ML12324A291

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2012 Palisades Nuclear Plant RO Initial Written Examination
ML12324A291
Person / Time
Site: Palisades Entergy icon.png
Issue date: 10/12/2012
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NRC/RGN-III
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Download: ML12324A291 (76)


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RO Question 1 Palisades 2012 NRC Initial License Exam Given the following:

  • The Plant is manually tripped in response to a loss of coolant accident
  • A Safety Injection Actuation Signal is received
  • EOP-1.0, Standard Post Trip Actions, are in progress
  • RIA-1805/1806/1807/1808, Containment Area Monitors, indicate 2 x 101 R/Hr
  • Containment pressure is 3.3 psig and slowly rising
  • Alarm EK-1126, CIS INITIATED, is not alarming Which one of the following actions is required to be performed based on the above conditions?
a. Ensure operating all available Containment Air Cooler A fans.
b. Push left or right High Radiation Initiate pushbuttons.
c. Close both Steam Generator Main Steam Isolation Valves.
d. Ensure open all Containment Air Cooler inlet and outlet valves.

RO Question 2 Palisades 2012 NRC Initial License Exam Given the following:

  • During the transient, RV-1039, Pressurizer Relief Valve, opens but does not re-seat
  • Pressurizer pressure is 2000 psia and lowering rapidly
  • Quench Tank pressure is off-scale low; the Control Room team determines that the pressure indication has failed
  • RV-1039 downstream tailpipe temperature is 240°F If RV-1039 does not re-seat, which one of the following indicates that RUD-1041, Quench Tank Rupture Disk, has actuated?
a. RV-1039 downstream tailpipe temperature lowers.
b. RV-1039 downstream tailpipe temperature rises.
c. Pressurizer level begins to lower.
d. Pressurizer level begins to rise.

RO Question 3 Palisades 2012 NRC Initial License Exam For a small break loss of coolant accident event, which one of the following heat removal methods is relied upon to ensure adequate heat removal from the core? (Assume no other events are in progress)

a. High Pressure Safety Injection (HPSI) flow only.
b. HPSI flow and Low Pressure Safety Injection flow.
c. Primary Coolant flow out of the break.
d. Steam Generators.

RO Question 4 Palisades 2012 NRC Initial License Exam Which one of the following correctly completes the statement below?

Per EOP-4.0, Loss of Coolant Accident Recovery, the indication that the Control Room team uses to determine when to trip the last two Primary Coolant Pumps (PCPs) is (1) and the reason for tripping all PCPs under these conditions is to (2) .

a. (1) Primary Coolant System (PCS) subcooling less than 25°F (2) prevent damaging a PCP
b. (1) PCS subcooling less than 25°F (2) minimize PCS inventory loss
c. (1) Pressurizer (PZR) pressure less than minimum for PCP operation (2) prevent damaging a PCP
d. (1) PZR pressure less than minimum for PCP operation (2) minimize PCS inventory loss

RO Question 5 Palisades 2012 NRC Initial License Exam Given the following with the Plant at full power:

  • Alarm EK-0913, PRI COOLANT PUMP VIB ALERT/MON TROUBLE, annunciates
  • Primary Coolant Pump, P-50A, vibration indicates 17 mils on VIA-0131A, P-50A Vibration Monitor Using the diagram of the Control Room panel layout below, which one of the following lists an alternate location where P-50A vibration may be monitored?
a. Panel C-02.
b. Panel C-12.
c. Panel C-11.
d. Panel C-11R.

RO Question 6 Palisades 2012 NRC Initial License Exam Given the following with the Plant at full power:

  • EK-0709, VOLUME CONTROL TANK HI-LO LEVEL, annunciates
  • EK-0740, CHARGING PUMPS DISCHARGE LO PRESS, annunciates
  • Pressurizer level is lowering slowly
  • Charging flow has risen to 140 gpm
  • Letdown flow is stable at 40 gpm
  • TI-0212, Charging Line Temperature Indicator, has lowered from 380°F to 250°F
  • TICA-0201, Regenerative Heat Exchanger Outlet Temperature Indicator, has lowered from 240°F to 110°F Which one of the following describes the event that is occurring based on the above conditions?
a. Letdown line leak downstream of the Letdown Heat Exchanger.
b. Letdown line leak upstream of the Letdown Heat Exchanger.
c. Charging line leak downstream of the Regenerative Heat Exchanger.
d. Charging line leak upstream of the Regenerative Heat Exchanger.

RO Question 7 Palisades 2012 NRC Initial License Exam Which one of the following is an immediate action of ONP-17, Loss of Shutdown Cooling?

a. Suspend all operations involving a reduction of Primary Coolant System boron concentration.
b. Stop the operating Low Pressure Safety Injection Pump if Shutdown Cooling flow is less than 170 gpm.
c. Secure the Primary Coolant System Clean-up System.
d. Stop all Refueling Operations.

RO Question 8 Palisades 2012 NRC Initial License Exam CV-0945 and CV-0946, Component Cooling Water (CCW) Heat Exchanger Inlet Valves, receive an open signal during emergency conditions.

Which one of the following describes (1) the condition that generates the open signal and (2) the reason?

a. (1) Safety Injection Signal (SIS).

(2) Ensures 100% cooling is available post SIS.

b. (1) Recirculation Actuation Signal (RAS).

(2) Ensures 100% cooling is available post RAS.

c. (1) SIS.

(2) Provides minimum flow protection for CCW pumps.

d. (1) RAS.

(2) Provides minimum flow protection for CCW pumps.

RO Question 9 Palisades 2012 NRC Initial License Exam Given the following with the Plant operating at full power:

  • The Reactor remains at full power
  • The Reactor Operator attempts to trip the Reactor using the pushbutton on Panel C-02, but is not successful
  • The Reactor Operator then successfully trips the Reactor using the pushbutton on Panel C-06 Based on the above conditions, which one of the following describes the expected status of (1) Reactor Trip Breakers, 42-1RPS and 42-2RPS, and (2) the Red RPS Trip Light on the CRDM Clutch Power Supplies on Panel C-06? (See picture of Clutch Power Supply below)

Red RPS Trip Light

a. (1) CLOSED (2) OFF
b. (1) CLOSED (2) LIT
c. (1) TRIPPED (2) OFF
d. (1) TRIPPED (2) LIT

RO Question 10 Palisades 2012 NRC Initial License Exam Given the following:

  • The Plant has been tripped from full power due to a Steam Generator (S/G) tube rupture in the B S/G
  • A loss of all offsite power occurred following the trip
  • The highest Loop Hot Leg (TH) temperature is 526°F
  • The average Qualified Core Exit Thermocouple (CET) temperature is 532°F
  • A cooldown is in progress using the Atmospheric Steam Dump Valves Which one of the following is the minimum amount, in °F, that the Primary Coolant System needs to be cooled to allow Pressurizer pressure to be lowered to 940 psia?
a. 2°F by highest Loop TH.
b. 8°F by average of Qualified CETs.
c. 14°F by highest Loop TH.
d. 20°F by average of Qualified CETs.

RO Question 11 Palisades 2012 NRC Initial License Exam Given the following:

  • The Plant has been manually tripped from 50% power in response to a trip of the only operating Main Feed Pump
  • After completion of EOP-1.0, Standard Post Trip Actions, the Control Room team transitions to EOP-7.0, Loss of All Feedwater Recovery
  • All Primary Coolant Pumps have been secured Which one of the following describes the indication(s) that the Control Room team will monitor to ensure adequate Primary Coolant System (PCS) Heat Removal via Steam Generators (S/G) in accordance with EOP-7.0?
a. PCS Loop TC only.
b. PCS Loop TC and S/G level.
c. PCS Loop TH and S/G level.
d. Average Core Exit Thermocouple temperature and S/G level.

RO Question 12 Palisades 2012 NRC Initial License Exam Given the following with the Plant in MODE 3:

  • Diesel Generator (D/G) 1-2 is out of service for maintenance
  • A loss of all offsite power occurs
  • D/G 1-1 did not automatically start
  • The Control Room team implements EOP-3.0, Station Blackout Recovery Assuming it has been five (5) minutes since the loss of offsite power, which one of the following is required to be performed prior to attempting to start and load D/G 1-1?
a. Perform EOP Supplement 24, SW and CCW Hydraulic Shock Prevention.
b. Perform EOP Supplement 28, Supplementary Actions for Loss of Power.
c. Ensure alarm EK-0532, BUS 1C OR 1D OVERCURRENT LOCKOUT, is clear.
d. Place Remote-Local-Transfer Switch on D/G 1-1 Gage Board in LOCAL.

RO Question 13 Palisades 2012 NRC Initial License Exam Given the following with the Plant in MODE 3:

  • A loss of all offsite power occurs
  • Both Diesel Generators (D/G) start and sequence loads as designed Which one of the following loads must be manually started after the D/Gs have completed sequencing loads?
a. Instrument Air Compressors.
b. Charging Pumps.
c. Control Room HVAC.
d. Containment Air Cooler Fans.

RO Question 14 Palisades 2012 NRC Initial License Exam THIS QUESTION DELETED FROM THE EXAM Given the following with the Plant at full power:

  • During the transient, Y40, Preferred AC Bus, de-energizes
  • Pressurizer pressure is 1725 psia and lowering slowly
  • Containment pressure is 4.2 psig and rising
  • The following alarms annunciate:

o EK-1126, CIS INITIATED o EK-1342, SAFETY INJ INITIATED Which one of the following describes the action(s) required, if any, based on the above conditions for the Right Channel of Containment Spray and Safety Injection?

a. Containment Spray and Safety Injection must be manually initiated.
b. Containment Spray must be manually initiated only.
c. Safety Injection must be manually initiated only.
d. No actions required; Containment Spray and Safety Injection will automatically initiate.

RO Question 15 Palisades 2012 NRC Initial License Exam Given the following with the Plant at full power:

  • A loss of D21-2, DC Bus, occurs
a. CV-0847, Containment Service Water Supply Valve, is closed.
b. Main Steam Isolation Valve Control power is lost.
c. CV-1359, Non-critical Service Water Isolation Valve, is closed.
d. All Control Room annunciators have been lost.

RO Question 16 Palisades 2012 NRC Initial License Exam Given the following with the Plant at full power:

  • Alarm EK-1347, CONTAINMENT AIR COOLERS SERV WATER LEAK, annunciates
  • The Control Room team takes all required Operator Actions of the alarm response procedure to attempt to isolate the leak
  • After these actions are complete, it is noted that the alarm has not cleared Based on the above conditions, which one of the following correctly completes the statement below describing the location and minimum flow rate of the leak?

The leak is (1) Containment Air Cooler and has a flow rate of at least (2) gpm.

(Assume there is only one leak).

a. (1) not on a (2) 700
b. (1) on one (2) 300
c. (1) not on a (2) 300
d. (1) on one (2) 700

RO Question 17 Palisades 2012 NRC Initial License Exam Given the following with the Plant at full power:

  • Alarm EK-1105, AIR COMPRESSORS STANDBY COMP RUNNING, annunciates
  • A few seconds later, the following alarms annunciate:

o EK-1101, CONTAINMENT INSTR AIR LO PRESS o EK-1102, INSTRUMENT AIR LO PRESS o EK-1103, SERVICE AIR LO PRESS

  • The Control Room team diagnoses a Plant Air System leak and implements ONP-7.1, Loss of Instrument Air
  • Instrument Air pressure is 83 psig and steady
  • EK-1101, EK-1102, and EK-1103 have not cleared Which one of the following describes (1) the location of the leak and (2) the correct action per ONP-7.1?
a. (1) Service Air System.

(2) Ensure personnel utilizing breathing air stop work and leave their area.

b. (1) Instrument Air System.

(2) Supply the Instrument Air System from T-9C, HP Control Air Compressor Tank.

c. (1) Service Air System.

(2) Isolate Fire Water to the Track Alley Sprinkler system.

d. (1) Instrument Air System.

(2) Commence isolating major Instrument Air headers to isolate the leak.

RO Question 18 Palisades 2012 NRC Initial License Exam Given the following with the Plant at full power:

  • A voltage disturbance occurs on the Grid
  • Main Generator reactive load changes from zero (0) MVARS to 300 MVARs in
  • Alarm EK-0303, VOLTAGE REGULATOR LIMITER OPERATION, annunciates
  • The Control Room team determines that the Minimum Excitation Limiter has actuated
  • The Main Generator Voltage Regulator is then transferred to Direct Control (DC) in accordance with the associated Alarm Response Procedure Which one of the following describes the impact of using the DC Regulator to maintain Main Generator terminal voltage?
a. The Generator Loss of Field Relay (340) is blocked from actuating.
b. The Volts/HZ Limiter Relay (395) is blocked from actuating.
c. The Main Generator Capability curves are not valid.
d. Automatic Voltage Regulator limits will not function.

RO Question 19 Palisades 2012 NRC Initial License Exam Given the following:

  • A Plant trip has occurred due to a Condenser low vacuum condition
  • MO-2087, Volume Control Tank Outlet Valve, is open and will not close Which one of the following emergency boration flow paths must be utilized in accordance with SOP-2A, Attachment 14, Emergency Manual Boration, for the above conditions?
a. MO-2169 and MO-2170, Boric Acid Storage Tank Gravity Feed Valves.
b. MO-2160, SIRWT Outlet to Charging Pump Suction.
c. MO-2140, Boric Acid Pumped Feed Isolation Valve.
d. MO-3072, HPSI Train 2 Charging Cross Connect Valve.

RO Question 20 Palisades 2012 NRC Initial License Exam Which one of the following correctly completes the statement below?

The guidance of ONP-23.3, Loss of Refueling Water Accident, requires that the Low Pressure Safety Injection Loop Injection Valves shall be fully (1) prior to Containment Water level reaching 595 9 to allow the Reactor Cavity to be re-filled from the (2) .

(Assume the Fuel Transfer Tube Flange is removed and Door-950, Spent Fuel Pool (SFP)

South Tilt Pit Gate, is removed.)

a. (1) open (2) Containment Sump
b. (1) open (2) SFP Cooling System
c. (1) closed (2) Containment Sump
d. (1) closed (2) SFP Cooling System

RO Question 21 Palisades 2012 NRC Initial License Exam Given the following with the Plant in MODE 3:

  • Primary Coolant System temperature is 532°F
  • Pressurizer pressure is 2060 psia
  • Pressurizer level is 42% and steady
  • P-55A, Charging Pump, is in service
  • P-55C, Charging Pump, is out of service for maintenance
  • Then, a Steam Generator (S/G) tube leak develops Which one of the following is the minimum S/G tube leak rate value that will cause Pressurizer level indication to continuously lower for the above conditions? (Assume no operator actions occur.)
a. 11 gpm.
b. 15 gpm.
c. 53 gpm.
d. 91 gpm.

RO Question 22 Palisades 2012 NRC Initial License Exam Given the following with the Plant operating at full power:

  • ONP-14 directs implementation of ONP-26, Rapid Power Reduction
  • A power reduction of 300% per hour is in progress Which one of the following alarms, if annunciating, requires a Reactor trip under these conditions in accordance with ONP-26?
a. EK-0605C, TM/LO PRESSURE CHANNEL PRE-TRIP.
b. EK-0962, STEAM GENERATOR E-50A LO LEVEL.
c. EK-0606A, HIGH POWER RATE PRE-TRIP/ASI.
d. EK-0912, ROD POSITION 8 INCHES DEVIATION.

RO Question 23 Palisades 2012 NRC Initial License Exam The Plant is in MODE 5 with V-78, Penetration and Fan Room Supply, and V-79, Penetration and Fan Room Exhaust, aligned per the picture below LIT SUPPLY FAN V-78 PENETRATION AND FAN ROOM HS-8035 LIT EXHAUST FAN V-79 Then, EK-1366, PLANT AREA MONITORING HI RADIATION, annunciates due to a high alarm on RIA-5710, Penetration and Fan Room Area Monitor.

Which one of the following lists the expected indication for V-78 and V-79 due to EK-1366?

V-78 V-79

a. OFF OFF
b. ON OFF
c. OFF ON
d. ON ON

RO Question 24 Palisades 2012 NRC Initial License Exam Given the following:

  • The Control Room has been evacuated
  • ONP-25.1, Fire Which Threatens Safety Related Equipment, and ONP-25.2, Alternate Safe Shutdown Procedure, have been implemented
  • EOP-1.0, Standard Post Trip Actions, are in progress Which one of the following describes the location(s), if any, available for determining Primary Coolant System subcooling for the above conditions?
a. None.
b. C-150, Auxiliary Hot Shutdown Panel or C-33, Redundant Safety Injection Panel.
c. C-150 only.
d. C-33 only.

RO Question 25 Palisades 2012 NRC Initial License Exam While verifying natural circulation in the Primary Coolant System (PCS) during the performance of EOP-8.0, Loss of Offsite Power/Forced Circulation Recovery, which one of the following would indicate that natural circulation flow is not present in the PCS?

a. Loop Hot Leg temperatures (TH) are steady.
b. The difference between Average Qualified CETs and TH is 18°F.
c. Loop Cold Leg temperatures (TC) are steady.
d. The difference between Average Qualified CETs and TC is 42°F.

RO Question 26 Palisades 2012 NRC Initial License Exam Given the following:

  • The Plant has been tripped due to a steam line break from the A Steam Generator (S/G)
  • The Control Room team is performing actions to isolate the A S/G in accordance with EOP Supplement 17, A S/G ESDE Isolation Checklist Which one of the following correctly completes the statement below?

The preferred method of isolating the Atmospheric Steam Dump Valves (ADVs) is by closing the (1) because (2) .

a. (1) Control Air Supply Valve to the ADVs (2) the Manual Isolation Valves may not be accessible
b. (1) Control Air Supply Valve to the ADVs (2) it allows the valve to be quickly re-opened if necessary
c. (1) ADV Manual Isolation Valves (2) the quick open feature may actuate due to the valve accumulator not being isolated with the Control Air Supply Valve
d. (1) ADV Manual Isolation Valves (2) the quick open feature may actuate due to backup Nitrogen not being isolated with the Control Air Supply Valve

RO Question 27 Palisades 2012 NRC Initial License Exam Given the following with the Plant at full power:

  • P-55A, Charging Pump, is in service
  • Then, the Reactor Operator notes the following:

o Containment sump level is rising o Volume Control Tank (VCT) level is 78.0%

o Pressurizer (PZR) level is 56.9%

  • The Control Room team implements ONP-23.1, Primary Coolant Leak
  • The Control Room Supervisor directs the performance of a Primary Coolant System (PCS) leak rate calculation After ten (10) minutes which one of the following describes the condition(s) listed in the table below that require the Reactor to be tripped in accordance with ONP-23.1? (consider each condition separately and assume PCS temperature has remained stable)

Condition VCT Level (%) PZR level (%)

A 73.3 57.0 B 74.9 56.9 C 76.8 56.1 D 74.5 57.4

a. Conditions A, B, C, and D.
b. Conditions A, B, and C only.
c. Conditions A and B only.
d. Condition A only.

RO Question 28 Palisades 2012 NRC Initial License Exam Given the drawing below of PR-0140B, Primary Coolant Pump, P-50D, Seal Pressure Recorder, and the following pump conditions:

  • Controlled Bleedoff temperature is 120°F
  • Controlled Bleedoff flow is 1 gpm
  • Controlled Bleedoff pressure is 90 psig Which one of the following malfunctions has occurred to the P-50D Seal?
a. The upper seal (3rd stage) has failed.
b. The middle seal (2nd stage) has failed.
c. The lower seal (1st stage) has failed.
d. The upper (3rd stage) pressure breakdown device has plugged.

RO Question 29 Palisades 2012 NRC Initial License Exam Given the following with the Plant at full power:

  • Pressurizer level is 57% and stable
  • P-55A, Charging Pump, is in service
  • EK-0701, REGEN HT EX TUBE OUTLET HI TEMP, annunciates on Panel C-12
  • TICA-0201, Regenerative Heat Exchanger Outlet Temperature Indicator, is 472°F
  • TI-0212, Charging Line Temperature Indicator, is 440°F Several minutes later during the investigation of EK-0701, the Control Room team notes the following:
  • TICA-0201, Regenerative Heat Exchanger Outlet Temperature Indicator, is 460°F
  • TI-0212, Charging Line Temperature Indicator, is 410°F Assuming no Operator action, which one of the following identifies the expected Charging and Letdown flow rates due to the above conditions?

CHARGING LETDOWN FLOW FLOW

a. 0 gpm 0 gpm
b. 33 gpm 0 gpm
c. 33 gpm 40 gpm
d. 44 gpm 40 gpm

RO Question 30 Palisades 2012 NRC Initial License Exam Given the following with the Plant in MODE 4:

  • The Primary Coolant System (PCS) is solid with P-55B, Charging Pump, in service
  • P-50A and P-50C, Primary Coolant Pumps, are in service
  • PCS pressure is being maintained at 250 psia with PIC-0202, Intermediate Letdown Pressure Controller, in MANUAL
  • A PCS cooldown is in progress Which one of the following correctly completes the statement below?

To maintain PCS pressure at 250 psia as the PCS cooldown continues, Letdown flow must be (1) by adjusting the output (2) on PIC-0202.

a. (1) lowered (2) lower
b. (1) lowered (2) higher
c. (1) raised (2) lower
d. (1) raised (2) higher

RO Question 31 Palisades 2012 NRC Initial License Exam Given the following with the Plant in MODE 6:

  • The Reactor Cavity is flooded to 647 2 elevation
  • The Control Room team has been requested to de-energize 2400V Bus 1D for maintenance Which one of the following lists two LPSI Loop Injection Valves that will both be able to be operated from the Control Room if Bus 1D is de-energized?
a. MO-3008, LPSI to Reactor Coolant Loop 1A.

MO-3010, LPSI to Reactor Coolant Loop 1B.

b. MO-3010, LPSI to Reactor Coolant Loop 1B.

MO-3014, LPSI to Reactor Coolant Loop 2B.

c. MO-3012, LPSI to Reactor Coolant Loop 2A.

MO-3014, LPSI to Reactor Coolant Loop 2B.

d. MO-3008, LPSI to Reactor Coolant Loop 1A.

MO-3012, LPSI to Reactor Coolant Loop 2A.

RO Question 32 Palisades 2012 NRC Initial License Exam Given the following:

  • A loss of coolant accident has occurred
  • The Control Room team implements EOP-4.0, Loss of Coolant Accident
  • Safety Injection and Containment High Pressure (CHP) initiate as designed
  • Safety Injection Refueling Water Tank level reaches 2% and a Recirculation Actuation Signal (RAS) occurs
  • The Control Room team commences actions of EOP Supplement 42, section 2.0, Post-RAS Actions
  • The Reactor Operator notes that CV-3030, Containment Sump Outlet Valve to West Safeguards, did not open Which one of the following describes (1) the effect, if any, on High Pressure Safety Injection (HPSI) flow and (2) the effect on Containment Spray flow upon completion of EOP Supplement 42, section 2.0 for the above conditions?

HPSI flow capacity will be (1) and Spray flow capacity will be (2) .

a. (1) unaffected (2) reduced by approximately two-thirds
b. (1) unaffected (2) reduced by approximately one-third
c. (1) reduced by approximately one-half (2) reduced by approximately two-thirds
d. (1) reduced by approximately one-half (2) reduced by approximately one-third

RO Question 33 Palisades 2012 NRC Initial License Exam Which one of the following correctly completes the statement below describing the minimum required level and source of makeup water for T-73, Quench Tank?

The Quench Tank is maintained at a minimum water level of (1) by adding makeup water using (2) .

a. (1) 70%

(2) P-90A or P-90B, Primary Makeup Tank Pumps

b. (1) 70%

(2) P-79A or P-79B, Primary System Makeup Transfer Pumps

c. (1) 40%

(2) P-90A or P-90B

d. (1) 40%

(2) P-79A or P-79B

RO Question 34 Palisades 2012 NRC Initial License Exam Given the following with the Plant in MODE 4:

  • A Plant cooldown is in progress
  • The Reactor Operator has just started a second Component Cooling Water (CCW)

Pump in preparation for placing the Shutdown Cooling System in service

  • The Nuclear Plant Operator reports the following CCW Heat Exchanger differential pressure (dp) indications:

o E-54A - 14.1 psi o E-54B - 12.5 psi Which one of the following describes the CCW Heat Exchanger dp indication, if any, that is within the guidelines for two pump operation per SOP-16, Component Cooling Water System?

a. E-54A only.
b. E-54B only.
c. Neither.
d. Both.

RO Question 35 Palisades 2012 NRC Initial License Exam Given the following with the Plant at full power:

  • P-52A, Component Cooling Water (CCW) Pump, is in service
  • CCW Pump discharge header pressure is 107 psig
  • Then, alarm EK-1170, COMPONENT CLG EX E-54A HI-LO TEMP, annunciates
  • CCW temperature is 89°F and rising slowly
  • CV-0821 and CV-0822, CCW HX E-54A and E-54B Temp. Control Valves, are full open
  • Lake Michigan water temperature is 81°F with all three Service Water Pumps in service Which one of the following describes (1) an impact on the Plant due to the above conditions and (2) the correct action?
a. (1) Rising Letdown temperature.

(2) Place CV-2023, Demineralizers T-51A/B & T-52 Bypass Valve, to BYPASS.

b. (1) Rising PCP seal temperature.

(2) Throttle open CV-0823 and CV-0826, CCW HX SW High Capacity Outlets.

c. (1) Rising Letdown temperature.

(2) Start P-52B or P-52C, CCW Pump.

d. (1) Rising PCP seal temperature.

(2) Start P-52B or P-52C.

RO Question 36 Palisades 2012 NRC Initial License Exam Given the following with the Plant in MODE 4:

  • A Primary Coolant System (PCS) heatup is in progress
  • Pressurizer (PZR) steam bubble formation is in progress in accordance with SOP-1C, Primary Coolant System - Heatup
  • PCS temperature is 265°F
  • PZR pressure is 273 psia
  • PZR temperature is 401°F and rising Which one of the following describes (1) the lowest temperature which the PZR must be heated to form a steam bubble and (2) an indication that a steam bubble has formed in the PZR?
a. (1) 406°F.

(2) Letdown flow is greater than charging flow with PZR pressure constant.

b. (1) 409°F.

(2) Sudden PZR pressure rise when saturation temperature is reached.

c. (1) 409°F.

(2) Letdown flow is greater than charging flow with PZR pressure constant.

d. (1) 406°F.

(2) Sudden PZR pressure rise when saturation temperature is reached.

RO Question 37 Palisades 2012 NRC Initial License Exam Given the following with the Plant at full power:

  • RPS Channel B for A Steam Generator Low Level trip is BYPASSED Which one of the following additional instrument failures will result in an automatic Reactor trip for the above conditions? (refer to the below graphic of S/G level instrumentation)

A S/G B S/G LIA-0702 LI-0751A LI-0751B LI-0751C LI-0751D LIA-0704 LI-0752A LI-0752B LI-0752C LI-0752D

a. LI-0751A, S/G E-50A Low Level Indicator, fails low.
b. LI-0752B, S/G E-50B Low Level Indicator, fails low.
c. LIA-0702, S/G E-50A Level Alarm Indication, fails low.
d. LIA-0702 fails high.

RO Question 38 Palisades 2012 NRC Initial License Exam Given the following:

  • The Plant is at 10% power
  • A loss of Y20, Preferred AC Bus, occurs
  • The Control Room team bypasses all B Channel Reactor Protective System (RPS) trips
  • Then, a loss of Y10, Preferred AC Bus, occurs For the above conditions, which one of the following describes the effect, if any, on the RPS and the reason?
a. A Reactor trip signal will be generated due to a Loss of Load signal caused by a Main Steam Isolation.
b. A Reactor trip signal will be generated due to a loss of power to the AB Matrix Relays.
c. No effect; trip logic is two-out-of-three with B RPS channels bypassed.
d. A Reactor trip signal will be generated due to a high Startup Rate trip signal caused by loss of two Wide Range Nuclear Instruments.

RO Question 39 Palisades 2012 NRC Initial License Exam Given the following:

  • A loss of coolant accident outside Containment has occurred from full power
  • EOP-4.0, Loss of Coolant Accident Recovery, has been implemented
  • Pressurizer pressure is 1410 psia
  • The Control Room team is preparing to reset the Safety Injection Signal (SIS)

Which one of the following describes (1) the minimum corrected Pressurizer level associated with Safety Injection throttling criteria that must be met prior to resetting SIS and (2) the minimum action(s) that will reset SIS?

a. (1) 28%.

(2) Push left and right Safety Injection RESET pushbuttons only.

b. (1) 28%.

(2) Turn left and right SIAS BLOCK Handswitches to BLOCK and push left and right Safety Injection RESET pushbuttons.

c. (1) 42%.

(2) Push left and right Safety Injection RESET pushbuttons only.

d. (1) 42%.

(2) Turn left and right SIAS BLOCK Handswitches to BLOCK and push left and right Safety Injection RESET pushbuttons.

RO Question 40 Palisades 2012 NRC Initial License Exam Given the following conditions with the Plant operating at 60% power:

  • Diesel Generator (D/G) 1-1 starts and sequences loads as designed
  • D/G 1-2 will not start

o EK-1163, CRITICAL SERV WATER HEADER B LO PRESSURE o EK-1164, CRITICAL SERV WATER HEADER A LO PRESSURE o EK-1165, NON-CRITICAL SERV WATER LO PRESS

  • Both Critical SW Header pressures are 31 psig and stable
  • Pressurizer pressure is 1900 psia and stable Which one of the following actions is required to be taken first per EOP-1.0, Standard Post Trip Actions, to restore Critical SW Header pressures for the above conditions?
a. Close Containment Air Cooler Outlet Valves as necessary to raise SW pressure > 42 psig.
b. Close CV-0847, Containment SW Supply Valve to Containment.
c. Close CV-1359, Non-critical SW Isolation Valve.
d. Start additional SW Pumps as necessary to raise SW pressure > 42 psig.

RO Question 41 Palisades 2012 NRC Initial License Exam Given the following with the Plant operating at full power:

  • A manual Plant trip is initiated in response to a steam line break from the A Steam Generator
  • Containment pressure reaches 6.0 psig For the components listed below, which one of the following describes the expected configuration due to the above conditions?
  • V-4A, Containment Air Cooling (CAC) Recirc Fan
  • CV-0869, VHX-4 Containment Air Cooler Inlet Valve
  • CV-0867, VHX-4 Containment Air Cooler Outlet Valve V-4A CV-0869 CV-0867
a. ON OPEN OPEN
b. OFF CLOSED OPEN
c. ON OPEN CLOSED
d. ON CLOSED OPEN

RO Question 42 Palisades 2012 NRC Initial License Exam Given the following:

  • A Plant trip has occurred in response to a steam line break inside Containment
  • The following alarms are annunciating:

o EK-0504, 2400V BUS 1D BKR 152-203 TRIP o EK-0532, BUS 1C OR 1D OVERCURRENT LOCKOUT

  • EOP-6.0, Excess Steam Demand Event, is implemented
  • Containment pressure is 41 psia and lowering slowly
  • T-58, Safety Injection Refueling Water Tank, level is 44% and lowering slowly For the above conditions, which one of the following lists (1) the maximum pressure at which any operating Containment Spray Pump may be secured and (2) the Containment Spray Pump that will be secured?
a. (1) 35 psia.

(2) P-54A.

b. (1) 35 psia.

(2) P-54B or P-54C.

c. (1) 28 psia.

(2) P-54A.

d. (1) 28 psia.

(2) P-54B or P-54C.

RO Question 43 Palisades 2012 NRC Initial License Exam Given the following:

  • 386AST, Turbine Trip Lockout Relay, does not actuate when the Turbine trips Which one of the following correctly completes the statement below describing how automatic operation of the Atmospheric Steam Dump Valves (ADVs) will be affected during the Plant trip?

The ADVs (1) operate upon a Quick Open signal and (2) operate in the Modulate mode.

a. (1) will not (2) will
b. (1) will (2) will not
c. (1) will not (2) will not
d. (1) will (2) will

RO Question 44 Palisades 2012 NRC Initial License Exam Given the following with the Plant at full power:

  • A Plant trip occurs due to steam line rupture inside Containment
  • Containment pressure rises to a maximum of 3.1 psig
  • B S/G Pressure indicates 540 psia Which one of the following describes the expected response of the Main Steam Isolation Valves (MSIVs) and Feed Regulating Valves (FRVs) to this event?
a. Both A and B S/G MSIVs close.

Only A S/G FRV closes.

b. Both A and B S/G MSIVs close.

Both A and B S/G FRVs close.

c. Only A S/G MSIV closes.

Both A and B S/G FRVs close.

d. Only A S/G MSIV closes.

Only A S/G FRV closes.

RO Question 45 Palisades 2012 NRC Initial License Exam Given the following during a Plant power ascension:

  • P-1A, A Main Feed Pump (MFP), is in service with HIC-0526, P-1A Turbine Driver K-7A Speed Controller, in CASCADE
  • P-1B, B MFP, is being placed in service with HIC-0529, P-1B Turbine Driver K-7B Speed Controller, in MANUAL with turbine speed at the minimum governor setting Which one of the following correctly completes the statement below describing the logic necessary to transfer HIC-0529 to CASCADE? (refer to the above picture of HIC-0529)

When the green PF light indicates (1) , the (2) is depressed.

a. OFF CASCADE (C) Pushbutton
b. ON (flashing)

CASCADE (C) Pushbutton

c. OFF AUTO (A) Pushbutton
d. ON (flashing)

AUTO (A) Pushbutton

RO Question 46 Palisades 2012 NRC Initial License Exam Given the following with the Plant at full power:

o A Steam Generator (S/G) - 90 gpm o B S/G - 110 gpm Which one of the following describes whether any additional AFW Pumps will automatically start due to the above conditions?

a. No additional AFW Pumps will start.
b. P-8B, AFW Pump, will automatically start after 30.5 seconds.
c. P-8C, AFW Pump, will automatically start after 30.5 seconds.
d. P-8C will automatically start after 112.5 seconds.

RO Question 47 Palisades 2012 NRC Initial License Exam Given the following during a loss of all offsite power event:

  • Diesel Generator (D/G) 1-2 is supplying 2400 VAC Bus 1D loads
  • D/G 1-2 load is 2890 kW Which one of the following is the least amount of load that must be removed from D/G 1-2 to be below the two-hour operational load limit?
a. 100 kW.
b. 200 kW.
c. 300 kW.
d. 400 kW.

RO Question 48 Palisades 2012 NRC Initial License Exam Given the following with the Plant at 50% power:

  • The Chemical Volume Control System is aligned for double charging and letdown with P-55A and P-55B, Charging Pumps, in service
  • Then, a ground occurs on the DC Electrical Distribution System and the following alarms annunciate:

o EK-0547, 125V DC BUS GROUND o EK-0548, 125V DC BUS UNDERVOLTAGE/ TROUBLE o EK-0765, NO PCS PROTECTION CHANNEL B

  • The Control Room team determines that D21-1, DC Bus, Supply Fuse, FUZ/D21-1, has blown Which one of the following describes (1) an impact on the Plant due to the above conditions and (2) the action required to mitigate the impact?
a. (1) Pressurizer level is rising.

(2) Place in-service Pressurizer Level Controller in MANUAL and raise letdown flow.

b. (1) Pressurizer level is rising.

(2) Manually secure P-55A and P-55B by opening supply breakers at LCC-12, 480V Load Control Center.

c. (1) Main Steam Isolation Valves (MSIVs) will not automatically close on Containment Isolation if required.

(2) Direct an Auxiliary Operator (AO) to verify closed all Turbine Valves if a Containment Isolation signal occurs.

d. (1) MSIVs will not automatically close on Containment Isolation if required.

(2) Direct an AO to unlatch the MSIV solenoids if a Containment Isolation signal occurs.

RO Question 49 Palisades 2012 NRC Initial License Exam Given the following:

  • A loss of all offsite power occurs
  • Both Diesel Generators (D/G) start due to bus undervoltage Which one of the following correctly completes the statement below regarding actuation of the Normal Shutdown Sequencer (NSD) for the associated D/G?

is the last event to occur that causes the Normal Shutdown Sequencer to actuate and begin sequencing loads onto the associated D/G.

a. D/G jacket water pressure relay actuation.
b. 2400 VAC bus load shed completion.
c. D/G output voltage reaching 2200 volts.
d. D/G output breaker closing.

RO Question 50 Palisades 2012 NRC Initial License Exam RE-1113, Waste Gas Process Monitor Radiation Element, consists of a detector mounted on one side of the Waste Gas discharge pipe with a window through the pipe wall, with the pipe four inches in diameter (see below). The detector is a point detector located one-inch from the inner diameter of the pipe.

RE-1113 Window Position B Position A Waste Gas Pipe Detector 1 in.

4 in.

5 in.

Which one of the following correctly completes the statement below comparing the difference in radiation readings for a hot particle that passes along the side of the pipe closest to the detector (Position A above) to the same hot particle that passes along the side of the pipe farthest away from the detector (Position B above)?

The reading for Position A will be times greater than the reading for Position B.

a. 4
b. 5
c. 16
d. 25

RO Question 51 Palisades 2012 NRC Initial License Exam Which one of the following Service Water (SW) valves does not have controls available in the Control Room for operation?

a. CV-0878, West ESS Room Cooler VHX-27B SW Inlet.
b. CV-0885, Diesel Generator 1-2 SW Inlet.
c. CV-0879, ESS Pump Seal Cooling SW Supply.
d. CV-0826, CCW HX E-54B SW Outlet.

RO Question 52 Palisades 2012 NRC Initial License Exam Given the following with the Plant at full power:

  • PS-1318, P-7C, SW Pump, discharge pressure switch, is isolated for maintenance
  • P-7C is in STANDBY Which one of the following correctly completes the statement below describing operation of P-7C for the above conditions?

P-7C will (1) if P-7A trips and; P-7C will (2) if BS-1319, P-7B Discharge Basket Strainer, indicates 10 psig differential pressure.

(consider each of these events separately)

a. (1) not start (2) start
b. (1) not start (2) not start
c. (1) start (2) not start
d. (1) start (2) start

RO Question 53 Palisades 2012 NRC Initial License Exam Which one of the following correctly completes the statement below describing C-2B, Instrument Air Compressor, cooling?

The cooling medium to C-2B compressor package is (1) and the cooling medium to E-18B, C-2B Aftercooler, is (2) .

a. (1) Air (2) Critical Service Water (SW)
b. (1) Critical SW (2) Critical SW
c. (1) Critical SW (2) Non-critical SW
d. (1) Air (2) Non-critical SW

RO Question 54 Palisades 2012 NRC Initial License Exam Given the following:

  • FIC-0736A and FIC-0737A, P-8C AFW Flow Controllers, are in AUTO set for 130 gpm
  • Then, a loss of all Instrument Air occurs
  • Instrument Air pressure lowers to zero (0) psig Which one of the following correctly completes the statement below describing how the loss of Instrument Air affects CV-0736A and CV-0737A, P-8C Flow Control Valves, if at all, due to the above conditions?

CV-0736A and CV-0737A will

a. fail closed.
b. not be affected since they have N2 bottle backup.
c. not be affected since they have air accumulator backup.
d. fail open.

RO Question 55 Palisades 2012 NRC Initial License Exam With the Plant at full power, a Containment High Radiation signal is received.

Which one of the following contains valves that would all be expected to automatically close?

a. CV-0770, Steam Generator B Blowdown Isolation CV-1064, Clean Waste Receiver Tank Vent CV-2009, Letdown Containment Isolation
b. CV-1358, Nitrogen to Containment Isolation CV-1007, Primary System Drain Tank Outlet CV-0910, Component Cooling Water to Containment Isolation
c. CV-0734, S/G B Bypass Feed Regulating Valve CV-1101, Containment Vent Header Isolation CV-0770, Steam Generator B Blowdown Isolation
d. CV-1037, Clean Waste Receiver Tanks Recirc Isolation CV-0701, Steam Generator A Feed Regulating Valve CV-0939, Shield Cooling Surge Tank Fill Isolation

RO Question 56 Palisades 2012 NRC Initial License Exam Given the following with the Plant initially at 100% power:

  • Preparations are being made to lower Plant power to 50% due to a problem with Steam Generator chemistry
  • A 500 gallon continuous boration of the Primary Coolant System is commenced at 7 gpm Which one of the following correctly completes the statement below describing the expected effect on Moderator Temperature Coefficient (MTC) and Axial Shape Index (ASI) due to the boration?

MTC will be (1) and ASI will be (2) .

a. (1) Less negative (2) More negative (less positive)
b. (1) More negative (2) More negative (less positive)
c. (1) Less negative (2) More positive (less negative)
d. (1) More negative (2) More positive (less negative)

RO Question 57 Palisades 2012 NRC Initial License Exam Given the following with the Plant in MODE 3:

  • All four Primary Coolant Pumps (PCPs) are in service
  • 4160V Bus 1A de-energizes due to a fault Which one of the following correctly completes the statement below regarding which PCPs are affected and the effect, if any, on Pressurizer spray flow capability due to the above conditions?

PCPs (1) are affected by the loss of Bus 1A and Pressurizer spray flow capability is (2) .

a. (1) A and B (2) reduced
b. (1) A and B (2) not affected
c. (1) A and C (2) reduced
d. (1) A and C (2) not affected

RO Question 58 Palisades 2012 NRC Initial License Exam Given the following:

  • The Plant is at 60% power
  • LIC-0101B, Pressurizer Level Controller, is in service in the CASCADE mode
  • SS-TAVE, Avg Temp Display Select Switch, on Panel C-02 is in the LOOP 2 position
  • Then, a malfunction causes the Loop 2 TAVE signal to fail low Which one of the following correctly completes the statement below describing the effect on LIC-0101B setpoint?

LIC-0101B setpoint will indicate

a. 100%.
b. 57%.
c. 42%.
d. 0%.

RO Question 59 Palisades 2012 NRC Initial License Exam Given the following:

  • The Plant is in MODE 6 with Refueling operations in progress
  • Reactor Cavity level is 647 6
  • P-67A, Low Pressure Safety Injection Pump, is in service providing Shutdown Cooling flow
  • Then, a loss of Y40, Preferred AC Bus, occurs Which one of the following describes (1) the impact due to the loss of Y40 and (2) the correct immediate action(s)?
a. (1) Source Range Nuclear Instrumentation is lost.

(2) Suspend operations involving a reduction in Primary Coolant System (PCS) boron concentration.

b. (1) Source Range Nuclear Instrumentation is lost.

(2) Suspend core alterations and positive reactivity additions.

c. (1) Shutdown Cooling flow is lost.

(2) Suspend core alterations and positive reactivity additions.

d. (1) Shutdown Cooling flow is lost.

(2) Suspend operations involving a reduction in PCS boron concentration.

RO Question 60 Palisades 2012 NRC Initial License Exam Given the following:

  • A manual Plant trip occurs in response to a loss of coolant accident inside Containment
  • Core Exit Thermocouple (CET) indications are not available on the Plant Process Computer Using the diagram of the Control Room panel layout below, which one of the following describes the alternate CET indications that are available?
a. Only qualified CET indications are available on Panel C-11A.
b. Only qualified CET indications are available on Panel C-12.
c. Only one CET indication per core quadrant is available on Panel C-11A.
d. All qualified and unqualified CET indications are available on Panel C-11A.

RO Question 61 Palisades 2012 NRC Initial License Exam Given the following:

  • The Plant is in MODE 5
  • The Containment Equipment Hatch is open
  • A Containment purge is in progress
  • V-6A, Main Exhaust Fan, is in service
  • Then, Alarm EK-1126, CIS INITIATED, annunciates Which one of the following describes an effect on the Plant due to EK-1126 alarming?
a. CV-1805, CV-1806, CV-1807, and CV-1808, Containment Purge Exhaust Valves, close.
b. V-1B, V-2B, V-3B and V-4B, Containment Air Cooler Fans, trip.
c. V-6A, Main Exhaust Fan, trips and associated damper closes.
d. PO-1890, Air Room Purge Damper, closes.

RO Question 62 Palisades 2012 NRC Initial License Exam Given the following:

  • TAVE is currently 537°F and lowering slowly
  • Main steam pressure is 930 psia and lowering slowly Which one of the following lists the expected positions of the Turbine Bypass Valve (TBV) and Atmospheric Steam Dump Valves (ADVs) for the above conditions?

TBV ADVs

a. Modulating Modulating
b. Modulating Full Open
c. Full Open Full Open
d. Full Open Modulating

RO Question 63 Palisades 2012 NRC Initial License Exam Given the following:

  • The Plant is in MODE 2
  • A startup from a forced outage is in progress Which one of the following correctly completes the statement below describing when the Loss of Load Reactor Protective System (RPS) trip is enabled during the startup?

The Loss of Load RPS trip is enabled by the Nuclear Instrumentation System at (1) power and is verified enabled by observing (2) alarm clearing.

a. (1) 15%

(2) EK-06D2, LOSS OF LOAD TRIP CHANNEL BYPASS

b. (1) 15%

(2) EK-06D1, ZERO POWER MODE BYPASS

c. (1) 10-4%

(2) EK-06D2, LOSS OF LOAD TRIP CHANNEL BYPASS

d. (1) 10-4%

(2) EK-06D1, ZERO POWER MODE BYPASS

RO Question 64 Palisades 2012 NRC Initial License Exam Given the following conditions:

  • Alarm EK-0207, STACK EFF RAD C-169 HIGH, is received in the Control Room during a release of T-101B, Waste Gas Decay Tank
  • RIA-2326, Normal Range Noble Gas Stack Monitor, is in alarm Which one of the following will automatically occur due to the above conditions?
a. V-6A/B, Main Exhaust Fans, trip and their associated dampers close.
b. RIA-2327, High Range Noble Gas Stack Monitor, is placed in service.
c. RIA-2326, Normal Range Noble Gas Stack Monitor, scale transfers from cpm to R/Hr.
d. V-14A/B, Radwaste Area Exhausters, trip and their associated dampers close.

RO Question 65 Palisades 2012 NRC Initial License Exam Given the following:

  • P-9A, Motor Driven Fire Pump, is out of service for maintenance
  • A demand on the Fire Protection System (FPS) causes FPS pressure to lower to 73 psig Which one of the following lists all Fire Protection System Pumps that are expected to be in service due to the above conditions?
a. P-9B, Diesel Driven Fire Pump, and P-41, Diesel Driven Cooling Tower Fire Pump.
b. P-13, Fire System Jockey Pump, and P-9B, and P-41.
c. P-13 and P-9B.
d. P-9B only.

RO Question 66 Palisades 2012 NRC Initial License Exam Which one of the following Control Room operations is not acceptable for two-handed operation per EN-OP-115, Conduct of Operations?

a. Performing a manual scram using individual Control Rod clutch toggle switches.
b. Securing Primary Coolant Pumps during performance of an EOP.
c. Opening Safety Injection Loop Injection Valves during performance of an EOP.
d. Closing Main Steam Isolation Valves when directed by a GOP.

RO Question 67 Palisades 2012 NRC Initial License Exam Given the following:

  • A fire in the Plant has been reported to the Control Room
  • The Control Room Operator has sounded the fire alarm Which one of the following is not an additional responsibility of the Control Room Operator after the fire alarm has been sounded?
a. Maintain communications with the Fire Brigade Leader via radio and/or telephone.
b. Ensure assistance is requested from Van Buren County for Covert and South Haven Fire Departments.
c. Notify the Operations Fire Marshall if the fire affects safety related areas or equipment.
d. Announce the Fire Brigade muster location on the Public Address system.

RO Question 68 Palisades 2012 NRC Initial License Exam Which one of the following correctly completes the statement below?

If a parameter on the Plant Process Computer is displayed in yellow text, this signifies that the parameter

a. has exceeded the warning setpoint only.
b. has exceeded the warning and alarm setpoint.
c. was manually entered.
d. is out of range.

RO Question 69 Palisades 2012 NRC Initial License Exam Which one of the following correctly completes the statement below describing the design of the Shutdown and Regulating Control Rod interlocks?

During a Reactor startup, any Regulating Control Rod group is capable of being withdrawn when all Shutdown Control Rods are above a minimum of (1) inches and during a Reactor shutdown any Shutdown Control Rod group is capable of being inserted when all Regulating Control Rods are below a maximum of (2) inches.

a. (1) 130 (2) 6
b. (1) 130 (2) 4
c. (1) 124 (2) 6
d. (1) 124 (2) 4

RO Question 70 Palisades 2012 NRC Initial License Exam With the Plant at full power, which one of the following lists the minimum amount by which Pressurizer level would need to rise to exceed the Technical Specification limit?

a. 4%.
b. 6%.
c. 10%.
d. 12%.

RO Question 71 Palisades 2012 NRC Initial License Exam Given the following:

  • A maintenance activity is planned that will cause an expected alarm in the Control Room for at least two shifts
  • The equipment associated with the alarm is normally in service in the current Plant MODE Which one of the following describes (1) an action that will be taken to identify the alarm associated with the maintenance activity and (2) the location for documenting the alarm in accordance with EN-OP-115-08, Annunciator Response?
a. (1) A field deficiency tag will be placed next to the annunciator window.

(2) Annunciator Log.

b. (1) A field deficiency tag will be placed next to the annunciator window.

(2) Equipment Status Log.

c. (1) An annunciator flag will be placed on the annunciator window.

(2) Annunciator Log.

d. (1) An annunciator flag will be placed on the annunciator window.

(2) Equipment Status Log.

RO Question 72 Palisades 2012 NRC Initial License Exam Given the following:

  • The Operator has received a total dose of 1790 mrem year-to-date
  • The Operator is not wearing breathing protection
  • The area dose rate is 27 mrem/hour
  • The airborne levels are 5 DAC (Derived Air Concentration)
  • The task will take exactly 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Which one of the following correctly completes the statement below?

After this task is completed, the Operator will have exactly remaining until reaching the Entergy routine annual administrative dose limit.

a. 131 mrem
b. 146 mrem
c. 156 mrem
d. 631 mrem

RO Question 73 Palisades 2012 NRC Initial License Exam Given the following:

  • T-101B, Waste Gas Decay Tank, batch release is in progress
  • Then, V-6A, Main Exhaust Fan, trips
  • V-6B, Main Exhaust Fan, will not start Which one of the following describes the correct action to secure the T-101B release from the Control Room?
a. Secure all Auxiliary Building Ventilation.
b. Secure V-14A/B, Radwaste Area Exhausters.
c. Set the function switch on RIA-1113, Waste Gas Discharge Monitor, to 1.
d. Adjust the trip setpoint for RIA-1113 to below the current reading.

RO Question 74 Palisades 2012 NRC Initial License Exam With the Plant at full power, which one of the following is the lowest Primary Coolant System unidentified leak rate which ONP-23.1, Primary Coolant Leak, actions are designed to mitigate? Assume the leak rate was calculated in accordance with DWO-1, Operators Daily/Weekly Items, MODES 1, 2, 3, and 4.

a. 0.10 gpm.
b. 0.15 gpm.
c. 0.40 gpm.
d. 1.00 gpm.

RO Question 75 Palisades 2012 NRC Initial License Exam Which one of the following correctly defines the term Safety Function as used in the Emergency Operating Procedures?

a. Any condition or action needed to ensure that irradiated fuel remains covered with coolant for heat removal and radiation shielding requirements.
b. Any condition or action needed to preclude inadvertent dilution, criticality, power excursions, control rod manipulations, or loss of shutdown margin, and to monitor core reactivity behavior.
c. Any function performed by a system or component needed to mitigate a loss of the Primary Coolant System or Containment Barriers.
d. Any condition or action needed to either prevent core damage or to minimize radiation releases to the general public.