ML102390056

Initial Exam 2010-301 Final RO Written Exam

ML102390056
Person / Time
Site:	Mcguire, McGuire
Issue date:	08/25/2010
From:	NRC/RGN-II
To:
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Download: ML102390056 (95)

Text

U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:

Date: Facility/Unit: McGuire Region: I III IV Reactor Type: CE BW GE Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.

Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicants Signature Results Examination Value Points Applicants Score Points Applicants Grade Percent

MCGU IRE NUCLEAR STATION Question: I 2010 MNS RO NRC Examination 1

point)

Given the following conditions on Unit 1:

• The unit is operating at 40% RTP

• NCP C trips on overcurrent Assuming no operator action, which ONE (1) of the following describes the effect on the Departure from Nucleate Boiling Ratio (DNBR) AND reactor thermal power?

A. DNBR will INCREASE.

Reactor power decreases and stabilizes at a new lower thermal power.

B. DNBR will DECREASE.

Reactor power decreases and stabilizes at a new lower thermal power.

C. DNBR will INCREASE.

Reactor power initially decreases and then returns to 40% thermal power.

D. DNBR will DECREASE.

Reactor power initially decreases and then returns to 40% thermal power.

Page 1 of 75

MCGU IRE NUCLEAR STATION Question: 2 2010 MNS RO NRC Examination point)

Given the following conditions on Unit 1:

• Unit is operating at 100% RTP

• The controller for 1 KC-1 32 (Letdown Hx Outlet Temp Ctrl) has been placed in MANUAL due to erratic operation

• Subsequently, NV letdown flow is increased by 10 GPM as requested by Chemistry As letdown temperature increases, NC system boron concentration will (1) AND if letdown temperature continues to increase, letdown flow will automatically bypass the demineralizer at (2)

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

A. 1. INCREASE

2. 120°F B. 1. INCREASE

2. 138°F C. 1. DECREASE

2. 120°F D. 1. DECREASE

2. 138°F Page 2 of 75

MCGUIRE NUCLEAR STATION Question: 3 2010 MNS RO NRC Examination ooint)

Given the following conditions on Unit 1:

• Unit is in MODE 5 with ND Train A in service

• 1NI-173A (Train A ND to A & B CL) is OPEN

• ND flow is being reduced by throttling 1 ND-29A (A ND HX Outlet) in preparation for removing ND from service IND-68A (A ND Pump & A HX Mini-flow) will open if 1A ND pump flow decreases to less than a MAXIMUM of (1) . The Operators in the Control Room can verify that 1 ND-68A has opened by recirc flow indication on (2)

Which ONE (1) of the following completes the statements above?

A. 1. 325GPM

2. theOAC ONLY B. 1. 325GPM

2. a chart recorder on MC-7 AND the QAC C. 1. 750 GPM

2. theOACONLY D. 1. 750 GPM

2. a chart recorder on MC-7 AND the QAC Page 3 of 75

MCGU IRE NUCLEAR STATION Question: 4 2010 MNS RO NRC Examination point)

Given the following conditions on Unit 1:

• The unit is in MODE 4

• The crew is increasing NC system temp and pressure for unit startup

• ND Train A is in service

• NC system temperature is being maintained at 140°F If instrument air is lost to 1 ND-34 (A & B ND Hx Byp) the valve will fail (I) AND NC system temperature will (2)

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

A. 1. OPEN

2. INCREASE B. 1. CLOSED

2. INCREASE C. 1. OPEN

2. DECREASE D. 1. CLOSED

2. DECREASE Page 4 of 75

MCGUIRE NUCLEAR STATION Question: 5 2010 MNS RO NRC Examination 1 point)

Concerning the operation of Engineering Safeguards Modulating Control Valves:

Upon receipt of a (1) signal, the modulating control valve circuit will (2) the control valves.

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

A. 1. Safety Injection ONLY

2. maintain VI aligned to B. 1. Safety Injection ONLY

2. vent air off C. 1. Safety Injection OR Blackout

2. maintain VI aligned to D. 1. SafetylnjectionORBiackout

2. vent air off Page 5 of 75

MCGUIRE NUCLEAR STATION Question: 6 2010 MNS RO NRC Examination 1 point)

Unit I is operating at 100% RTP.

Given the foflowing indications for Unit I CLAs:

1A lB IC 1D Pressure 630 PSIG 570 PSIG 590 PSIG 615 PSIG Level 7305 GAL 6970 GAL 6890 GAL 7375 GAL Which ONE (1) of the following describes how the ECCS system is affected (if at all) by the CLA parameters listed above?

A. 18 CLA ONLY is INOPERABLE.

B. 1 C CLA ONLY is INOPERABLE.

C. lA and 1C CLAs are INOPERABLE.

D. 18 and 1 D CLA5 are INOPERABLE.

Page 6 of 75

MCGUIRE NUCLEAR STATION Question: 7 2010 MNS RO NRC Examination point)

Given the following conditions on Unit 1:

• A unit startup is in progress following refueling

• The crew is preparing to draw a bubble in the Pressurizer.

• NC system pressure is 360 PSIG

• NC system is in Solid Ops with LTOP in service

• The IA NC pump is RUNNING

1. Per Selected Licensee Commitment 16.5-4 (Pressurizer), what is the MAXIMUM allowable Pressurizer heat up rate?

2. Based on current plant conditions, how are non-condensable gases removed from the NC system?

A. 1. 75°F in anyone hourperiod

2. Cycle Pressurizer PORVs B. 1. 75°F in any one hour period

2. Cycle the Reactor Vessel Head vents C 1 100°Finanyonehourpenod

2. Cycle Pressurizer PORV5 D. 1. 100°F in anyone hour period

2. Cycle the Reactor Vessel Head vents Page 7 of 75

MCGUIRE NUCLEAR STATION Question: 8 2010 MNS RO NRC Examination 1 point)

Concerning the operation of 1KC-122 (KC Surge Tank Vent Valve):

When a (1) alarm is received on 1 EMF-46A(B), 1 KC-122 will automatically close and the valve (2)

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

A. 1. Trip 1

2. must be locally re-opened B. 1. Trip I

2. will automatically re-open when the alarm clears C. 1. Trip 2

2. must be locally re-opened D. 1. Trip 2

2. will automatically re-open when the alarm clears Page 8 of 75

MCGU IRE NUCLEAR STATION Question: 9 2010 MNS RO NRC Examination I point)

Given the following conditions on Unit 1:

• Repairs have just been completed on the SLIM module for 1 NC-29 (Pressurizer Spray Valve)

• The OATC has just completed throttling 1 NC-29 with its controller in MANUAL to verify proper operation of the SLIM

• 1NC-29 controller is now in AUTO After completion of testing the Pressurizer Pressure Master Controller soft controls indicate as follows:

/CTIVE FRESSURE CONTROL PZR PRESSURE ERRR 01 PSIG MIN DEMANO MAX OEMANO HEATER NIR1AL 5PRAY FtRV

1. What is the current demand for the Bank C heaters?

2. At what PRESSURE ERROR will the Backup heaters energize?

A. 1. 17%

2. () 17 PSIG B. 1. 17%

2. () 25 PSIG C. 1. 83%

2. () 17 PSIG D. 1. 83%

2. () 25 PSIG Page 9 of 75

MCGUIRE NUCLEAR STATION Question: 10 2010 MNS RO NRC Examination point)

Given the following conditions and sequence of events on Unit 1:

• The unit is operating at 100% RTP

• The crew enters AP-016 (Malfunction of Nuclear Instrumentation) due to N-42 lower detector failing LOW

• IAE has placed the required bistables in the trip condition per AP-016

• A complete loss of 1EKVA occurs Which ONE (1) of the following lists the required procedure flowpath for these conditions?

A. Continue in AP-016 B. Enter AP-003 (Load Rejection)

C. Enter E-0 (Reactor Trip or Safety Injection)

D. Enter AP-015 (Loss of Vital or Aux Control Power)

Page 10 of 75

MCGUIRE NUCLEAR STATION Question: 11 2010 MNS RO NRC Examination point)

Given the following conditions on Unit 1:

• A Small-Break LOCA has occurred

• The crew has reached the step in E-1 (Loss of Reactor or Secondary Coolant) to reset SI and the Sequencers

• The crew is unable to reset the Sequencers Which ONE (1) of the following describes the locations where Operators must be dispatched to de-energize BOTH Sequencers?

A. IEVDA;1EVDB B. 1EVDA;IEVDD C. 1EVDB;1EVDC D. 1EVDC;IEVDD Page 11 of 75

MCGUIRE NUCLEAR STATION Question: 12 2010 MNS RO NRC Examination point)

Given the following conditions on Unit 1:

• The unit is operating at 100% RTP

• A small NC System leak occurs inside Containment

• Annunciator 1AD-9 lAS, (CONT .5 PSIG ALERT) is received Which ONE (1) of the following is an expected response of the VL AHUs and the Containment Pipe Tunnel Booster Fans (PTBFs)?

A. All VL AHU(s) start and shift to HIGH speed Both PTBFs start and shift to HIGH speed B. All VL AHU(s) start and shift to HIGH speed The PTBFs are running according to their switch positions C. Operating VL AHU(s) shift to HIGH speed, Idle fans remain OFF Both PTBFs start and shift to HIGH speed D. Operating VL AHU(s) shift to HIGH speed, Idle fans remain OFF The PTBFs are running according to their switch positions Page 12 of 75

MCGUIRE NUCLEAR STATION Question: 13 2010 MNS RO NRC Examination 1 point)

Which ONE (1) of the following describes the operation of the RV System if Containment pressure reaches 2.8 PSIG?

A. The RV Containment isolation valves will Auto Close on the (ST) signal.

Containment cooling will be provided to the RN non-essential header.

B. The RV Containment isolation valves will Auto Close on the (Se) signal.

Containment cooling will be provided to the RN non-essential header.

C. The RV header is isolated from the RN header by the (ST) signal.

The RV pumps will Auto Start on RN non-essential header low pressure to supply the Containment AHUs.

D. The RV header is isolated from the RN header by the (Se) signal.

The RV pumps will Auto Start on RN non-essential header low pressure to supply the Containment AHUs.

Pagel3of75

MCGUIRE NUCLEAR STATION Question: 14 2010 MNS RO NRC Examination I point)

Given the following conditions on Unit 1:

• The unit is increasing power after a forced shutdown

• OPI1IN61 00/003 (Controlling Procedure for Unit Operation) is in effect

• 1A CF pump is in service

• When 40% RTP is reached, the crew closes 1HM-95 (AS toA&B CF Pumps)

• When 1HM-95 closes, the crew observes the 1A CF pump speed and DIP decreasing and FRVs opening

1. What is the cause of the indications described above?

2. What action is required to continue the power increase?

A. 1. isp-i (SM to CF Pump iA) is closed.

2. Dispatch an operator to open iSP-i. Main Steam is the primary supply to the CF pumps between 20% and 80% RTP.

B. 1. iSP-I (SM to CF Pump 1A) is closed.

2. Dispatch an operator to open ISP-i. Main Steam is the primary supply to the CF pumps between 20% and 100% RTP.

C. 1. MSR cross over steam pressure is inadequate.

2. 1HM-95 must be reopened. MSR crossover steam is the primary supply to the CF pumps between 40% and 80% RTP.

D. 1. MSR cross over steam pressure is inadequate.

2. 1HM-95 must be reopened. MSR crossover steam is the primary supply to the CF pumps between 40% and 100% RTP.

Page 14 of 75

MCGUIRE NUCLEAR STATION Question: 15 2010 MNS RO NRC Examination 1 point)

Given the following conditions on Unit 1:

• The unit is in MODE 1 at 10% RTP

• 1AD-9 /A5 (ICE COND LOWER INLET DOORS OPEN) alarm is LIT

• The lower inlet door position display panel indicates that a door is open

• The door is confirmed to be cracked opened. The door will not move further open and cannot be closed

• No other alarms related to the ice condenser, NE system or AHUs are lit Which of the following is REQUIRED to be entered based on the current plant conditions?

1. Tech Spec 3.6.13 Ice Condenser Doors

2. Tech Spec 36.12 Ice Bed

3. Selected Licensee Commitment 16.6-3 Ice Condenser Door Position Monitoring System A. 1 ONLY B. 1 and 2 ONLY C. 1 and 3 ONLY D. 1,2,and3 Page 15 of 75

MCGUIRE NUCLEAR STATION Question: 16 2010 MNS RO NRC Examination point)

Given the following conditions on Unit 1:

• The unit is in MODE 4 with A Train ND in service

• A CRUD Burst has been initiated and clean up is in progress

• Unknown to the Operators, I ND-35 (ND Sys to FWST Isol) has developed a small leak past its seat (0.5 GPM)

1. Which of the following describes the operational concern associated with this condition?

2. In accordance with OP/i 1A162001014 (Refueling Water System) what alignment would be required to address the radiological effects of this event?

A. I. In creased radiation levels at the FWST enclosure.

2. The FWST would be placed in purification with the FW pump for clean up.

B. 1. In creased radiation levels at the FWST enclosure.

2. The FWST suction piping would be placed in recirculation using the FW Recirc pumps to dilute the crud deposited in the ECCS suction piping.

C. 1. The formation of hot spots in the ECCS suction piping downstream of 1FW-27 (FWST to ND Pump IsoI).

2. The FWST would be placed in purification with the FW pump for clean up.

D. 1. The formation of hot spots in the ECCS suction piping downstream of 1FW-27 (FWSTt0 ND Pump Isol).

2. The FWST would be placed in recirculation using the FW Recirc pumps to dilute the crud deposited in the ECCS suction piping.

Page 16 of75

MCGUIRE NUCLEAR STATION Question: 17 2010 MNS RO NRC Examination point)

Given the following conditions on Unit 1:

• A LOCA has occurred inside Containment

• Containment pressure is 3.4 PSIG

• The crew is preparing to initiate a cooldown per ES 1.2 (Post LOCA Cooldown and Depressuration)

Which ONE (1) of the following must occur to allow reopening the MS IVs for the given conditions?

A. Reset the Main Steam Isolation signal ONLY.

B. Reset the Phase B AND Main Steam Isolation signals ONLY.

C. Containment pressure must be reduced below 3 PSIG AND reset the Main Steam Isolation signal ONLY.

D. Containment pressure must be reduced below 3 PSIG AND reset BOTH the Main Steam Isolation signal and Phase B Isolation signal.

Page 17 of 75

MCGUIRE NUCLEAR STATION Question: 18 2010 MNS RO NRC Examination 1 point)

Given the foHowing conditions on Unit 1:

• The unit is operating at 45% RTP

• Channel 1 Main Turbine Impulse pressure indicates 310 PSIG

• Channel 2 is indicating 0 PSIG

• The AMSAC UNBLOCK light is DARK Which ONE (1) of the following describes the current status of the AMSAC system?

A. Auto actuation is NOT functional.

The loss of CF flow path auto actuation can NOT be restored until the failed impulse channel is repaired.

B. Auto actuation is NOT functional.

The loss of CF flow path auto actuation can be restored by depressing the AMSAC Actuation U NBLOC K pushbutton.

C. Auto actuation will occur if both Feedwater pumps trip.

The loss of CF flow path auto actuation can NOT be restored until the failed impulse channel is repaired.

D. Auto actuation will occur if both Feedwater pumps trip.

The loss of CF flow path auto actuation can be restored by depressing the AMSAC Actuation UNBLOCK pushbutton.

Page 18 of 75

MCGUIRE NUCLEAR STATION Question: 19 2010 MNS RO NRC Examination point)

Given the following conditions on Unit 1:

• The unit has experienced a Loss of all AC

• Crew has implemented ECA 0.0 (Loss Of All AC Power)

• Unit 1 Control has been swapped to the SSF

• An NEO has been dispatched to close the feeder breaker for 1CA-161 C (CA Suction Hdr RN Supply Isol)

Based on the conditions described above which ONE (1) of the following states where the NEC would be dispatched to perform this action?

A. SMXG B. SMXG1 C. SDSP-1 D. 1EVDA-1 Page 19 of 75

MCGUIRE NUCLEAR STATION Question: 20 2010 MNS RO NRC Examination 1 point)

Given the following conditions on Unit I:

• B Train of essential equipment is in operation on Unit I

• OP/i 1N63501002 (Diesel Generator) is in progress with the 1A Diesel running in parallel to the grid when the following sequence of events occurs:

o Load is reduced on the diesel to 200KW in anticipation of opening the Emergency Breaker o The RO accidentally OPENS the Normal Feeder Breaker from 1ATC The Blackout Sequencer Actuated Train A status light on S1-14 Which ONE (1) of the following completes the statement above?

A. illuminates and the iA DG load increases B. remains dark and the iA DG load increases C. illuminates and the IA DC Emergency Breaker trips open, then re-closes 8.5 seconds later D. remains dark and the iA DG Emergency Breaker trips open, then re-closes 8.5 seconds later Page 20 of 75

MCGUIRE NUCLEAR STATION Question: 21 2010 MNS RO NRC Examination point)

Given the following plant conditions:

• Both Units operating at 100% RTP

• A complete Loss of Offsite Power occurred on Unit 1

• IA DIG started but subsequently tripped on Low Lube Oil Pressure

• 30 seconds have passed since the Loss of Offsite Power occurred Which ONE (1) of the following describes the condition of the components listed below?

1. 125 VDC Vital Distribution Center (EVDA)

2. Annunciator lAD-i 1 I B2 (Seq A Loss of Control Pwr)

A. 1. Energized

2. LIT B. 1. Energized

2. DARK C. 1. De-energized

2. LIT D. 1. De-energized

2. DARK Page 21 of75

MCGUIRE NUCLEAR STATION Question: 22 2010 MNS RO NRC Examination point)

Given the following plant conditions:

• Both Units are operating at 100% RTP

• Battery 1DP is aligned for equalizing charge

• The DC Output breaker for Charger 1 DS has tripped open Which ONE (1) of the following describes the current status of Bus 1DP?

A. Bus 1 DP will be de-energized.

B. Bus 1 DP will be energized from Charger I DP ONLY.

C. Bus I DP will be energized from Chargers 1 DP and 2DP.

D. Bus I DP will be energized from Charger IDP and Battery IDP.

Page 22 of 75

MCGU IRE NUCLEAR STATION Question: 23 2010 MNS RO NRC Examination point)

Given the following:

• Unit 1 is shutdown in MODE 3

• Auxiliary Transformer 1ATA is tagged out for repairs

• All unit loads are being supplied by Auxiliary Transformer 1ATB

1. A Blackout will occur if open.

2. The DG Sequence is ONLY enabled if emergency bus minimum voltage and frequency setpoints are met.

Which ONE (1) of the following completes the statements above?

A. 1. PCB58&9

2. Committed B. 1. PCBs11&12

2. Committed C. 1. PCB58&9

2. Accelerated D. 1. PCB5II&12

2. Accelerated Page 23 of 75

MCGUIRE NUCLEAR STATION Question: 24 2010 MNS RO NRC Examination 1 point)

Which ONE (1) of the following lists the EMFs that will automatically stop the Auxiliary Building Unfiltered Exhaust Fans (IABFXF-IAI1 B) on a Trip 2 alarm?

A. 1 EMF 36(L) Unit Vent Gas (Low Range) OR 1 EMF 36(H) Unit Vent Gas (High Range)

B. 1 EMF 36(L) Unit Vent Gas (Low Range) OR 1 EMF 37 Unit Vent Iodine C. 1 EMF 35(L) Unit Vent Particulate (Low Range) OR 1EMF 37 Unit Vent Iodine D. 1 EMF 35(L) Unit Vent Particulate (Low Range) OR 1 EMF 36(H) Unit Vent Gas (High Range)

Page 24 of 75

MCGUIRE NUCLEAR STATION Question: 25 2010 MNS RO NRC Examination 1 point)

Which ONE (1) of the following is an effect if flow is lost to the Nuclear Service Water System Essential Header? (Assume the equipment listed is in service)

A. PD pump bearing oil temperature increases.

B. NC Pump motor bearing temperature increases.

C. MD CA Pump motor bearing temperature increases.

D. Steam Generator Blowdown Heat Exchanger outlet temperature increases.

Page 25 of 75

MCGUIRE NUCLEAR STATION Question: 26 2010 MNS RO NRC Examination 1 point)

Due to a leak on the VI system the following indications were observed:

• IAD-12 Cl (VIA/S Lo Pressure) is LIT

• OVIP-5090 (VIA/S Press) dropped to a lowest reading of 86 PSIG and is now 89 PSIG and increasing Which ONE (1) of the following describes automatic actions which have occurred as a result of the indicated pressure transient?

A. G and H VI Compressors auto-started ONLY.

B. IVI-820 (VI to VS Supply) auto-closed ONLY.

C. 1VI-820 auto-closed AND lVI-1812 (VI Dryer Bypass Vlv) has auto-opened.

D. G and H VI Compressors auto-started AND 1VI-820 (VI to VS Supply) auto closed.

Page 26 of 75

MCGUIRE NUCLEAR STATION Question: 27 2010 MNS RO NRC Examination I point)

Given the following:

• Unit 1 is operating at 100% RTP when a loss of VI event occurs

• AP-22 (Loss of VI) has been implemented

• VI header pressure is 55 PSIG and decreasing Which ONE (1) of the following system effects would be the FIRST to require the crew to trip the reactor in accordance with AP-22?

A. Decreasing SIG levels B. Loss of RN supply to Containment C. Loss of NC pump seal leakoff to the VCT D. PZR level approaching the High Level Trip setpoint Page 27 of 75

MCGUIRE NUCLEAR STATION Question: 28 2010 MNS RO NRC Examination 1 point)

Given the following conditions on Unit 1:

• A LOCA has occurred inside Containment

• Containment pressure is currently 3.5 PSIG Which ONE (1) of the following describes the MINIMUM steps required before KC can be restored to Containment?

A. Reset Phase A B. Reset Phase B C. Reduce Containment pressure below 1.0 PSIG, reset Phase A D. Reduce Containment pressure below 3.0 PSIG, reset Phase B Page 28 of 75

MCGUIRE NUCLEAR STATION Question: 29 2010 MNS RO NRC Examination point)

Give the following conditions on Unit 1:

• The unit is in MODE 3 withdrawing S/D banks in preparation for startup

• 1AD-2 / D1O (RPI Urgent Alarm) Annunciator has just alarmed

• DRPI and QAC RODS position indication for rod D-8 has been lost What is the FIRST action required by SLC 16.7.9 (Rod Position Indication System -

Shutdown)?

A. Place rods in manual ONLY.

B. Place rods in manual AND drive all rods in.

C. Immediately open the reactor trip breakers.

D. Restore rod position indication within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Page 29 of 75

MCGUIRE NUCLEAR STATION Question: 30 2010 MNS RO NRC Examination 1 point)

Given the following conditions on Unit 1:

• The unit is at 100% RTP

• All Pressurizer heaters are energized in MANUAL

• The SLIM for 1 NV-238 (Charging Flow Control) has been placed in MANUAL due to a malfunction of the Pressurizer Level Master Controller

• The OATC reduces the 1NV-238 SLIM output to reduce Pressurizer level

• Charging Line Flow is inadvertently reduced to 18 GPM If the 1NV-238 controller output remains constant, after 5 minutes Pressurizer level will be (1) AND the Pressurizer heaters will be (2)

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

A. 1. DECREASING

2. OFF B. 1. DECREASING 2.ON C. 1. INCREASING

2. OFF D. 1. INCREASING 2.ON Page 30 of 75

MCGUIRE NUCLEAR STATION Question: 31 2010 MNS RO NRC Examination 1 point)

Unit 1 is operating at 100% RTP. The following indications are observed on the Digital Rod Position Indication (DRPI) system:

• D-4 rod indication is RED

• Associated rod group background is ORANGE

• IAD-2 I D10 (RPI URGENT FAILURE) is LIT Which ONE (1) of the following describes the condition of rod D-4?

A. Rod D-4 is fully inserted.

B. Rod D-4 is at half accuracy.

C. Rod D-4 position cannot be determined.

D. Rod D-4 is greater than 231 steps withdrawn.

Page 31 of75

MCGUIRE NUCLEAR STATION Question: 32 2010 MNS RO NRC Examination I point)

Given the following conditions on Unit 1:

• Unit is shutdown in MODE 6 for Refueling

• While responding to a series of alarms associated with the NIs the operator notices that the Instrument Power and Control Power lights on the PR N43 drawers are DARK Which ONE (1) of the following is the cause of these indications?

A. Inverter 1 EVIA has tripped.

B. The feeder breaker for panelboard 1 EKVB has tripped.

C. lnverter I EVIC has tripped.

D. The feeder breaker for panelboard I EKVD has tripped.

Page 32 of 75

MCGU IRE NUCLEAR STATION Question: 33 2010 MNS RO NRC Examination 1 point)

Which ONE (1) of the following sets of indications can be read outside the Main Control Room on BOTH the Auxiliary Shutdown Panel (ASP) AND the Safe Shutdown Facility (SSF) Control Panel?

A. SR Neutron Flux AND SIG WR Levels B. SR Neutron Flux AND Pressurizer Level C. Incore Thermocouples AND SIG WR Levels D. Incore Thermocouples AND Pressurizer Level Page 33 of 75

MCGUIRE NUCLEAR STATION Question: 34 2010 MNS RO NRC Examination point)

Given the following on Unit 1:

• A LOCA occurred 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago

• The 1A H2 Recombiner was placed in service per EPI1IN5000IG-1 Enclosure 4 (Placing H2 Recombiners In Service)

• Containment pressure was 5 PSIG when the Recombiner was placed in service Current Conditions are as follows:

• Containment pressure is 1.5 PSIG Based on the conditions above the recombiner Power Setting was (1) when the recombiner was placed in service and should now be set to (2)

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

REFERENCE PROVIDED A. 1. 49.8KW

2. 45.3KW B. 1. 49.8KW

2. 45.8KW C. 1. 50.3KW

2. 45.3KW D. 1. 50.3KW

2. 45.8KW Page 34 of 75

MCGUIRE NUCLEAR STATION Question: 35 2010 MNS RO NRC Examination 1 point)

Given the following events and conditions associated with the Unit 1 SFP:

• A Lo-Lo alarm is received for OAC point M1A0004 (SFP Level)

• The operators read (-)2.i ft SFP level and steady on the main control board

• The operating KF pump has tripped

• An NEO reports a large leak in the auxiliary building but the leak has now slowed to a trickle For the event described above the leak must be associated with the KF pump (1) piping and (2) would be utilized to monitor increasing radiation levels associated with the loss of SFP level.

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

A. 1. discharge

2. 1EMF-42 (U-i Spent Fuel Bldg Vent)

B. i. discharge

2. iEMF-17 (Spent Fuel Bldg Refuel Brdg)

C. 1. suction

2. 1EMF-42 (U-i Spent Fuel Bldg Vent)

D. i. suction

2. 1EMF-17 (Spent Fuel Bldg Refuel Brdg)

Page 35 of 75

MCGUIRE NUCLEAR STATION Question: 36 2010 MNS RO NRC Examination point)

Given the following conditions on Unit 1:

• A unit shutdown is in progress

• Operators have blocked the CA Auto-Start signal

• At 0200 both Main Feed Pumps trip Given the following plant conditions and times:

Time Condition 0200 0205 0210 0215 0220 Tave(°F) 551 552 552 553 554 NC Press. (PSIG) 1951 1953 1958 1951 1957 NRSGA(%) 24 16 25 18 10 NRSGB(%) 26 18 22 14 9 NRSGC(%) 28 20 26 13 8 NRSGD(%) 23 15 16 19 9 Which ONE (1) of the following lists the EARLIEST time that the Turbine Driven CA pump would have automatically started?

A. 0205 B. 0210 C. 0215 D. 0220 Page 36 of 75

MCGUIRE NUCLEAR STATION Question: 37 2010 MNS RO NRC Examination 1 point)

Given the following conditions on Unit 1:

• Reactor Power is currently being increased from 55% to 90% RTP at 3%/hr following a Refueling Outage

1. How is the withdrawal of control rods affected?

2. What changes (if any) to NCS boron concentration will be required?

REFERENCE PROVIDED A. 1. NOT restricted

2. Dilution is required.

B. 1. NOT restricted

2. Dilution is NOT required.

C. 1. Restricted

2. Dilution is required.

D. 1. Restricted

2. Dilution is NOT required.

Page 37 of 75

MCGUIRE NUCLEAR STATION Question: 38 2010 MNS RO NRC Examination 1 point)

Given the following plant conditions:

• Waste Gas Decay Tank A is aligned for planned release

• Waste Gas Decay Tank E is also mistakenly aligned for release while in service

• EMF-50 (L) Waste Gas Discharge is not detecting release activity Which ONE (1) of the following would be the result if the release exceeds expected activity levels?

A. The release is monitored by 2EMF-36(L) (Unit 2 Unit Vent Gas). However, no automatic termination will occur.

B. The release is monitored by 2EMF-36(L) which will automatically terminate the release if a Trip 2 alarm is reached.

C. The release is monitored by 1 EMF-36(L) (Unit 1 Unit Vent Gas). However, no automatic termination will occur.

D. The release is monitored by 1 EMF-36(L) which will automatically terminate the release if a Trip 2 alarm is reached.

Page 38 of 75

MCGUIRE NUCLEAR STATION Question: 39 2010 MNS RO NRC Examination point)

Given the following conditions on Unit 1:

• A Reactor Trip and Safety Injection have occurred due to a Small-Break LOCA

• The crew has entered E-O (Reactor Trip or Safety Injection) and has reached Step 7:

Check ESF Monitor Light Panel on energized train(s)

This check is performed to prevent (1) AND to (2)

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

A. 1. water from entering the steam lines due to uncontrolled CA flow

2. ensure Containment release paths are isolated B. 1. excessive NC system cooldown due to uncontrolled CF flow

2. ensure Containment release paths are isolated C. 1. water from entering the steam lines due to uncontrolled CA flow

2. ensure automatic actuation of Containment Spray and Containment Isolation Phase B if containment pressure exceeded 3 PSIG D. 1. excessive NC system cooldown due to uncontrolled CF flow

2. ensure automatic actuation of Containment Spray and Containment Isolation Phase B if containment pressure exceeded 3 PSIG Page 39 of 75

MCGU IRE NUCLEAR STATION Question: 40 2010 MNS RO NRC Examination 1 point)

Given the following conditions on Unit 1:

• The unit is in MODE 3 at full temperature and pressure

• The crew has entered AP/1/A/5500/O11 (Pressurizer Pressure Anomalies) due to Pressurizer pressure decreasing very slowly

• Pressurizer pressure is 2150 PSIG

• PRT pressure is 2 PSIG Given the above conditions, determine which ONE (1) of the following would indicate a leaking PORV and the state of the fluid in the PORV discharge?

REFERENCE PROVIDED PORV Discharge Temperature State of the Effluent A. 240-280°F Saturated Vapor B. 200-240°F Saturated Vapor C. 240-280°F Wet Vapor D. 200-240°F Wet Vapor Page 40 of 75

MCGUIRE NUCLEAR STATION Question: 41 2010 MNS RO NRC Examination 1 point)

Given the following conditions on Unit 1:

• The unit has experienced a Reactor Trip and Safety Injection due to a Small-Break LOCA

• The crew has just completed the actions of E-0 (Reactor Trip or Safety Injection)

• NV pump flow to the NC system Cold Legs is 390 GPM

• NC system pressure is 1300 PSIG and stable

• SG pressures are 1092 PSIG and stable

• NC system subcooling on the ICCM is 22°F and stable Which ONE (1) of the following describes plant conditions upon transition to E-1 (Loss of Reactor or Secondary Coolant)?

SGs NC Pumps Required for Running? Heat Removal?

A. YES YES B. YES NO C. NO YES D. NO NO Page 41 of7S

MCGUIRE NUCLEAR STATION Question: 42 2010 MNS RO NRC Examination 1 point)

Unit 1 was operating at 100% RTP. Given the following trends on the 1A NCP:

Time 0200 0205 0210 0215 Pump#1 Seal D/P (PSID) 215 210 205 195 Lower pump bearing temp (°F) 221 225 228 231

1. 1 seal outlet temp (°F) 205 227 235 251 Motor winding temp (°F) 312 314 316 323 What is the LATEST time at which the 1A NCP must be secured?

A. 0200 B. 0205 C. 0210 D. 0215 Page 42 of 75

MCGUIRE NUCLEAR STATION Question: 43 2010 MNS RO NRC Examination 1 point)

A loss of all charging and seal injection flow on Unit 1 has resulted in a failure of the lB NCP #2 Seal.

The lB NCP #1 Seal Leak-off flow is going (1) lB NCP #2 Seal Standpipe (2) level alarm is LIT.

Which ONE (1) of the following completes the statements above?

A. 1. DOWN

2. LOW B. 1. DOWN

2. HIGH C. 1.UP

2. HIGH D. 1.UP

2. LOW Page 43 of 75

MCGUIRE NUCLEAR STATION Question: 44 2010 MNS RO NRC Examination 1 point)

Given the following conditions on Unit 1:

• Unit is in Mode 5

• Both Trains of ND are initially in service

• NC system temperature is being maintained at 140°F

• Subsequently, both ND pumps trip

• The crew has implemented AP-19 (LOSS OF ND OR ND SYSTEM LEAKAGE)

• Efforts to restore an ND pump to service have been unsuccessful If a MAXIMUM NC system temperature of (1) is exceeded, AP-19 will direct the crew to stop attempts to restore an ND pump and (2) to restore cooling to the NC system.

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

A. 1. 180°F

2. initiate NC system feed and bleed B. 1. 180°F

2. attempt to start an NC pump C. 1. 212°F

2. initiate NC system feed and bleed D. 1. 212°F

2. attempt to start an NC pump Page 44 of 75

MCGUIRE NUCLEAR STATION Question: 45 2010 MNS RO NRC Examination 1 point)

Based on the current Pressurizer Pressure Channel indications below:

Pressurizer Pressure Channels Which ONE (1) of the following lists the Selected pressure output to the Pressurizer Pressure Master Controller:

1. Based on the pressure indications shown above?

2. If Pressurizer Pressure Channel 3 fails low?

A. 1. 2240 PSIG

2. 2230 PSIG B. 1. 2235 PSIG

2. 2232.5 PSIG C. 1. 2240 PSIG

2. 2232.5 PSIG D. 1. 2235PS1G

2. 2230 PSIG Page 45 of 75

MCGUIRE NUCLEAR STATION Question:

• 46 2010 MNS RO NRC Examination 1 point)

Given the following conditions on Unit 1:

• Pzr level is slowly decreasing

• Charging flow is slowly increasing

• NC system temperature is decreasing slowly

• SIG levels are being controlled at program level

• The Rod Control Power Mismatch (PMM) indication is (+)1 .5°F Which ONE (1) of the following describes the procedure that will be entered and the FIRST action required based on current conditions?

A. AP/1/N55001001 (Steam Leak)

Reduce turbine load to maintain Rx power less than or equal to 100%.

B. AP/1/A155001001 (Steam Leak)

Manually throttlel NV-238 (Charging Line Flow Control) to stabilize Pzr level.

C. AP/1/A5500/010 (Reactor Coolant Leak) Case II (NC System Leak)

Reduce turbine load to maintain Rx power less than or equal to 100%.

D. AP/11N5500/010 (Reactor Coolant Leak) Case II (NC System Leak)

Manually throttle 1 NV-238 (Charging Line Flow Control) to stabilize Pzr level.

Page 46 of 75

MCGUIRE NUCLEAR STATION Question: 47 2010 MNS RO NRC Examination point)

Given the following conditions on Unit 1:

• The unit has experienced a feedwater line break of the 1A S/G inside containment and a total loss of feedwater

• FR-H.1 (Response to Loss of Secondary Heat Sink) has been entered and feed and bleed of the NC system was initiated

• Shortly after opening the PORVs, the Turbine Driven CA pump is returned to service and a source of feedwater is available

• CETsarestable

• All S/G WR levels are indicating 0%

• Containment pressure is 3.5 PSIG

1. Based on the conditions described above which ONE (1) of the following describes the criteria for restoration of CA flow?

2. What is the basis for the restoration of flow criteria?

A. 1. Restore cooling to ALL intact S/Cs at a rate not to exceed 100 GPM

2. To minimize additional NC cooldown causing thermal stress to the reactor vessel B. 1. Restore cooling to ALL intact S/Cs at a rate not to exceed 100 GPM

2. To minimize the thermal stress o the S/C to prevent failure of S/C components C. 1. Restore cooling to ONE intact S/C at a rate not to exceed 100 GPM

2. To minimize additional NC coo Idown causing thermal stress to the reactor vessel D. 1. Restore cooling to ONE intact S/C at a rate not to exceed 100 GPM

2. To minimize the thermal stress on the S/G to prevent failure of S/G components Page 47 of 75

MCGUIRE NUCLEAR STATION Question: 48 2010 MNS RO NRC Examination 1 point)

Given the following plant conditions:

• Due to a fault at the switch yard, the site has experienced a LOOP

• Unit I subsequently lost both D/Gs

• Due to a rupture of the Diesel VI compressor discharge piping, VI header pressure is indicating 0 PSIG

• The crew is performing ECA 0.0 (Loss of All AC Power)

• Prior to this event, Unit I was at 100% RTP with normal LID in service and flow being controlled with 1 NV-459 (UI Variable L/D Orifice Outlet Flow Cntrl)

• The Crew is performing Step 6 of ECA 0.0 Check NC System ISOLATED Assuming no manual operator action has been taken associated with these components, which ONE (I) of the following correctly lists the expected As Found positions for the valves listed below?

o INV-35A (Variable LID Orifice Outlet Cont Isol) o 1NV-1A (NC LID Isol To Regen Hx)

A. 1NV-35A-CLOSED INV-IA -CLOSED B. INV-35A-OPEN INV-1A -CLOSED C. INV-35A-CLOSED 1NV-1A -OPEN D. INV-35A-OPEN INV-1A -OPEN Page 48 of 75

MCGUIRE NUCLEAR STATION Question: 49 2010 MNS RO NRC Examination point)

Given the following conditions on Unit 1:

• A loss of offsite power has occurred

• 1A and 1 B DGs have started and loaded normally Based on the following loading profile for 1A DG:

DG 1A LOAD (KW) 5000 4800 4600 4400 j 4200 ___- -- - - - -

I -

4000 3800 4

3600 3400 4:00 5:00 6:00 7:00 8:00 9:00 10:00

==DG 1A LOAD (KW)

1. The maximum design load limit for CONTINUOUS operation was FIRST exceeded at (1)

2. The maximum design load limit for operation in an OVERLOAD condition was FIRST exceeded at (2)

Which ONE (1) of the following completes the statements above?

A. 1. 0430

2. 0600 B. 1. 0600

2. 0745 C. 1. 0430

2. 0745 D. 1. 0600

2. 0830 Page 49 of 75

MCGU IRE NUCLEAR STATION Question: 50 2010 MNS RO NRC Examination 1 point)

The Kirk Key interlocks located on the Vital Battery Charger Connection Boxes (ECB-1 thru 4) associated with EVCA, EVCB, EVCC and EVCD prevent Which ONE (1) of the following completes the statement above?

A. supplying A Train Busses from the B Train Source B. tying a Unit 1 power source to a Unit 2 power source C. energizing more than one battery from the Standby Charger D. supplying two I 25v DC Distribution Centers from the Standby Charger Page 50 of 75

MCGUIRE NUCLEAR STATION Question: 51 2010 MNS RO NRC Examination 1 point)

Given the following conditions on Unit 1:

• The unit is at 100% RTP

• Train swap is in progress and currently both trains of KC and RN have been placed in service.

• The 1A RN pump TRIPPED

• A Unit 2 electrical fault causes a B/C associated with 2ETA.

Based on the conditions described above and assuming no operator action, which ONE (1) of the following describes the effect of this event on Unit 1?

A. Cooling flow would be lost to the 1A KC HX due to Unit 1 RN Train separation.

The lB RN Train suction and discharge alignment would be unaffected.

B. Cooling flow would be lost to the 1A KC HX due to Unit 1 RN Train separation.

The lB RN Train suction and discharge would realign to the SNSWP.

C. The lB RN Pump would continue to supply cooling for the 1A KC HX because the Unit I RN Train cross connect valves remain open.

The lB RN Train suction and discharge would realign to the SNSWP.

D. The lB RN Pump would continue to supply cooling for the 1A KC HX because the Unit 1 RN Train cross connect valves remain open.

The lB RN Train suction and discharge alignment would be unaffected.

Page 51 of75

MCGUIRE NUCLEAR STATION Question: 52 2010 MNS RO NRC Examination 1 point)

Given the foflowing conditions on Unit 1:

• A loss of offsite power has occurred

• Both EDG5 failed to start

• ECA-0.0 (Loss of All AC Power) has been implemented

• VI Header pressure is 20 PSIG Based on the conditions above, CA flow may have to be controlled locally to prevent Which ONE (1) of the following completes the statement above?

A. SG overfill B. CA pump runout C. lossofheatsink D. loss of shutdown margin Page 52 of 75

MCGU IRE NUCLEAR STATION Question: 53 2010 MNS RO NRC Examination point)

Unit 1 & 2 are operating at 100% RTP:

• The TCC has notified the Control Room that the uReal Time Contingency Analysis (RTCA) indicates that switchyard voltage would NOT be adequate should a Unit Trip occur

• The CR Supervisors implement AP/1/A/5500/05 and AP/2/A/5500/05, Generator Voltage and Electric Grid Disturbances

• The OAC is not in service

• Unit 1 Main Generator Voltage is 23.8 KV

• Unit 2 Main Generator Voltage is 24.2 KV

• Unit 1 & 2 Main Generator MWs are 1200

• Unit 1 Main Generator MVARs are 450

• Unit 2 Main Generator MVARs are 475

• 2 pressure on both generators is 75 PSIG H

Which ONE (1) of the following actions is required to be taken by the Unit 1 & 2 crews?

REFERENCE PROVIDED A. Depress RAISE on the VOLTAGE ADJUST for Unit I ONLY.

B. Depress RAISE on the VOLTAGE ADJUST for Unit 2 ONLY.

C. Depress LOWER on the VOLTAGE ADJUST for Unit 1 ONLY.

D. Depress LOWER on the VOLTAGE ADJUST for Unit 2 ONLY.

Page 53 of 75

MCGUIRE NUCLEAR STATION Question: 54 2010 MNS RO NRC Examination 1 point)

Given the following conditions on Unit 1:

• A Reactor Trip and SI have occurred due to low Pressurizer pressure

• Crew is performing the actions of E-0 (Reactor Trip or SI)

• SI termination criteria cannot be met at this time

• Containment parameters are normal

• Both ND pumps are tripped

• FWST level indicates 340 inches

• 1EMF-1 (ND Area Monitor) is in Trip 2 at 1.5E2 mREM/hr

• 1EMF-41 (Aux Bldg Ventilation) is in Trip 2 alarm Based on the above indications, the crew will transition to (1) and the strategy implemented to mitigate this event is (2)

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

A. 1. ECA-1 .1 (Loss of Emergency Coolant Recirculation)

2. to identify and isolate the break B. 1. ECA-1 .1 (Loss of Emergency Coolant Recirculation)

2. to delay depletion of the FWST by reducing outflow and initiating makeup C. 1. ECA-1 .2 (LOCA Outside Containment)

2. to identify and isolate the break D. 1. ECA-1 .2 (LOCA Outside Containment)

2. to delay depletion of the FWST by reducing outflow and initiating makeup Page 54 of 75

MCGUIRE NUCLEAR STATION Question:

• 55 2010 MNS RO NRC Examination 1 point)

Given the following conditions on Unit 1:

• A medium-break LOCA occurred in Containment

• Containment pressure peaked at 2.7 PSIG and is slowly decreasing

• The crew has implemented FR-H.1 (Response to Loss of Secondary Heat Sink)

• All attempts to restore flow to the S/Gs from the CA system have been unsuccessful

1. Based on these conditions, the NC pumps must be stopped to

2. The EARLIEST time (based on S/G conditions) that the crew is required to establish NC system bleed and feed is when W/R level in at least 3 S/Gs is less than Which ONE (1) of the following completes the statements above?

A. 1. prevent NC pump impeller damage due to low pressure operation

2. 24%

B. 1. prevent NC pump impeller damage due to low pressure operation

2. 36%

C. 1. conserve secondary inventory by reducing NC system heat input

2. 24%

D. 1. conserve secondary inventory by reducing NC system heat input

2. 36%

Page 55 of 75

MCGUIRE NUCLEAR STATION Question: 56 2010 MNS RO NRC Examination point)

Given the following conditions on Unit 1:

• EP/1/N5000/ECA-1.1, Loss of Emergency Coolant Recirculation, has just been implemented

• The FWST LEVEL LO-LO alarm is LIT Which ONE (1) of the following actions are required FIRST?

A. When FWST level decreases to less than 20 inches, reset Containment Spray AND stop the NS pumps.

B. When FWST level decreases to less than 20 inches, stop the NS pumps ONLY.

C. Immediately reset Containment Spray AND stop the NS pumps.

D. Immediately stop the NS pumps ONLY.

Page 56 of 75

MCGUIRE NUCLEAR STATION Question: 57 2010 MNS RO NRC Examination i point)

Given the following conditions on Unit 1:

• An ATWS has occurred

• The crew has entered FR-S.I (Response to Nuclear Generation/ATWS)

• During the initiation of emergency boration, the following indications are noted:

o Charging Flow= 47 GPM o Letdown Flow = 75 GPM o NC system pressure is 2300 PSIG o IA NV pump is ON with suction aligned to the VCT o lAand lB BAT pumps are ON o 1NV-265B (Boric Acid To NV Pumps) is open o INV-244A (Chrg Line Cont Isol) is open o 1NV-245B (Chrg Line Cont Isol) is open In accordance with FR-Si, the MINIMUM required emergency boration flow is (1) and if that flow is NOT met the Operator will (2)

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

A. 1. 3OGPM

2. increase charging flow B. 1. 6OGPM

2. increase charging flow C. 1. 3OGPM

2. align the NV pump suction to the FWST D. I. 6OGPM

2. align the NV pump suction to the FWST Page 57 of 75

MCGUIRE NUCLEAR STATION Question: 58 2010 MNS RO NRC Examination 1 point)

Given the following conditions on Unit 1:

• Pressurizer Level transmitter 1 has failed low

• Prior to removing the Level Channel 1 from service, a leak develops on the reference leg for Pressurizer Level transmitter 2 Based on these conditions, the indication for Pressurizer Level Channel 2 fails (1)

AND the Pressurizer Level Master Controller (2)

Which ONE of the following completes the statement above?

A. 1. low

2. swaps to MANUAL B. 1. low

2. remainsinAUTO C. 1. high

2. swaps to MANUAL D. 1. high

2. remains in AUTO Page 58 of 75

MCGUIRE NUCLEAR STATION Question: 59 2010 MNS RO NRC Examination 1 point)

Unit I is operating at 97% RTP when a Reactor Trip occurs. Given the following conditions:

Channel Flux Level SUR SRN31 OCPS ODPM SRN32 OCPS ODPM 1RN35 AMPS 10 l.1x1O -l/3DPM IR N36 11 AMPS 9.5x10 -1/3 DPM PRN41 12%

PRN42 1 0%

PR N43 0%

PRN44 0%

Which ONE (1) of the following statements describes why the Source Range Nuclear Instruments are NOT indicating?

A. P-i 0 (Nuclear at Power) status light is LIT.

B. P-6 (S/R Block Permissive) status light is LIT.

C. P-b (Nuclear at Power) status.light is DARK.

D. P-6 (S/R Block Permissive) status light is DARK.

Page 59 of 75

MCGUIRE NUCLEAR STATION Question: 60 2010 MNS RO NRC Examination 1 point)

Given the following conditions on Unit 1:

• Unit is currently at 35% RTP

• A unit shutdown is in progress

• Intermediate Range Channel N35 fails

• N35 Level Trip Bypass switch has been placed in BYPASS in accordance with AP-16 (Malfunction of Nuclear Instrumentation)

• N35 Instrument Power fuses and Control Power fuses have been removed for troubleshooting Which ONE (1) of the following describes the actions required to prevent a Reactor Trip and the MINIMUM power level at which those actions must be performed if the unit shutdown is continued?

A. N35 Control Power fuses ONLY must be installed or a Reactor Trip will occur when power decreases to less than 10% RTP.

B. N35 Control Power fuses ONLY must be installed or a Reactor Trip will occur when power decreases to less than 25% RTP.

C. N35 Control Power fuses AND Instrument Power fuses must be installed or a Reactor Trip will occur when power decreases to less than 10% RTP.

D. N35 Control Power fuses AND Instrument Power fuses must be installed or a Reactor Trip will occur when power decreases to less than 25% RTP.

Page 60 of 75

MCGUIRE NUCLEAR STATION Question: 61 2010 MNS RO NRC Examination 1 point)

An NED reports a leak in the 1A NV pump room. Water from the leak is spraying into the air and is also collecting on the floor.

Radiation Protection (RP) is notified and determines the water is contaminated. RP reports that the radiation from the leak is exclusively a skin dose and absorption concern.

The radiation emitted from the contamination is predominately (1)

This event results in a Trip 2 alarm on 1 EMF-41 (Aux Building Ventilation). The Auxiliary Building Ventilation (2)

Which ONE (1) of the following completes the statements above?

A. 1. Alpha

2. supply and exhaust fans will trip B. 1. Beta

2. supply and exhaust fans will trip C. 1. Alpha

2. filter train will be placed in service D. 1. Beta

2. filter train will be placed in service Page 61 of 75

MCGUIRE NUCLEAR STATION Question: 62 2010 MNS RO NRC Examination 1 point)

Given the following plant conditions:

• The Control Room has been evacuated due to a chlorine gas leak

• AP-17 (Loss of Control Room) has been implemented on both units

• An Operator has been dispatched to control IA & 1D SG PORV5 using AP-17, Enclosure 7 (Manual Control of PORVs)

The Operator dispatched to perform Enclosure 7 will control the SG PORVs using manual loaders located in the (1) To establish control of the SG PORVs the Operator must (2)

Which ONE (I) of the following completes the statements above?

A. 1. Exterior Doghouse

2. open the VI supply from the local manual loader ONLY B. 1. Interior Doghouse

2. open the VI supply from the local manual loader ONLY C. 1. Exterior Doghouse

2. open the VI supply from the local manual loader AND close the VI supply from the Control Room manual loader D. 1. Interior Doghouse

2. open the VI supply from the local manual loader AND close the VI supply from the Control Room manual loader Page 62 of 75

MCGUIRE NUCLEAR STATION Question:

• 63 2010 MNS RO NRC Examination 1 point)

Given the following conditions on Unit 1:

• The unit was operating at 100% RTP with a VQ release in progress

• A Rx Trip was manually initiated due to the 1A S/G FRV failing closed

• The resulting transient resulted in a tube rupture on the 1A SIG

• The crew has manually initiated Safety Injection

• Both trains Cont Vent Isol Reset lights on 1MC-11 are LIT

• IVQ-IA (U-i Cont Air Release Inside 1501) indicates OPEN

• No AUTO SI setpoints have been exceeded

• 1EMF 38, 39 & 40 readings have remained less than Trip 2 values Based on these conditions, the Containment Ventilation Isolation Reset Lights should be (1) AND the Operators shall (2)

Which ONE (1) of the following completes the statements above?

A. 1. DARK

2. close 1VQ-iA B. 1. DARK

2. verify IVQ-1A remains OPEN C. 1. LIT

2. close 1VQ-1A D. 1.LIT

2. verify IVQ-iA remains OPEN Page 63 of 75

MCGUIRE NUCLEAR STATION Question: 64 2010 MNS RO NRC Examination 1 point)

Which ONE of the following will generate a LOSS OF SUBCOOLING (AD2-D5) annunciator in the Control Room?

A. 2°F subcooling on Loop A TH B. 0°F subcooling on Loop B TH C. 2°F subcooling on Loop C TH D. 0°F subcooling on Loop D TH Page 64 of 75

MCGUIRE NUCLEAR STATION Question: 65 2010 MNS RO NRC Examination 1 point)

Given the following conditions on Unit 1:

• A cooldown is being performed in accordance with ES-O.2 (Natural Circulation Cooldown)

• The crew has reached the step in ES-02 to initiate a depressurization of the NC system

• The crew observes that 2 CRDM fans are running

1. Based on the conditions above, the depressurization continue.

2. The basis, per ES-O.2 Background Document for checking the number of CRDM fans running is to Which ONE (1) of the following completes the statements above?

A. 1.can

2. enhance natural circulation flow B. 1. can

2. prevent voiding in the reactorvessel head C. 1. can NOT

2. enhance natural circulation flow D. 1. can NOT

2. prevent voiding in the reactor vessel head Page 65 of 75

MCGUIRE NUCLEAR STATION Question: 66 2010 MNS RO NRC Examination 1 point)

Given the following conditions on Unit 1:

• A Small-Break LOCA has occurred

• Attempts to mitigate the event have been unsuccessful

• Core Exit Thermocouples are 6 30°F and STABLE

• Subcooling is (-)5°F and STABLE

• A and B NC pumps have been secured

• C and D NC pumps are running In order to satisfy the requirements for the Critical Safety Function for Core Cooling, which ONE (1) of the following is required Reactor Vessel DIP based on the conditions above?

REFERENCE PROVIDED A. Train A 15%, Train B 15%

B. Train A 15%, Train B 23%

C. Train A 23%, Train B 15%

D. Train A 23%, Train B 23%

Page 66 of 75

MCGUIRE NUCLEAR STATION Question:

• 67 2010 MNS RO NRC Examination 1 point)

Given the following:

• Operators are performing valve lineups on the Unit 1 Secondary

• Several valves are approximately 15 feet above the floor level In accordance with the Nuclear Generation Department Safe Work Practices Pocket Manual, the Operators performing the manipulations can work safely using a securely placed extension ladder and Which ONE (1) of the following completes the statement above?

A. a safety belt with the lanyard attached to a nearby 6 diameter pipe B. a full body harness with the lanyard attached to a nearby 4 diameter pipe C. a safety belt with the lanyard attached to a nearby vertical scaffolding member D. a full body harness with the lanyard attached to a nearby horizontal scaffolding member Page 67 of 75

MCGUIRE NUCLEAR STATION Question: 68 2010 MNS RO NRC Examination 1 point)

In accordance with Tech Spec 2.1.1 (Reactor Core Safety Limits) Bases, the proper functioning of the (1) AND (2) prevent exceeding the Departure from Nucleate BoiHng Reactor Core Safety Limit.

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

A. 1. Rod Control System

2. Pressurizer Safety Valves B. 1. Rod Control System

2. Main Steam Safety Valves C. 1. Reactor Protection System

2. Pressurizer Safety Valves D. 1. Reactor Protection System

2. Main Steam Safety Valves Page 68 of 75

MCGUIRE NUCLEAR STATION Question: 69 2010 MNS RO NRC Examination 1 point)

With Unit I operating at 100% RTP, which ONE (1) of the following exceeds the limits of Tech Spec 3.4.13 (RCS Operational Leakage)?

A. 6 GPM identified leakage B. 0.5 GPM unidentified leakage C. 140 GPD tube leakage in 1C SC D. 356 GPD total primary-to-secondary leakage through all SGs Page 69 of 75

MCGU IRE NUCLEAR STATION Question: 70 2010 MNS RO NRC Examination 1 point)

Given the following conditions on Unit 1:

• The NV system is being aligned for startup

• The procedure being used calls for independent verification of a single valve located in a room with a general dose rate of 130 mREM/hr

• Estimated time to independently verify the valves position is 10 minutes

• There are no known hot spots in the area

• There is no airborne activity in this room

• The room has no surface contamination areas

• Assume any necessary approvals are obtained In accordance with NSD 700 (Verification Techniques), independent verification of the valve above (1) be waived because (2)

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

A. 1. may

2. the general area dose rate is greater than 100 mREM/hr B. 1. may NOT

2. the general area dose rate is less than 1 REM/hr C. 1. may

2. the radiation exposure for a single verification would exceed the allowable limit D. 1. may NOT

2. the radiation exposure for a single verification is within the allowable limit Page 70 of 75

MCGUIRE NUCLEAR STATION Question: 71 2010 MNS RO NRC Examination 1 point)

Regarding the use of Electronic Dosimeters (ED):

• If a DOSE alarm setpoint is exceeded, the alarm will (1)

• If a DOSE RATE alarm setpoint is exceeded, the alarm will (2)

Which ONE (1) of the following completes the statements above?

A. 1. not clear until the ED is reset

2. clear when the dose rate drops below the alarm setpoint B. 1. not clear until the ED is reset

2. not clear until the ED is reset C. 1. automatically clear after 10 seconds

2. clear when the dose rate drops below the alarm setpoint D. 1. automatically clear after 10 seconds

2. not clear until the ED is reset Page 71 of 75

MCGUIRE NUCLEAR STATION Question: 72 2010 MNS RO NRC Examination 1 point)

Given the following conditions on Unit 1:

• The unit has experienced several fuel pin failures

• You have been directed to tag out the 1 B NI pump

• The lB NI pump room general area is 400 mREM/hr

• To reach the 1 B NI pump room you must transit through a 6 REM/hr high radiation area for 2 minutes and return via the same route

• Your current accumulated annual dose is 1000 mREM

• An RWP has been written for this job which has your Electronic Dosimeter (ED) alarm set for your EXCLUDE exposure limit Based on the conditions above, what is your MAXIMUM allowable stay-time in the 1 B NI pump room for hanging the tagout to prevent your ED from alarming before you exit the RCA?

A. 30 minutes B. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> D. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Page 72 of 75

MCGUIRE NUCLEAR STATION Question: 73 2010 MNS RO NRC Examination point)

Given the following conditions on Unit 1:

• A Reactor Trip and Safety Injection have occurred

• Main Steam and ALL feedwater is isolated to all SGs

• TD CA pump is running.

• All SG level instruments agree and indicate as follows:

Which ONE (1) of the following describes the condition of the SGs?

A. 1A lB 1C 1D Faulted Ruptured j Intact Intact B. 1A lB 1C 1D Faulted R uptu red Ruptured Intact C. 1A lB 1C 1D Ruptu red Faulted Ruptured Intact D. 1A lB 1C ID Ruptured Faulted Intact Intact Page 73 of 75

MCGUIRE NUCLEAR STATION Question:

• 75 2010 MNS RO NRC Examination 1 point)

Given the following indications on Unit 1:

• 1AD-2 I C8 (PIR OVER POWER STOP ALERT) is in LIT

• Tavg is 578°F and stable

1. Which ONE (1) of the following lists the MINIMUM conditions that will cause the alarm above?

2. Which ONE (1) of the following is the required action for the above condition per OP/11N61001010 C, Annunciator Response for Panel 1AD-2?

A. 1. OnePRchannelgreaterthanlO9%

2. Initiate RCS boration to reduce power B. 1. One PR channel greater than 103%

2. Reduce turbine load to reduce power C. 1. One PR channel greater than 103%

2. Initiate RCS boration to reduce power D. 1. OnePRchannelgreaterthanlo9%

2. Reduce turbine load to reduce power Page 75 of 75

Reference Listfor: 2010 MNS RO NRC Examination U-i Data Book Curve 1.8 EP Generic Enc G-1 End. 4 Data Book Sect. 1.3 Enc. 4.3 Steam Tables Unit I & 2 Generator Capability Curves EP/IIAI5000IF-O Page 5 of 11 Printed 7/13/2010 2:36:53 PM

MNS GENERIC ENCLOSURES PAGE NO.

EP/1/A15000/G-1 Enclosure 4-Page 1 of 8 UNIT 1 Placing H2 Recombiners In Service Rev 25 ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED

1. Select one train of H2 Recombiner to be placed in service:

. To start 1A H 2 Recombiner, GOTO Step 2.

OR

. To start lB H 2 Recombiner, GOTO Step 5.

2. Determine IA H 2 Recombiner power setting as follows:

a. Determine PRESSURE FACTOR, CP from Data Book Curve 1.8.

b. Multiply lA REFERENCE POWER listed on Data Book Curve 1.8 by PRESSURE FACTOR, CP to determine 1A Hydrogen Recombiner Power Setting.

1A:

lA REFERENCE POWER PRESSURE FACTOR, CP 1A Power Setting

c. Record lA POWER SETTING

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U NIT I Pagelof4 OP/i /A/61 00/022 Unit 1 Data Book Section 1 .3 Enclosure 4.3 Fuel Maneuvering Limits NOTES: 1: Fuel Maneuvering Limits apply to power increases NOT power decreases.

2: Maneuvering Limits are based on REACTOR POWER not GENERATOR POWER.

3: Contact the Reactor Group if there are any questions concerning the Fuel Maneuvering Limits.

Definitions Ramp Rate Ramp rate is the core power increase time averaged over a maximum period of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2. Conditioned Power Level

a. Operating Category 1: During initial cycle startup (including first core startup and any cold shutdown in which fuel assemblies were handled) prior to achieving 100% RTP for 72 cumulative hours out of any 7 day operating period at power.

CPL highest power level sustained for at least 72 cumulative hours (does not have to be consecutive) out of any 7 day operating period at power.

b. Operating Category 2: After achieving the 100% RTP requirement above.

CPL highest power level sustained for at least 72 cumulative hours (does not have to be consecutive) out of the preceding 30 day operating period at power.

UNIT I

U NIT I Page2of4 OP/i /A/61 00/022 Unit 1 Data Book Section 1.3 Enclosure 4.3 Fuel Maneuvering Limits Allowable Ramp Rates Initial cycle startup No Rate Restrictions from 0% RTP to 40% RTP Recommended rate of < 3%/hour between 40% RTP and 100%

RTP, but to accomodate secondary side efficiency changes, rate shall never exceed:

3% step change increase 4% power increase in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 7% power increase in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 10% power increase in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Subsequent power maneuvering No Rate Restrictions from 0% RTP to 40% RTP, if CPL <40% RTP No Rate Restrictions from 0% RTP to CPL, if CPL > 40% RTP When CPL> RTPBE, no step change increase shall exceed 10%

When RTPBE > 40% AND RTPBE > CPL, recommended rate of

<3 %/hour; but to accomodate secondary side efficiency changes, rate shall never exceed:

3% step change increase 4% power increase in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 7% power increase in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 10% power increase in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> UNIT I

U NIT I Page3of4 OP/1/A161 00/022 Unit 1 Data Book Section 1.3 Encbsure 4.3 Fuel Maneuvering Limits Ill. Control Rod Movement Initial Cycle Startup Applicable for initial startup following refueling, or following cold shutdown where fuel assemblies were handled within the reactor vessel.

Control Rod Withdrawal Rate Limit of 3 steps/hour above 50% RTP concurrent with power increase. There are no control rod movement rate limits when RTP is held constant.

Once the rods have been withdrawn to a given position at a given power level, during subsequent maneuvers there are no restrictions on rod withdrawals to the previous position up to that power level.

Subseciuent Startups There are no restrictions on rod withdrawals to the maximum withdrawn position and corresponding power level that has occurred since the most recent startup.

For withdrawals beyond the maximum withdrawn position, limit withdrawal to 3 steps per hour concurrent with power increase.

There are no control rod withdrawal limits when RTP is constant.

UNIT I

Unit I Page 4 of 4 OP/i /A16 100/22 Unit 1 Data Book Section 1.3 Enclosure 4.3 Fuel Maneuvering Limits POWER RAMP RESTRICTIONS ITIALSTARTUPFOLLOWINGREFUELING MEN DED RAMP = 3%/HOUR, 40%FP 100%FP TDOWN OR FOLLOWING COLD SHUTDOWN) Yes -

\MAX RAMP 3% STEP CHANGE, 4% in 1 HOUR, 7% in 2)

AS S EMBL IES HAN DLED HOURSand10%in3HOURS No FP FOR 72 CUMULATIVE CPL=HIGHEST POWER LEVEL SUSTAINED HOURS OUT OF ANY 7 DAY FOR AT LEAST 72 CUMULATIVE HOURS OPERATING PERIOD AT POWE (CONSECUTIVE OR NON-CONSECUTIVE(

OUT OF AN Y 7 DAY OPERAT INC PERIOD AT POWER Yes ZPERATING CATEGORY CPL=HIGHEST POWER LEVEL 7 SUSTAINED FOR AT LEAST 72 CUMULATIVE HOURS (CONSECUTIVE OR NON CONSECUTIVE) OUT OF THE PRECEDING 30 DAY OPERATING PERIOD AT POWER 4-.

RECOMMENDED RAMP = 3% / HOUR MAX RAMP 3% STEP CHANGE, 4% in 1 HOUR, 7% in 2)

HOURS and 10% in 3 HOURS No 4

Rx PowerCPL No RATE RESTRICTIONS STEP INCREASE SHALL EXCEED 10%

Rx POWER CPL N -

CPL-100%RTP RECOMMENDED RAMP = 3% / HOUR, CPL 100 / F MAX RAMP = 3% STEP CHANGE, 4% in 1 HOU R, 7%

HOURS and 10% in 3 HOURS I

No 40%-100% RTP NO RATE RESTRICTIONS UP TO OMMENDED RAMP = 3% / HOUR, 40% 100%FP MAX RAMP = 3% STEP CHANGE, 4% in 1 HOUR, 7%

40% RTP

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MNS CRITICAL SAFETY FUNCTION STATUS TREES I PAGE NO. I EPJ1JA/5000/F-O I Core Cooling Page 1 of 1 I 5 of 11 I I

UNIT 1 4 REACTOR VESSEL DIP SETPOINTS FOR DEGRADED CORE COOLING Requi,ed PEACTOR VESSEL D/P Number of TEN A TEN S NC Pumps With l NC Pump With 1C NC Pump On ON OFF ON OFF 4 44% N/A 44% N/A 3 30% 24% 30% 24%

2 23% 15% 23% 15%

1 16% 10% 16% 10%

Examination KEYfor: 2010 MNS RO NRC Examination Question Answer Number 1 D 2 B 3 D 4 A 5 B 6 D 7 D 8 D 9 D 10 C 11 B 12 A 13 D 14 A 15 A 16 A 17 A 18 D 19 C 20 B 21 B 22 C 23 D 24 C 25 C Printed 7/13/2010 2:38:51 PM Page 1 of 3

Examination KEYfor: 2010 MNS RO NRC Examination Question Answer Number 26 D 27 A 28 B 29 C 30 C 31 C 32 C 33 B 34 B 35 B 36 A 37 C 38 D 39 B 40 D 41 A 42 A 43 B 44 A 45 B 46 A 47 D 48 A 49 B 50 B Printed 7/13/2010 2:38:52 PM Page 2 of3

Examination KEYfor: 2010 MNS RO NRC Examination Question Answer Number 51 B 52 A 53 C 54 C 55 C 56 C 57 C 58 C 59 B 60 A 61 D 62 C 63 A 64 D 65 B 66 B 67 B 68 D 69 C 70 C 71 A 72 B 73 D 74 B 75 B Printed 7/13/2010 2:38:52 PM Page 3 of 3