ML13148A356

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2013 Byron Nuclear Station Initial License Examination Administered Written Examination
ML13148A356
Person / Time
Site: Byron  Constellation icon.png
Issue date: 04/29/2013
From:
Exelon Generation Co
To:
Division of Reactor Safety III
References
Download: ML13148A356 (58)
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Text

2013 NRC RO Initial License Written Examination Page 1 of 58 QUESTION # 001 Given:

  • Unit 1 is at 100% power, normal at-power alignment.
  • A Main Generator TRIP occurs.
  • All 6.9 KV bus ABT interlocks fail to actuate.

Following the event, the RCPs RUNNING are:

a. 1A and 1C
b. 1B and 1A
c. 1C and 1D
d. 1D and 1B QUESTION # 002 Given:
  • The unit is at 100% power.
  • Rod control is in Manual, with CBD at 221 steps.

If the Moderator Temperature Coefficient (MTC) is -5.0 pcm/°F, under which of the following, would the MTC move CLOSEST to a value of 0.0 pcm/°F?

a. 5 step rod INSERTION
b. BORATION of 100 gallons
c. Load Rejection of 100 MWe
d. DILUTION of 100 gallons

2013 NRC RO Initial License Written Examination Page 2 of 58 QUESTION # 003 Given:

  • Unit 2 is performing a cooldown in MODE 4 on A Train RH, preparing to enter Mode 5 in the next hour.
  • 2RH606, HX 2A FLOW CONT VLV, has spuriously CLOSED Answer the following two (2) questions concerning this event.
1) 1)- The cooldown RATE will ...
2) 2)- The procedure used to reestablish control of 2RH606 is an attachment in
a. 1) Rise
2) BOA PRI-5, CONTROL ROOM INACCESSIBILITY
b. 1) Lower
2) 2BOA ELEC-5, LOCAL EMERGENCY CONTROL OF SAFE SHUTDOWN EQUIPMENT
c. 1) Lower
2) 2BOA PRI-5, CONTROL ROOM INACCESSIBILITY
d. 1) Rise
2) 2BOA ELEC-5, LOCAL EMERGENCY CONTROL OF SAFE SHUTDOWN EQUIPMENT QUESTION # 004 Unit 1 is in MODE 5
  • The RCS is solid with RH letdown in service
  • 1PI-615, 1B RH PUMP DISCHARGE pressure indicates 555 psig
  • RCS Wide Range pressure is 405 psig
  • 1-6-A3 RH SUCT PRESS HIGH
  • 1-6-B2 RH PUMP 1B DSCH PRESS HIGH System pressures are SLOWLY RISING at 10 psig per minute What is the status of the RH system relief valves 1 minute after receiving the above annunciators?
a. ONLY the RH pump discharge relief valve is LIFTING.
b. pump suction and discharge relief valves are BOTH CLOSED.
c. ONLY the RH pump suction relief valve is LIFTING.
d. RH suction AND discharge relief valves are BOTH LIFTING.

2013 NRC RO Initial License Written Examination Page 3 of 58 QUESTION # 005 Given the following plant conditions on Unit 1:

  • Reactor power is 25%
  • The crew is ramping the unit in accordance with 1BGP 100-3, POWER ASCENSION
  • 11 minutes ago SSPS train A ESF relay K626 (CNMT ISOL PHASE B) inadvertently actuated The following alarms are annunciated on Control Room annunciator panel 1-7:
  • A4-D4; RCP 1_, THERM BARR CC WTR FLOW LOW
  • E5; RCP BRNG CC WTR TEMP HIGH Answer the following two (2) questions:
1) Which parameter is expected to RISE?
2) What action is required to protect equipment?
a. 1) RCP Motor Bearing temperature
2) Reset the Phase B and re-open the valves that closed
b. 1) RCP Motor Bearing temperature
2) Trip the Reactor, then trip the RCPs
c. 1) RCP Seal Leak-off flow
2) Reset the Phase B and re-open the valves that closed
d. 1) RCP Seal Leak-off flow
2) Trip the Reactor, then trip the RCPs QUESTION # 006 Under which of the following conditions will the running SI pump(s) indicate the HIGHEST amps?
1. Inadvertent SI signal in Mode 1
2. Filling the SI Accumulators in Mode 2
3. During LOCA conditions when RCS pressure is 1200 psig
4. Upon realignment to Cold Leg Recirculation 20 minutes after LOCA initiation
a. 1
b. 2
c. 3
d. 4

2013 NRC RO Initial License Written Examination Page 4 of 58 QUESTION # 007 Given:

Unit 2 is at 100% power with all systems normally aligned for this condition.

Due to a turbine malfunction:

  • A large turbine load rejection has occurred resulting in both Pressurizer PORVs OPENING for about 30 seconds, with the Unit remaining on-line.
  • The Pressurizer PORVs have subsequently CLOSED.
  • PRT pressure indicates 8 psig.
  • PRT temperature indicates 120°F.

In regards to the above condition, answer the following two (2) questions concerning the changes to the PRT:

1. What normal function will be PREVENTED under this condition?
2. What procedure(s) will you use to restore the PRT to the original conditions?
a. 1) filling the PRT because 2RY-8030, PW to PRT ISOL VLV automatically CLOSES
2) BOP RY-4, DRAINING THE PRT and BOP RY-6, TEMPERATURE CONTROL OF THE PRT
b. 1) venting the PRT because 2RY-469, PRT to GW ISOL VLV automatically CLOSES
2) ONLY BOP RY-6, TEMPERATURE CONTROL OF THE PRT
c. 1) filling the PRT because 2RY-8030, PW to PRT ISOL VLV automatically CLOSES
2) ONLY BOP RY-6, TEMPERATURE CONTROL OF THE PRT
d. 1) venting the PRT because 2RY-469, PRT to GW ISOL VLV, automatically CLOSES
2) BOP RY-4, DRAINING THE PRT and BOP RY-6, TEMPERATURE CONTROL OF THE PRT

2013 NRC RO Initial License Written Examination Page 5 of 58 QUESTION # 008 Given:

  • Unit 1 experienced a LOCA from full power.
  • All systems responded as designed.
  • U-0 CC HX is aligned to Unit 1.
  • The crew is currently performing 1BEP ES-1.3, TRANSFER TO COLD LEG RECIRCULATION.

The crew is at step 1 of the procedure, Establish CC Flow to the RH Heat Exchangers, and has OPENED 1CC9412A, CC TO RH HX 1A ISOL VLV.

The crew is now OPENING 1CC9412B, CC TO RH HX 1B ISOL VLV.

What happens to CC flowrate through the 1A RH HX when 1CC9412B fully OPENS?

a. LOWERS from 5000 gpm to just over 3000 gpm.
b. LOWERS from >6000 gpm to just over 5000 gpm.
c. RISES from 3000 gpm to just under 5000 gpm.
d. RISES from 5000 gpm to > 6000 gpm.

QUESTION # 009 Given:

  • Unit 1 is shutting down for a refueling outage.
  • Reactor power is 10%.
  • The control boards are aligned per 1BGP 100-4, POWER DESCENSION, for this power level.

1PT507, MAIN STEAM HEADER PRESSURE, has FAILED to 100% of span.

The initial response of the Pressurizer Pressure Control system to this transient is to

a. OPEN spray valves and DE-ENERGIZE/ramp off Heaters
b. OPEN spray valves and ENERGIZE/ramp on Heaters
c. CLOSE spray valves and ENERGIZE/ramp on Heaters
d. CLOSE spray valves and DE-ENERGIZE/ramp off Heaters

2013 NRC RO Initial License Written Examination Page 6 of 58 QUESTION # 010 Given:

  • Unit 1 is at 100% and in a normal alignment for this power level.
  • Pressurizer pressure is 2233 psig and STABLE.
  • The following conditions exist for the Pressurizer Pressure and Level controls:
  • Master Pressurizer Pressure Controller, 1PK-455A, is in AUTO with output at 43%
  • Master Pressurizer Level Controller, 1LK-459, is in AUTO with output at 41%
  • 1 set of Pressurizer Back-up heaters are energized in MANUAL
  • The Variable heaters are showing minimum current
  • Both Pressurizer Spray valves show dual position indication The NSO depresses the "MAN" pushbutton of the Master Pressurizer Pressure Controller.

Then, the NSO depresses the "increase/raise" pushbutton for 1 second.

In response to these actions, the Pressurizer Spray valves will throttle ___(1)___.

Over the next few minutes the indicated Pressurizer level will ___(2)___.

a. (1) OPEN (2) RISE
b. (1) OPEN (2) Remain CONSTANT
c. (1) CLOSE (2) Remain CONSTANT
d. (1) CLOSE (2) RISE

2013 NRC RO Initial License Written Examination Page 7 of 58 QUESTION # 011 Given the following Unit 1 conditions:

  • Reactor power is 5%
  • An Instrument failure causes Bypass Permissive Light P-7 to EXTINGUISH
  • A grid disturbance has resulted in:

o All 6.9 KV bus voltages drop to 5200 V o Grid Frequency remains at 59.9 Hz In response, ALL RCPs will ___(1)___

AND the Reactor will ___(2)___.

(1) (2)

a. trip trip
b. trip remain at power
c. remain running remain at power
d. remain running trip QUESTION # 012 Given:
  • Unit 2 is at 95% power in a normal alignment for this condition.
  • With NO Operator action:

If a portion of the B Train ESF system malfunctions such that the following valves go to their ESF Actuation condition, what is the effect on the RCS over the NEXT ten (10) minutes?

  • 2CV112D, RWST TO CHG PMPS SUCT VLV.
  • 2SI8801B, CHG PMPS TO COLD LEGS INJ ISOL VLV.

RCS Tave change is driving rods ...

a. IN and PZR level is RISING.
b. OUT and PZR level is RISING
c. IN and Letdown is ISOLATED.
d. OUT and Letdown is ISOLATED.

2013 NRC RO Initial License Written Examination Page 8 of 58 QUESTION # 013 During an SI, the Containment Chilled Water System aligns such that:

the SX flow to the Containment Chillers ___(1)_____, and the Containment Chilled Water Pump ___(2)_____.

(1) (2)

a. is bypassed remains running
b. is bypassed trips
c. remains in service trips
d. remains in service remains running QUESTION # 014 Given:
  • 1B DG is out of service.
  • A Loss of All AC power has occurred on Unit 1, due to a series of electrical faults, coincident with a Loss of Coolant Accident
  • Unit 1 has implemented 1BCA 0.0, LOSS OF ALL AC POWER
  • ACB 1413, DG 1A FEED TO 4KV, indicating lights are extinguished Unit 2 is UNAFFECTED by the event At Unit 1's request, Unit 2 has made crosstie power available What will power the 1A CS pump?
a. 1A Diesel Generator
b. 2A Diesel Generator
c. SAT 242-1
d. SAT 242-2

2013 NRC RO Initial License Written Examination Page 9 of 58 QUESTION # 015 In MODE 3 how many Containment Spray (CS) Trains and Containment Cooling Trains (CCT) are required to be OPERABLE to meet Tech. Spec. LCO 3.6.6, CONTAINMENT SPRAY AND COOLING SYSTEMS?

CS CCT

a. 1 1
b. 1 2
c. 2 1
d. 2 2 QUESTION # 016 Given:
  • Unit 1 is MOL at 75% power steady state conditions, with the following:

o Main Generator MW output is 901MWe.

o DEH is in "MW IN".

o RCS average temperature is at 579.5 °F.

o Rods are in Manual.

Average Reactor Coolant Temperature has just DROPPED 0.7°F to 578.8°F, but Megawatts have remained CONSTANT.

Which ONE of the following could have caused this to occur?

a. A single S/G PORV inadvertently OPENED.
b. An EO just swapped the Aux. Steam header supply from Unit 1 to Unit 2.
c. A single S/G Safety inadvertently OPENED.
d. Letdown temperature dropped by 2°F.

2013 NRC RO Initial License Written Examination Page 10 of 58 QUESTION # 017 Given:

Unit 2 is at 100% power, in a normal alignment.

  • The Unit experienced a Loss of DC bus 211.
  • The Reactor is manually TRIPPED on LOWERING SG levels.
  • An SI has just ACTUATED.

Of the following, as SG levels LOWER, when will the 2A AFW pump START?

a. At the time of the SI Signal
b. When manually started from 2PM06J
c. At the time when SG levels reach the Lo-2 setpoint
d. Only when locally started QUESTION # 018 Given:
  • Unit 1 is at 55% power
  • All other systems are normally aligned for the current power level
  • 1B and 1C Feedwater pumps are operating in AUTO
  • An inadvertent AMS signal actuation has caused both U-1 AF pumps to start and deliver flow to the U-1 SGs
  • ALL U-1 SG NR levels begin to RISE
  • NO other actuations occur as a result of the inadvertent AMS signal With NO operator actions, FW system conditions stabilize in 10 minutes. Compared to BEFORE the AF pumps started, the CURRENT conditions are...
a. LOWER demand on 1SK-509A, MASTER FW PUMP SPEED CONTROLLER, and HIGHER Feedwater Pump Suction Pressure on 1PI-CB014
b. LOWER RPM on 1SI-285, FW PUMP 1C SPEED INDICATION, and HIGHER demand on 1FK540, FW REG VLV 1FW540, controller.
c. HIGHER demand on 1SK-509B, FW PUMP 1B SPEED CONTROLLER, and HIGHER MS/FW HDR DP on 1PI-509
d. HIGHER demand on 1C FW Pump Low Pressure governor Valve Indication and HIGHER SG HDR PRESS on 1PI-507

2013 NRC RO Initial License Written Examination Page 11 of 58 QUESTION # 019 Given:

  • Unit 1 is at 100% power in a normal alignment
  • A Reactor TRIP has occurred simultaneously with the LOSS of Instrument Bus 111
  • ALL SG levels are 17% NR With NO operator action what is the status of the Aux Feed system?
a. 1A AF pump is running but is NOT delivering flow to ANY SG 1B AF pump is running and delivering flow to ALL SGs
b. BOTH AF pumps are running and delivering flow to ALL SGs
c. 1A AF pump is NOT running 1B AF pump is running and delivering flow to ALL SGs
d. NEITHER AF pump is currently running QUESTION # 020 Given:
  • Unit 2 is at full power.
  • The Inverter for Instrument Bus 214 failed two hours ago.
  • Operators responded per 2BOA ELEC-2, LOSS OF INSTRUMENT BUS Unit 2
  • Instrument Bus 214 has been reenergized via the Constant Voltage Transformer (CVT).
  • Troubleshooting of the 214 Inverter is now in progress with the appropriate LCOARs entered.
  • During the troubleshooting Unit 2 experienced a loss of offsite power (LOOP).
  • 2A Diesel Generator (DG) started and energized Bus 241.

Assuming all components function correctly, which of the following describes the plant response for the 2B DG?

2B DG will...

a. START, ENERGIZE Bus 242, and START all required loads on the Sequencer
b. START, ENERGIZE Bus 242, but NOT START loads on the Sequencer
c. START but NOT ENERGIZE Bus 242
d. NOT START

2013 NRC RO Initial License Written Examination Page 12 of 58 QUESTION # 021 Given:

Unit 1 is at 100% power in a normal alignment for this power level.

What is the significance of this alarm?

Bus 157 has LOST Normal Control Power but Reserve Control Power ...

a. may be available through a NO-BLOW Link by MANUALLY placing it in service from the OPPOSITE train DC Bus.
b. will AUTOMATICALLY transfer through a NO-BLOW Link fed from the OPPOSITE train DC Bus.
c. may be available through a NO-BLOW Link by MANUALLY placing it in service from the SAME DC Bus.
d. will AUTOMATICALLY transfer through a NO-BLOW Link fed from the SAME DC Bus.

QUESTION # 022 Given:

  • Unit 1 is at 100% power in a normal full power alignment.
  • Annunciator 1-4-A5, BUS 111 INVERTER TROUBLE, has just alarmed.
  • An Equipment Operator (EO) has been dispatched to investigate this alarm.

With these conditions, you would expect the EO to report that Instrument Inverter 111 ...

a. AC input breaker is OPEN and DC current output of Battery Charger 111 has RISEN.
b. DC input breaker is OPEN and DC current output of Battery Charger 111 has DROPPED.
c. AC input breaker is OPEN and DC current output of Battery Charger 111 has remained CONSTANT.
d. DC input breaker is OPEN and AC current output of Inverter 111 has RISEN.

2013 NRC RO Initial License Written Examination Page 13 of 58 QUESTION # 023 Given:

You have started the 1A DG from the control room in accordance with BOP DG-11, DIESEL GENERATOR STARTUP. Actions are being taken to parallel the 1A DG to Bus 141.

Your control board indications are as follows:

  • Incoming Voltage: 122 volts
  • Running Voltage: 124 volts
  • Sync Scope is rotating Slowly in the SLOW direction If the DG Output Breaker were CLOSED, which of the following would occur/be observed on the two (2) 1PM01J Control Board meters below?

DG 1A Output VARs DG 1A Output Watts

a. OUT at/near 0
b. IN goes UP
c. OUT goes UP
d. IN at/near 0

2013 NRC RO Initial License Written Examination Page 14 of 58 QUESTION # 024 Given:

  • Unit 1 is at 100% power
  • 1A and 1B CW pumps are operating
  • 1C CW pump is shutdown
  • Unit 1 is supplying CW blowdown
  • A release of 0WX01T, Liquid Radwaste Release Tank, is in progress with 0PR01J, LIQUID RELEASE EFFLUENT RAD MON, online The following occurs:
  • A problem with 1CW018, U-1 CW B/D ISOL VLV, causes total station CW blowdown flow to drop to 5800 gpm.

With the above condition, the AUTOMATIC plant response will be....

a. an EQUIPMENT FAILURE of the 0PR01J, due to a loss of process flow but NOT a termination of the liquid release.
b. termination of the liquid release by an OPERATE FAILURE of the 0PR01J, due to a loss of sample flow.
c. termination of the liquid release by a DIRECT low blowdown flow signal to the Release Tank Discharge Isolation Valves.
d. a CIRC WTR BLOWDOWN FLOW LOW alarm at 0PL01J panel but NOT a termination of the liquid release.

2013 NRC RO Initial License Written Examination Page 15 of 58 QUESTION # 025 Given:

  • Both units were at 100% power in a normal alignment for this power and have just experienced a Loss of All AC Power.
  • Both units have entered the appropriate procedures.

Currently:

  • The 1B DG is the ONLY power source available for BOTH Units
  • Busses 142 and 242 are energized
  • The 1B SX pump has tripped on a motor fault Which of the following valves will be manipulated to allow SX cooling for the 1B DG's continued operation?
a. 0SX146 CC HX 0 OUTLT VLV
b. 1SX034, PP 1B XTIE VLV
c. 1SX005 and 2SX005, CC HX 0 INLT VLVs.
d. 2SX005, CC HX 0 INLT VLV, and 0SX007, U-0 CC HX OUTLT VLV QUESTION # 026 Given the following plant conditions:
  • Both Units are at 100%, with all systems in normal alignment.
  • 1A and 2B SX pumps are currently running, with 140 amps running current indicated for each pump.
  • 1A SX discharge pressure is 100 PSIG.

The NSO notes the following changes to the SX system:

  • 1A SX pump current LOWERS to 130 amps then stabilizes.
  • 1A SX pump discharge pressure on 1PM06J RISES to 110 PSIG then stabilizes.

The cause of this change to SX is that...

a. 1SX001A, PP 1A SUCT VLV, was CLOSED.
b. 1SX143A, 1A SX PP DSCH DWST OF STRNR ISOL VLV, was CLOSED.
c. 1SX033, PP 1A SX XTIE VLV, was CLOSED.
d. 1SX150A, 1A SX STRN BKWH OUTLET TO TR SYS ISOL VLV, was OPENED.

2013 NRC RO Initial License Written Examination Page 16 of 58 QUESTION # 027 Given:

A 4 inch line break in the...

a. IA header will result in BOTH IA and SA depressurizing at approximately the same rate.
b. SA header will result in ONLY SA depressurizing.
c. SA header will result in BOTH IA and SA depressurizing at approximately the same rate.
d. IA header will result in ONLY IA depressurizing.

QUESTION # 028 Given:

  • Unit 2 is in Mode 1.
  • The 2A, 2C, and 2D RCFCs are operating in high speed.
  • The 2B RCFC is in standby.

The following indications are observed on the Unit 2 RCFC Dry Bulb temperatures:

  • 2A RCFC Inlet Temperature 119°F.
  • 2B RCFC Inlet Temperature 126°F.
  • 2C RCFC Inlet Temperature 124°F.
  • 2D RCFC Inlet Temperature 119°F.

Per Tech Spec 3.6.5, Containment Air Temperature, ...

a. NO action is necessary because the average of ALL OPERATING RCFC temperatures are within the appropriate LCO limit(s).
b. the action requirement must be applied because the average of ALL OPERATING RCFC temperatures EXCEEDS the LCO upper limit.
c. the action requirement must be applied because the average of ALL RCFC temperatures EXCEEDS the LCO upper limit.
d. NO action is necessary because ALL the RCFC temperatures are within the appropriate LCO limit(s).

2013 NRC RO Initial License Written Examination Page 17 of 58 QUESTION # 029 Concerning BEP-0, REACTOR TRIP OR SAFETY INJECTION, Step 3, which states; Verify Power To 4KV ESF Busses.

Answer the following:

(1) The primary function of this step is to ensure ...

(2) The reason for this step is to ...

a. (1) electric power to at least one 4KV ESF Bus.

(2) determine if the EDGs are supplying any ESF busses.

b. (1) electric power to BOTH 4KV ESF Busses.

(2) ensure power to operate ALL safeguards equipment.

c. (1) electric power to at least one 4KV ESF Bus.

(2) ensure adequate power to operate REQUIRED safeguards equipment.

d. (1) electric power to BOTH 4KV ESF Busses.

(2) determine if the EDGs are supplying any ESF busses.

QUESTION # 030 Given:

  • Unit 1 is at 100% power
  • All systems are normally aligned
  • 1RY456, PZR PORV, fails to 10% open and CANNOT be closed or isolated.
  • PRT pressure is currently 15 psig
  • PRT temperature is 170°F.
  • RCS pressure is currently 2000 psig Based on the above indications, 1TI-463, PORV TEMP, would currently be indicating...

(choose closest answer)

a. 170°F
b. 212°F
c. 250°F
d. 635°F

2013 NRC RO Initial License Written Examination Page 18 of 58 QUESTION # 031 Given:

A LOCA has occurred, with SI actuated.

The crew has transitioned from 1BEP-0, REACTOR TRIP OR SAFETY INJECTION, to 1BEP-1, LOSS OF REACTOR OR SECONDARY COOLANT.

Current conditions are:

  • RCPs have been tripped
  • CETC temperature is 580°F and STABLE
  • RCS pressure is 1310 psig and STABLE SI has been RESET BOTH RH pumps have been stopped and placed in STBY.

A SAT fault occurs that DE-ENERGIZES both 4KV ESF busses The DGs load as designed What ECCS pump control switch or ESF switch manipulations will you perform based on the conditions above?

a. BOTH RH and BOTH SI pumps must be restarted using the MCB control switches.
b. Place ONLY the RH pump control switches in PULL OUT
c. ONLY the SI pumps must be restarted using the MCB control switches.
d. Manually initiate a Safety Injection QUESTION # 032 Given:
  • A Design Bases LOCA occurs.
  • ALL ECCS systems FAIL in addition to the CS system.

During the transition from Natural Circulation cooling to Reflux Boiling, which of the following parameters STOPS lowering?

a. SG Pressure
b. Containment Pressure
c. RCS Th
d. RCS Tc

2013 NRC RO Initial License Written Examination Page 19 of 58 QUESTION # 033 Given:

  • Unit 1 is at 35% power in a normal alignment for this condition.

o Annunciator 1-13-E5, RCP TRIP, has just LIT due to a trip of the 1A RCP.

Based on 1PM05J indications:

(1) Which 1A RCP control switch lights will be LIT?

(2) Compared to BEFORE the event, five minutes later, indicated loop DELTA Temp for loops 1B, 1C and 1D are ...

a. (1) stop ONLY (2) lower.
b. (1) stop AND disagreement (2) lower.
c. (1) stop AND disagreement (2) higher.
d. (1) stop ONLY (2) higher.

QUESTION # 034 Given the following plant conditions on Unit 1:

  • The reactor is at full power with the plant in a normal lineup.
  • Letdown is 120 gpm
  • VCT level is 50%.
  • 1LT-112, VCT level transmitter, develops an erroneous signal with a constant output of 95%.

If NO Operator action is taken for 10 minutes:

VCT level will drop until the VCT __(1)__. The running CV pump ammeter will indicate __(2)__.

____(1)____ _______(2)_______

a. level reaches 37%. NO change in amps.
b. level reaches 20%. LOWERING amps.
c. level reaches 5%. LOWERING amps.
d. is empty. FLUCTUATING amps.

2013 NRC RO Initial License Written Examination Page 20 of 58 QUESTION # 035 Given:

  • Unit 2 is in MODE 5 with LSIVs open
  • All loops are filled.
  • NO RCPs are running but enough are available to satisfy Tech. Specs.
  • 2RH607, HX 2B FLOW CONT VLV, has failed OPEN.

Which of the following RCS Temperature instruments would react to this failure FIRST?

a. A - Loop narrow range Tcold
b. B - Loop wide range Tcold
c. Core Exit Thermocouples
d. D - Loop wide range Thot QUESTION # 036 Given:
  • Unit 1 has been in Shutdown Cooling for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in preparation for a refuel outage.
  • BOTH U-1 CC pumps are operating.
  • Current CC HX Outlet Temperature is 100°F Then:
  • CC flow is reduced by 50% due to a loss of a CC pump
  • the above temperature starts RISING by 1°F per minute How long will it take to reach CC HX Outlet Temperature HIGH operating limit?
a. 5 minutes
b. 18 minutes
c. 20 minutes
d. 25 minutes

2013 NRC RO Initial License Written Examination Page 21 of 58 QUESTION # 037 Which ONE of the following selections is used as verification that the reactor is subcritical prior to exiting 2BFR-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS, following an ATWS event?

a. Negative Startup Rate on the IR channels AND PR channels less than 5%
b. Startup Rate MORE NEGATIVE than -0.2 DPM on the IR channels AND PR channels less than 5%.
c. Reactor Trip and Bypass breakers are OPEN AND all rod bottom lights are LIT
d. Negative Startup Rate on the SR channels AND PR channels less than 5%.

QUESTION # 038 Given:

  • Unit 2 has tripped from 100% power
  • Annunciator 2-11-D1, STEAM LINE LOW PRESS SI/RX TRIP, is LIT The following procedure transitions have been performed:
  • 2BCA 2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS The crew is currently at Step 2 of 2BCA 2.1, CONTROL FEED FLOW TO MINIMIZE RCS COOLDOWN Steam generator pressures are as follows:
  • 2A 240 psig and LOWERING
  • 2B 230 psig and LOWERING
  • 2C 280 psig and RISING
  • 2D 240 psig and LOWERING With the above conditions, the U2 Operators will...
a. transition directly to 2BEP-2.
b. transition to 2BEP ES-0.0, REDIAGNOSIS, then transition to 2BEP-1, LOSS OF REACTOR OR SECONDARY COOLANT.
c. continue in the present procedure until completed.
d. complete the SI Termination steps, then transition to 2BEP-2.

2013 NRC RO Initial License Written Examination Page 22 of 58 QUESTION # 039 On a Loss of Heat Sink, if the criteria for initiating Bleed and Feed are met, why are the PZR PORVs both manually OPENED instead of being allowed to cycle?

a. To prevent exceeding the DP pressure limit across the SG U-tubes.
b. To permit adequate feed of subcooled ECCS flow.
c. To minimize RCS Subcooling.
d. To raise PZR level high enough to compensate for any Reactor Vessel void collapse.

QUESTION # 040 Given:

  • Unit 1 is at 100% power in a normal alignment, when a Loss of Offsite Power (LOOP) occurs.
  • Operators have started ramping the Unit offline.
  • When power reaches 27%, the Main Generator TRIPS.

Of the following, which procedure is entered next?

a. 1BEP 0, REACTOR TRIP OR SAFETY INJECTION
b. 1BOA TG-8, TURBINE TRIP BELOW P8
c. 1BOA ELEC-4, LOSS OF OFFSITE POWER
d. 1BCA 0.0, LOSS OF ALL AC POWER QUESTION # 041 Given:
  • Unit 2 is at 100% power in a normal line up for this condition
  • Instrument Bus 212 has just DE-ENERGIZED Which of the following automatic features is LOST?
a. 2RY455A Automatic OPENING on High pressure
b. Automatic Rod WITHDRAWAL
c. Automatic Rod INSERTION
d. P-10 Permissive "Nuclear at Power"

2013 NRC RO Initial License Written Examination Page 23 of 58 QUESTION # 042 Given:

  • Unit 2 is at 75% power, normal alignment.
  • The 2A Regen HX is in service with 120 gpm letdown flow.

The following sequence of events occurs:

  • A control power fuse for 2IA065, INSTRUMENT AIR INSIDE CNMT ISOL VLV, blows in 2PM11J.
  • Instrument Air to Unit 2 containment is isolated and ALL air operated valves in containment are in their FAIL position.
  • Five (5) minutes later, the defective fuse is replaced and 2IA065 is re-opened.
  • Instrument Air is fully restored to Unit 2 containment.

NO other operator actions have been taken (i.e. assume all CVCS valve control switches have NOT been moved from their normal at power alignment).

With the above conditions, the NSO monitoring 2PM05J will note which of the following letdown valves has AUTOMATICALLY RE-OPENED?

a. 2CV8149A, 45 GPM LTDWN ORIF 2A ISOL VLV
b. 2CV8160, LTDWN LINE CONT ISOL VLV
c. 2CV459, LTDWN LINE ISO VLV
d. 2CV8389A, LTDWN TO REGEN HX 2A ISOL VLV

2013 NRC RO Initial License Written Examination Page 24 of 58 QUESTION # 043 Given:

  • U-1 was at 100% power, normally aligned

The crew entered:

  • 1BEP-0, REACTOR TRIP OR SAFETY INJECTION and at step 32 based on abnormal radiation in the Aux. Bldg transitioned to:
  • 1BCA-1.2, LOCA OUTSIDE CONTAINMENT The crew is currently at Step 2, Try to Identify and Isolate Break 1SI8835, SI PUMP TO COLD LEG ISOLATION VALVE, has just been CLOSED.

At the completion of step 2, 1SI8835 would be left CLOSED if:

a. CETC temperatures begin LOWERING.
b. SI pump discharge pressure begins RISING.
c. RCS pressure begins RISING.
d. Pressurizer level begins RISING.

QUESTION # 044 Given:

An event occurred on Unit-1 which resulted in a LOCA with Containment Spray Actuation.

The crew has transitioned to 1BCA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION, when cold leg recirculation capability could not be verified in 1BEP-1, LOSS OF REACTOR OR SECONDARY COOLANT.

The current conditions are:

  • One Trains of CS is running
  • The crew has just completed step 12 in BCA-1.1 to Establish One Train of ECCS Flow.
  • RWST level has just reached 8%.

What must be done next?

a. Go to 1BEP-ES1.3, TRANSFER TO COLD LEG RECIRCULATION.
b. Go to 1BCA-1.3, SUMP BLOCKAGE CONTROL ROOM GUIDELINE
c. STOP ONLY the CS pump aligned to the RWST.
d. Place switches for pumps taking suction from the RWST in PULL-OUT.

2013 NRC RO Initial License Written Examination Page 25 of 58 QUESTION # 045 The basis for stopping the RCPs in BFR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, is that it allows the operator...

a. more control over cooldown via natural circulation when feedwater is established.
b. to reduce the heat addition to the RCS and extend the inventory in the steam generators.
c. time to establish a higher flow rate for high pressure SI thus raising the RCS cooldown rate.
d. time to depressurize the intact steam generators in order to reduce RCS pressure and inject accumulators.

QUESTION # 046 The following plant conditions exist:

Unit 1 Unit 2

  • Power 90% 100%
  • Voltage Regulator ON ON
  • Generator Field Amps 110 and RISING 75 and LOWERING
  • Generator Field Forcing alarm LIT NOT LIT
  • ComEd Grid status Stable
  • 345kV bus 7 voltage 356kV increasing Complete the two statements below:

(1) Your action is to...

(2) and the reason for taking the action is:

a. (1) place the Voltage Regulator to OFF and LOWER the field amps to <100 using the BASE ADJUSTER.

(2) to prevent over-exciting the Main Power Transformers.

b. (1) place the Voltage Regulator to OFF and LOWER the field amps to <100 using the BASE ADJUSTER.

(2) to prevent a Main Generator TRIP.

c. (1) place the Voltage Regulator to OFF and LOWER the field amps to <109 using the VOLT ADJUSTER.

(2) to prevent a Main Generator TRIP.

d. (1) place the Voltage Regulator to OFF and LOWER the field amps to <109 using the VOLTAGE ADJUSTER.

(2) to prevent over-exciting the Main Power Transformers.

2013 NRC RO Initial License Written Examination Page 26 of 58 QUESTION # 047 Given:

  • Reactor power is 99% and STABLE.
  • All systems are in automatic, operating normally.
  • Tave is 586°F.
  • Tref is 586°F.
  • The secondary plant is STABLE.

Control Bank D rods have just started stepping OUT at 8 steps per minute.

  • Annunciator 1-10-D5, BANK DELTA ROD STOP C-11, just alarmed.

Control Bank D rods are continuing to step OUT at 8 steps per minute.

Your FIRST actions as the Unit NSO, based on these indications, will be to...

a. TRIP the reactor.
b. place the Rod Bank Select Switch to the SHUTDOWN BANK D position and exercise rods by stepping the rods in 7 steps and out 7 steps.
c. place the Rod Bank Select Switch to the CONTROL BANK D position and adjust turbine load and/or boron concentration to match Tave to Tref.
d. place the Rod Bank Select Switch to the MANUAL position and if rod motion continues, cycle the IN-OUT switch.

2013 NRC RO Initial License Written Examination Page 27 of 58 QUESTION # 048 Given:

  • Unit 1 has just ramped down to 80%.
  • ROD DEV POWER RNG TILTS, (1-10-A7), annunciates.
  • The NSO observed a rod ratcheting into the core and placed rods in MANUAL.
  • Control bank D is at 185 steps and rod D4 in control bank D is at 60 steps.

The problem is repaired 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> later.

  • NO rod motion has occurred.
  • The operators are ready to realign the rods.

During the realignment, reactor power is restricted to less than __(1)__ % and the LARGEST Tave to Tref mismatch is limited to __(2)__ °F.

a. (1) 50 (2) 3
b. (1) 70 (2) 3
c. (1) 50 (2) 1
d. (1) 70 (2) 1 QUESTION # 049 Which of the listed Rad Monitors will (1) start a fan AND (2) place a filter unit on line due to High Area radiation?
a. 0AR055/56, FHB INCIDENT
b. 2AR11/12, CONT FUEL HANDLING INCIDENT
c. 0AR039, FHB CRANE
d. 2AR020/21, CONT HI RANGE AREA MONITOR

2013 NRC RO Initial License Written Examination Page 28 of 58 QUESTION # 050 Given:

  • A liquid release is in progress from Release Tank 0WX01T.
  • 0PR01J, LIQUID RADWASTE EFFLUENT RAD MONITOR, has ALARMED on the RM-11 with a DARK BLUE Color.

Answer the following concerning this condition:

(1) What monitor condition does the color represent?

(2) The Liquid Release has...

a. (1) Equipment Failure (2) terminated.
b. (1) Operate Failure (2) terminated.
c. (1) Equipment Failure (2) continued.
d. (1) Operate Failure (2) continued.

QUESTION # 051 Why does the annunciator response procedure for an Alert condition on 1AR022A, 1A Main Steamline, require you to notify Chemistry?

Chemistry is notified to ...

a. sample the 1A SG for rising activity.
b. prepare for a conductivity excursion from a leaking main condenser tube.
c. raise the rate of blowdown flow from the 1A SG.
d. determine high temperature effects on the monitor.

2013 NRC RO Initial License Written Examination Page 29 of 58 QUESTION # 052 Given:

  • The unit is in an accident condition.

The STA is monitoring the Status Trees and reports that:

  • CETC Temperature is 568°F and RISING
  • RCS Pressure is 1150 psig and LOWERING The condition of the RCS Coolant at the Core Exit is ...
a. supersaturated vapor.
b. subcooled liquid.
c. superheated steam.
d. saturated steam.

QUESTION # 053 Given:

  • The plant is at 100% power.
  • All control systems are in a normal/automatic line-up.
  • The controlling PZR level transmitter, LT-459 sticks at the full power value.
  • Then a ramp has started to 80% power.

Which of the following describes the subsequent charging flow and Master PZR Level controller response? (Assume NO operator action is taken aside from initiating the ramp)

Charging Master PZR Level Flow Controller Demand

a. lowers lowers
b. lowers rises
c. unchanged lowers
d. unchanged rises

2013 NRC RO Initial License Written Examination Page 30 of 58 QUESTION # 054 Given:

  • The unit is at 100% power, in a normal alignment.
  • The reactor does NOT TRIP, and power operation continues uninterrupted.

Which of the following is the likely cause of this annunciator?

a. CNMT Hi Range Area Monitor RE-AR21 failed HIGH
b. CNMT Fuel Handling Incident Monitor RE-AR11 failed HIGH.
c. One of the two CNMT Spray Actuation switches on PM06J was taken to ACTUATE.
d. CNMT Purge Exhaust Monitor RE-PR001 failed HIGH.

QUESTION # 055 Given the following sequence of events:

  • Unit 1 is at 100% power with Pressurizer pressure channel 1PT-455 bistables TRIPPED
  • All other equipment is in a normal alignment Subsequently, Pressurizer pressure transmitter 1PT-458 FAILS LOW causing a low Pressurizer pressure SI.

5 minutes later the crew has transitioned to 1BEP ES-1.1, SI TERMINATION.

The NSO depresses BOTH SI RESET pushbuttons, The BYPASS-PERMISSIVE PANEL silence, acknowledge, and reset pushbuttons are depressed.

With the above conditions, which of the following BYPASS-PERMISSIVE LIGHTS will be LIT?

a. AUTO SI BLOCKED
b. PZR SI BLOCK TRN A
c. SI ACTUATED
d. PZR LOW PRESS SI BLOCK PERMISSIVE P11

2013 NRC RO Initial License Written Examination Page 31 of 58 QUESTION # 056 Given:

  • Reactor Power - 33%
  • Gen MW - 342 MWe
  • Rod Control - Automatic with CBD at 144 steps
  • PZR level - on program
  • RCS Tave - on program Answer the following:

If Turbine Impulse Pressure Transmitter, PT-505, fails LOW, over the next few minutes the ...

(1) RCS temperature will...

(2) PZR level will...

a. (1) rise (2) rise
b. (1) rise (2) remain the same
c. (1) lower (2) remain the same
d. (1) lower (2) lower QUESTION # 057 Implementation of 2BFR C.1, RESPONSE TO INADEQUATE CORE COOLING, is safety significant when CETCs are > 1200°F because additional operator action is required to ...
a. limit containment pressure to less than the design pressure.
b. prevent core uncovery.
c. maintain coolable core geometry.
d. ensure adequate heat removal capability of the Steam Generators.

2013 NRC RO Initial License Written Examination Page 32 of 58 QUESTION # 058 Given:

  • Unit 1 is at 100% power.
  • All systems are normally aligned.

Which of the following components will LOSE power if 480V MCC 133X4 is DE-ENERGIZED?

a. 1VP02CA, 1A Containment Charcoal Filter Unit Fan.
b. 1CV8324A, Charging to Regen HX 1A Isolation Valve.
c. 1IP07E, Instrument Inverter 113.
d. 1CV460 Letdown Line Isolation Valve.

QUESTION # 059 Given:

  • 5 minutes ago, Unit 1 reactor was manually tripped from 5% power during a normal shutdown.
  • All systems operated as designed.
  • Current SG Narrow Range levels are ALL 50% and stable.
  • ALL alarms at 1PM05J have been acknowledged, but NOT reset.

With the above conditions, if the NSO momentarily places the ROD CONT STARTUP switch on 1PM05J, to the START UP position ...

a. all control rod group step counters will reset to zero.
b. alarm 1-11-A1, MANUAL RX TRIP, will clear (slow flash).
c. alarm 1-10-E6, ROD AT BOTTOM, will clear (slow flash).
d. the Rod Drive M-G set input breakers will close.

2013 NRC RO Initial License Written Examination Page 33 of 58 QUESTION # 060 Given:

  • The Unit is in MODE 6 performing fuel moves.

Answer the following two (2) questions concerning radiation monitor 0RE-AR039, FUEL HANDLING BUILDING CRANE, and the effects it will have on FHB fuel movement.

(1) In which color coded monitor condition will communication between the monitor and the RM-11 be lost?

(2) How will fuel movement be restricted if the RM-11 cursor is RED?

a. (1) Yellow (2) Prevents ALL crane motion
b. (1) Magenta (2) Prevents ALL crane motion
c. (1) Yellow (2) Prevents UPWARD motion ONLY
d. (1) Magenta (2) Prevents UPWARD motion ONLY QUESTION # 061 During a cooldown on Unit 1, the following conditions exist:
  • RCS loop Tave indications - 550°F (1A), 548°F (1B), 551°F (1C), 548°F (1D)
  • Steam header pressure - 1030 psig
  • Steam Dump Mode Selector switch - STM PRESS MODE
  • The operator bypasses P-12 in accordance with 1BGP 100-5, PLANT SHUTDOWN AND COOLDOWN
  • Steam Dump Controller - MAN set at 30% demand What is the status of the Steam Dump valves following the operator's actions?

(Assume NO jumpers have been installed that would impact normal steam dump operation)

a. ONLY THREE valves in group 1 are fully OPEN. ALL other valves are CLOSED.
b. THREE valves in group 1 are fully OPEN and THREE valves in group 2 are partially OPEN.
c. ALL valves are CLOSED.
d. THREE valves in group 1 are partially OPEN.

2013 NRC RO Initial License Written Examination Page 34 of 58 QUESTION # 062 Given:

  • A release of the 0A Gas Decay Tank (GDT) is in progress per BCP 400-TWASTE GAS, Gaseous Effluent Release Form Type: Waste Gay Decay Tank.
  • Subsequently, the 0B (on line) GDT relief valve fails (sticks) open.
  • The rise in flow past 0PR02J, GDT EFFLUENT, rad monitor causes the skid to exceed the high radiation ALARM setpoint.

With the above conditions, ...

a. the 0A GDT effluent will be AUTOMATICALLY isolated, but the 0B GDT effluent can NOT be isolated.
b. BOTH the 0A and 0B GDT effluents will be AUTOMATICALLY isolated.
c. the 0A GDT effluent must be MANUALLY isolated, but the 0B GDT effluent can NOT be isolated.
d. BOTH the 0A and 0B GDT effluents must be MANUALLY isolated by CLOSING 0GW014,WASTE GAS DISCH VLV.

QUESTION # 063 Unit 2 is at 100% power with:

  • All systems are in a normal alignment for this power, with
  • 2B and 2C MFW pumps operating.
  • 2A, B, and C CD/CB pumps operating
  • 2D CD/CB pump is in standby The 2C CD/CB pump trips on overcurrent. All systems/components respond as designed.

This event causes the following annunciators:

  • 2-17-A9 CD/CB PUMP TRIP
  • 2-17-B9 CD/CB PUMP AUTO START You have entered 2BOA SEC-1, SECONDARY PUMP TRIP- Unit 2.

Which of the below actions is specified per 2BOA SEC-1?

a. Initiate a CD/FW Runback
b. Verify 2CD152, CONDENSATE PUMPS RECIRC VLV CLOSES automatically
c. Verify 2CB113C, CB PP RECIRC VLV CLOSES 30 seconds after the pump tripped
d. Verify 2CD157A/B, GLAND STEAM CONDENSER BYPASS VLV CLOSE automatically

2013 NRC RO Initial License Written Examination Page 35 of 58 QUESTION # 064 If the NORMAL source of make-up water to the Mechanical Draft Cooling Towers is LOST, which system provides the automatic EMERGENCY water source?

a. Circ. Water
b. CW Makeup
c. Well Water
d. SX Makeup QUESTION # 065 Given:
  • Both units are operating normally at 100% power.
  • A hydrant valve was opened and fire protection system header pressure LOWERED to 130 psig.
  • All fire protection system components operate as designed.

The hydrant valve has been CLOSED and system pressure is now 160 psig.

What, if any, control switch manipulations will be performed to restore the system to a normal alignment?

a. NO action required to restore the system to normal.
b. LOCALLY place the 0A Motor Driven Fire Pump control switch in TRIP then release.
c. Place the 0A Motor Driven Fire Pump control switch in the MCR in TRIP then release.
d. LOCALLY place the 0A Motor Driven Fire Pump control switch in STOP then release AND 0B Diesel Driven Fire Pump control switch in OFF.

2013 NRC RO Initial License Written Examination Page 36 of 58 QUESTION # 066 Given:

  • The U-1 Unit Supervisor (US) is currently behind the control boards attending a brief.
  • Subsequently a transient occurs on U-1 requiring an immediate operator action step from an approved procedure to stabilize the plant.

In accordance with OP-AA-101-111, ROLES AND RESPONSIBILITIES OF ON-SHIFT PERSONNEL, the Reactor Operator will perform the action ...

a. promptly after receiving a peer check.
b. promptly from memory without waiting for the US to confirm the action.
c. only after the procedure is in hand and the RO has read the step.
d. only after the US is at the Unit desk and agrees with verbalization of the action.

QUESTION # 067 In accordance with 1BGP 100-6 REFUELING OUTAGE, which of the following requires suspension of fuel assembly movements in the containment?

a. One Fuel Building Exhaust Ventilation system Inoperable
b. Loss of communications between the Control Room and Refueling Station personnel in containment
c. Loss of one Source Range Post Accident Neutron Monitor
d. Refueling cavity level is 23'6" above the top of the Reactor Vessel Flange

2013 NRC RO Initial License Written Examination Page 37 of 58 QUESTION # 068 Considering the Feedwater system and SG differences between the Units:

Which unit has a Feedwater pump delta-P program of 80 to 218 psid?

Which unit has a Lo-2 SG Level Reactor Trip setpoint of 36.3% narrow range level?

Unit that has:

Delta-P program of 80 Lo-2 SG Level Reactor Trip to 218 psid setpoint of 36.3%

a. 1 1
b. 1 2
c. 2 1
d. 2 2 QUESTION # 069 Given:
  • Unit 1 is at 100% power, normal alignment.
  • Maintenance is needed on 480V Unit Sub Station (U.S.S.) (rackable) breakers.

Which one of the below cases would require entry into LCO 3.8.9, DISTRIBUTION SYSTEMS OPERATING?

Racking out ...

a. load breaker on Bus 132X for 1VP01CD, RCFC FAN 1D HIGH SPEED BKR.
b. load breaker on Bus 133X for 1WO01PA, PRI. CONT. CHILLED WATER PP.
c. feed breaker to Bus 132X to remove stuck breaker for 1TO06P, TURBINE BEARING OIL PP.
d. feed breaker to Bus 133X to remove stuck breaker for 1VQ01CA, CONT PURGE SUPPLY FAN.

2013 NRC RO Initial License Written Examination Page 38 of 58 QUESTION # 070 Given:

  • Unit 1 is performing a refueling outage.
  • The following conditions existed at turnover:
  • RCS Temp 190°F
  • 1B RH Train INOPERABLE due to stuck closed suction valve.
  • 1B and 1D RCS Loops LSIVs OPEN with RCPs secured.

During the shift, draining of the 1B and 1D SGs is commenced. Level is currently ~10% NR Level.

Which ONE of the following is an ACTION that is REQUIRED to be performed per Technical Specifications?

a. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> start either 1B or 1D RCP.
b. IMMEDIATELY suspend all operations involving a reduction in RCS boron concentration.
c. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate action to place the 1B RH Train in operation.
d. IMMEDIATELY initiate action to restore 1B and 1D SG level above required value.

2013 NRC RO Initial License Written Examination Page 39 of 58 QUESTION # 071 You are assigned a task in a tank room in the Auxiliary Building.

  • The room was recently surveyed and the following radiological conditions are listed on the RWP survey map:
  • General area radiation levels: 110 mR/Hr.
  • Airborne radiation is 0.25 DAC.
  • Contamination levels of 250dpm/100cm2 beta/gamma and 25 dpm/100cm2 alpha.

When you arrive at the room, there are 2 posted signs as follows:

  • Caution- Radiation Area
  • Caution- Contamination Area What actions (if any) are required/allowed and why?
a. Do NOT proceed; notify RP Department because the Radiation Area posting is INCORRECT.
b. Do NOT proceed; notify RP Department because the Contaminated Area posting is INCORRECT.
c. Do NOT proceed; notify RP Department because the room also requires a posting of Caution- Airborne Radioactivity Area.
d. Proceed with the assigned task because ALL postings ARE correct and complete.

QUESTION # 072 When people have entered containment, in accordance with BAP 1450-1, ACCESS TO CONTAINMENT, each of the following activities are allowed EXCEPT...

a. changing reactor power by 1%.
b. a Control Rod position adjustment while in MODE 1.
c. a reactor startup.
d. RCS dilution.

2013 NRC RO Initial License Written Examination Page 40 of 58 QUESTION # 073 Given the following plant conditions:

  • RCS pressure is 300 psig.

If 100 GPM leaks develop in both the 1A CC Heat Exchanger and the 1A RH Heat Exchanger, the SX system __(1)__ become contaminated, because __(2)__.

___(1)___ ____________(2)___________

a. will NOT RH pressure is LESS than CC pressure, which is LESS than SX pressure
b. will RH pressure is GREATER than CC pressure, which is GREATER than SX pressure
c. will NOT RH pressure is GREATER than CC pressure, which is LESS than SX pressure
d. will NOT RH pressure is LESS than CC pressure, which is GREATER than SX pressure QUESTION # 074 Given:
  • A LOCA has occurred on Unit 1.
  • 1BEP-0, RX TRIP OR SAFETY INJECTION, was entered and a transition was made to
  • 1BEP-1 LOSS OF REACTOR OR SECONDARY COOLANT, The STA has identified an ORANGE path for one of the Critical Safety Function Status Trees.

There are still two (2) Status Trees left to evaluate, to complete the "pass".

Procedure usage rules require the crew to ...

a. implement the applicable BFR at the discretion of the Shift Manager
b. complete the actions of 1BEP-1, then implement the applicable BFR.
c. immediately implement the applicable BFR, then continue the current pass through the Status Trees.
d. continue current pass through the Status Trees. If NO red path condition is encountered, then implement the applicable BFR.

2013 NRC RO Initial License Written Examination Page 41 of 58 QUESTION # 075 Given:

A problem with DC Bus 113 has resulted in the LOSS of ALL Unit 1 annunciator windows.

Regarding the annunciator loss, per 1BOA ELEC-7, LOSS OF ANNUNCIATORS, the operators are directed to monitor ...

a. changes in Unit 1 load.
b. the Unit 1 SER for all changes of alarm status.
c. Unit 1 local panels and equipment at 15 minute intervals.
d. the process computer for points automatically removed from scan because of the failure.

2013 NRC SRO Initial License Written Examination Page 42 of 58 QUESTION # 076 Given:

  • Unit 1 is at 100% power in a normal full power alignment.
  • An instrumentation malfunction has resulted in RCS Pressure lowering to 2150 psig. The failed instrumentation channel is currently being addressed by Byron procedures. RCS pressure remains stable at 2150 psig.

How long can the unit remain in this present condition until ACTION must be taken?

a. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
b. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
c. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
d. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> QUESTION # 077 10 CFR 50.67 contains dose limits for a Steam Generator Tube Rupture. These limits are

___(1)___ Rem TEDE for an individual at the boundary of the exclusion area for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> OR

___(2)___ Rem TEDE for an individual in the Main Control Room for the duration of the event.

a. (1) 50 (2) 25
b. (1) 10 (2) 15
c. (1) 15 (2) 10
d. (1) 25 (2) 5

2013 NRC SRO Initial License Written Examination Page 43 of 58 QUESTION # 078 Given:

The crew took conservative action to TRIP the reactor and manually initiate a Safety Injection due to RISING Containment Pressure. All Safety Systems responded as designed, except as noted below. 1BEP-0, REACTOR TRIP OR SAFETY INJECTION has been implemented by your crew.

Immediately following the reactor trip the following conditions are noted:

  • PZR Level Lowering RAPIDLY
  • PZR Pressure Lowering RAPIDLY
  • Tave is 535 °F and continuing to Lower
  • All S/G Levels Lowering RAPIDLY
  • All SG Pressures Lowering RAPIDLY
  • Containment pressure is 9.2 psig and RISING
  • All MSIVs are currently OPEN
  • The diagnostic steps are complete and the appropriate transition HAS BEEN MADE.

From the following selections, which procedure transition will be made NEXT?

a. BEP ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION.
b. 1BCA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS.
c. 1BEP ES-1.1, SI TERMINATION.
d. 1BEP-2, FAULTED STEAM GENERATOR ISOLATION.

2013 NRC SRO Initial License Written Examination Page 44 of 58 QUESTION # 079 Given:

  • All equipment operated as designed.
  • The crew has transitioned to 1BEP ES-1.1, SI TERMINATION, from 1BEP-1, Loss of Reactor or Secondary coolant.
  • At step 4 of 1BEP ES-1.1, the crew secures all but one charging pump as directed.
  • After one charging pump is secured, RCS pressure begins to slowly and steadily LOWER.

With the above conditions, the Unit Supervisor will direct the crew to ...

a. manually re-initiate SI and transition to 1BEP-0, REACTOR TRIP OR SAFETY INJECTION
b. re-start the charging pump to stabilize RCS pressure and return to 1BEP-1
c. transition to 1BEP ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION
d. re-start the charging pump to stabilize RCS pressure and continue with 1BEP ES-1.1 QUESTION # 080 Which of the following events must be reported to the Illinois Emergency Management Agency?
a. Unit 2 is in MODE 5 AND ALL MCR annunciators have been unavailable for the last 20 minutes.
b. Unit1 is in MODE 3 and RCS UNIDENTIFIED leakrate is 7.5 gpm.
c. Unit 2 is in MODE 1 following a LOSS of offsite power AND the U-2 DGs have been energizing the ESF buses for the past 30 minutes.
d. Unit 1 is in MODE 3 AND DC Bus 112 has been DEENERGIZED for the last 30 minutes.

2013 NRC SRO Initial License Written Examination Page 45 of 58 QUESTION # 081 Given the following sequence of events on Units 1 & 2:

  • BOTH units were at full power.
  • Flooding was reported in the Auxiliary Building on the Unit 1 side.
  • 0BOA PRI-8, AUX BUILDING FLOODING has been entered.
  • It has been determined that an SX pipe break is the source of the flooding and it is currently NOT isolated.

Answer the following concerning this event.

(1) 0BOA PRI-8, AUX BUILDING FLOODING, directs entry into ...

(2) This is done to REDUCE ...

a. (1) 1/2 BOA PRI-7, Attachment B, ALIGNING EMERGENCY FP COOLING TO CENT CHG PUMP OIL COOLER, then 1/ 2 BOA PRI-7, ESSENTIAL SERVICE WATER MALFUNCTION.

(2) damage from flooding.

b. (1) 1/2 BOA PRI-7, Attachment B, ALIGNING EMERGENCY FP COOLING TO CENT CHG PUMP OIL COOLER, then 1/ 2 BOA PRI-7, ESSENTIAL SERVICE WATER MALFUNCTION.

(2) Core Damage Frequency

c. (1) 0BOA PRI-7, LOSS OF ULTIMATE HEAT SINK then 1/2 BOA PRI-7, ESSENTIAL SERVICE WATER MALFUNCTION.

(2) damage from flooding.

d. (1) 0BOA PRI-7, LOSS OF ULTIMATE HEAT SINK then 1/2 BOA PRI-7, ESSENTIAL SERVICE WATER MALFUNCTION.

(2) Core Damage Frequency

2013 NRC SRO Initial License Written Examination Page 46 of 58 QUESTION # 082 Given:

  • Unit 1 was initially at 100% power
  • The crew noted rising trends on ALL Main Steamline radiation monitors The following leak rate estimates were just confirmed via sample:

Steam Generator Primary to Secondary LEAKAGE 1A 0.15 gpm 1B 0.12 gpm 1C 0.04 gpm 1D 0.10 gpm NO other RCS Operational Leakage is present.

In accordance with Technical Specifications ...

a. the Unit Supervisor will direct the crew to place Unit 1 in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
b. the Unit Supervisor will direct entry into LCO 3.0.3.
c. the Unit Supervisor will direct the crew to place Unit 1 in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> where it may remain indefinitely.
d. unit one may remain in MODE 1 indefinitely.

2013 NRC SRO Initial License Written Examination Page 47 of 58 QUESTION # 083 Given:

  • Unit 1 was at 100% power.
  • All systems were normally aligned.
  • Intermediate Range SUR is -0.3 dpm.
  • RCS temperature is 550°F and DROPPING uncontrollably.
  • RCS pressure is 2200 psig and STEADY.
  • ALL other systems are normally aligned.
  • BA Transfer pumps will NOT run.

Based on the above conditions, the SRO will direct a/an

a. Safety Injection Actuation and transition to 1BEP-0, REACTOR TRIP OR SAFETY INJECTION.
b. emergency boration from the RWST per 1BOA PRI-2, EMERGENCY BORATION, while continuing in 1BEP ES-0.1.
c. transition to 1BFR-S.2, RESPONSE TO LOSS OF CORE SHUTDOWN.
d. transition to 1BOA PRI-2, EMERGENCY BORATION, while suspending actions of 1BEP ES-0.1.

QUESTION # 084 Step 1 of BFR-C.3, RESPONSE TO SATURATED CORE COOLING, checks if the RH system has been placed in the Shutdown Cooling Mode of operation.

Which ONE (1) of the following describes the basis for this step?

a. To ensure an ORANGE or RED condition in Core Cooling will NOT arise while performing this procedure.
b. If RH is in shutdown cooling mode, the saturated core cooling condition is a problem with RH and this procedure will identify and isolate the affected train.
c. To Verify RH is aligned for long term cooling if the appropriate conditions are met.
d. If RH is in Shutdown Cooling Mode, the saturated core cooling condition is a problem with RH and this procedure will NOT address this.

2013 NRC SRO Initial License Written Examination Page 48 of 58 QUESTION # 085 Given:

  • Unit U-1 is at 100% power in a normal full power alignment
  • The Gross Failed Fuel Monitor, 1PR006, has just gone into High Alarm.
  • There has been NO change in the Unit 1 full power alignment.

Per 1BOA PRI-4, ABNORMAL PRIMARY CHEMISTRY, you will direct Chemistry to perform each of the following EXCEPT ...

a. sample for RCS Cobalt-60
b. sample for RCS Dose Equivalent I-131
c. calculate a decontamination factor for the Letdown Mixed Bed Demineralizer
d. sample for RCS Xenon-133 QUESTION # 086 Given:
  • Unit 2 is at 100% power, normal alignment.
  • An INADVERTENT SI occurs.

One minute later, the ECCS high head injection header ruptures BETWEEN 2SI8801A, CHG PMPS TO COLD LEG INJ ISOL VLV, and containment.

NO other leaks exist.

Current plant conditions are:

  • Pressurizer level is 28% and STABLE.
  • Pressurizer pressure is 2100 psig and slowly RISING.
  • RCS temperature is 557°F and STABLE.

With the above conditions the Unit Supervisor will direct the crew to transition to...

a. 2BCA-1.2, LOCA OUTSIDE CONTAINMENT
b. 2BEP ES-1.1, SI TERMINATION
c. 2BEP-1 LOSS OF REACTOR OR SECONDARY COOLANT
d. 2BOA PRI-1, EXCESSIVE PRIMARY PLANT LEAKAGE

2013 NRC SRO Initial License Written Examination Page 49 of 58 QUESTION # 087 Given:

  • Unit 2 is in MODE 5 having just completed a core reload.

The System Engineer and an NSO are executing a planned activity and are currently re-energizing the 7300 cabinets in accordance with BOP RP-11, 7300 CABINET POWER SUPPLY ENERGIZATION/DE-ENERGIZATION.

The System Engineer believes a breaker may have been inadvertently mispositioned.

Per OP-AA-108-101, CONTROL OF EQUIPMENT AND SYSTEM STATUS, who is responsible for completion of Mispositioned Plant Components Requirements in accordance with OP-AA-108-112, PLANT STATUS AND CONFIGURATION?

a. Outage Planning
b. System Engineering
c. Shift Management
d. Work Control QUESTION # 088 Given:
  • Unit 1 is at 60% power and in a normal alignment for this power level.
  • The 1A, 1B, and 1C RCFCs are ALL running in fast speed. 1D is in STBY.

Per the Annunciator Response procedure and the Technical Specifications, answer the following:

(1) You will direct the NSO to ...

(2) IF the RCFC is determined to be INOPERABLE what is the MAXIMUM completion time to restore it to OPERABLE status per Tech Specs.?

a. (1) START 1D RCFC and STOP 1C RCFC (2) 3 Days
b. (1) START 1D RCFC and STOP 1C RCFC (2) 7 Days
c. (1) SHIFT 1C RCFC to low speed (2) 3 Days
d. (1) SHIFT 1C RCFC to low speed (2) 7 Days

2013 NRC SRO Initial License Written Examination Page 50 of 58 QUESTION # 089 Given:

  • Both units are at 100% power
  • The operating crew is performing BOP AP-53, ISOLATING SYSTEM AUX TRANSFORMER 242-1 AND 242-2 WHILE UNIT IS AT POWER, for a scheduled maintenance SAT outage.

Unit 1 is in a normal alignment EXCEPT:

  • ACB 1414, BUS 241 FEED TO 4KV BUS 141 is CLOSED
  • ACB 1424, BUS 242 FEED TO 4KV BUS 142 is CLOSED Unit 2 has the following ESF electrical alignment:
  • ACB 2412, SAT 242-1 FEED TO 4KV BUS 241, is OPEN and RACKED OUT
  • ACB 2422, SAT 242-2 FEED TO 4KV BUS 242, is OPEN and RACKED OUT
  • ACB 2414, BUS 141 FEED TO 4KV BUS 241 is CLOSED
  • ACB 2424, BUS 142 FEED TO 4KV BUS 242 is CLOSED BOTH units DGs are in standby with ALL output breakers OPEN in NAT Answer the following:

(1) Currently, Tech Spec 3.8.1- AC SOURCES OPERATING, Condition A, One or More Busses with One Required Qualified Circuit Inoperable is required to be entered for ...

(2) The MAXIMUM time allowed in this configuration is ___.

a. (1) BOTH units (2) 14 days
b. (1) BOTH units (2) 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
c. (1) Unit 2 ONLY (2) 14 days
d. (1) Unit 2 ONLY (2) 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

2013 NRC SRO Initial License Written Examination Page 51 of 58 QUESTION # 090 Given:

  • You are the WEC Supervisor
  • Unit 1 is at 78% power in "coastdown" prior to the start of the next refueling outage
  • Contract personnel are in the containment performing preparation work
  • Containment Access is through the Containment Access Facility (CAF)

The Access Control Guard reports to you that the CAF entrance inner door CANNOT be opened from INSIDE containment.

With this condition, your action, per BAP 1450-1, ACCESS TO CONTAINMENT, is to ...

a. continue to enter containment through the CAF but exit through 426' elevation of the FHB.
b. redirect ALL containment entry/exit activities to be performed at 426' elevation of the Fuel Handling Building.
c. contact the Containment Coordinator for direction.
d. evacuate the containment.

QUESTION # 091 Given:

  • Unit 1 is at 100% power in a normal full power alignment EXCEPT:
  • ALL bistables associated with Pressurizer pressure channel 1PT-458 are TRIPPED per 1BOA INST-2 , OPERATION WITH A FAILED INSTRUMENT CHANNEL Which of the following will be the procedure flowpath you will direct your crew to follow WHEN 1A Tave channel fails HIGH?
a. 1BGP 100-4, POWER DESCENSION and shutdown the unit within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
b. 1BEP-0, REACTOR TRIP OR SAFETY INJECTION, then to 1BEP ES-1.1, SI TERMINATION.
c. 1BOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL, Attachment A, RCS NARROW RANGE RTD CHANNEL
d. 1BEP-0, REACTOR TRIP OR SAFETY INJECTION, then to 1BEP ES-0.1, REACTOR TRIP RESPONSE.

2013 NRC SRO Initial License Written Examination Page 52 of 58 QUESTION # 092 Given:

  • You are the Unit 1 Unit Supervisor.
  • The unit is at 100% power and in a normal full power alignment The follow annunciators have just ALARMED:
  • 0-37-A4, UNIT 1 AREA FIRE and
  • 1PM09J, 1S-29, AUTOMATIC SUPPRESSION TURB BRNG The Turbine 1 Equipment Operator has just reported the existence of a fire at the number 7 main turbine/generator bearing.

Your response, as the Unit Supervisor, to this event per BAP 1100-10, RESPONSE PROCEDURE FOR FIRE is to notify the ...

a. Fire Marshall and begin E-Plan evaluation.
b. Shift Manager and begin E-Plan evaluation.
c. Shift Manager and begin Reportability Manual evaluation.
d. Fire Marshall and begin Reportability Manual evaluation.

2013 NRC SRO Initial License Written Examination Page 53 of 58 QUESTION # 093 Given:

  • A LOCA has occurred on Unit 1 During the initial performance of 1BEP-0, REACTOR TRIP OR SAFETY INJECTION, at step 15, the following plant conditions are noted:
  • Containment pressure is 6 psig and RISING
  • RCS pressure is 1750 psig and STABLE
  • SG pressures are 1175 psig
  • BOTH AF pumps failed to start and CANNOT be manually started
  • SG Levels (NR)are:

1A 25% 1B 24% 1C 26% 1D 30%

Based on the above conditions, the NEXT procedure the US will transition to is ...

a. 1BFR-C.2, RESPONSE TO DEGRADED CORE COOLING, because core cooling is the highest priority safety function NOT being met.
b. 1BEP-1 LOSS OF REACTOR OR SECONDARY COOLANT, because SG levels are currently adequate.
c. 1BFR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, and 1BFR-H.1 will be performed because a secondary heat sink is necessary.
d. 1BFR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, then immediately transition to 1BFR-C.2, RESPONSE TO DEGRADED CORE COOLING, because a secondary heat sink is NOT required.

2013 NRC SRO Initial License Written Examination Page 54 of 58 QUESTION # 094 Given:

  • A NSO has the following 2 week schedule.
  • This is during a NON-outage period and all work to be performed is covered by work hour rules.
  • The starting time for each shift FALLS ON THE LISTED DAY: i.e. the first shift listed starts at 7 pm on Sunday night.
  • Today's date is 1/5.
  • An emergent activity needs to be performed requiring an extra NSO to be called out to work on 1/5 from 3 to 11pm to complete this activity.

Would you call this NSO to work the 1/5 3-11pm shift? If the answer is no, the reason is ...

Sunday 1/1 7pm - 7am Monday 1/2 7pm - 7am Tuesday 1/3 7pm - 7am Wednesday 1/4 OFF Thursday 1/5 OFF Friday 1/6 11am - 7pm Saturday 1/7 7am - 7pm Sunday 1/8 11pm - 7am Monday 1/9 11pm - 7am Tuesday 1/10 7pm - 7am Wednesday 1/11 7pm - 7am Thursday 1/12 OFF Friday 1/13 OFF Saturday 1/14 OFF

a. Yes, no work hour limits have been exceeded.
b. No, greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> worked in a 7 day period.
c. No, less than a 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> break between successive work periods.
d. No, no 34 hour3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> break in a nine (9) day period.

2013 NRC SRO Initial License Written Examination Page 55 of 58 QUESTION # 095 Given:

  • An operating surveillance is commenced on a Monday morning that is expected to take several days to complete.
  • On Wednesday afternoon of the same week, an RO assigned to continue work on the surveillance discovers that the procedure revision being used was superseded with an editorial change just that Wednesday morning.
  • The RO comes to you with this information and asks you to determine how to proceed.

What is your action/decision, as SRO, in accordance with HU-AA-104-101, PROCEDURE USE AND ADHERENCE?

a. Initiate a temporary procedure change to the old revision, to match the current revision, then the surveillance can be completed using the superseded (old) revision.
b. Transfer data and placekeeping from the superseded revision to the new revision. NO provision exists for using the superseded revision.
c. After reviewing the old revision ensuring that it can be performed as written, the surveillance can be completed using the superseded (old) revision.
d. The surveillance must be re-performed from the beginning with the latest revision. NO provision exists for using the superseded revision.

QUESTION # 096 Given:

  • During a routine swap of condensate pumps, the 1C pump did NOT start.
  • An IR was written and work package prepared to troubleshoot the cause of the pump NOT starting.
  • The pump is currently NOT out of service.
  • The maintenance crew has just arrived to begin troubleshooting.

Your responsibility as the Unit Supervisor for this activity, in accordance with MA-AA-716-004, CONDUCT OF TROUBLESHOOTING, is ...

a. develop the troubleshooting plan AND approve the troubleshooting plan
b. approve the troubleshooting plan AND execute the troubleshooting plan
c. re-assess unit risk based on the troubleshooting plan AND execute the troubleshooting plan
d. re-assess unit risk based on the troubleshooting plan AND authorize the work

2013 NRC SRO Initial License Written Examination Page 56 of 58 QUESTION # 097 Given:

  • The unit has been operating at 100% power for 30 days.
  • The unit tripped during a Loss Of Off-Site Power event.
  • CST level is at Tech Spec MINIMUM level.
  • Both AF pumps are running.
  • S/G PORVs are being used to dump steam to control the RCS at NOT and NOP.

Discussion is ongoing as to whether to place the Unit in MODE 4 on shutdown cooling to allow plant repairs and surveillance testing.

According to the Tech Spec Bases, what is the MAXIMUM time, IN HOURS, the plant may remain in the present condition before commencing a cooldown, and still be assured there is an adequate water supply from the CST to the AF pumps ?

a. 2
b. 4
c. 6
d. 8 QUESTION # 098 Given:
  • Unit 1 has experienced an event requiring Emergency Plan implementation.
  • Personnel are preparing to enter Area 5 Penetration Area to rescue an injured worker.
  • The rescuers are expected to receive 10 Rem exposure during the rescue.
  • Command and Control has been transferred to the EOF.

Which of the following is the HIGHEST level of authority required to authorize this exposure?

a. Corporate Emergency Director
b. OSC Director
c. Station Emergency Director
d. Radiation Protection Manager

2013 NRC SRO Initial License Written Examination Page 57 of 58 QUESTION # 099 Given the following plant conditions:

  • 0C and 0D VA Exhaust Fans are OOS.
  • A Unit 2 Containment gaseous release is pending.

In addition to the Radiation Protection Department, which position holds the responsibility to waive the requirement for VA fans to be in operation, to perform a Containment release?

a. Operations Director
b. Unit Supervisor
c. Station Duty Officer
d. Shift Manager QUESTION # 100 Given the following:
  • Unit 1is in MODE 4, with 120°F subcooling
  • Pressurizer level is 25% and stable
  • 1A RH pump amps, discharge flow and pressure begins to fluctuate
  • NO annunciators are alarming due to the fluctuations Which procedural action will you direct the crew to take FIRST?
a. REDUCE the affected pump flow by LOWERING demand on 1RH618, HX 1A BYP FLOW CONT VLV in accordance with 1BOA PRI-10, LOSS OF RH COOLING.
b. TRIP the affected pump and ENTER 1BOA PRI-10, LOSS OF RH COOLING.
c. REDUCE the affected pump flow by LOWERING the demand on 1RH606, HX 1A FLOW CONT VLV, in accordance with BOP RH-6, OPERATION OF THE RH SYSTEM IN SHUTDOWN COOLING.
d. OPEN 1RH610, RH Pp 1A MINIFLOW VLV, in accordance with BOP RH-6, OPERATION OF THE RH SYSTEM IN SHUTDOWN COOLING.

2013 Byron Initial License Written Examination Key Page 58 of 58 001 c. 021 c. 041 b. 061 a. 081 b.

002 b. 022 a. 042 d. 062 a. 082 a.

003 c. 023 d. 043 c. 063 b. 083 b.

004 b. 024 c. 044 d. 064 d. 084 d.

005 b. 025 c. 045 b. 065 b. 085 a.

006 d. 026 c. 046 b. 066 b. 086 b.

007 d. 027 a. 047 d. 067 b. 087 c.

008 b. 028 b. 048 b. 068 d. 088 b.

009 c. 029 c. 049 a. 069 c. 089 b.

010 b. 030 c. 050 b. 070 d. 090 d.

011 d. 031 c. 051 a. 071 a. 091 d.

012 b. 032 d. 052 c. 072 c. 092 b.

013 b. 033 b. 053 a. 073 b. 093 c.

014 c. 034 d. 054 b. 074 d. 094 d.

015 d. 035 c. 055 a. 075 b. 095 c.

016 a. 036 c. 056 d. 076 a. 096 d.

017 d. 037 a. 057 c. 077 d. 097 a.

018 a. 038 a. 058 a. 078 b. 098 c.

019 c. 039 b. 059 a. 079 c. 099 d.

020 a. 040 a. 060 d. 080 c. 100 a.

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