OPERATE HPCI to maintain RPV Water Level.

_____ B. Division 1 130 VDC power to the inverter, it is required to SHUTDOWN HPCI and use RCIC to maintain RPV Water Level.

_____ C. Division 2 130 VDC power to the inverter, it is required to OPERATE HPCI to maintain RPV Water Level.

_____ D. Division 2 130 VDC power to the inverter, it is required to SHUTDOWN HPCI and use RCIC to maintain RPV Water Level.

Fermi 2 - 2008 NRC RO License Exam QUESTION 4 With the plant operating at full power, a relay malfunction resulted in the following annunciators:

  • 1D1, DIV I CSS ACTUATED.

What will be the affect, if any, of this failure on Emergency Diesel Generators?

_____ A. Emergency Diesel Generators 11 and 12 will remain in STANDBY.

_____ B. Emergency Diesel Generators 11 and 12 will START and LOAD with ALL trips active.

_____ C. Emergency Diesel Generators 11 and 12 will START and LOAD with ONLY essential trips active.

_____ D. Emergency Diesel Generators 11 and 12 will START AND OPERATE UNLOADED with ONLY essential trips active.

Fermi 2 - 2008 NRC RO License Exam QUESTION 5 Which ONE of the following Reactor Pressure Vessel piping taps is SHARED by the Standby Liquid Control System Injection Line?

_____ A. Jet Pump Differential Pressure tap

_____ B. Core Plate Differential Pressure tap

_____ C. Core Spray Line Break Detection tap

_____ D. Control Rod Drive Water Differential Pressure tap

Fermi 2 - 2008 NRC RO License Exam QUESTION 6 Following a manual reactor scram the following occurred:

  • The Reactor Mode Switch was placed in SHUTDOWN.
  • Scram Reset Switch, C7100-M605 was turned to the GP 1/4 AND GP 2/3 positions and released.
  • SRM and IRM detectors were selected and the DRIVE IN pushbutton was depressed.
  • ALL RPV and Containment parameters remained constant prior to the second scram.

What was the cause of the SECOND scram and why did it occur?

_____ A. Alarm 3D51, SRM PERIOD SHORT, was received due to driving in SRM and IRM detectors and an automatic scram resulted.

_____ B. Alarm 3D97, APRM NEUTRON FLUX UPSCALE TRIP, was received due to the production of delayed neutrons from delayed neutron precursors.

_____ C. Alarm 3D86, MN STM LINE ISO VALVE CLOSURE CHANNEL TRIP, was received due to the failure to adjust Gland Seal Pressure resulting in an MSIV isolation on loss of vacuum and the subsequent scram.

_____ D. Alarm 3D94, DISCH WATER VOL HI LEVEL CHANNEL TRIP, was received and the reactor scram occurred because the SDV High Level Bypass Switch was not placed in BYPASS and the SDV filled faster than it drained after the first scram was reset.

Fermi 2 - 2008 NRC RO License Exam QUESTION 7 A reactor startup is in progress. The reactor has been declared critical and the operator has established a 150 sec period. ALL IRMs are on ~ 50 range 4. The following indications are observed:

  • 3D63, IRM UPSCALE alarms.
  • 3D59, IRM CH A/E/C/G UPSCALE TRIP/INOP alarms.
  • 3D73, TRIP ACTUATORS A1/A2 TRIPPED alarms.
  • 3D113, CONTROL ROD WITHDRAWAL BLOCK alarm These indications were CAUSED by:

_____ A. IRM E power supply failure.

_____ B. IRM E being ranged to range 3.

_____ C. IRM E being ranged to range 5.

_____ D. IRM E being withdrawn from the core.

Fermi 2 - 2008 NRC RO License Exam QUESTION 8 Which ONE of the following PROVIDES POWER for the Intermediate Range Channel B instrument drawer?

_____ A. 120/208 VAC Cabinet 72E-2B-1

_____ B. 120 VAC UPS Distribution Cabinet B

_____ C. 48/24 VDC DC Distribution Cabinet 2IA1-3

_____ D. 48/24 VDC DC Distribution Cabinet 2IB1-3

Fermi 2 - 2008 NRC RO License Exam QUESTION 9 A reactor startup is in progress, the following conditions exist.

  • The Mode Switch is in the START & HOT STBY position.
  • NO SRMs are bypassed.
  • The SRM detectors are PARTIALLY WITHDRAWN.

Which ONE of the following sets of conditions will RESULT in a rod withdrawal block?

_____ A. IRMs on range 3. ALL SRMs indicating 90 cps.

_____ B. IRMs on range 1. ALL SRMs indicating 120 cps.

_____ C. IRMs on range 2. SRM "A" indicating 90 cps, ALL OTHER SRMs indicating 150 cps.

_____ D. IRMs on range 4. SRM "A" indicating 90 cps, ALL OTHER SRMs indicating 120 cps.

Fermi 2 - 2008 NRC RO License Exam QUESTION 10 Plant shutdown is in progress. A control rod is being inserted from position 48 to position 00.

The B Level LPRM readings will most SIGNIFICANTLY DECREASE as the rod passes through positions ____________.

_____ A. 08 to 04

_____ B. 20 to 16

_____ C. 32 to 28

_____ D. 44 to 40

Fermi 2 - 2008 NRC RO License Exam QUESTION 11 Reactor Core Isolation Cooling (RCIC) is operating in the TEST MODE with the following conditions:

  • E51-R614, RCIC Pump Flow Controller is in "AUTOMATIC".
  • RCIC Turbine Speed is 2950 rpm.
  • P1100-F606, CST Common Return Isolation Valve is OPEN.
  • E41-K820, Test Isolation/PCV E41-F011 Controller, is in MANUAL at 20%

OPEN.

Which ONE of the following describes the STABILIZED response of RCIC Turbine Speed AND system flow AFTER PCV E41-F011 is THROTTLED an ADDITIONAL 5% in the CLOSED direction?

_____ A. RCIC Turbine SPEED will be HIGHER.

System indicated FLOW will be HIGHER.

_____ B. RCIC Turbine SPEED will be LOWER.

System indicated FLOW will be LOWER.

_____ C. RCIC Turbine SPEED will be HIGHER.

System indicated FLOW will be AT THE INITIAL VALUE.

_____ D. RCIC Turbine SPEED will be LOWER.

System indicated FLOW will be AT THE INITIAL VALUE.

Fermi 2 - 2008 NRC RO License Exam QUESTION 12 With Primary Containment Pneumatic Supply System DIV I Inboard and Outboard Isolation Valves, T4901-F601 AND F465 SHUT, how are the Automatic Depressurization System Valves affected?

_____ A. ADS Valves WILL operate if the logic is actuated, WITHOUT any further operator action.

_____ B. ADS Valves WILL NOT operate if the logic is actuated. Operators MUST use Alternate Depressurization systems.

_____ C. ADS Valves WILL operate if the logic is actuated. NIAS automatically aligns, WITHOUT any further operator action.

_____ D. ADS Valves WILL NOT operate if the logic is actuated. Operators MUST clear and reset isolations and realign Nitrogen to the Drywell.

Fermi 2 - 2008 NRC RO License Exam QUESTION 13 While monitoring the Primary Containment Isolation System (PCIS) Group Isolation mimic (ISO MIMIC) on P601, an Isolation signal is received.

For the statements below, which ONE is correct for valve groups that have received an isolation signal and have correctly completed their response to that signal.

When the Isolation signal has initiated, for a group of valves that are NOT wired in series, a:

_____ A. GREY ISO SIG PRESENT message is displayed, on the P601 PCIS mimic, to indicate an isolation signal is present AND when ALL isolation valves in that PCIS Group are CLOSED, they indicate RED.

_____ B. GREY ISO SIG PRESENT message is displayed, on the P601 PCIS mimic, to indicate an isolation signal is present, AND when ALL isolation valves in that PCIS Group are CLOSED, they indicate GREEN.

_____ C. YELLOW ISO SIG PRESENT message is displayed, on the P601 PCIS mimic, to indicate an isolation signal is present AND when ALL isolation valves in that PCIS Group are CLOSED, they indicate RED.

_____ D. YELLOW ISO SIG PRESENT message is displayed, on the P601 PCIS mimic, to indicate an isolation signal is present, AND when ALL isolation valves in that PCIS Group are CLOSED, they indicate GREEN.

Fermi 2 - 2008 NRC RO License Exam QUESTION 14 Safety Relief Valve G Tailpipe Vacuum Breaker is STUCK OPEN.

Which ONE of the following affects will result from this condition?

_____ A. Steam will be released to the TORUS when SRV G is OPEN.

_____ B. Steam will be released to the DRYWELL when SRV G is OPEN.

_____ C. Damage may occur to the SRV TAILPIPE when SRV G is OPEN.

_____ D. Water will be drawn up the SRV TAILPIPE after SRV G is SHUT.

Fermi 2 - 2008 NRC RO License Exam QUESTION 15 Which ONE of the following indicates an OPEN Safety Relief Valve?

_____ A. Reactor Thermal Power LOWERING from 3430 Mwt to 3258 Mwt.

_____ B. Safety Relief Valve Tailpipe SLOWLY RISING from 170°F to 221°F.

_____ C. Total Indicated Steam Flow RISING from 13.4 Mlbm/hr to 14.1 Mlbm/hr.

_____ D. Total Feed Flow at 14.1 Mlbm/hr WITH Total Steam Flow at 13.4 Mlbm/hr.

Fermi 2 - 2008 NRC RO License Exam QUESTION 16 The plant is operating at 10% POWER with the Reactor Mode Switch in RUN. The following conditions exist:

  • The North Reactor Feed Pump Turbine is in service.
  • SULCV is 25% OPEN.
  • SULCV M/A Station is in AUTO.
  • Interruptible Air Supply (IAS) to N21-F400A, N RFP Min Flow Line FCV has CRACKED AND is SEPARATING.
  • N RFP Suction Flow is RISING.
  • N RFP Suction Pressure has LOWERED to 550 psig and STABILIZED.

What will be the EFFECT of this failure on the Feedwater Level Control System, and what actions are REQUIRED?

With air pressure SLOWLY LOWERING, N21-F400A, N RFP Min Flow Line FCV will:

_____ A. OPEN, which will cause RPV Water Level to LOWER. It is required toINITIATE Standby Feedwater to maintain RPV Water Level.

_____ B. SHUT, which will cause RPV Water Level to RISE. It is required to LOWER the setpoint of C32-R620, STARTUP LCV CONTROLLER to maintain RPV Water Level.

_____ C. OPEN, which will NOT AFFECT RPV Water Level due to response of C32-R620, STARTUP LCV CONTROLLER. It is required OPERATE N21-F400A, N RFP Min Flow Line FCV using local manual handwheel operation to regulate minimum flow.

_____ D. SHUT, which will NOT AFFECT RPV Water Level due to response of C32-R620, STARTUP LCV CONTROLLER. It is required OPERATE N21-F400A, N RFP Min Flow Line FCV using local manual handwheel operation to regulate minimum flow.

Fermi 2 - 2008 NRC RO License Exam QUESTION 17 The plant is in the process of a plant startup after a refueling outage. Containment inerting is in progress with Oxygen content at 20% and going down slowly. In support of this evolution, Division 2 Standby Gas Treatment (SGTS) is running and is aligned to the Drywell.

A malfunction in the initiation logic causes a FALSE Low Reactor Water Level 2 signal to be initiated.

Based on this malfunction, what is the resultant effect on the Oxygen concentration in Drywell?

The Drywell Oxygen concentration will:

_____ A. LOWER at a faster rate due to the resulting automatic RISE in SGTS flow.

_____ B. REMAIN THE SAME because T4600-F402, DW 24 PURGE ISO VLV CLOSED.

_____ C. LOWER at a slower rate because T4600-F407, RBHVAC TO SGTS ISO VLV OPENED.

_____ D. RISE due to the increased flow from SGTS OPENING the Reactor Building to Torus Vacuum Breakers.

Fermi 2 - 2008 NRC RO License Exam QUESTION 18 The plant is operating at full power with Div 2 SGTS OUT OF SERVICE for maintenance.

The following indications occur:

  • 8D35, DIV I SGTS AIR FLOW STOPPED, alarms
  • T4600-F004A, Div 1 SGTS Exhaust Fan Inlet Isolation Damper, is CLOSED.

Which ONE of the following describes the affect of these conditions, if any, and the Emergency Operating Procedure Leg required to mitigate the condition, if any?

_____ A. NO CHANGE IN DIFFERENTIAL PRESSURE between the Reactor Building and the environs, NO EOP usage is required.

_____ B. INCREASING DIFFERENTIAL PRESSURE between the Reactor Building and the environs, which would FIRST result in an Entry Condition for the Secondary Containment Control EOP Leg.

_____ C. DECREASING DIFFERENTIAL PRESSURE between the Reactor Building and the environs, which would FIRST result in an Entry Condition for the Radiation Release Control EOP Leg.

_____ D. DECREASING DIFFERENTIAL PRESSURE between the Reactor Building and the environs, which would FIRST result in an Entry Condition for the Secondary Containment Control EOP Leg.

Fermi 2 - 2008 NRC RO License Exam QUESTION 19 When operating the 480V ESF Bus Tie Breakers for Live Bus Transfer, the 4160V ESF Buses are verified powered from their normal offsite power source.

Attempting to manually close these breakers with either bus powered from an EDG will result in _______________________________________.

_____ A. an overspeed trip of an EDG

_____ B. a sustained overload condition of the EDG

_____ C. no breaker closure due to a protective interlock

_____ D. equipment damage from paralleling out of phase

Fermi 2 - 2008 NRC RO License Exam QUESTION 20 Reactor Pressure is 900 psig and RHR Loop B is running in response to a valid LPCI initiation signal.

Which ONE of the following is the INDICATED flow on the Division II RHR System Flow Recorder?

_____ A. 0 gpm

_____ B. 3,000 gpm

_____ C. 10,000 gpm

_____ D. 20,000 gpm

Fermi 2 - 2008 NRC RO License Exam QUESTION 21 With a LOSS of Division 2 ESF 260/130 VDC Batteries AND Chargers, which ONE of the following will result?

_____ A. Breakers on 4160V Busses 65E and 13EC will lose control power.

_____ B. C11-F110B, Scram Pilot Air Header Backup Scram Valve, will actuate.

_____ C. MCC 72CF Feed will auto throw-over from 72C Pos 3C to 72F Pos 5C.

_____ D. Breakers CM and CF will not open on generator relaying or with the manual control switches on COP H11-P804.

Fermi 2 - 2008 NRC RO License Exam QUESTION 22 With the plant operating at full power, 10D72, BOP 260/130V BATTERY 2PC TROUBLE alarms. A COMPLETE LOSS of BOP DC has occurred.

IF operation of main turbine generator components is desired, which ONE of the following operator actions is REQUIRED under this condition?

_____ A. TRIP Breakers CM and CF using COP H11-P804 control switches.

_____ B. TRIP the Generator Field Breaker using COP H11-P804 control switch.

_____ C. TRIP Breakers CM and CF using LOCAL Emergency Trip pushbuttons.

_____ D. TRIP the Turbine Generator by ARMING AND DEPRESSING the Turbine Trip pushbutton on COP H11-P804.

Fermi 2 - 2008 NRC RO License Exam QUESTION 23 Following a Loss of Offsite Power, the grid has been restored, conditions are as follows:

  • EDG 11 is supplying ESF Bus 64B by way of EDG Bus 11EA and ESF-EDG Bus Tie Breaker B8.
  • Synchroscope Switch for ESF Bus 64B Normal Feeder Breaker B6 is ON.
  • ALL conditions are met for paralleling the EDG with Offsite Power.

When the B6 Breaker is CLOSED, the operating mode of EDG 11 will shift to the

______(1)______ mode.

Following breaker closure, the EDG 11 Governor must be immediately adjusted to PREVENT a(n) ______(2)______ condition.

_____ A. (1) Speed Droop (2) overload

_____ B. (1) Speed Droop (2) reverse power

_____ C. (1) Isochronous (2) overload

_____ D. (1) Isochronous (2) reverse power

Fermi 2 - 2008 NRC RO License Exam QUESTION 24 Which ONE of the following Air Compressors will DIRECTLY TRIP due to a Low Cooling Water Flow signal? (NOT a High Temperature signal.)

_____ A. D001, Control Air Compressor

_____ B. D002, Control Air Compressor

_____ C. D001, East Station Air Compressor

_____ D. D002, Center Station Air Compressor

Fermi 2 - 2008 NRC RO License Exam QUESTION 25 Interruptible Air System (IAS) Air Header Pressure supplied to the RBCCW Temperature Control Valve and Differential Pressure Control Valve is LOWERING due to an Air Header leak causing RBCCW Air Operated Valves to move towards their FAIL position.

How will Non Interruptible Air System (NIAS) Aftercooler Air Temperature be affected by this condition?

Aftercooler Air Temperature will:

_____ A. RISE due to Differential Pressure Control Valve failing SHUT.

_____ B. LOWER due to Differential Pressure Control Valve failing OPEN.

_____ C. RISE due to RBCCW Temperature Control Valve failing SHUT.

_____ D. LOWER due RBCCW Temperature Control Valve failing OPEN.

Fermi 2 - 2008 NRC RO License Exam QUESTION 26 With the plant operating at 100% power, when the following occurs:

  • 9D10, DIV 1 480 V ESS BUS 72C BKR TRIPPED, alarms.
  • CMC Switch for BUS 64C POS C11, 4160V FEED TO BUS 72C, indicates TRIPPED.

Given these indications, which ONE of the following correctly describes the impact on the Reactor Building Closed Cooling Water (RBCCW) Pumps?

_____ A. ONLY P4200-C001, North RBCCW Pump, has lost power.

_____ B. ONLY P4200-C003, South RBCCW Pump, has lost power.

_____ C. BOTH P4200-C001 AND P4200-C002, North and Center RBCCW Pumps, have lost power.

_____ D. BOTH P4200-C003 AND P4200-C002, South and Center RBCCW Pumps, have lost power.

Fermi 2 - 2008 NRC RO License Exam QUESTION 27 The reactor is at 5% power during a plant startup. While a control rod is being withdrawn, Rod Select Power is LOST.

Which ONE of the following describes the affect of this loss?

When Rod Select Power is LOST, the control rod is de-selected, and rod motion will:

_____ A. STOP, the control rod may eventually settle due to leakage but NO settle function will occur.

_____ B. STOP, the control rod settles to the next notch as the Settle Bus is automatically energized for 4.4 seconds.

_____ C. CONTINUE UNTIL the Rod Movement Control Switch is released; the control rod settles to the next notch as the Settle Bus is automatically energized for 4.4 seconds.

_____ D. CONTINUE ONLY if the Rod Out Notch Override Switch is positioned to Emergency In; the control rod may eventually settle due to leakage but NO settle function will occur.

Fermi 2 - 2008 NRC RO License Exam QUESTION 28 Following a transient, the following conditions exist:

  • RPV Water Level is 92 inches.
  • Reactor Pressure is 1000 psig.
  • Blowdown Mode of RWCU is being used as an Alternate Pressure Control System per EOP-1 RPV Control.

Which ONE of the following describes the FIRST AUTOMATIC response of RWCU valves to this condition?

_____ A. BEFORE piping failure occurs, the G3300-F033, RWCU Blowdown FCV will automatically close due to LOW Upstream Pressure.

_____ B. BEFORE piping failure occurs, the G3300-F033, RWCU Blowdown FCV will automatically close due to HIGH Downstream Pressure.

_____ C. AFTER piping failure occurs, G3352-F001 and G3352-F004, RWCU Containment Isolation Valves will automatically close due to HIGH Differential Flow.

_____ D. AFTER piping failure occurs, G3352-F001 and G3352-F004, RWCU Containment Isolation Valves will automatically close due to HIGH Area Temperature.

Fermi 2 - 2008 NRC RO License Exam QUESTION 29 The plant was operating at rated power when a manual reactor scram was inserted.

The following conditions exist:

  • The Reactor Mode Switch has been placed in SHUTDOWN.
  • The scram has NOT been reset.

What are the MINIMUM actions necessary to reset the Control Rod Drift indications on the Full Core Display (vertical section of panel H11-P603)?

(NOTE: The choices are arranged in MIMIMUM to MAXIMUM order.)

_____ A. MOMENTARILY rotate ROD DRIFT ALARM Switch to RESET.

_____ B. RESET the reactor scram. After Control Rods have settled at position 00, MOMENTARILY rotate ROD DRIFT ALARM Switch to RESET.

_____ C. RESET the reactor scram. SELECT each Control Rod with a drift alarm.

After Control Rod has settled at position 00, MOMENTARILY rotate ROD DRIFT ALARM Switch to RESET. REPEAT for each Control Rod with a drift alarm.

_____ D. SELECT each Control Rod with a drift alarm. MOMENTARILY place ROD MOVEMENT CONTROL Switch to OUT NOTCH. After Control Rod has settled at position 00, MOMENTARILY rotate ROD DRIFT ALARM Switch to RESET. REPEAT for each Control Rod with a drift alarm.

Fermi 2 - 2008 NRC RO License Exam QUESTION 30 Traversing In-core Probe (TIP) Channel A is INSERTED INTO THE CORE for calibration of Local Power Range Monitors (LPRMs). A TRIP of ONE Reactor Feed Pump occurs and RPV Water Level lowers to 160 inches before recovering to 195 inches.

Which of the following describes the AUTOMATIC TIP response?

_____ A. C51F001A, TIP Channel A Shear Valve FIRES, ISOLATING the drive mechanism.

_____ B. The INSERTED TIP detector WITHDRAWS into the shield chamber, AND C51F002A, TIP Channel A Ball Valve, CLOSES.

_____ C. The INSERTED TIP detector WITHDRAWS AND STOPS outboard of the Indexer, AND C51F002A, TIP Channel A Ball Valve, CLOSES.

_____ D. The TIP drive CONTINUES TO INSERT the detector to the Core Top Limit AND COMPLETES the TIP trace. The detector then WITHDRAWS into the shield chamber AND C51F002A, TIP Channel A Ball Valve, CLOSES

Fermi 2 - 2008 NRC RO License Exam QUESTION 31 With Reactor Power at 65%, a Control Rod is being WITHDRAWN.

Alarm 3D109, RBM UPSCALE/INOP alarms.

Which ONE of the following describes the TRIP SETPOINT of the Rod Block Monitor AND the EFFECT of this condition at this power level?

Considering the CURRENT Reactor Power, the TRIP SETPOINT of the Rod Block Monitor is:

_____ A. 107.2 %; a Control Rod Block WILL result.

_____ B. 107.2%; a Control Rod Block WILL NOT result.

_____ C. 112.2 %; a Control Rod Block WILL result.

_____ D. 112.2 %; a Control Rod Block WILL NOT result.

Fermi 2 - 2008 NRC RO License Exam QUESTION 32 While hoisting an irradiated fuel assembly, the SLACK CABLE indicator energizes and the fuel assembly FALLS to the Top Guide. Bubbles rise to the surface of the Reactor Cavity.

Based on the CURRENT conditions AND a single instruments condition, which ONE of the following alarms will ACTUATE AND INITIATE AUTOMATIC actions which limit the release of Airborne Radioactivity?

_____ A. 3D32, DIV I/II RB VENT EXH RADN MONITOR UPSCALE

_____ B. 3D31, DIV I / II FP VENT EXH RADN MONITOR UPSCALE

_____ C. 3D27, DIV I / II FP VENT EXH RADN MONITOR DNSCL / INOP

_____ D. 3D36, DIV I/II RB VENT EXH RADN MONITOR UPSCALE TRIP

Fermi 2 - 2008 NRC RO License Exam QUESTION 33 How are RPV Water Level Instruments affected by ISOLATING the Reference Leg Keep Fill supply from the Control Rod Drive System?

The concern associated with ISOLATING the Reference Leg Keep Fill supply is that INDICATED RPV Water Level:

_____ A. will be HIGHER than actual, due to Reference Leg Temperature RISING.

_____ B. will be HIGHER than actual, due to Reference Leg Pressure LOWERING.

_____ C. may be INACCURATE during depressurization due to gas accumulation in the Reference Leg.

_____ D. may be INACCURATE during accident conditions due to steam displacing water from the Reference Leg.

Fermi 2 - 2008 NRC RO License Exam QUESTION 34 With the plant operating at full power, when the following occurs:

  • 4D97, GENERATOR BUS COOLING TEMPERATURE HIGH alarms.
  • GENERATOR BUS CLG FAN DISCHARGE PRESSURE Red Light is ON.

Which ONE of the following failures is INDICATED by these conditions?

_____ A. 480 VAC Bus 72R has TRIPPED.

_____ B. ALL TBCCW Pumps have TRIPPED.

_____ C. Iso Phase Bus South Cooling Fan, S1200-C002, has TRIPPED.

_____ D. TBCCW Cooling Water Valve, P43-F209 has LOST Instrument Air.

Fermi 2 - 2008 NRC RO License Exam QUESTION 35 With the plant in COLD SHUTDOWN, the following conditions exist:

  • RPV Water Level is 197 inches, STABLE.

Which ONE of the following describes the EXPECTED effect, if any, on RPV Water Level when the LAST operating Condenser Pump TRIPS?

_____ A. RPV Water Level will NOT CHANGE, due to a redundant suction supply.

_____ B. RPV Water Level will LOWER, due a Low Suction Pressure TRIP of the operating CRD Pump.

_____ C. RPV Water Level will LOWER THEN RISE, due the effect of suction transfer on the operating CRD Pump.

_____ D. RPV Water Level will LOWER THEN RISE, due a Low Suction Pressure TRIP of the operating CRD Pump followed by a Reactor Scram.

Fermi 2 - 2008 NRC RO License Exam QUESTION 36 With the plant operating at full power, the following alarms and indications exist:

  • 6D21, E/W OFF GAS RECOMBINER TEMPERATURE HIGH/LOW alarms.
  • The West Off Gas Recombiner is in service and is indicating 805°F on N62-R815, Off Gas Components Temperature Recorder.

Which ONE of the following should be performed to control Off Gas Recombiner Temperature?

_____ A. VERIFY N62-F400, 18" Manifold Steam Supply TCV, is OPEN.

_____ B. VERIFY N62-F400, 18" Manifold Steam Supply TCV, is SHUT.

_____ C. VERIFY P73-P100, HWC Hydrogen Injection Rack is ISOLATED.

_____ D. VERIFY N62-N013A, Thermostatic Controlled Electric Heaters, at 600°F.

Fermi 2 - 2008 NRC RO License Exam QUESTION 37 Which ONE of the following is the power source for D11-K609A, Fuel Pool (EAST) Vent Exhaust Duct Radiation Monitor?

_____ A. Modular Power Unit 1

_____ B. Modular Power Unit 3

_____ C. Modular Power Unit 5

_____ D. Reactor Protection System Div 1

Fermi 2 - 2008 NRC RO License Exam QUESTION 38 The plant is in MODE 5 with movement of RECENTLY irradiated fuel in progress.

Due to a damper malfunction, Reactor Building Vacuum is 0 inches water gauge.

Which ONE of the following actions is REQUIRED by Technical Specifications?

_____ A. Suspend fuel movement IMMEDIATELY.

_____ B. Restore Secondary Containment Pressure WITHIN ONE HOUR.

_____ C. Start BOTH Divisions of Standby Gas Treatment System IMMEDIATELY.

_____ D. Verify at least ONE door is closed at each Reactor Building access WITHIN ONE HOUR.

Fermi 2 - 2008 NRC RO License Exam QUESTION 39 Following a trip of ONE Reactor Recirculation Pump, why is it necessary to limit operating Recirculation Pump Speed to 75%?

_____ A. To PREVENT Recirculation Pump runout due to reduced backpressure.

_____ B. To PREVENT excessive vibration of Reactor Vessel internal components.

_____ C. To REDUCE Reactor Power to within the Technical Specification Limit for Single Loop Operation.

_____ D. To REDUCE APRM Simulated Thermal Power Trip Setpoints until the setpoints are adjusted for Single Loop Operation.

Fermi 2 - 2008 NRC RO License Exam QUESTION 40 The reactor has scrammed due to a LOSS of Offsite Power.

ONLY EDGs 13 & 14 have started and loaded.

What is the SOURCE of power to the station DC loads?

_____ A. Div 1 Chargers are supplying Div 1 DC loads.

Div 2 Chargers are supplying Div 2 DC loads.

_____ B. Div 1 Batteries are supplying Div 1 DC loads.

Div 2 Chargers are supplying Div 2 DC loads.

_____ C. Div 1 Chargers are supplying Div 1 DC loads.

Div 2 Batteries are supplying Div 2 DC loads.

_____ D. Div 1 Batteries are supplying Div 1 DC loads.

Div 2 Batteries are supplying Div 2 DC loads.

Fermi 2 - 2008 NRC RO License Exam QUESTION 41 The plant is operating at full power when the following annunciators and indications are received:

  • 9D17, DIV I ESS 130 V BATTERY 2PA TROUBLE
  • 9D21, DIV I EDG SEQUENCER TROUBLE
  • 1D6, DIV I CSS LOGIC POWER FAILURE
  • 1D8, RHR LOGIC A 125 VDC BUS POWER FAILURE
  • 1D62, STM LK DET HPCI LOGIC POWER FAILURE
  • Loss of valve position indications for ALMOST all RCIC Valves
  • Loss of breaker control switch indications for ALL Div 1 ESF Bus breakers Based on THESE alarms and indications, select the correct DIAGNOSIS AND EFFECT, if any, on Division I EDGs ability to mitigate a Loss of Offsite Power.

_____ A. ONLY the Division I Batteries have been lost. Division I EDGs WILL NOT START if Offsite Power is LOST.

_____ B. ONLY the Division I Batteries have been lost. Division I EDGs WILL AUTO START if Offsite Power is LOST.

_____ C. BOTH Division I Battery Chargers AND BOTH Division I Batteries have been lost. Division I EDGs WILL NOT START if Offsite Power is LOST.

_____ D. BOTH Division I Battery Chargers AND BOTH Division I Batteries have been lost. Division I EDGs WILL AUTO START if Offsite Power is LOST.

Fermi 2 - 2008 NRC RO License Exam QUESTION 42 The plant is at 35% power when the turbine trips. The reactor will ___________________.

_____ A. SCRAM AND reactor pressure will INCREASE due to decay heat

_____ B. SCRAM AND reactor pressure will REMAIN CONSTANT due to BPV operation

_____ C. REMAIN OPERATING AND reactor power will INCREASE due to Feedwater Temperature change

_____ D. REMAIN OPERATING AND reactor power will DECREASE due to Feedwater Temperature change

Fermi 2 - 2008 NRC RO License Exam QUESTION 43 With the plant operating at 85% power, the in-service 52 inch Manifold Pressure Transmitter fails HIGH.

Which ONE of the following describes the affect of this failure, with no operator actions?

Reactor Pressure will:

_____ A. RISE until an automatic Reactor Scram occurs. Pressure will then be controlled by MANUAL operation of the Bypass Valves.

_____ B. RISE until an automatic Reactor Scram occurs. Pressure will then be controlled by AUTOMATIC operation of the Bypass Valves.

_____ C. LOWER until an automatic Reactor Scram occurs. Pressure will then be controlled by AUTOMATIC operation of the Bypass Valves.

_____ D. LOWER until an automatic Reactor Scram occurs. Pressure will then be controlled by AUTOMATIC operation of the Safety Relief Valves.

Fermi 2 - 2008 NRC RO License Exam QUESTION 44 The Control Room (CR) has become UNINHABITABLE. As a result, the plant has entered 20.000.19, SHUTDOWN FROM OUTSIDE THE CONTROL ROOM.

The transfer of certain CR controls to OUTSIDE the CR is needed to:

_____ A. allow rapid re-entry into the CR.

_____ B. preclude the effects of hot shorts.

_____ C. continue shutdown and cooldown.

_____ D. allow proper fire fighting response.

Fermi 2 - 2008 NRC RO License Exam QUESTION 45 Foreign material has partially covered the tube sheet at the inlet to the Stator Cooling Water Heat Exchanger.

Which ONE of the following describes the AUTOMATIC response of the system?

The Temperature Control Valve, throttling:

_____ A. Stator Water, will reposition to permit more flow to BYPASS the Heat Exchanger.

_____ B. Stator Water, will reposition to permit more flow THROUGH the Heat Exchanger.

_____ C. Turbine Building Closed Cooling Water, will reposition to permit more flow to BYPASS the Heat Exchanger.

_____ D. Turbine Building Closed Cooling Water, will reposition to permit more flow THROUGH the Heat Exchanger.

Fermi 2 - 2008 NRC RO License Exam QUESTION 46 The plant is operating at 100% power.

  • 7D53, STATION AIR HEADER PRESSURE LOW, alarms.
  • P50-R802, Station Air Header Pressure is 90 psig (lowering).

Which ONE of the following is the FIRST REQUIRED action per 20.129.01, Loss of Station and / or Control Air and the REASON for that action?

It is REQUIRED to start:

_____ A. ANY available Station Air Compressors to prevent the INBOARD Main Steam Isolation Valves from drifting shut.

_____ B. Div 1 AND Div 2 Control Air Compressors to prevent the INBOARD Main Steam Isolation Valves from drifting shut.

_____ C. ANY available Station Air Compressors to prevent the OUTBOARD Main Steam Isolation Valves from drifting shut.

_____ D. Div 1 AND Div 2 Control Air Compressors to prevent the OUTBOARD Main Steam Isolation Valves from drifting shut.

Fermi 2 - 2008 NRC RO License Exam QUESTION 47 The plant is in MODE 4, with the following conditions:

Due to a leak BETWEEN E1150-F008, RHR SDC Outboard Isolation Valve AND E1150-F009, RHR SDC Inboard Suction Isolation Valve, RPV Water Level lowered to 170 inches.

Why does 20.205.01, Loss of Shutdown Cooling, REQUIRE starting a Recirculation Pump?

While aligning:

_____ A. RHR Loop B for Shutdown Cooling operation, it is required to provide forced circulation through the core.

_____ B. RHR Loop B for Shutdown Cooling operation, it is required to remove decay heat to prevent an inadvertent mode change.

_____ C. Alternate Reactor Coolant Circulation and Decay Heat Removal, it is required to provide forced circulation through the core.

_____ D. Alternate Reactor Coolant Circulation and Decay Heat Removal, it is required to remove decay heat to prevent an inadvertent mode change.

Fermi 2 - 2008 NRC RO License Exam QUESTION 48 With the plant in MODE 5, REFUELING.

Which ONE of the following is the MINIMUM acceptable Water Level above the Reactor Vessel Flange, AND the reason for that limit?

_____ A. 20.5 feet provides adequate Iodine absorption following an accident.

_____ B. 20.5 feet provides adequate shielding of personnel during core alterations.

_____ C. 26.5 feet provides adequate Iodine absorption following an accident.

_____ D. 26.5 feet provides adequate shielding of personnel during core alterations.

Fermi 2 - 2008 NRC RO License Exam QUESTION 49 Which malfunction below, were it to occur during a LOCA, would be MOST LIKELY to cause the Primary Containment to exceed a Design Limit?

Consider each malfunction, independently, as the ONLY malfunction.

Assume that NO operator action is taken in response to the malfunction.

_____ A. Safety Relief Valve B2104-F013H has a break in its Tailpipe.

_____ B. SST 65 TRIPS and Emergency Diesel Generator 13 FAILS TO START.

_____ C. ALL Drywell Spray Valves FAIL TO OPEN when attempting to initiate Drywell Spray.

_____ D. ALL Torus to Drywell Vacuum Breaker Check Valves FAIL TO OPEN when Drywell Spray is in operation.

Fermi 2 - 2008 NRC RO License Exam QUESTION 50 Following a Main Steam Line Break, outside of containment, AND an automatic reactor scram, the following conditions exist:

  • Reactor Pressure is 1115 psig, LOWERING.
  • RPV Water Level lowered to 150 inches AND recovered.

Which ONE of the following describes how Decay Heat will be removed from the reactor WITHOUT operator action?

_____ A. Safety Relief Valves will AUTOMATICALLY OPEN.

_____ B. Main Turbine Bypass Valves will AUTOMATICALLY OPEN.

_____ C. Reactor Core Isolation Cooling (RCIC) will AUTOMATICALLY START.

_____ D. Reactor Feedwater Pump Turbines will OPERATE on MINIMUM FLOW.

Fermi 2 - 2008 NRC RO License Exam QUESTION 51 Following a plant transient and a reactor scram, the following conditions exist:

  • RHR Pump A is injecting with ONE Pump at 13,500 gpm.
  • Div 1 Core Spray is injecting with TWO Pumps at 7,750 gpm.
  • Torus Pressure is 5.5 psig.
  • Torus Level is -60 inches.
  • Torus Temperature is 205°F.
  • RPV Pressure is 85 psig (steady).
  • RPV Water Level is -10 inches (rising).

The Nuclear Operator in the reactor building calls to report the RHR and Core Spray Pumps are rattling.

To maintain long term injection capability, which of the following is the MAXIMUM injection permissible?

_____ A. Core Spray Div 1 Flow - 7,000 gpm RHR Flow - 11,000 gpm

_____ B. Core Spray Div 1 Flow - 7,000 gpm RHR Flow - 12,500 gpm

_____ C. Core Spray Div 1 Flow - 8,000 gpm RHR Flow - 11,000 gpm

_____ D. Core Spray Div 1 Flow - 8,000 gpm RHR Flow - 12,500 gpm

Fermi 2 - 2008 NRC RO License Exam QUESTION 52 E2101-C001A, Div 1 Core Spray Pump is being operated in Full Flow Test, when a transient occurs resulting in the following plant conditions:

  • Drywell Pressure is 1.48 psig.
  • RPV Water Level is 30 inches.
  • Reactor Pressure is 520 psig.

Which ONE of the following describes the status of the OTHER Division 1 Core Spray Pump, E2101-C001C?

Core Spray Pump C:

_____ A. REMAINS in standby, because it has NOT received a start signal.

_____ B. has STARTED and IS NOT injecting because a common Full Flow Test Valve is OPEN.

_____ C. has STARTED and IS NOT injecting because a permissive condition has NOT been satisfied.

_____ D. has STARTED and IS INJECTING because ALL permissive conditions HAVE BEEN satisfied.

Fermi 2 - 2008 NRC RO License Exam QUESTION 53 The plant is in an emergency condition and the following Primary Containment parameters exist:

  • Torus Water Level is 0 inches.
  • Drywell Temperature is 275°F.
  • Drywell Pressure is 4 psig.
  • Torus Pressure is 3 psig.

NOTE: See attached reference.

If Drywell Sprays were INITIATED, which ONE of the following will occur?

_____ A. The Torus to Drywell Vacuum Breakers will NOT operate due to low Differential Pressure.

_____ B. Convective Cooling WILL RESULT in Nitrogen being drawn into the Drywell by operation of the Torus to Drywell Vacuum Breakers.

_____ C. The Torus to Drywell Vacuum Breakers capacity WILL BE EXCEEDED and damage to the Primary Containment Vent system will occur.

_____ D. Evaporative Cooling WILL RESULT in Oxygen being drawn in to the Torus by operation of the Reactor Building to Torus Vacuum Breakers.

Fermi 2 - 2008 NRC RO License Exam QUESTION 54 RCIC is being used to control RPV Water Level with its suction aligned to the Torus when a leak in the Torus occurs.

Which ONE of the following will occur FIRST as Torus Level continues to lower?

_____ A. RCIC will TRIP due to Low Suction Pressure.

_____ B. RCIC will TRIP due to Low Cooling Water Flow.

_____ C. RCIC suction will AUTO TRANSFER to the CST due to Low Suction Pressure.

_____ D. RCIC suction will AUTO TRANSFER to the CST due to Low Torus Water Level.

Fermi 2 - 2008 NRC RO License Exam QUESTION 55 Per the Emergency Operating Procedure Bases, what is the significance of Torus Water Temperature reaching 120°F while Reactor Power is 10 %?

NOTE: See attached reference

_____ A. If Emergency Depressurization is conducted at this point, the Heat Capacity Limit will NOT be exceeded.

_____ B. If Torus Water Temperature continues to increase AND is being used as the injection source, Reactor Power will LOWER.

_____ C. If Standby Liquid is injected at this point, Hot Shutdown Boron Weight will be injected BEFORE the Heat Capacity Limit is reached.

_____ D. If ALL injection to the RPV is Terminated and Prevented at this point, RPV Water Level will remain ABOVE TAF when Reactor Power reaches 3%.

Fermi 2 - 2008 NRC RO License Exam QUESTION 56 Why does 29.100.01, Radioactivity Release Control, Sheet 5, permit restarting isolated HVAC systems outside Secondary Containment?

Restarting HVAC Systems:

_____ A. provides DILUTION to lower the radioactivity concentration being released.

_____ B. ensures ACCESSIBILITY is maintained inside the Secondary Containment.

_____ C. provides FILTRATION AND ADSORPTION of radioactivity and an elevated release path.

_____ D. preserves building accessibility AND discharges radioactivity through an elevated, monitored release point.

Fermi 2 - 2008 NRC RO License Exam QUESTION 57 Following a Loss of Offsite Power, a fire is in progress.

RCIC has started WITHOUT an initiation signal.

Which ONE of the following actions is REQUIRED and WHY?

Complete the plant shutdown using:

_____ A. RCIC; because NO operator action is required to achieve injection.

_____ B. Standby Feedwater; because RCIC CANNOT be relied upon as a makeup source and is required to be disabled.

_____ C. HPCI; because RCIC CANNOT be relied upon as a makeup source and is required to remain running as a backup source.

_____ D. HPCI; because RCIC AND Standby Feedwater CANNOT be relied upon as a makeup source and are required to remain running as a backup source.

Fermi 2 - 2008 NRC RO License Exam QUESTION 58 Following a Grid Disturbance, conditions are as follows:

  • Generator Power is 1160 Mwe.
  • Reactive Power is 360 MVAR (LAG).

The System Dispatcher has requested additional reactive load support to maintain grid voltage.

Considering the Enrico Fermi Generator 2 Capability Curve, which ONE of the following actions is REQUIRED?

_____ A. RAISE Recirculation Flow to increase the Reactive Load on the Generator.

_____ B. LOWER Recirculation Flow, because Generator Load limits have been EXCEEDED.

_____ C. MANUALLY RAISE the Voltage Regulator setting, to increase the Reactive Load on the Generator.

_____ D. MANUALLY LOWER the Voltage Regulator setting, because Reactive Load limits have been EXCEEDED.

Fermi 2 - 2008 NRC RO License Exam QUESTION 59 The plant is at 100% when a Main Turbine Trip occurred.

Which ONE of the following describes the plant conditions that will CAUSE a Main Turbine Trip AND the BASIS for that trip?

The Main Turbine has tripped due to:

_____ A. TWO of the Narrow Range Level instruments having a level of 214". This will prevent the erosion of the Main Turbine Blades.

_____ B. the SELECTED Narrow Range Level instrument having a level of 214".

This will prevent the erosion of the Main Turbine Blades.

_____ C. TWO of the Narrow Range Level instruments having a level of 214".

This will prevent the erosion of the Main Steam piping and Main Control Valve seats.

_____ D. the SELECTED Narrow Range Level instrument having a level of 214".

This will prevent the erosion of the Main Steam piping and Main Control Valve seats.

Fermi 2 - 2008 NRC RO License Exam QUESTION 60 With the plant operating at full power, the following conditions exist:

  • A Nitrogen Regulator failure caused Drywell Pressure to rise to 1.75 psig.
  • NO RPS actuation occurred.

Assuming ONLY these conditions, which ONE of the following describes the resulting trend of Drywell Temperature?

Drywell Temperature will:

_____ A. REMAIN CONSTANT because ALL Drywell Cooling Fans are unaffected.

_____ B. RISE due to the Two Speed Drywell Cooling Fans shifting from FAST to OFF.

_____ C. RISE due to the Two Speed Drywell Cooling Fans shifting from FAST to SLOW speed.

_____ D. LOWER due to the Two Speed Drywell Cooling Fans shifting from SLOW to FAST speed.

Fermi 2 - 2008 NRC RO License Exam QUESTION 61 The plant is operating at full power and the following conditions exist:

  • 8D41, Div 1 DW Temperature High alarms.
  • 14 DW Cooling Fans are operating.
  • T47-R803A, point 16 indicates > 185°F.
  • P42-K803, RBCCW to TCV P42-F400 CTRLR, valve position indicates 100%.
  • Lake Temperature is 71ºF.

The AVERAGE Drywell Temperature has risen from 132°F to 135°F during the last 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Which ONE of the following actions is appropriate?

_____ A. Place RBCCW Supplemental Cooling in service.

_____ B. SHIFT DW Cooling Fans 1, 2, 3, and 4 to LOW speed per 23.415, Drywell Cooling System.

_____ C. Operate ALL available Drywell Cooling per 29.100.01, Sheet 2, Primary Containment Control.

_____ D. Manually INITIATE EECW and EESW Systems per 20.127.01, Loss of Reactor Building Closed Cooling Water System.

Fermi 2 - 2008 NRC RO License Exam QUESTION 62 The reactor is in MODE 2, with Reactor Pressure at 800 psig, when the following occurs:

  • The operating CRD pump TRIPS.

What action is REQUIRED in accordance with procedure 20.106.01, CRD Hydraulic System Failure?

_____ A. PLACE the Mode Switch in SHUTDOWN.

_____ B. IMMEDIATELY START the standby CRD pump.

_____ C. Within 20 minutes, CLOSE C1100-F034, CRD Charging Water Header Isolation Valve.

_____ D. Within 20 minutes, START at least one CRD pump AND FULLY INSERT Control Rod 30-27.

Fermi 2 - 2008 NRC RO License Exam QUESTION 63 Which ONE of the following is the BASIS for the Main Steam Tunnel HIGH Temperature Isolation?

The Main Steam Tunnel High Temperature Isolation will:

_____ A. LIMIT the escape of radioactivity from the MSL Tunnel to the Reactor Building HVAC system.

_____ B. PREVENT exceeding the Environmental Qualification temperature limits on the MSIV control solenoids.

_____ C. PROTECT the integrity of the Secondary Containment AND ensure the continued operability of safe shutdown equipment.

_____ D. MINIMIZE radioactive releases to the environment AND limit the inventory loss from the reactor under all accident conditions.

Fermi 2 - 2008 NRC RO License Exam QUESTION 64 The plant is operating at 100% power, when the following alarms and indications occur:

  • 16D6, REAC/AUX BLDG FIRST FLOOR HIGH RADN alarms.
  • H11-P816 panel indicates an ALARM on Channel 12, First Floor RB Neutron Monitoring Equipment Room Which ONE of the following plant CONDITIONS would be CONSISTENT with THESE INDICATIONS?

_____ A. A steam leak has developed in RCIC piping.

_____ B. Spent Fuel Handling operations are in progress.

_____ C. Traversing In-core Probe movement is in progress.

_____ D. SRM detectors are being withdrawn for post maintenance testing.

Fermi 2 - 2008 NRC RO License Exam QUESTION 65 29.100.01, Sheet 5, Secondary Containment and Rad Release, directs operating available sump pumps whenever Secondary Containment area or sump levels exceed their Max Normal Operating levels.

What is the BASIS for this action?

This action is BASED on:

_____ A. MINIMIZING the spread of contamination within the Secondary Containment.

_____ B. MAINTAINING water levels below the point at which equipment required for safe shutdown will fail.

_____ C. PREVENTING the uncontrolled release of liquid radioactive effluents from the Secondary Containment.

_____ D. CONTAINING leakage from a primary system within systems design for storage of radioactive liquids.

Fermi 2 - 2008 NRC RO License Exam QUESTION 66 During a Refuel Outage, with the Reactor Mode Switch in REFUEL, the following conditions exist:

Which ONE of the following conditions caused the alarm?

The Refuel Bridge is:

_____ A. over the core with the Grapple FULL UP and the Trolley Hoist is NOT LOADED.

_____ B. over the core with the Grapple FULL DOWN and the Trolley Hoist is NOT LOADED.

_____ C. NOT over the core with the Grapple FULL UP and the Trolley Hoist is LOADED.

_____ D. NOT over the core with the Grapple FULL DOWN and the Trolley Hoist is LOADED.

Fermi 2 - 2008 NRC RO License Exam QUESTION 67 After a ONE WEEK VACATION, a Nuclear Station Operator is scheduled to work the following schedule:

Sunday Monday Tuesday Wednesday Thursday Friday Saturday OFF 12 hrs 12 hrs 12 hrs 12 hrs 8 hrs OFF Per MGA 17, Working Hour Limits, which ONE of the following is the ADDITIONAL hours this person can be scheduled to work WITHOUT exceeding any administrative limits?

_____ A. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> on Tuesday

_____ B. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> on Thursday

_____ C. 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> on Friday

_____ D. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on Sunday

Fermi 2 - 2008 NRC RO License Exam QUESTION 68 The plant is operating at 50% power. What is the MAXIMUM amount of TOTAL Reactor Coolant System Leakage allowed for continued plant operation?

_____ A. 2 gpm

_____ B. 5 gpm

_____ C. 25 gpm

_____ D. 50 gpm

Fermi 2 - 2008 NRC RO License Exam QUESTION 69 Which ONE of the following is required when a visible break CANNOT be used to disconnect a piece of equipment from its power supply?

_____ A. Independent verification of the danger tag.

_____ B. An approved grounding device installed on the load side.

_____ C. A safety observer is stationed for all work performed on the equipment.

_____ D. An approved blocking device and a method for determining that power is removed.

Fermi 2 - 2008 NRC RO License Exam QUESTION 70 With the plant operating at 80% power, at 0800 on February 8, 2008. EDG 11 is discovered INOPERABLE.

Which ONE of the following describes LATEST TIME that SR 3.8.1.1, Verification of Offsite Circuits, must be completed, after the EDG is initially discovered inoperable, WITHOUT entering into a condition which requires a unit shutdown?

_____ A. 0900 on February 8, 2008

_____ B. 1600 on February 8, 2008

_____ C. 1800 on February 8, 2008

_____ D. 0800 on February 9, 2008

Fermi 2 - 2008 NRC RO License Exam QUESTION 71 With core alterations in progress, a fuel assembly contacts the core top guide, resulting in 16D1, RB REFUELING AREA FIFTH FLOOR HIGH RADN alarm.

Indications are as follows:

  • ARM 15, RB5 Spent Fuel Pool Area Radiation Monitor indicates 25 mr/hr, RISING.
  • ARM 17, RB5 Refuel Floor Lo Range Area Radiation Monitor indicates 30 mr/hr, RISING.

Which ONE of the following is the FIRST Control Room action required?

_____ A. Sound the Plant Area alarm.

_____ B. Verify a complete PCIS Group 3 Isolation.

_____ C. Verify the Standby Gas Treatment System starts.

_____ D. Shutdown the Emergency Makeup Fan of the non-operating CCHVAC division.

Fermi 2 - 2008 NRC RO License Exam QUESTION 72 Which ONE of the following conditions will cause the Division 1 AXM to AUTOMATICALLY SHIFT from STANDBY to OPERATE?

_____ A. Automatic start of Division 1 SGTS.

_____ B. Automatic shift of CCHVAC to the Recirc Mode.

_____ C. High Radiation Trip of Div 1 or 2 Containment High Range Radiation Monitors.

_____ D. High Radiation Alarm on the Div 1 SGTS SPING Medium Range Noble Gas Channel.

Fermi 2 - 2008 NRC RO License Exam QUESTION 73 With the plant operating at 100% power, the following conditions exist:

  • Drywell Pressure increased to 1.75 psig.
  • NO actuations occurred.

With these conditions, which ONE of the following actions is REQUIRED?

It is REQUIRED to:

_____ A. Place the Reactor Mode Switch in SHUTDOWN AND enter Sheet 1, RPV Control ONLY.

_____ B. Initiate Standby Liquid Control AND enter Sheet 1A, RPV Control- ATWS AND Sheet 2, Primary Containment Control.

_____ C. Place the Reactor Mode Switch in SHUTDOWN AND enter Sheet 1, RPV Control AND Sheet 2, Primary Containment Control.

_____ D. Place the Reactor Mode Switch in SHUTDOWN AND enter Sheet 1A, RPV Control- ATWS AND Sheet 2, Primary Containment Control.

Fermi 2 - 2008 NRC RO License Exam QUESTION 74 Which ONE of the following is an IMMEDIATE Action for a CONFIRMED fire in accordance with 20.000.22, Plant Fires?

_____ A. Identify the type or class of fire.

_____ B. Announce the fire alarm over the Hi-Com system.

_____ C. Dispatch an operator to verify the magnitude and location of the fire.

_____ D. Establish communications between the Control Room and the Fire Brigade.

Fermi 2 - 2008 NRC RO License Exam QUESTION 75 Per EP-290, Emergency Notifications, when the State Emergency Operations Center (SEOC) is functional, how are Emergency Communications affected?

After the State Emergency Operations Center is FUNCTIONAL, the Fermi 2 Communicator is:

_____ A. NO LONGER required to make notifications to Canada.

_____ B. NO LONGER required to make notifications to Monroe and Wayne counties.

_____ C. NO LONGER required to make notifications to the Nuclear Regulatory Commission.

_____ D. STILL REQUIRED to notify Monroe and Wayne counties, the State of Michigan, and Canada.

Fermi 2 - 2008 NRC SRO License Exam QUESTION 76 With the plant in MODE 4, Cold Shutdown, which ONE of the following describes the MINIMUM DC Sources REQUIRED OPERABLE and the reason for that requirement?

_____ A. ONE subsystem consisting of TWO 130 VDC Batteries AND TWO Chargers. This will provide power necessary to mitigate a Design Basis Loss of Coolant Accident.

_____ B. ONE subsystem consisting of TWO 130 VDC Batteries AND TWO Chargers. This will provide power necessary to mitigate an inadvertent Reactor Vessel Draindown.

_____ C. TWO subsystems consisting of TWO 130 VDC Batteries AND TWO Chargers. This will provide power necessary to mitigate a Design Basis Loss of Coolant Accident.

_____ D. TWO subsystems consisting of TWO 130 VDC Batteries AND TWO Chargers. This will provide power necessary to mitigate an inadvertent Reactor Vessel Draindown.

Fermi 2 - 2008 NRC SRO License Exam QUESTION 77

  • The plant was operating at full power when a fire in the Cable Spreading Room (Zone 11) occurred.
  • A Loss of Offsite Power has occurred resulting in an EOP entry condition due to RPV Water Level.
  • This transient has been complicated by the spurious operation of numerous components and smoke in the control room.

Which ONE of the following procedures contains measures which will MOST EFFECTIVELY mitigate the effects of SPURIOUS operation of components?

_____ A. 29.100.01, Sheet 1, RPV CONTROL

_____ B. 20.300.OFFSITE, LOSS OF OFFSITE POWER

_____ C. 20.000.19, SHUTDOWN FROM OUTSIDE THE CONTROL ROOM

_____ D. 20.000.18, SHUTDOWN FROM THE DEDICATED SHUTDOWN PANEL

Fermi 2 - 2008 NRC SRO License Exam QUESTION 78 During an accident condition AFTER Emergency RPV Depressurization, the following conditions exist:

  • RPV Pressure is 50 psig.
  • Drywell Temperature is 250°F, RISING.
  • Drywell Pressure is 42 psig, RISING.
  • Torus Pressure is 42.5 psig, RISING.

Which ONE of the following actions is REQUIRED?

_____ A. INITIATE Drywell Sprays per 29.100.01 Sheet 2, PRIMARY CONTAINMENT CONTROL.

_____ B. VENT the Drywell IRRESPECTIVE of offsite radioactivity release limits per 29.ESP.07 Section 3.0.

_____ C. VENT the Torus REMAINING WITHIN offsite radioactivity release limits per 29.ESP.07 Section 2.0.

_____ D. EXIT 29.100.01 Sheet 2, PRIMARY CONTAINMENT CONTROL AND enter the RPV Flooding Procedure.

Fermi 2 - 2008 NRC SRO License Exam QUESTION 79 An ATWS is in progress following a condenser boot rupture, with plant conditions as follows:

  • Reactor Power is 8%.
  • RPV Water Level is 150 inches.
  • APRM DOWNSCALE Lights are NOT lit.
  • Suppression Pool Temperature is 118°F.
  • Low-Low Set is controlling reactor pressure at 1020 psig.

If the above parameters remain CONSTANT, which ONE of the following is the HIGHEST RPV Water Level that may be MAINTAINED?

_____ A. +214 inches

_____ B. +114 inches

_____ C. 0 inches

_____ D. -25 (minus 25) inches

Fermi 2 - 2008 NRC SRO License Exam QUESTION 80 Following a transient, the following conditions exist:

  • RPV Water Level is 16 inches, LOWERING 2 inches per minute.
  • Reactor Pressure is 1000 psig.
  • Torus Water Level is -38 inches, LOWERING 2 inches per minute.

Which ONE of the following actions should be ordered FIRST?

_____ A. DEPRESSURIZE the reactor by opening Turbine Bypass Valves.

_____ B. DEPRESSURIZE the reactor by opening FIVE Safety Relief Valves.

_____ C. SHUTDOWN the HPCI Turbine to prevent direct pressurization of the Torus.

_____ D. PREVENT Core Spray AND LPCI Pump Injection, because injection is NOT needed.

Fermi 2 - 2008 NRC SRO License Exam QUESTION 81 While operating the reactor in MODE 1, a restriction of cooling water flow through a fuel bundle causes fuel clad overheating and fission product release into the reactor coolant. The following plant conditions exist:

  • Reactor Power is 18%.
  • Reactor Pressure is 940 psig.
  • RPV Water Level is 100 inches.
  • Site Boundary Release corresponds to 4.90 REM to an Adults Thyroid AND is RISING.

Given these conditions, which ONE of the following actions is REQUIRED?

_____ A. Use the Safety Relief Valves to perform a reactor cool down at LESS THAN a 90°F/hr rate.

_____ B. Use HPCI and RCIC in the Test Mode to perform a reactor cool down at LESS THAN a 90°F/hr rate.

_____ C. Use the Safety Relief Valves to perform a reactor cool down at GREATER THAN a 90°F/hr rate.

_____ D. Use Main Turbine Bypass Valves to perform a reactor cool down at GREATER THAN a 90°F/hr rate.

Fermi 2 - 2008 NRC SRO License Exam QUESTION 82 At time 1200, a fire was reported in Bus 64B, position B10, the power supply breaker for E2101-C001A Division 1 Core Spray Pump A. At time 1215, the Fire Brigade has requested that the Bus be de-energized prior to attempting extinguishment.

Which ONE of the following Emergency Action Levels (EAL) is REQUIRED, and what is the CRITERIA for that EAL?

It is REQUIRED to DECLARE an:

_____ A. ALERT, due a fire inside the PROTECTED AREA for 15 minutes.

_____ B. ALERT, due to a fire involving SAFE SHUTDOWN EQUIPMENT.

_____ C. UNUSUAL EVENT, due a fire inside the PROTECTED AREA for 15 minutes.

_____ D. UNUSUAL EVENT, due to a fire involving SAFE SHUTDOWN EQUIPMENT.

Fermi 2 - 2008 NRC SRO License Exam QUESTION 83 The plant is operating at full power. RPV Water Level is 196 inches. Flow Input from the B Feedwater Line has FAILED LOW.

Which ONE of the conditions will RESULT, and what action will be REQUIRED?

ACTUAL RPV Water Level WILL:

_____ A. LOWER until a Reactor Scram occurs. It is required to enter 29.100.01 Sheet 1, RPV Control and restore RPV Water Level.

_____ B. RISE until BOTH Reactor Feedwater Pump Turbines TRIP. It is required to enter 23.107.01, Loss of Feedwater or Feedwater Control.

_____ C. STABILIZE at a HIGHER LEVEL. It is required to restore RPV Water Level MANUALLY per 23.107.01, Loss of Feedwater or Feedwater Control.

_____ D. REMAIN UNCHANGED in Forced Single Element control. It is required to place the Level Control Mode Switch in 1 ELEM per 23.107, Reactor Feedwater and Condensate Systems.

Fermi 2 - 2008 NRC SRO License Exam QUESTION 84 Fermi-2 is starting up following a Refueling Outage. HPCI TESTING is in progress.

  • Reactor Power is 16%.
  • Drywell Pressure is 1.25 psig.
  • Torus Pressure is 0.10 psig.
  • Torus Water Average Temperature is 98°F.
  • Drywell Average Air Temperature is 155°F.

Based upon the ABOVE conditions, which parameter listed BELOW REQUIRES a Technical Specification Action Statement to be ENTERED?

_____ A. Torus Pressure

_____ B. Drywell Pressure

_____ C. Drywell Temperature

_____ D. Torus Water Temperature

Fermi 2 - 2008 NRC SRO License Exam QUESTION 85 During the execution of 29.100.01 Sheet 5, Secondary Containment and Radiation Release, the operability of equipment required to perform a safe shutdown is assured by which ONE of the following?

IF the Radiation Level(s) is(are) increasing in the Reactor Building SE Quad, Emergency Depressurization is REQUIRED when the:

_____ A. Radiation Level in any ONE AREA EXCEEDS the MAX NORMAL value.

_____ B. Radiation Levels in MORE THAN ONE AREA EXCEED the MAX SAFE value.

_____ C. Radiation Levels in MORE THAN ONE AREA EXCEED the MAX NORMAL value.

_____ D. Radiation Level in any ONE AREA is CONFIRMED by a MAX SAFE Area Temperature OR MAX SAFE Water Level in the SAME AREA.

Fermi 2 - 2008 NRC SRO License Exam QUESTION 86 The plant is in MODE 2, STARTUP, following a Refueling Outage. Engineering has determined that ALL the MSIVs have had unqualified valve control manifolds installed during outage maintenance which will cause LONGER stroke times over the cycle.

Which ONE of the following is the MINIMUM Required Action AND the REASON for that action, according to Technical Specifications?

_____ A. NO ACTIONS are required, because Primary Containment Isolation capability is NOT REQUIRED OPERABLE in MODE 2.

_____ B. It is REQUIRED to SHUT ONLY ONE MSIV in each Main Steam Line.

The basis for this action is to limit the severity of the MAXIMUM Reactor Pressure spike following a spurious MSIV closure at power.

_____ C. It is REQUIRED to SHUT ONLY ONE MSIV in EACH Main Steam Line.

The basis for this action is to limit the MAXIMUM Radiological Release following a Design Basis Accident.

_____ D. It is REQUIRED to SHUT BOTH MSIVs in ALL Main Steam Lines.

The basis for this action is to limit the MAXIMUM Radiological Release following a Design Basis Accident.

Fermi 2 - 2008 NRC SRO License Exam QUESTION 87 Following a Loss of Offsite Power, the following conditions occur at the listed time:

  • 12:01 ONLY EDG 14 has started and loaded.
  • 12:05 Drywell Pressure is 1.0 psig and STABLE.
  • 12:10 RPV Water Level is 64 inches, LOWERING 4 inches per minute.

Given these conditions, which ONE of the following describes the RESPONSE of the Automatic Depressurization System (ADS), AND the operator ACTIONS which should be ordered?

ADS WILL OPEN Safety Relief Valves at:

_____ A. 12:20. It is required to INHIBIT ADS PRIOR to automatic actuation AND MANUALLY Emergency Depressurize the reactor at a specified RPV Water Level.

_____ B. 12:27. It is required to INHIBIT ADS PRIOR to automatic actuation AND MANUALLY Emergency Depressurize the reactor at a specified RPV Water Level.

_____ C. 12:20. It is required to VERIFY ADS automatically ACTUATES AND MAXIMIZE Injection with Low Pressure ECCS Pumps and restore RPV Water Level to a specified Water Level Band.

_____ D. 12:27. It is required to VERIFY ADS automatically ACTUATES AND MAXIMIZE Injection with Low Pressure ECCS Pumps and restore RPV Water Level to a specified Water Level Band.

Fermi 2 - 2008 NRC SRO License Exam QUESTION 88 A reactor startup is in progress using GOP 22.000.02, PLANT STARTUP TO 25% POWER.

The following plant conditions exist:

  • 3D63, IRM UPSCALE has alarmed on IRMs which are still on Range 3.

Which ONE of the following actions SHOULD be directed?

_____ A. Up-range the remaining IRMs to clear the ROD BLOCK so rod withdrawal can resume.

_____ B. Up-range remaining IRMs to Range 4 AND allow the power rise to continue at the current rate.

_____ C. Insert rods AND lower power below the ROD BLOCK setpoint for the remaining IRM Channels.

_____ D. Up-range remaining IRMs to Range 4, THEN IMMEDIATELY Insert rods, to slow down the power rise.

Fermi 2 - 2008 NRC SRO License Exam QUESTION 89 The plant is operating at 100% power, when the following occurs:

  • 4D91, ELECTRIC GOVERNOR TROUBLE Alarms.
  • Generator Power is 1150 Mwe, RISING.
  • Reactor Pressure is 1005 psig, LOWERING.

With THESE conditions, Average Power Range Monitors WILL BE:

_____ A. RISING; it is required to MANUALLY SCRAM the reactor to avoid an APRM Simulated Thermal Power scram.

_____ B. RISING; it is required to LOWER BOTH RR MG Set Speeds to avoid an APRM Simulated Thermal Power scram.

_____ C. LOWERING; it is required to VERIFY a successful transfer to the standby Pressure Regulator AND RAISE Pressure Setpoint by 3.5 psig.

_____ D. LOWERING; it is required to PLACE the Reactor Mode Switch in SHUTDOWN to avoid a Main Steam Isolation Valve Closure scram.

Fermi 2 - 2008 NRC SRO License Exam QUESTION 90 Following a Loss of Coolant Accident (LOCA) with an electrical plant malfunction, plant conditions are as follows:

  • RPV Water Level is 35 inches, LOWERING.
  • Reactor Pressure is 250 psig, LOWERING.
  • 345 kV Mat Power Indicating Lights are OFF.
  • EDG 13 is LOADED carrying Bus 65E.
  • Bus 65F and Bus 14ED Power Indicating Lights are OFF.
  • Bus 72F and Bus 72ED Power Indicating Lights are OFF.

Which ONE of the following lists the electrical procedure which SHOULD be executed to provide MAXIMUM Low Pressure ECCS Injection to support 29.100.01, Sheet 1, RPV Control actions?

_____ A. 20.300.65F, Loss of Bus 65F, due to Bus 65F being LOCKED OUT.

_____ B. 20.300.72F, Loss of Bus 72F, due to Bus 72F being LOCKED OUT.

_____ C. 20.307.01, Emergency Diesel Generator Failure, due to EDG 14 failing to start.

_____ D. 20.300.SBO, Loss of Offsite and Onsite Power, due to a combination of electrical malfunctions.

Fermi 2 - 2008 NRC SRO License Exam QUESTION 91 With the plant operating at full power, the following conditions exist:

  • ALL available Torus Cooling was initiated.

Which ONE of the following describes how Torus Cooling operation will affect Torus Temperature?

Operating ALL available Torus Cooling with ONE FULLY OPEN Safety Relief Valve will:

_____ A. LOWER Torus Water Temperature below the LOWEST Technical Specification LCO value.

_____ B. MAINTAIN Torus Water Temperature at a CONSTANT temperature until the Safety Relief Valve is successfully CLOSED.

_____ C. NOT MAINTAIN Torus Water Temperature BELOW the Technical Specification LCO value which requires a Reactor Shutdown.

_____ D. MAINTAIN Torus Water Temperature BELOW the Technical Specification LCO value applicable when testing which adds heat to the Torus is in progress.

Fermi 2 - 2008 NRC SRO License Exam QUESTION 92 The plant is operating at full power.

The following Drywell Floor and Equipment Drain Sump Effluent Integrator readings (total gallons pumped) have been noted for the past 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:

Time Floor Drain Equipment Drain Leak Rate Leak Rate Integrator Integrator Floor (gpm) Equipment (gpm) 0000 89321 27861 2.3 16.4 0800 90543 35805 2.54 16.55 1600 92079 44181 3.2 17.45 0000 94383 52821 4.8 18.0 With these conditions, which ONE of the following is CORRECT?

_____ A. NO Drywell Leakage limit has been exceeded.

_____ B. TOTAL LEAKAGE has exceeded the leakage limit.

_____ C. IDENTIFIED LEAKAGE has exceeded the leakage limit.

_____ D. UNIDENTIFIED LEAKAGE INCREASE has exceeded limits within a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.

Fermi 2 - 2008 NRC SRO License Exam QUESTION 93 During a reactor startup, Control Rod withdrawal is in progress at 20% power.

The following indications are received:

  • 3D8, DIV I/II OFF GAS RADN MONITOR UPSCALE alarms.
  • 3D12, DIV I/II OFF GAS RADN MONITOR HIGH-HIGH alarms.
  • D11-K601A and B Off Gas Radiation Monitors indicate 1200 mr/hr, RISING.
  • At H21-P275A, Hydrogen Analyzer Panel, BOTH Channels indicate 0.1% H2.
  • Off Gas Flow is 15 cfm.

Which ONE of the following CAUSED these indications, and what action is REQUIRED?

These indications are CAUSED by:

_____ A. a fuel cladding failure. It is required to enter 20.000.07, Fuel Cladding Failure.

_____ B. increased Main Condenser air inleakage. It is required to enter 20.125.01, Loss of Main Condenser Vacuum.

_____ C. an Off Gas Recombiner malfunction. It is required to enter 20.712.01, High Hydrogen Concentration / Explosion in the Off-Gas System.

_____ D. an expected increase in Nitrogen-16 (N16) production from the reactor. It is required to notify Chemistry of the power increase and obtain samples per 74.000.19, Chemistry Routine Surveillances.

Fermi 2 - 2008 NRC SRO License Exam QUESTION 94 With the plant in end of cycle coast down, all Control Rods are at position 48 and Reactor Power is 97%. Preparations are being made to shutdown for a Refuel Outage.

Which ONE of the following is an APPROVED method of adding positive reactivity AND obtaining additional energy from the core?

_____ A. SHUTDOWN Heater Drain Pumps per 23.108, Extraction Steam and Heater Drains.

_____ B. RAISE Core Flow to 110 Mlbm/hr per 22.000.03, Power Operation 25% to 100% to 25%.

_____ C. RAISE the Pressure Regulator setting per 22.000.03, Power Operation 25% to 100% to 25%.

_____ D. BYPASS Feedwater Heater #6 North and South by opening N2100-F603, #6 FW Heaters Bypass Valve per 23.108, Extraction Steam and Heater Drains.

Fermi 2 - 2008 NRC SRO License Exam QUESTION 95 A Work Request has been released to replace the Div 1 RHRSW Radiation Monitor Sample Pump. Due to parts difficulties, the work group is requesting that the Work Request be DEACTIVATED.

Per MOP05, Control of Equipment, which ONE of the following describes when the Shift Manager MAY deactivate the package?

The Shift Manager MAY deactivate the package:

_____ A. once the protection has been released AND the existing configuration has been evaluated per ODE 6, Operator Challenges.

_____ B. once the existing configuration has been evaluated and controlled by MES12, Performing Temporary Modifications, then protection can be released.

_____ C. after noting the deactivation on the Safety Tagging Record AND the existing configuration has been evaluated per ODE 6, Operator Challenges.

_____ D. after noting the deactivation on the Safety Tagging Record AND the existing configuration has been evaluated per MES12, Performing Temporary Modifications

Fermi 2 - 2008 NRC SRO License Exam QUESTION 96 Following a Refueling Outage, the following conditions exist:

  • ALL RPV Head Closure Bolts are FULLY TENSIONED.
  • The Reactor Mode Switch is in REFUEL and Control Rod exercising is in progress.

NOTE: For this particular instance, Special Operations TS 3.10.4 does not apply.

Which ONE of the following is the correct MODE of operation, based on these conditions?

_____ A. MODE 2, STARTUP

_____ B. MODE 3, HOT SHUTDOWN

_____ C. MODE 4, COLD SHUTDOWN

_____ D. MODE 5, REFUEL

Fermi 2 - 2008 NRC SRO License Exam QUESTION 97 Following an accident, it is required to estimate Core / Fuel Damage using the following Containment High Range Radiation Monitor (CHRRM) readings and conditions:

  • Reactor was SHUTDOWN at 1200.
  • CHRRM Readings were taken at 1300.
  • DIV 1 CHRRM indicates 2.0 x 104 R/hr.
  • DIV 2 CHRRM indicates 1.5 x 104 R/hr.

NOTE: See attached references.

Which ONE of the following is the CORRECT Core / Fuel Damage calculation, based on these readings?

% Gap Release  % of Fermi-2  % of Regulatory Upper Bound LOCA Guide 1.3 LOCA (H) (J) (K)

_____ A. 21.4 5.0 1.9

_____ B. 28.6 6.7 2.5

_____ C. 115.4 30.0 8.8

_____ D. 153.8 40.0 11.8

Fermi 2 - 2008 NRC SRO License Exam QUESTION 98 During a DECLARED EMERGENCY, a leak develops in an area that is accessible, but now radiologically contaminated. The Shift Manager has directed that an investigation be performed IMMEDIATELY.

In accordance with MRP05, ALARA / RWPs, what are the RWP REQUIREMENTS for entry into the area for investigation?

_____ A. A written Specific RWP must be issued.

_____ B. A General RWP already exists for this type of event.

_____ C. A revision to the General RWP for that area must be issued.

_____ D. A verbally issued RWP may be used for timely plant response.

Fermi 2 - 2008 NRC SRO License Exam QUESTION 99 While executing 29.100.01 Sheet 1A, ATWS RPV Control, Emergency Depressurization is REQUIRED. Conditions are as follows:

  • Standby Liquid Injection has been INITIATED.
  • Injection has been Terminated and Prevented as required.
  • Reactor Pressure is 850 psig LOWERING.
  • RPV Water Level is -30 inches LOWERING.

Which ONE of the following actions is REQUIRED to be ordered?

_____ A. RAISE RPV Water Level above -25 inches using INSIDE the shroud systems FIRST.

_____ B. RAISE RPV Water Level above -25 inches using OUTSIDE the shroud systems FIRST.

_____ C. WAIT until RPV Pressure LOWERS to 230 psig, THEN RAISE RPV Water Level above -25 inches using INSIDE the shroud systems FIRST.

_____ D. WAIT until RPV Pressure LOWERS to 230 psig, THEN RAISE RPV Water Level above -25 inches using OUTSIDE the shroud systems FIRST.

Fermi 2 - 2008 NRC SRO License Exam QUESTION 100 The plant is operating at full power, when a transient occurs, resulting in the following conditions:

  • Blue Scram Valve Lights, on the full core display, are ALL LIT.
  • The Turbine Generator is ON LINE.
  • Reactor Power is 30%.
  • ADS is INHIBITED.
  • FSQ 1-8 is COMPLETE.
  • RPV Water Level is at 60 inches, LOWERING at 4 inches per minute.
  • Torus Water Temperature is 90°F, due to HPCI starting.

Which ONE of the following EOP ACTIONS should have HIGHEST PRIORITY, based on these conditions?

_____ A. Start Torus Cooling per 23.205.

_____ B. Vent the Scram Air Header per 29.ESP.03.

_____ C. Deenergize Scram Solenoids per 29.ESP.03.

_____ D. Defeat RPV Level 1 MSIV Isolation Signals per 29.ESP.11.

Fermi 2 - 2008 NRC SRO License Exam Fermi 2 - 2008 NRC SRO License Exam

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