Text

Initial Exam 2010-301 Final SRO Written Exam
	ML102390061
Person / Time
Site:	Mcguire, McGuire
Issue date:	08/25/2010
From:	; NRC/RGN-II
To:	;
References
	Download: ML102390061 (124)
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U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date: Facility/Unit: McGuire Region: I Ill 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 overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to complete the combined examination, and 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months if you are only taking the SRO portion.

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

Applicants Signature Results RO/SRO-OnlyfTotal Examination Values / / Points Applicants Score / / Points Applicants Grade / / Percent

MCGU IRE NUCLEAR STATION Question: I 2010 MNS SRO 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. DNBRwiIIINCREASE.

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 100

MCGUIRE NUCLEAR STATION Question: 2 2010 MNS SRO NRC Examination point)

Given the following conditions on Unit 1:

Unit is operating at 100% RTP

The controller for I 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 100

MCGU IRE NUCLEAR STATION Question: 3 2010 MNS SRO NRC Examination I point)

Given the following conditions on Unit 1:

Unit is in MODE 5 with ND Train A in service

I NI-I 73A (Train A ND to A & B CL) is OPEN

ND flow is being reduced by throttling I 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 (I) . 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. I. 325GPM

2. the OAC ONLY B. 1. 325GPM

2. a chart recorder on MC-7 AND the OAC C. I. 750 GPM

2. theOAC ONLY D. 1. 750 GPM

2. a chart recorder on MC-7 AND the OAC Page 3 of 100

MCGUIRE NUCLEAR STATION Question:

4 2010 MNS SRO NRC Examination 1 point)

Given the following conditions on Unit 1:

The unit is in MODE4

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 (1) 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 100

MCGUIRE NUCLEAR STATION Question: 5 2010 MNS SRO 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. ventairoff C. 1. SafetyinjectionORBlackout

2. maintain VI aligned to D. 1. Safety Injection OR Blackout

2. ventairoff Page 5 of 100

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

Unit 1 is operating at 100% RTP.

Given the following indications for Unit 1 CLAs:

1A lB 1C 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. 1 B CLA ONLY is INOPERABLE.

B. lC CLA ONLY is INOPERABLE.

C. IA and 1C CLAs are INOPERABLE.

D. 1 B and 1 D CLAs are INOPERABLE.

Page 6 of 100

MCGUIRE NUCLEAR STATION Question: 7 2010 MNS SRO NRC Examination 1 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 any one hour period

2. Cycle Pressurizer PORVs B. 1. 75°F in anyone hourperiod

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

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

2. Cycle the Reactor Vessel Head vents Page 7 of 100

MCGUIRE NUCLEAR STATION Question: 8 2010 MNS SRO NRC Examination I point)

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

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

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

A. 1. Trip I

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

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

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

2. will automatically re-open when the alarm clears Page 8 of 100

MCGUIRE NUCLEAR STATION Question: 9 2010 MNS SRO NRC Examination (1 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:

ACTIVE FRESSURE CONTROL PZR PRESSURE ERRP -10 01 PSIG I MIN DEMAND MAX DEMAND I\

HEATER NR4AL EPRAY RRV

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. ()25PSIG C. 1. 83%

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

2. () 25 PSIG Page 9 of 100

MCGUIRE NUCLEAR STATION Question: 10 2010 MNS SRO NRC Examination i 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 IEKVA 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 100

MCGUIRE NUCLEAR STATION Question: 11 2010 MNS SRO NRC Examination I 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;IEVDB B. IEVDA;IEVDD C. IEVDB;IEVDC D. IEVDC;IEVDD Page 11 of 100

MCGUIRE NUCLEAR STATION Question: 12 2010 MNS SRO 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 1A8, (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 100

MCGUIRE NUCLEAR STATION Question: 13 2010 MNS SRO 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 (Si-) signal.

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

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

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

Page 13 of 100

MCGUIRE NUCLEAR STATION Question: 14 2010 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The unit is increasing power after a forced shutdown

OP/1/N6100/003 (Controlling Procedure for Unft Operation) is in effect

IA CF pump is in service

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

When 1HM-95 closes, the crew observes the IA CF pump speed and DIP decreasing and FRVs opening I. What is the cause of the indications described above?

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

A. I. 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 80% RTP.

B. 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 100% RTP.

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

2. 1 HM-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 100

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

Given the following conditions on Unit 1:

The unit is in MODE I at 10% RTP

1AD-9 /A5 (ICE COND LOWER IN LET 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, NF system or AHU5 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 3.6.12 Ice Bed

3. Selected Licensee Commitment 16.6-3 Ice Condenser Door Position Monitoring System A. 1 ONLY B. 1 and 2 ONLY C. Iand3ONLY D. 1,2,and3 Page 15 of 100

MCGU IRE NUCLEAR STATION Question: 16 2010 MNS SRO NRC Examination 1 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, 1 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 IA/62001014 (Refueling Water System) what alignment would be required to address the radiological effects of this event?

A. 1. Increased radiation levels at the FWST enclosure.

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

B. 1. Increased 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. I. The formation of hot spots in the ECCS suction piping downstream of 1FW-27 (FWST to ND Pump Isol).

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 (FWST to 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 of 100

MCGUIRE NUCLEAR STATION Question:

17 2010 MNS SRO NRC Examination (1 point)

Given the foflowing 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 MSIVs for the given conditions?

A. Reset the Main Steam Isolation signal ONLY.

B. Reset the Phase BAND 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 100

MCGUIRE NUCLEAR STATION Question:

18 2010 MNS SRO NRC Examination 1 point)

Given the following 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 N BLOC 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 100

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

Given the foflowing 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 NEC 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. SMXGI C. SDSP-1 D. 1EVDA-1 Page 19 of 100

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

Given the following conditions on Unit 1:

B Train of essential equipment is in operation on Unit 1

OP/i /A/6350/002 (Diesel Generator) is in progress with the IA 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 Sl-14 Which ONE (1) of the following completes the statement above?

A. illuminates and the 1A DG load increases B. remains dark and the 1A DG load increases C. illuminates and the 1A DG Emergency Breaker trips open, then re-closes 8.5 seconds later D. remains dark and the 1A DG Emergency Breaker trips open, then re-closes 8.5 seconds later Page 20 of 100

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

Given the following plant conditions:

Both Units operating at 100% RTP

A complete Loss of Offsite Power occurred on Unit 1

1A 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 I 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 of 100

MCGUIRE NUCLEAR STATION Question: 22 2010 MNS SRO NRC Examination 1 point)

Given the following plant conditions:

Both Units are operating at 100% RTP

Battery IDP 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 I DP will be energized from Charger I DP ONLY.

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

D. Bus 1DP will be energized from Charger IDP and Battery 1DP.

Page 22 of 100

MCGUIRE NUCLEAR STATION Question: 23 2010 MNS SRO NRC Examination (1 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. PCBs8&9

2. Committed B. 1. PCBs11&12

2. Committed C. 1. PCB58&9

2. Accelerated D. 1. PCBsI1&12

2. Accelerated Page 23 of 100

MCGU IRE NUCLEAR STATION Question: 24 2010 MNS SRO NRC Examination

.1 point)

Which ONE (1) of the following lists the EMFs that will automatically stop the Auxiliary Building Unfiltered Exhaust Fans (IABFXF-1AII 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. I 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 1 EMF 37 Unit Vent Iodine D. I EMF 35(L) Unit Vent Particulate (Low Range) OR I EMF 36(H) Unit Vent Gas (High Range)

Page 24 of 100

MCGUIRE NUCLEAR STATION Question: 25 2010 MNS SRO 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 100

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

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

1AD-12 Cl (VINS Lo Pressure) is LIT

OVIP-5090 (VINS 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. 1VI-820 (VI to VS Supply) auto-closed ONLY.

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

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

Page 26 of 100

MCGUIRE NUCLEAR STATION Question: 27 2010 MNS SRO NRC Examination 1 point)

Given the following:

Unit I 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 100

MCGUIRE NUCLEAR STATION Question:

28 2010 MNS SRO 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 PhaseA 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 100

MCGUIRE NUCLEAR STATION Question: 29 2010 MNS SRO NRC Examination 1 point)

Give the following conditions on Unit 1:

The unit is in MODE 3 withdrawing SID banks in preparation for startup

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

DRPI and DAC 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Page 29 of 100

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

Given the following condftions 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 1 NV-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 2.0FF B. 1. DECREASING 2ON C. 1. INCREASING

2. OFF D. 1. INCREASING 2.ON Page 30 of 100

MCGUIRE NUCLEAR STATION Question: 31 2010 MNS SRO 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

1AD-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 of 100

MCGUIRE NUCLEAR STATION Question: 32 2010 MNS SRO 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 I EVIA has tripped.

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

C. Inverter I EVIC has tripped.

D. The feeder breaker for panelboard 1 EKVD has tripped.

Page32of 100

MCGUIRE NUCLEAR STATION Question: 33 2010 MNS SRO 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 S/G WR Levels D. Incore Thermocouples AND Pressurizer Level Page 33 of 100

MCGUIRE NUCLEAR STATION Question: 34 2010 MNS SRO NRC Examination 1 point)

Given the following on Unit 1:

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

The 1A H2 Recombiner was placed in service per EP/1/A15000/G-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 100

MCGUIRE NUCLEAR STATION Question: 35 2010 MNS SRO 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 (-)2.1 ft SFP level and steady on the main control board

The operating KF pump has tripped

An NEC 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. 1. discharge

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

C. 1. suction

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

D. 1. suction

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

Page 35 of 100

MCGUIRE NUCLEAR STATION Question: 36 2010 MNS SRO NRC Examination 1 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 100

MCGUIRE NUCLEAR STATION Question: 37 2010 MNS SRO 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 100

MCGUIRE NUCLEAR STATION Question: 38 2010 MNS SRO NRC Examination I 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 100

MCGUIRE NUCLEAR STATION Question: 39 2010 MNS SRO 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 coold own 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 100

MCGUIRE NUCLEAR STATION Question: 40 2010 MNS SRO NRC Examination 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/A15500/011 (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 100

MCGUIRE NUCLEAR STATION Question: 41 2010 MNS SRO 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 of 100

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

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

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

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 IA NCP must be secured?

A. 0200 B. 0205 C. 0210 D. 0215 Page 42 of 100

MCGUIRE NUCLEAR STATION Question: 43 2010 MNS SRO NRC Examination 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 100

MCGUIRE NUCLEAR STATION Question: 44 2010 MNS SRO NRC Examination

\ 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-.1 9 (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 teed 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 100

MCGUIRE NUCLEAR STATION Question: 45 2010 MNS SRO 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 100

MCGUIRE NUCLEAR STATION Question:

46 2010 MNS SRO NRC Examination 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/N5500/001 (Steam Leak)

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

B. API1IAI5500IOO1 (Steam Leak)

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

C. APIIIAI5500IO1 0 (Reactor Coolant Leak) Case II (NC System Leak)

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

D AP/1/N5500/O10 (Reactor Coolant Leak) Case II (NC System Leak)

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

Page 46 of 100

MCGUIRE NUCLEAR STATION Question: 47 2010 MNS SRO NRC Examination i 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-Ri (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/Gs 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/Gs 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 C. 1. Restore cooling to ONE intact S/G at a rate not to exceed 100 GPM

2. To minimize additional NC cooldown causing thermal stress to the reactor vessel D. 1. Restore cooling to ONE intact S/G 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 100

MCGUIRE NUCLEAR STATION Question: 48 2010 MNS SRO NRC Examination 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 1 was at 100% RTP with normal LID in service and flow being controlled with 1 NV-459 (U 1 Variable LID 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 (1) of the following correctly lists the expected As Found positions for the valves listed below?

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

A. INV-35A-CLOSED INV-1A -CLOSED B. 1 NV-35A OPEN 1NV-1A -CLOSED C. 1NV-35A-CLOSED 1NV-1A -OPEN D. 1 NV-35A OPEN 1NV-IA -OPEN Page 48 of 100

MCGU IRE NUCLEAR STATION Question: 49 2010 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

A loss of off-site 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 E

4800 -

C 4600 4400 :_:::::

4200 1 -

Z_

4000 -E 3800 __ - - - - -

3600 3400 4:00

---H---

5:00 6:00 7:00 8:00 Z4 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 100

MCGUIRE NUCLEAR STATION Question: 50 2010 MNS SRO NRC Examination l 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 1 25v DC Distribution Centers from the Standby Charger Page 50 of 100

MCGUIRE NUCLEAR STATION Question: 51 2010 MNS SRO 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 I 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 IA KC HX because the Unit 1 RN Train cross connect valves remain open.

The 18 RN Train suction and discharge would realign to the SNSWP.

D. The I B 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 of 100

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

Given the following conditions on Unit 1:

A loss of offsite power has occurred

Both EDGs 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 run out C. lossofheatsink D. loss of shutdown margin Page 52 of 100

MCGUIRE NUCLEAR STATION Question:

53 2010 MNS SRO NRC Examination 1 point)

Unit I & 2 are operating at 100% RTP:

The TCC has notified the Control Room that the Real 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 API2IA/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 I 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 1 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 100

MCGUIRE NUCLEAR STATION Question: 54 2010 MNS SRO 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. toidentifyandisolatethebreak D. 1. ECA-1 .2 (LOCA Outside Containment)

2. to delay depletion of the FWST by reducing outflow and initiating makeup Page 54 of 100

MCGUIRE NUCLEAR STATION Question: 55 2010 MNS SRO 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 100

MCGUIRE NUCLEAR STATION Question:

56 2010 MNS SRO NRC Examination 1 point)

Given the following conditions on Unit 1:

EP/1/A15000/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 100

MCGUIRE NUCLEAR STATION Question: 57 2010 MNS SRO NRC Examination 1 point)

Given the following conditions on Unit 1:

An ATWS has occurred

The crew has entered FR-SI (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 1A NV pump is ON with suction aligned to the VCT o lAand lBBATpumpsareON o 1NV-265B (Boric Acid To NV Pumps) is open o 1NV-244A (Chrg Line Cont Isol) is open o INV-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. I. 3OGPM

2. align the NV pump suction to the FWST D. 1. 6OGPM

2. align the NV pump suction to the FWST Page 57 of 100

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

Given the following conditions on Unit 1:

Pressurizer Level transmitter-I has failed low

Prior to removing the Level Channel I 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 (I)

AND the Pressurizer Level Master Controller (2)

Which ONE of the following completes the statement above?

A. 1. low

2. swapstoMANUAL B. 1. low

2. remainsinAUTO C. 1. high

2. swapstoMANUAL D. I. high -

2. remainsinAUTO -

Page 58 of 100

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

Unit 1 is operating at 97% RTP when a Reactor Trip occurs. Given the following conditions:

Channel Flux Level SUR SR N31 0 CPS 0 DPM SR N32 0 CPS 0 DPM 1RN35 AMPS 10 1.Ix1O -1/3DPM IR N36 11 AMPS 9.5x10 -1/3 DPM PRN41 12%

PR N42 0%

PRN43 0%

PR N44 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-i 0 (Nuclear at Power) status light is DARK.

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

Page 59 of 100

MCGU IRE NUCLEAR STATION Question: 60 2010 MNS SRO 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 troubles hooting 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 100

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

An NEC reports a leak in the IA 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 emiffed from the contamination is predominately (1)

This event results in a Trip 2 alarm on I 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 100

MCGUIRE NUCLEAR STATION Question: 62 2010 MNS SRO 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 1A & ID SC PORVs using AP-17, Enclosure 7 (Manual Control of PORV5)

The Operator dispatched to perform Enclosure 7 will control the SG PORVs using manual loaders located in the (1) To establish control of the SC 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 100

MCGUIRE NUCLEAR STATION Question: 63 2010 MNS SRO NRC Examination 1 point)

Given the following conditions on Unit 1:

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

A Rx Trip was manually initiated due to the 1A SIG 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 11 lights on 1MC-1 1 are LIT

1VQ-1A (U-i Cont Air Release Inside Isol) 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-1A B. 1. DARK

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

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

2. verify 1VQ-.1A remains OPEN Page 63 of 100

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

Which ONE of the foflowing 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 100

MCGUIRE NUCLEAR STATION Question:

65 2010 MNS SRO 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-O.2 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 reactor vessel 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 100

MCGUIRE NUCLEAR STATION Question: 66 2010 MNS SRO NRC Examination I 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 630°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 100

MCGUIRE NUCLEAR STATION Question: 67 2010 MNS SRO NRC Examination 1 point)

Given the following:

Operators are performing valve lineups on the Unit I 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 100

MCGUIRE NUCLEAR STATION Question: 68 2010 MNS SRO NRC Examination I point)

In accordance with Tech Spec 21.1 (Reactor Core Safety Limits) Bases, the proper functioning of the (1) AND (2) prevent exceeding the Departure from Nucleate Boiling 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 100

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

With Unit I operating at 1 00% 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 100

MCGUIRE NUCLEAR STATION Question: 70 2010 MNS SRO 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 100

MCGUIRE NUCLEAR STATION Question: 71 2010 MNS SRO 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 100

MCGUIRE NUCLEAR STATION Question: 72 2010 MNS SRO 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months C. 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months D. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Page 72 of 100

MCGUIRE NUCLEAR STATION Question: 73 2010 MNS SRO 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 Faulted lB Ruptured 1C Intact J ID Intact 1A lB IC ID Faulted Ruptured Ruptured Intact C. IA lB lC 1D Ruptu red Faulted Ruptured Intact D. 1A lB 1C 1D Ruptured Faulted Intact Intact Page 73 of 100

MCGUIRE NUCLEAR STATION Question: 74 2010 MNS SRO NRC Examination point)

Given the following conditions on Unit 1:

A Site Area Emergency has been declared

A Site Assembly is being conducted in accordance with RPIO/A/5700/O1 I (Conducting a Site Assembly, Site Evacuation, or Containment Evacuation)

In accordance with Enclosure 4.3 (OSM Actions for Site Assembly) the announcement for the Site Assembly shall be repeated (1) until notification that the Site Assembly has been completed and the Site Assembly shall be completed within (2)

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

A. 1. every2ominutes

2. 30 minutes B. 1. every 10 minutes

2. 30 minutes C. 1. every2ominutes

2. 75 minutes D. 1. every 10 minutes

2. 75 minutes Page 74 of 100

MCGUIRE NUCLEAR STATION Question: 75 2010 MNS SRO NRC Examination 1 point)

Given the following indications on Unit 1:

IAD-2 / C8 (P/R OVER POWER STOP ALERT) is in LIT

Tavg is 578°F and stable

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

2. Which ONE (1) of the following is the required action for the above condition per OP/IIA/61 00/0 10 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 100

MCGUIRE NUCLEAR STATION Question: 76 2010 MNS SRO NRC Examination 1 point)

Given the following conditions on Unit 1:

The unit was initially at 100% RTP

#1 Seal Leakoff on IA NC pump indicates 6.5 GPM

AP-08 (Malfunction of NC Pump) Case I (NC Pump Seal or Pump Lower Bearing Malfunction has been implemented

The crew has reached the steps in AP-08 to trip the Reactor and stop the 1A NC pump In accordance with AP-08, Enclosure 2 (NC Pump Post Trip Actions For #1 Seal Failure) must be performed within 3-5 minutes after stopping the 1A NC pump to prevent (1) . The requirement to perform these actions is applicable (2)

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

A. 1. damage to the 1A NC pump #2 & #3 seals

2. only while AP-08 is in effect B. 1. damage to the 1A NC pump #2 & #3 seals

2. even after transition from AP-08 to E-0 C. 1. the VCT from exceeding design temperature limits

2. only while AP-08 is in effect D. 1. the VCT from exceeding design temperature limits

2. even after transition from AP-08 to E-0 Page 76 of 100

MCGUIRE NUCLEAR STATION Question: 77 2010 MNS SRO NRC Examination point)

Given the following conditions on Unit 1:

The unit is in Mode 5

NC system temperature is currently 112°F

lAND Train is in service

A special test procedure is to be run which requires BOTH NI pumps to be run in parallel and aligned to inject into the NC system.

Which ONE (1) of the following describes the requirements per Tech Spec 3.4.12 (LTOP) Bases?

A. Secure two PORVs open with associated block valves open and power removed.

This action protects against brittle fracture due to pressurized thermal shock of the reactor vessel.

B. Secure two PORVs open with associated block valves open and power removed.

This action protects against brittle fracture due to cold overpressure of the reactor vessel.

C. Establish an RCS vent of 2.75 square inches and verify at least ONE Operable PZR PORV.

This action protects against brittle fracture due to pressurized thermal shock of the reactor vessel.

D. Establish an RCS vent of > 2.75 square inches and verify at least ONE Operable PZR PORV.

This action protects against brittle fracture due to cold overpressure of the reactor vessel.

Page 77 of 100

MCGUIRE NUCLEAR STATION Question: 78 2010 MNS SRO NRC Examination 1 point)

Given the following conditions on Unit 1:

The unit is at 12% RTP preparing to roll the main turbine

M1A1276 (Ui CA Temp at Chk Vlv 1CA-37) alarms on the OAC

1 CA-37 (#1 TD CA to SIG D)

Based on the above conditions:

1. In accordance with 0P111N62501002 (Auxiliary Feedwater System), what method would FIRST be used to reduce the temperature at the check valve?

2. How would this action affect the operability of the TD CA Pump?

A. 1. Close 1CA-36 AB (Ui TD CA Pump Disch to 1D S/C Control) and monitor temperature for 15 mm.

2. The U-I TD CA Pump remains OPERABLE.

B. 1. Close 1CA-36AB (Ui TD CA Pump Disch tolD S/G Control) and monitor temperature for 15 mm.

2. The U-I TD CA Pump shall be declared INOPERABLE, C. 1. Close 1CA-38B(U1 TD CA Pump Dischto 1D S/C Isol) and starttheTD CA pump aligned for recirculation to the UST.

2. The U-i TD CA Pump remains OPERABLE.

D. 1. Close 1CA-38B (Ui TD CA Pump Disch to 1D S/C Isol) and start the TD CA pump aligned for recirculation to the UST.

2. The U-I TD CA Pump shall be declared INOPERABLE.

Page 78 of 100

MCGUIRE NUCLEAR STATION Question: 79 2010 MNS SRO NRC Examination 1 point)

Unit I is operating at 1 00% RTP with B train components in service with a normal RN system alignment. I B RN pump amps are swinging.

The following annunciators are in alarm:

B RN Pump Suction Lo Press

B RN Pump Discharge Lo Press Which ONE (1) of the following is the required response to the above conditions based on the implementation of AP-20 (Loss of RN)?

A. Implement Case 1, Loss of Operating RN Train Swap alignment to the Nuclear Service Water Pond and place the lA RN pump in service B. Implement Case 1, Loss of Operating RN Train Place the 1A RN pump in service and remain on Low Level Intake C. Implement Case 2, Loss of Low level or RC Supply Crossover Swap alignment to the Nuclear Service Water Pond and place the 1A RN pump in service D. Implement Case 2, Loss of Low level or RC Supply Crossover Place the lA RN pump in service and remain on Low Level Intake Page 79 of 100

MCGUIRE NUCLEAR STATION Question: 80 2010 MNS SRO NRC Examination point)

With both Units at 100% RTP the following occurs:

Loss of Offsite Power occurred on Unit 1

Both DGs started and loaded as designed

1A DIG subsequently trips on overspeed

At Step 17 of ES 0.1 (Reactor Trip Response), the decision is made to implement AP-07 (Loss of Electrical Power)

Which ONE (1) of the following describes the Time Critical actions directed by the CRS to mitigate this event per AP-07?

A. Complete Enc. 7 (DC Bus Alignment) to realign Battery Charger EVCA to Unit 2 within one hour.

B. Complete Enc. 7 (DC Bus Alignment) to realign Battery EVCA to Battery Charger EVCS within one hour.

C. Complete Generic Enc. 13 (VC and VA System Operation) to restart the Train A VC/YC Chiller within 37.5 minutes.

D. Complete Generic Enc. 13 (VC and VA System Operation) to swap Train A VC/YC Chiller power and water to Unit 2 and restart chiller within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 15 minutes.

Page 80 of 100

MCGUIRE NUCLEAR STATION Question: 81 2010 MNS SRO NRC Examination point)

Given the following conditions on Unit 1:

The unit is currently at 80% RTP with a power increase in progress

Power Range channel N-43 fails due to a faulty power supply

N-43 has been removed from service in accordance with AP-16 (Malfunction of Nuclear Instrumentation)

N-43 will be repaired in approximately 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

1. In accordance with Tech Spec 3.2.4 (QPTR), Quadrant Power Tilt Ratios shall be determined by

2. Quadrant Power Tilt limits prevent exceeding power distribution design limits.

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

A. 1. calculation using the remaining three Power Range channels OR movable incore detectors

2. RADIAL B. 1. using the movable incore detectors ONLY

2. RADIAL C. 1. calculation using the remaining three Power Range channels OR movable incore detectors

2. AXIAL D. 1. using the movable incore detectors ONLY

2. AXIAL Page 81 of 100

MCGUIRE NUCLEAR STATION Question: 82 2010 MNS SRO NRC Examination point)

Given the following conditions on Unit 1:

The unit is operating at 108 AMPS taking critical data

One condenser steam dump fails open

Crew is performing AP-Ol (Steam Leak)

Pressurizer level is stable

NC system temperature is 553°F and decreasing slowly

1. Based on the conditions above, to isolate the steam leak AP-Ol will direct the crew to

2. Isolating the steam leak is one of the design basis considerations for ensuring per Tech Spec 3.4.2, RCS Minimum Temperature for Criticality Basis.

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

A. 1. trip the Reactor and close the MSIVs

2. the reactor remains subcritical in the event of a reactor trip B. 1. take A and B STEAM DUMP INTLK BYP switches to OFF/RESET

2. the reactor remains subcritical in the event of a reactor trip C. 1. trip the Reactor and close the MSIVs

2. proper indication and response of the excore detectors D. 1. take A and B STEAM DUMP INTLK BYP switches to OFF/RESET

2. proper indication and response of the excore detectors Page 82 of 100

MCGUIRE NUCLEAR STATION Question: 83 2010 MNS SRO NRC Examination point)

Given the following conditions on Unit 1:

The unit is initially in MODE 3 with SD Banks withdrawn and NC System at full temperature and pressure

INC-32B (PZR PORV) fails open

AP-1 1 (Pressurizer Pressure Anomalies) has been implemented

The PORV isolation valve for 1 NC-32B will not close

An RO is directed to trip the Reactor and initiate Safety Injection

When attempted, both Reactor Trip breakers will not open In accordance with AP-il, the crew shall wait until the Reactor is tripped (1)

The crew will subsequently transition to (2)

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

A. 1. AND then initiate SI, even if the low pressure SI setpoint is exceeded

2. AP-34 (Shutdown LOCA)

B. 1. AND then initiate SI, even if the low pressure SI setpoint is exceeded

2. E-O (Reactor Trip or Safety Injection)

C. 1. OR the low pressure SI setpoint is reached to initiate SI

2. AP-34 (Shutdown LOCA)

D. 1. Qf the low pressure SI setpoint is reached to initiate SI

2. E-O (Reactor Trip or Safety Injection)

Page 83 of 100

MCGUIRE NUCLEAR STATION Question: 84 2010 MNS SRO NRC Examination 1 point)

Given the following conditions on Unit 1:

The unit is operating at 100% RTP

1C NCP Oil Reservoir Level alarm is received on the OAC

Oil level indication on the OAC is -2.0 inches

IC NC pump motor bearing temperature is 200°F

AP-08 (Malfunction of NC Pump) Case II (NC Pump Motor or Motor Bearing Malfunction) has been implemented Which ONE (1) of the following describes the ACTIONS to be directed by the CRS in accordance with AP-08 and the HIGHEST POWER allowed at which the NCP can be stopped?

A. Trip the Reactor, verify reactor power less than 10%, then stop the 1C NCP.

B. Trip the Reactor, verify reactor power less than 5%, then stop the 1C NCP.

C. Reduce reactor power to < 10% using AP-04 (Rapid Downpower), then stop the 1C NCP.

D. Reduce reactor power to < 5% using AP-04 (Rapid Downpower), then stop the IC NCP.

Page 84 of 100

MCGUIRE NUCLEAR STATION Question: 85 2010 MNS SRO NRC Examination point)

Unit I is operating at 100% RTP when the following alarms are received:

1AD-7 / Ji (NC PUMP SEAL INJ LO FLOW)

1AD-7 / 12 (REGEN HX LETDN HI TEMP)

1AD-7 I G2 (CHARGING LINE ABNORMAL FLOW)

The crew has implemented AP-12 (Loss of Letdown, Charging, or Seal Injection).

1. Based on plant conditions indicated by the alarms above, what actions are directed byAP-12?

2. What actions are directed by AP-1 2 regarding the restoration of letdown during the subsequent recovery?

A. 1. FIRST close the Letdown Orifice Isolations (1 NV-458A, 457A, 35A) and then close 1NV-IA, 2A (NC L/D Isol To Regen Hx).

2. Pressurize the letdown system locally.

B. 1. Close 1NV-IA, 2A (NC LID lsol To Regen Hx) and ensure that the Letdown Orifice Isolations (1NV-458A, 457A, 35A) auto-close.

2. Pressurize the letdown system locally.

C. 1. FIRST close the Letdown Orifice Isolations (1 NV-458A, 457A, 35A) and then close 1NV-1A, 2A (NC LID Isol To Regen Hx).

2. Pressurize the letdown system from the Control Room.

D. 1. Close INV-1A, 2A (NC L/D lsol To Regen Hx) and ensure that the Letdown Orifice Isolations (INV-458A, 457A, 35A) auto-close.

2. Pressurize the letdown system from the Control Room.

Page 85 of 100

MCGU IRE NUCLEAR STATION Question: 86 2010 MNS SRO NRC Examination point)

Given the following conditions on Unit 1:

1A, lB and ID Pressurizer heater group supply breakers open at 1100 on June 1 due to a lightning strike and cannot be reclosed

A reactor startup is in progress with reactor power at 1% RTP

Heater group IC is available Which ONE (1) of the following describes the required actions per Tech Spec 3.4.9, (Pressurizer)?

A. Restore PZR heater group 1A ONLY to operable status.

B. Restore PZR heatergroup 1AAND lB ONLY to operable status.

C. Restore PZR heater group 1AAND 1D ONLY to operable status.

D. Restore PZR heater group IA AND lB OR IA AND 1 D to operable status.

Page 86 of 100

MCGUIRE NUCLEAR STATION Question: 87 2010 MNS SRO NRC Examination point)

Given the following conditions on Unit 1:

NC system is in MODE 3

SIG tube leakage occurs on C S/G

AP-1 0 (NC System Leakage within the Capacity of Both NV Pumps), Case I (SIG Tube Leakage) has been implemented

Charging flow is 240 GPM The maximum charging flow limit specified by AP-lO is based on (1)

The basis for performing a rapid cooldown to a selected target temperature is (2)

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

A. 1. preventing NV pump runout

2. to ensure that there is sufficient NC System subcooling following depressurization B. 1. preventing Regen Hx tube vibration

2. to ensure that there is sufficient NC System subcooling following depressurization C. 1. preventing NV pump runout

2. to ensure NC system temperature is below the saturation temperature for the ruptured SG PORV lift pressure D. 1. preventing Regen Hx tube vibration

2. to ensure NC system temperature is below the saturation temperature for the ruptured SG PORV lift pressure Page 87 of 100

MCGU IRE NUCLEAR STATION Question: 88 2010 MNS SRO NRC Examination point)

Given the following conditions on Unit 1:

The unit was operating at 100% RTP when a total loss of onsite and offsite power occurred

1. In accordance with AP-1 5 (Loss of Vital or Aux Control Power), what is the MINIMUM voltage on the DC Vital busses which requires the Vital Batteries (EVCA, EVCB, EVCC, EVCD) to be removed from service?

2. After power is restored and the battery chargers are placed in service, in accordance with Tech Spec 3.8.4 (DC Sources Operating), what is the MINIMUM voltage required for the Vital Batteries to be OPERABLE while on float charge?

A. 1. liOvolts

2. 125 volts B. 1. lO5volts

2. 125 volts C. 1. liOvolts

2. ilOvolts D. 1. l05volts

2. ilOvolts Page 88 of 100

MCGUIRE NUCLEAR STATION Question: 89 2010 MNS SRO NRC Examination 1 point)

Unit 1 is operating at 100% RTP with t1 B Train equipment in service when the following sequence of events occurs:

The Low Level Intake suction has been lost due to fouling associated with the intake grating

The crew is performing Enclosure 1 of AP-20 (Aligning B Train RN to Pond)

ORN-152 (Train lB & 2B Disch to SNSWP) failed to open and all attempts to move the valve have failed

The following SNSWP level trend is observed on the OAC:

741 739 737 735 733 731 -

SNSWP Level (ft) 729 727 - -

725 -- --

723 721 4:00 5:00 6:00 7:00 8:00 9:00 10:00 11:00 Based on these conditions, the SNSWP level becomes initially INOPERABLE at (1)

The SNSWP minimum level ensures a sufficient volume of water to allow RN system operation for at least (2) following a design basis LOCA.

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

A. 1. 0450

2. 5 Days B. 1. 1040

2. 5 Days C. 1. 0450

2. 30 Days D. 1. 1040

2. 30 Days Page 89 of 100

MCGUIRE NUCLEAR STATION Question: 90 2010 MNS SRO NRC Examination 1 point)

Given the following conditions on Unit 1:

Unit was at 100% RTP when rod M-4 dropped due to a blown fuse

AP-14 (Rod Control Malfunction) has been implemented

1) In accordance with Tech Spec 3.1.4 (Rod Group Alignment Limits), if the rod can NOT be restored to within alignment limits, power must be reduced to less than or equal to within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

2) Per AP-14 power must be reduced to less than a MAXIMUM of to retrieve the dropped rod.

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

A. 1. 95%RTP

2. 75%RTP B. 1. 95%RTP

2. 50%RTP C. 1. 75%RTP

2. 50%RTP D. 1. 75%RTP

2. 75%RTP Page 90 of 100

MCGUIRE NUCLEAR STATION Question: 91 2010 MNS SRO NRC Examination 1 point)

Given the following conditions on Unit 1:

The unit is in MODE 5 following a refueling outage

PTI1IN4200/002 C (Containment Closure / Integrity) is in effect

Both trains of ND are in service

Both ND pumps trip and cannot be restarted

AP-19 (Loss of ND or ND System Leakage) has been implemented Which ONE (1) of the following describes actions required byAP-19 based on the conditions above?

A. Notify the WCC SRO to dispatch Operators to isolate any open penetrations ONLY.

B. Evacuate Containment AND notify the WCC SRO to dispatch Operators to isolate any open penetrations.

C. Notify the Containment Closure Coordinator to initiate Containment closure ONLY.

D. Evacuate Containment AND notify the Containment Closure Coordinator to initiate Containment closure.

Page 91 of 100

MCGUIRE NUCLEAR STATION Question: 92 2010 MNS SRO NRC Examination point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

AP-1 8 (High Coolant Activity) has been entered due to 1 EMF-1 8 (Reactor Coolant Filter 1A) in Trip 2 alarm Isotopic analysis of the NC system indicates the presence of Cobalt and Manganese which indicates that a (1) event has occurred and the required action in accordance with AP-18 to reduce the activity in the NC system is to (2)

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

A. 1. failed fuel

2. place the Cation Bed demineralizer in service B. 1. failed fuel

2. increase letdown flow C. 1. crud burst

2. place the Cation Bed demineralizer in service D. 1. crud burst

2. increase letdown flow Page 92 of 100

MCGUIRE NUCLEAR STATION Question: 93 2010 MNS SRO NRC Examination point)

Given the following conditions on Unit 1:

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

Containment pressure peaked at 2.5 PSIG

ES-i .2 (Post LOCA Cooldown and Depressurization) has been implemented

Both ND pumps are running

NC system pressure is 250 PSIG and decreasing slowly The FIRST FWST level and Containment Sump conditions that require stopping both ND pumps prior to swapping to the containment sump are FWST level (1) AND both CONT SUMP LEVEL GREATER THAN 2.5 FT alarms are (2)

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

A. 1. 200 inches

2. DARK B. 1. 260 inches

2. DARK C. 1. 200 inches

2. LIT D. 1. 260 inches

2. LIT Page 93 of 100

MCGUIRE NUCLEAR STATION Question: 94 2010 MNS SRO NRC Examination i point)

Unit 1 is operating at 100% RTP.

An active licensed STA may assume the duties of the Control Room Supervisor provided the CRS or relief SRO is available to return to the control room within (1) AND the periods during which the STA assumes SRO duties do not exceed (2) in duration.

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

A. 1. 10 minutes

2. 15 minutes B. 1. 15 minutes

2. 10 minutes C. 1. 15 minutes

2. 15 minutes D. 1. 10 minutes

2. 10 minutes Page 94 of 100

MCGUIRE NUCLEAR STATION Question: 95 2010 MNS SRO NRC Examination point)

Given the following conditions on Unit 1:

The unit is in a refueling outage

Fuel movement is in progress

A leak has developed which has caused level to drop in the spent fuel pool

The Spent Fuel Pool Level Low computer alarm has actuated In accordance with AP-40 (Loss of Refueling Canal Level), which ONE (1) of the following describes the FIRST action directed by the CRS to mitigate the current conditions?

A. Place the weir gate in position and inflate the seals.

B. Begin makeup to the pool from the Boric Acid Tank.

C. Move the fuel transfer cart to the reactor side and close 1 KF-122 (Fuel transfer tube block valve).

D. Move the fuel transfer cart to the spent fuel (pit) side and close 1 KF-122 (fuel transfer tube block valve).

Page 95 of 100

MCGUIRE NUCLEAR STATION Question: 96 2010 MNS SRO NRC Examination i point)

Given the following conditions on Unit 1:

. Unit I is operating at 100% RTP The following sequence of events occurs:

DATE TIME EVENT 0800 July10 ISA-49AB (Main Steam Supplyfrom SC 1Bt0TD CA Pump) declared INOPERABLE 0800 July 16 1SA-48ABC (Main Steam Supply from SC 1C to TD CA Pump) declared INOPERABLE 0100 July 17 1SA-49AB (Main Steam Supply from SC lB to TD CA Pump) returnedto OPERABLE status In accordance with Tech Spec 3.7.5 (AFW System), 1SA-48ABC must be returned to OPERABLE status by or the unit must be placed in MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and MODE 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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

REFERENCE PROVIDED A. 0800 on July 17 B. 0800 on July 20 C. 0800 on July 23 D. Ol000nJuly24 Page 96 of 100

MCGUIRE NUCLEAR STATION Question: 97 2010 MNS SRO NRC Examination 1 point)

Given the following conditions on Unit 1:

The unit is in MODE 5 preparing for a unit startup after refueling

You are the Unit 1 Control Room Supervisor

A Temporary Test procedure is being run on the 1 B Boric Acid pump

The OATC points out that several steps in the TT procedure should be concurrent verification steps to be consistent with similar steps in other test procedures In accordance with NSD 703 (Administrative Instructions for Technical Procedures) the change to the Temporary Test Procedure shall be processed as a (1) change.

For any procedure change, a 1 OCFR5O.59 Evaluation is NOT required (2)

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

A. 1. minor

2. for minor changes ONLY B. 1. major

2. for minor changes ONLY C. 1. minor

2. for minor changes OR if the procedure has been excluded from the 1 OCFR5O.59 process D. 1. major

2. for minor changes OR if the procedure has been excluded from the 1 OCFR5O.59 process Page 97 of 100

MCGUIRE NUCLEAR STATION Question: 98 2010 MNS SRO NRC Examination 1 point)

SLC 16.11.20 (Gas Storage Tanks) limits the quantity of radioactivity in each Waste Gas Decay Tank (WGDT).

The basis for this limit assures the amount of radioactivity released would be substantially lower than the dose guideline values of Which One (1) of the following completes the statement above?

A. 10 CFR 20 during routine WGDT releases.

B. 10 CFR 100 during routine WGDT releases.

C. 10 CFR 20 in the event of a WG System leak or failure.

D. 10 CFR 100 in the event of a WG System leak or failure.

Page 98 of 100

MCGUIRE NUCLEAR STATION Question:

99 2010 MNS SRO NRC Examination 1 point)

Given the following plant conditions:

You are tasked to evaluate four available work teams to perform repairs in a 1500 mREM/hr radiation field Which ONE (1) of the following work teams would maintain station radiation dose ALARA?

A. Two qualified male workers can complete the task working together in 15 minutes. Each worker has accumulated 325 mREM for the year.

B. A team consisting of a qualified male and qualified female worker can complete the task working together in 20 minutes. Each worker has accumulated 100 mREM this year.

C. A qualified male worker who has previously performed this task can complete the task in 20 minutes. However, he has exceeded his Alert level for exposure and will require a dose extension.

D. A team consisting of a qualified declared pregnant female worker and a non-qualified male worker who needs to qualify on this task can complete the task working together in 15 minutes. The female has no dose and the male worker has accumulated 200 mREM for the year.

Page 99 of 100

MCGUIRE NUCLEAR STATION Question: 100 2010 MNS SRO NRC Examination 1 point)

Given the following plant conditions:

An Unusual Event was declared on Unit 2.

Initial Notification to the States, Counties and the NRC has been completed.

The Emergency Coordinator has just made the decision to upgrade the classification to an Alert The NRC is required to be notified immediately but no more than (1) after change of classification.

After the initial notification of the change in classification is made to the State and Counties, follow up notifications are required to be made every (2) until the emergency is terminated.

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

A. 1. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

2. hour B. 1. Ihour

2. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C. 1. 15 minutes

2. hour D. 1. 15 minutes

2. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Page 100 of 100

Reference Listfor: 2010 MNS SRO 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 1 & 2 Generator Capability Curves EP/1/N5000/F-O Page 5 of ii Tech Spec 3.7.5 (AFW System)

Printed 7/13/2010 2:36:3 7 PM

MNS GENERIC ENCLOSURES PAGE NO.

EPI1IAI5000IG-1 Enclosure 4- Page 1 of 8 UNIT 1 Placing H2 Recombiners In Service R ev. 25 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

1. Select one train of H 2 Recombiner to be placed in service:

To start IA 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 IA REFERENCE POWER listed on Data Book Curve 1.8 by PRESSURE FACTOR, CP to determine IA Hydrogen Recombiner Power Setting.

1A: x lA REFERENCE POWER PRESSURE FACTOR, CP 1A Power Setting

c. Record lA POWER SETTING

OPI.. ..,6100122 Ui IT 1 ENCLOSURE 4.3 CURVE 1.8 HYDROGEN RECOMBINER POWER CORRECTION FACTOR vs. CONTAINMENT PRESSURE 1

EEE EEEEEE 7 EEEEIE I I LF PRE-LOCACONTAINMENTTEMP.

100°F IN LOWER COMPARTMENT f-- -Flj 16 AND 75°F IN UPPER COMPARTMENT )EZ 15 1.4 P

EEEtEEE LI.

ZE ZZ ZZ ZZ EE -

j REFERENCE POWER IA-35670KW 13 1.2 ZZEZLEZZ.Z 1.

L-2 6 8 POST-LOCA CONTAINMENT PRESSURE, psig UNIT 1

U NIT I Pagelof4 OPII/A161 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2. Conditioned Power Level

a. Operating Category I: 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/1/A161 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 7% power increase in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 10% power increase in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 7% power increase in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 10% power increase in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months UNIT I*

U NIT I Page 3of4 OP/i /A161 00/022 Unit 1 Data Book Section 1.3 Enclosure 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.

Subsequent 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

U nit I OP/i /A/61 00/22 Unit 1 Data Book Section 1.3 Enclosure 4.3 Fuel Maneuvering Limits POWER RAMP RESTRICTIONS IALSTARTUPFOLLOWINGREFUELING NO RESTRICTIONS < 40% FP TDO OR FOLLOWING COLD SHUTDO RECOMMENDED RAMP = 3% / HOUR, 40%FP 100/FP YesMP_ 3% STEP CHANGE, 4% in 1 Hin2 EL ASS EMBLIES HAN DLED No TINGCATEGORY1 100% FP FOR 72 CUMULATIVE ,/CPL=HIGHEST POWER LEVEL SUSTAINED\

FOR AT LEAST 72 CUMULATIVE HOURS HOURS OUT OF ANY 7 DAY No (CONSECUTIVE OR NON-CONSECUTIVE)

OPERATING PERIOD AT POWE ANO DAT /

Y 7 DAY OPERATING Yes INGQATEGQRY2 7 CPL=HIGHEST POWER LEVEL SUSTAINED FOR AT LEAST 72 CUMULATIVE HOURS (CONSECUTIVE OR NON CONSECUTIVE) OUT OF THE G30DRATING J PERIOD AT POWER OMMENDED RAMP = 3% / HOUR Yes 3% STEP CHANGE, 4% in 1 HOUR 7°/ in 2

-f No er-CPL No NO RATE RESTRICTIONS (No STEP INCREASE S HALJ EXCEED 10%,

CPL-100% RTP RECOMMENDED RAMP = 3%/HOUR, CPL -

MAX RAMP 3% STEP CHANGE 4E in 1 HOU R7%I/)

HOURSand1O%in3HOURS No 40%-100% RTP NO RATE RESTRICTIONS UP TO MMENDED RAMP = 3% / HOUR, 40% 100%F

)

40% RTP MAX RAMP = 3% STEP CHANGE, 4% in 1 HOUR, 7% in 2

) HOURS and 10% in 3 HOURS Unit I

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OW 11A161001022 Enclosure 4.3 vr.4rr I Table 3.1.4 IfeGnirc Nuclear Statiou Generator capability Curve ApplicatIon Guid ance 22.8kV Capability Curve (Curve 3.1.1 of Enclosure 4.3) to be used when generator 22.8kV and 24.0 kV. output voltage is between 2 24.0kV Capability Curve (Curve 3.1.2 of Enclos ure 4.3) to be used when generator output higher. voltage is 24.0 kV or NOTE: MVAR. limits provided in Enclos ure 4.3 are based upon Full Power (1200 MWs) power MVAR limits should be obtained operation. At reduced from generator capability curves. Actual MVAR operating generator voltage, H2 pressure, limits are based upon MW output, etc.

3 When enerator MVARS exceed capability curve, refer to AP /1/Al 5500 1005 (Gener Grid Disturbances) ator Voltage and Electric UNIT 1

MNS I I

CRITICAL SAFETY FUNCTiON STATUS TREES I PAGE NOI I

EP/1/A/5000/F-O 5f 11 Core Cooling - Page 1 of 1 Rev.4 UNIT 1 REACTOR VESSEL DIP SETPOINTS FOR DEGRADED CORE COOLING Required PEACTOR VESSEL D/P Number of TRN A TRN B NC Pumps With l NC unip 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%

AFW System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AFW) System LCO 3.7.5 Three AFW trains shall be OPERABLE.

NOTE Only one AFW train, which includes a motor driven pump, is required to be OPERABLE in MODE 4.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS NOTE LCO 3.0.4.b is not applicable when entering MODE 1 CONDITION REQUIRED ACTION COMPLETION TIME A. One steam supply to A.1 Restore steam supply to 7 days turbine driven AFW OPERABLE status.

pump inoperable. AND 10 days from discovery of failure to meet the LCO B. One AFW train B.1 Restore AFW train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable in MODE 1, 2 OPERABLE status.

or 3 for reasons other AND than Condition A.

10 days from discovery of failure to meet the LCO (continued)

McGuire Units 1 and 2 3.7.5-1 Amendment Nos. 221/203

AFW System 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A AND or B not met.

C.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR Two AFW trains inoperable in MODE 1, 2, or 3.

D. Three AFW trains D. 1 NOTE inoperable in MODE 1, LCO 3.0.3 and all other 2, or 3. LCO Required Actions requiring MODE changes are suspended until one AFW train is restored to OPERABLE status.

Initiate action to restore Immediately one AFW train to OPERABLE status.

E. Required AFW train E.1 Initiate action to restore Immediately inoperable in MODE 4. AFW train to OPERABLE status.

McGuire Units 1 and 2 3.7.5-2 Amendment Nos. 184/1 66

AFW System 3.7.5 SURVEILLANCE_REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Not applicable to automatic valves when THERMAL POWER is < 10% RTP.

Verify each AFW manual, power operated, and automatic 31 days valve in each water flow path, and in both steam supply flow paths to the steam turbine driven pump, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.5.2 NOTE Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after 900 psig in the steam generator.

Verify the developed head of each AFW pump at the flow In accordance test point is greater than or equal to the required with the Inservice developed head. Testing Program SR 3.7.5.3 NOTE Not applicable in MODE 4 when steam generator is relied upon for heat removal.

Verify each AFW automatic valve that is not locked, 18 months sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

(continued)

McGuire Units 1 and 2 3.75-3 Amendment Nos. 184/1 66

AFW System 3.7.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.5.4 NOTE

1. Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after 900 psig in the steam generator.

2. Not applicable in MODE 4 when steam generator is relied upon for heat removal.

Verify each AFW pump starts automatically on an actual 18 months or simulated actuation signal.

McGuire Units 1 and 2 3.7.5-4 Amendment Nos. 184/1 66

Examination KEYfor: 2010 MNS SRO 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 2:39:23 PM Page 1 of 4

Examination KEYfor: 2010 MNS SRO 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 2:39:23 PM Page 2 of 4

Examination KEYfor: 2010 MNS SRO 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 2:39:23 PJJ Page 3 of 4

Examination KEYfor: 2010 MNS SRO NRC Examination Question Answer Number 76 B 77 B 78 B 79 C 80 A 81 B 82 D 83 D 84 B 85 C 86 B 87 B 88 B 89 C 90 C 91 D 92 D 93 A 94 A 95 D 96 B 97 C 98 D 99 C 100 A Printed 7/13/2010 2:39:23 PM Page 4 of 4

ML102390061

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