Text

301 as Given SRO Written Exam with References and Answer Key
	ML12275A390
Person / Time
Site:	Mcguire, McGuire
Issue date:	09/28/2012
From:	; NRC/RGN-II
To:	;
References
	50-369/12-301, 50-370/12-301
	Download: ML12275A390 (106)
	v • d • e

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

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

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent 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-Only/Total Examination Values / / Points Applicants Score / / Points Applicants Grade / / Percent

McGuire Nuclear Station Question: I 2012 MNS SRO NRC Examination (1 point)

With Unit I operating at 50% RTP, a Reactor Trip signal will be generated on a Turbine trip provided 2/3 Auto Stop Oil pressures lower below the setpoint, which is (1) PSIG,OR 4/4 (2) are closed.

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

A. 1.45

2. Throttle valves B. 1.75

2. Throttle valves C. 1.45

2. Governor valves D. 1.75

2. Governor valves Page 1 of 100

McGuire Nuclear Station Question:

2 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

An inadvertent Phase A Containment Isolation occurs Based on the conditions above:

NC Pump Seal Water NC Pump RN Return Flow is Flow is A. isolated isolated B. isolated NOT isolated C. NOT isolated isolated D. NOT isolated NOT isolated Page 2 of 100

McGuire Nuclear Station Question:

3 2012 MNS SRO NRC Examination (1 point)

Unit 2 is operating at 100% RTP.

The NC System boron concentration will DECREASE if Letdown temperature is (1) by 10°F.

If LD Hx outlet temperature reaches (2) 2NV-127A (LD Hx Outlet 3-Way Temp Cntrl) will AUTO divert letdown flow to the VCT.

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

A. 1. LOWERED

2. 120°F B. 1. LOWERED

2. 138°F C. 1. RAISED

2. 120°F D. 1. RAISED

2. 138°F Page 3 of 100

McGuire Nuclear Station Question:

4 2012 MNS SRO NRC Examination (1 point)

Unit I was operating at 100% RTP when a LOCA occurred. Given the following events and conditions:

The crew attempted to align IA Train of the ND system to supply Containment Spray

I NS-43A (IA ND Hx Outlet to NS Cont Outside Isol) failed to open Which ONE (I) of the following statements describes the interlock that prevented I NS-43A from opening?

A. 1 NI-I 73A (IA ND to A & B Cold Legs Cont Outside Isol) was not closed.

B. I ND-58A (Train A ND to NV & NI Pumps) was not closed.

C. I NI-I 85A (RB Sump to Train A ND & NS) was not open.

D. CPCS signal was not present.

Page 4 of 100

McGuire Nuclear Station Question:

5 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

A small break LOCA has occurred

Bus 2EMXB-4 is locked out on protective relay actuation

The crew is performing ES-I .2 (Post LOCA Coo Idown and Depressurization)

In accordance with ES-I.2, during the NC system cooldown and depressurization, the Operators will isolate Cold Leg Accumulators (CLAs) (I) and depressurize CLAs (2)

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

A. l.AandC

2. BandD B. I. AandB

2. CandD C. I. BandD

2. AandC D. I.CandD

2. AandB Page 5 of 100

McGuire Nuclear Station Question:

6 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

. Unit is in Mode 5

. Preparations for refueling are in progress

. The crew is preparing to perform a Nitrogen purge of the VCT for an NC system Degas

. There is a bubble in the Pressurizer In accordance with OPIIIN6I 00/SD-I 0 (NC System, PRT and NCDT Degas):

Nitrogen is aligned to the VCT from (I )

The purpose for performing the Nitrogen purge is to (2)

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

A. I. Bulk Nitrogen

2. Remove air and non- condensable gases from the NC System in preparation for taking the plant solid.

B. I. Bulk Nitrogen

2. Remove Dissolved Hydrogen from the NC System to prevent formation of an explosive Hydrogen / Oxygen mixture.

C. I. Shutdown Waste Gas Decay Tank B

2. Remove air and non- condensable gases from the NC System in preparation for taking the plant solid.

D. I. Shutdown Waste Gas Decay Tank B

2. Remove Dissolved Hydrogen from the NC System to prevent formation of an explosive Hydrogen I Oxygen mixture.

Page 6 of 100

McGuire Nuclear Station Question:

7 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

. The unit is at 100% RTP

. B Train components are in service

. The crew implements AP-21 (Loss of KC or KC System Leakage) due to a loss ofthelBl KCpump At 0800 the following temperatures are observed on all NC pumps:

Parameter Temperature Increase Lower Motor Bearings 177°F +1 5°F/mm Upper Motor Bearings 182°F +1 .0°F/mm Pump Lower Radial Bearings 180°F +1 OF/mm Based on the conditions above, and considering that the trend does not change:

The NC pumps (1) Motor bearings will be the FIRST motor bearings to reach an operating limit.

The NC Pumps Lower Radial Bearing temperatures with reach their operating limit at (2)

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

A. 1. Lower

2. 0820 B. 1. Upper

2. 0820 C. 1. Lower

2. 0845 D. 1. Upper

2. 0845 Page 7 of 100

McGuire Nuclear Station Question:

8 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

. The unit is initially operating at I 00% RTP

. A Train components are in service

. The 2B sequencer is in TEST

An SI signal is received on BOTH Unit 2 ESF Trains

1) After load sequencing is complete (with no operator actions), which KC pumps are running?

2) Each train of KC pumps has a recirc valve which discharges to Which ONE (1) of the following completes the statements above?

A. 1. 2Aland2A2KCpumpsONLY

2. the KC Surge tank B. 1. 2Aland2A2KCpumpsONLY

2. its respective trains suction line C. 1. 2A1, 2A2, 2B1 and 2B2 KC pumps

2. the KC Surge tank D. 1. 2A1, 2A2, 2B1 and 2B2 KC pumps

2. its respective trains suction line Page 8 of 100

McGuire Nuclear Station Question:

9 2012 MNS SRO NRC Examination (1 point)

Regarding the design of the Pressurizer:

I ) Why are the Pressurizer Spray lines connected to the NC System cold legs?

2) Why is a constant flow maintained through the PZR spray lines?

A. I To provide a differential pressure between the surge line and the spray lines.

2. Prevents large differential temperature buildup across the spray nozzles.

B. I To provide a differential pressure between the surge line and the spray lines.

2. Reduce the number of valve cycles (open/closed) and resulting fatigue stress concerns on the valve internals.

C. 1. Turbulent flow at the NCP discharge provides better mixing of NC system for a more uniform boron concentration and pH control.

2. Prevents large differential temperature buildup across the spray nozzles.

D. 1. Turbulent flow at the NCP discharge provides better mixing of NC system for a more uniform boron concentration and pH control.

2. Reduce the number of valve cycles (open/closed) and resulting fatigue stress concerns on the valve internals.

Page 9 of 100

McGuire Nuclear Station Question:

10 2012 MNS SRO NRC Examination (1 point)

Unit I is operating at 30% RTP. Given the following events and conditions:

Main Turbine MW Loop is in service

lCNCpumptrips

No operator action has been taken After 15 minutes, with unit load unchanged, total steam flow from all Steam Generators (S/G) will be approximately (I) as compared to total steam flow from all S/Gs prior to the NC pump trip AND Pressure in S/Gs IA, lB and ID will be approximately (2) as compared to the pressure in those S/Gs prior to the NC pump trip.

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

A. 1. lower

2. lower B. 1. the same

2. lower C. I. lower

2. the same D. I. the same

2. the same Page 10 of 100

McGuire Nuclear Station Question:

11 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

Unit is operating at 70% RTP

The OATC determines that AUTO rod withdrawal is not functioning

Further investigation reveals that manual rod withdrawal is functioning normally

Control Bank D rods are currently at 190 steps Which ONE (1) of the following failures has caused this condition?

A. Turbine Impulse Pressure Channel II fails low.

B. Turbine Impulse Pressure Channel I fails low.

C. Loop2 LTChannelfaiIs high.

D. PR Channel N-41 fails high.

Page 11 of 100

McGuire Nuclear Station Question:

12 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

A Reactor Trip and Safety Injection have occurred due to a LOCA inside Containment Based on the following FWST level trend:

TIME 1500 1515 1530 1545 r

L FWS1 LEVEL ri 1 FWST LEVEL

( 1 r FWSI LEVEL CH1 400 400 400

=

300 w

C r E300 11 z

300 N

w C

200 206 200 E200

=

--P?E-tO

_100

_ -PRE1O 100

-PRE-LO I . =

=-1 00 ID Which ONE (1) of the following is the EARLIEST time a signal would be generated to automatically swap the ND pump suction to the Containment Sump?

A. 1500 B. 1515 C. 1530 D. 1545 Page 12 of 100

McGuire Nuclear Station Question:

13 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The unit is operating at 100% RTP

Containment pressure Channel II fails HIGH

The Channel II Containment Pressure High B/S has been TRIPPED

The Channel II Containment Pressure High High B/S has been BYPASSED Which ONE (1) of the following identifies the correct ESF actuation logic for the REMAINING Containment Pressure channels?

A. Safety Injection - 1/2; Phase B 1/3 B. Safety Injection - 1/2; Phase B-2/3 C. Safety Injection 1/3; Phase B 1/3 D. Safety Injection 1/3; Phase B-2/3 Page 13 of 100

McGuire Nuclear Station Question:

14 2012 MNS SRO NRC Examination (1 point)

Given the following initial conditions on Unit 1:

. The unit was operating at 100% RTP

. A leak on the RV system occurs inside Containment

. The crew isolates RVto Containmentto stopthe leak Subsequently, the following occurs:

. A steam break occurs on the I A S/C

Containment pressure peaked at 3.2 PSIG and is currently 1 .5 PSIG

The IA S/C has been isolated in accordance with E-2 (Faulted S/C Isolation)

The crew has transitioned to ES-I .1 (SI Terminaton) and is currently evaluating SI termination criteria The crew (I) have to use adverse Containment value for Subcooling.

The crew (2) have to use adverse Containment value for PZR level.

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

A. I. WILL

2. WILL B. I. WILL NOT

2. WILL C. I. WILL

2. WILL NOT D. I. WILL NOT

2. WILL NOT Page 14 of 100

McGuire Nuclear Station Question:

15 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

. NCS temperature is 205° F

. A plant heatup to normal operating temperature is in progress

. Annunciator IAD-9, A/S (ICE COND LOWER INLET DOORS OPEN) is lit

. A NEO reports that ONE ofthe Ice Condenser Lower Inlet doors is partially 0 pen

. An HVAC maintenance technician is dispatched to inspect the door and has determined that the door will open but cannot be closed

. The Ice Condenser Chart Recorder (1 NPRC-5000) indicates temperature for the affected ice bed is 19°F and slowly increasing

. No other annunciator alarms are present Based on the given conditions:

1) Based on the conditions above, Technical Specification (TS) LCO 3.6.12 (Ice Bed) LCO actions required to be taken.

2) The primary concern with the increasing ice bed temperature is Which ONE (1) of the following completes the statements above?

A. 1. are

2. increased ice bed sublimation B. 1. are NOT

2. increased ice bed sublimation C. 1. are

2. blockage of air flow due to volumetric expansion of the ice beds D. 1. are NOT

2. blockage of air flow due to volumetric expansion of the ice beds Page 15 of 100

McGuire Nuclear Station Question:

16 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

The unit was initially operating at 100% RTP

A LOCA occurs inside Containment

1) To MANUALLY start the Containment Air Return Fans (CARF5) a CPCS signal required.

2) In addition to other signals, an AUTOMATIC start of the CARFs requires a/an Which ONE (1) of the following completes the statements above?

A. 1. is

2. S signal (no associated time delay required)

B. 1. is not

2. time delay after S signal generated C. 1. is

2. time delay after S signal generated D. 1. is not

2. S signal (no associated time delay required)

Page 16 of 100

McGuire Nuclear Station Question:

17 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

A LOCA has occurred inside Containment

ES-I .3 (Transfer to Cold Leg Recirc) has been implemented

Containment pressure is 3.2 PSIG As a MINIMUM, to MANUALLY START the A Train NS Pump:

I) CPCS Train A pressure must be greater than the setpoint value of (I)

AND

2) (2) A Train NS Pump Discharge valve(s) must be OPEN.

Which ONE of the following completes the statements above?

A. 1. 0.80 PSIG

2. ONE B. I. 0.35 PSIG

2. ONE C. I. 0.80 PSIG

2. BOTH D. I. 0.35 PSIG

2. BOTH Page 17 of 100

McGuire Nuclear Station Question:

18 2012 MNS SRO NRC Examination (1 point)

Unit I is in Mode 3 conducting a plant cooldown and depressurization n accordance with OPIIIA/61 OOISD-2 (Cooldown to 400° F).

The following conditions exist:

. NC System pressure I 900 PSIG

. NCSystemtemperature 557°F

All Steam Generator pressures 1100 PSIG

Low Pressure SI and Low Pressure Steamline Isolation have been blocked

The operator has just begun an 80°F/hourcooldown.

Which ONE (1) of the following conditions would automatically close all four Main Steam Isolation Valves?

A. NC Pressure increases to 2000 PSIG.

B. Containment Pressure increases to 1.3 PSIG.

C. IA Steam Generator Pressure drops to 900 PSIG in 2 seconds.

D. 1 B Steam Generator Pressure drops to 700 PSIG over the next 30 minutes.

Page 18 of 100

McGuire Nuclear Station Question: 19 2012 MNS SRO NRC Examination (1 point)

The following conditions exist on Unit 1:

The plant is at 20% RTP

Power increase in progress The CF Control Bypass valves receive a full close demand signal from DCS when steam flow increases to a MINIMUM of (1)

The CF Control Bypass valves receive a full open demand signal from DCS when steam flow increases to a MINIMUM of (2)

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

A. 1. 25%

2. 75%

B. 1. 25%

2. 85%

C. 1. 30%

2. 75%

D. 1. 30%

2. 85%

Page 19 of 100

McGuire Nuclear Station Question:

20 2012 MNS SRO NRC Examination (1 point)

Given the following on Unit 2:

A reactor trip from 100% RTP has occurred

The TD CA pump tripped on overspeed upon starting

Bus 2ETB locked outdueto a ground faulton the bus If no operator action has adjusted CA flow rates, which ONE (1) of the following describes which S/Gs are currently being fed and the associated flow rates?

A. C and D S/Gs at 450 GPM to each S/G B. C and D S/Gs at 450 GPM total flow C. A and B S/Gs at 450 GPM to each S/G D. A and B S/Gs at 450 GPM total flow Page 20 of 100

McGuire Nuclear Station Question:

21 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

. The unitisatlOO% RTP

. B train equipment is in service

. I ETA Normal incoming breaker trips OPEN

. IA DIG starts and comes up to speed and voltage, but its output breaker does NOT close

An NEO reports that an 86N Relay is on Bus IETA lAW AP-07 (Loss of Electrical Power) Case II, Thermal Barrier Isolation Valves on (1) must be Ensured OPEN.

Based on the conditions above, if the BOP operator attempts to manually close the IA D/G Output Breaker, the breaker (2) close.

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

A. 1. Train B ONLY

2. WILL B. 1. Train BONLY

2. WILL NOT C. I. Train A and Train B

2. WILL D. 1. Train A and Train B

2. WILL NOT Page 21 of 100

McGuire Nuclear Station Question:

22 2012 MNS SRO NRC Examination (1 point)

Given the following initial conditions on Unit 1:

The unit is at 100% RTP

All NCPs are powered from their normal sources.

Each 6.9 KV bus Mode Select switch is in Auto.

Subsequently the following occurs:

A Generator Switchyard protective lockout occurs on I B Bus Line Based on the given conditions:

1) NCPIB

2) Bus ITB automatically to its alternate power supply.

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

A. 1. trips

2. fast B. 1. trips

2. slow C. 1. continues to run

2. fast D. 1. continuesto run

2. slow Page 22 of 100

McGuire Nuclear Station Question:

23 2012 MNS SRO NRC Examination (1 point)

Given the following plant conditions:

Both Units are operating at 100% RTP

Battery I DP is aligned for equalizing charge

The DC Output breaker for Charger I DS has tripped open Based on the conditions above, with no operator action, Bus I DP is Which ONE (1) of the following completes the statement above?

A. energized from Charger I DP and Battery I DP B. energized from Chargers IDP and 2DP C. energized from Charger IDP ONLY D. de-energized Page 23 of 100

McGuire Nuclear Station Question:

24 2012 MNS SRO NRC Examination (1 point)

Given the following condWons on Unit I:

The IA DIG has been placed in operation to facilitate a power swap on IETA from IATC to SATA

Indicated load is 400 KW and 75 KVARS

IA DG is currently powering I ETA with the I ETA Normal Breaker and I ETA Stdby Breaker OPEN When the IA D/G Gov Cntrl Raise pushbutton is depressed, frequency will (1)

When the IA DIG Volt Adjust is rotated to Raise, indicated KVARs will (2)

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

A. 1. Increase

2. Remain the same B. 1. Remain the same

2. Remain the same C. I. Increase

2. Increase D. I. Remain thesame

2. Increase Page 24 of 100

McGuire Nuclear Station Question:

25 2012 MNS SRO NRC Examination (1 point)

While performing daily surveillance checks on I EMF-33 (CondenserAir Ejector Exhaust), it is determined that the OPERATE light is OFF.

Which ONE (I) of the following actions is required in accordance with PT/I /A/4600/003 B (Daily Surveillance Items)?

A. Perform a source check of I EMF-33.

B. Verify operability of I EMF-36L (Unit Vent Gas Monitor) by checking OPERATE light lit and LOSS OF SAMPLE FLOW annunciator NOT in alarm.

C. Depress CLR (Clear) on the I EMF-33 touch controls.

D. Place the sample Pump in OFF, and then depress the RUN pushbutton for a MINIMUM of 5 seconds.

Page 25 of 100

McGuire Nuclear Station Question:

26 2012 MNS SRO NRC Examination (1 point)

Given the following conditions:

Unit 2 is at 100% RTP

A Loss of Offsite Power occurs on both Units I and 2 Based on the given conditions, if no operator actions occur, which ONE (1) of the following provides the assured source of cooling water to the Unit 2 Containment AHUs?

A. BOTH 2A AND 2B RN pumps B. RV pump selected in Auto C. 2A RN pump ONLY D. 2B RN pump ONLY Page 26 of 100

McGuire Nuclear Station Question: 27 2012 MNS SRO NRC Examination (1 point)

Given the following plant conditions:

Both units are operating at 100% RTP

An instrument air system leak develops in the Unit I Turbine Building

The Diesel VI Compressors (G & H) AUTO/OFF-RESET selector switches are in AUTO.

The following indications are observed in the Control Room:

I vi Based on the indications above, the Diesel VI Compressors (G & H) are (1)

AND lVl-1 812 (VI Air Dryer Bypass Filter Isol) is (2)

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

A. 1. NOTrunning

2. closed B. 1. running

2. closed C. 1. NOTrunning

2. open D. 1. running

2. open Page 27 of 100

McGuire Nuclear Station Question:

28 2012 MNS SRO NRC Examination (1 point)

Given the following conditions:

Fuel reload is in progress on Unit I

IEMF-16 (Containment Refueling Bridge) display goes dark due to a loss of Bus KRA Which ONE (1) of the following describes the procedure required to be implemented AND the effect of IEMF-16 on the Containment Evacuation alarm?

Procedure Containment Evacuation Alarm A. AP-07 (Loss of Electrical Power) Defeated B. AP-07 (Loss of Electrical Power) Actuated C. AP-I 5 (Loss of Vital or Aux Control Power) Defeated D. AP-I 5 (Loss of Vital or Aux Control Power) Actuated Page 28 of 100

McGuire Nuclear Station Question:

29 2012 MNS SRO NRC Examination (1 point)

A reactor start-up is in progress on Unit 2

. Reactor power is 2%

. The OATC is withdrawing control rods

. Another RO is monitoring/controlling SG level, steam dumps, and feedwater flow Based on the conditions above:

I To control NCS temperature, OP/2/A161 00/003 (Controlling Procedure for Unit Operation) Enclosure 4.1 (Power Increase) directs the operators to maintain within the desired range by adjusting steam dump control.

2. If the steam dump controller setpoint is not changed, with each rod pull SG pressure increases Which ONE (1) of the following completes the statements above?

A. 1. Tcold

2. initially, then returns to approximately the original value before the rod pull B. 1. Tave

2. initially, then returns to approximately the original value before the rod pull C. 1. Tcold

2. and stabilizes at a higher steam pressure than before the rod pull D. 1. Tave

2. and stabilizes ata highersteam pressure than before the rod pull Page 29 of 100

McGuire Nuclear Station Question:

30 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

. The unit is currently at 100% RTP, with pressurizer pressure control and level control in auto.

NC system pressure is decreasing slowly due to a leaking Pressurizer Code Safety valve (2NC-2)

At 1500, PRT pressure is INITIALLY at 3 PSIG and increasing at I PSIG I mm Over the next 30 minutes, if the reactor does NOT trip, the temperature indication on 2NCP-5960 (PZR Relief Valve Temperature 2NC-2) will (1) AND the rate of NC system depressurization will (2)

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

A. 1. increase

2. decrease B. 1. remain the same

2. remain the same C. 1. increase

2. remain the same D. 1. remain the same

2. decrease Page 30 of 100

McGuire Nuclear Station Question:

31 2012 MNS SRO NRC Examination (1 point)

Given the following conditions:

. Unit I is responding to a LOCA

. All sources of feedwater have been lost, SIG NR levels are I 7% and decreasing

. NC pumps are secured

. FR-C.1 (Response to Inadequate Core Cooling) has been implemented

. NI and NV pumps are unavailable

. Peak Containment pressure reached 2.5 PSIG

. S/G depressurization has failed to restore adequate core cooling

. Core Exit Thermocouples are currently indicating 12 10°F

. NC pump support requirements can NOT be met

. The ICCM Subcooling Margin Monitors (5MM) indicate:

0 Train A (-)25°F 0 Train B (-)35°F The reason for the difference in subcooling indication is that Train A Wide Range Loop pressureinputhasfailed (1)

Based on the conditions above, the NEXT major action required by FR-C.1 is to (2)

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

A. 1. LOW

2. restart NC pumps one ata time until CETs are less than 1200°F B. 1. HIGH

2. restart NC pumps one ata time until CETs are less than 1200°F C. 1. LOW

2. open all PZR PORVs and head vents to depressurize the NC system D. 1. HIGH

2. open all PZR PORVs and head vents to depressurize the NC system Page 31 of 100

McGuire Nuclear Station Question:

32 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

A LOCA has occurred inside Containment

During the recovery Containment is vented to the annulus and an Annulus Ventilation (VE) fan is to be started for Iodine removal

When the BOP attempts to start the IA yE Fan, it will not start To which ONE (1) of the following locations should a NEO be dispatched to inspect the feeder breaker for the IA VE Fan?

A. IMXJ B. IMXK C. IEMXC D. IEMXD Page 32 of 100

McGuire Nuclear Station Question:

33 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

. A LOCA has occurred inside Containment

. Containment pressure peaked at 3.2 PSIG

Containment pressure is currently 2.8 PSIG and LOWERING slowly

Ann ulus pressure is -4.0 WG and LOWERING (more negative)

Based on the given conditions above:

1) What is the current discharge flowpath of the VE (Annulus Ventilation) fans?

2) If annulus pressure continues to lower with no operator actions, at what pressure setpoint will a signal be generated to change the discharge flowpath of the VE fans?

Which ONE (1) of the following answers the questions above?

A. 1. UnitVent

2. -4.2WG B. 1. Annulus

2. -7.0WG C. 1. UnitVent

2. -7.0WG D. 1. Annulus

2. -4.2WG Page 33 of 100

McGuire Nuclear Station Question:

34 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

. The core has been off-loaded to the Spent Fuel Pool

. 2A KF Pump is running

. 2BKFPumpisoff

. A Loss of Off-Site Power occurs

2A and 2B D/Gs start and load normally

30 minutes after the loss of power, a Spent Fuel Pool Hi Temperature alarm is received Which ONE (1) of the following is the cause of this condition?

A. The 2A or 2B KF pump was not manually started (Sequencer reset required).

B. The 2A or 2B KF pump was not manually started (Sequencer reset NOT req uired).

C. The 2A KF pump ONLY did not automatically load on the Blackout sequence as designed.

D. The 2A and 2B KF pumps did not automatically load during the Blackout sequence as designed.

Page 34 of 100

McGuire Nuclear Station Question:

35 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

. The unit is currently in MODE 5

. Spent Fuel Pool fuel handling operations were secured 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago

. VF system is operating normally in accordance with OP/2/A/6450/004 (Fuel Pool Ventilation System)

Subsequently:

2EMF-42 (Fuel Building Ventilation Radiation Monitor) is in Trip 2 Based on the given conditions, which ONE (1) of the following describes the AUTOMATIC response of the Fuel Handling Building Ventilation system (VF) to the 2EMF-42 condition?

A. The Outside Air damper (D-1) will close.

B. The Exhaust Filter Bypass damper (D-5) will close.

C. The Supply fan AND Exhaust fans will stop.

D. The Supply fan will stop. The Exhaust fans will NOT stop.

Page 35 of 100

McGuire Nuclear Station Question: 36 2012 MNS SRO NRC Examination (1 point)

Given the following indications/conditions on Unit 1:

The unit is operating at 100% RTP

A loss of I EKVA occurs

NO Operator actions have been taken Based on the conditions above, what is the MINIMUM number of ADDITIONAL channels on S/G IA that must trip to cause a/an:

1) Feedwater Isolation Actuation?

2) Auxiliary Feedwater Actuation?

Feedwater Isolation Aux Feedwater Actuation A. 2 2 B. 2 I C. I 2 D. I I Page 36 of 100

McGuire Nuclear Station Question:

U 37 2012 MNS SRO NRC Examination (1 point)

Given the following condiUons on Unit 1:

. Unit shutdown in progress

. Power = 80% RTP and DECREASING

. lASGTube Leak=2OGPM

. Due to high activity, the Turbine Building Sump (TBS) is being pumped to the RC Discharge Based on the given plant conditions:

1. Which ONE (1) of the following would present a more significant radiation hazard to a member of the public at the site boundary due to the release?

2. What EMF Trip 2 automatic action(s) would ensure the release of radioactive material is ALARA?

A. I. Beta radiation from the decay of Tritium

2. TBS pump trips B. I. Beta radiation from the decay of Tritium

2. IWP-35 (WMT & VU CDT to RC Cntrl) closes C. I. Gamma radiation from the decay of Nitrogen-I 6

2. TBS pump trips D. i* Gamma radiation from the decay of Nitrogen-I 6

2. IWP-35 (WMT & VU CDT to RC Cntrl) closes Page 37 of 100

McGuire Nuclear Station Question:

38 2012 MNS SRO NRC Examination (1 point)

Given the following:

. The Instrument Air (VI) system is in a normal alignment and cross-connected to the Station Air (VS) system

. A leak occurs on the Instrument Air (VI) header

The VI header begins to slowly depressurize

The crew has implemented AP-22 (Loss of VI)

As the VI header depressurizes, the VI header will be isolated from the VS header by (1)

The VS air compressor (2) to maintain VS header pressure.

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

A. a manual isolation valve will start automatically B. a manual isolation valve must be manually started C. an automatic isolation valve will start automatically D. an automatic isolation valve must be manually started Page 38 of 100

McGuire Nuclear Station Question:

39 2012 MNS SRO NRC Examination (1 point)

A Reactor trip has occurred on Unit I.

In accordance with the Immediate Actions of E-O (Reactor Trip or Safety Injection):

One indication listed in the procedure that is used to verify thatthe reactor is tripped is (1)

If the turbine does not trip automatically and will not trip manually, the procedure willNEXTdirecttheoperatorto (2)

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

A. 1. IR SUR ZERO OR NEGATIVE

2. close the MSIVs AND MSIV bypasses B. 1. IRAMPS-GOINGDOWN

2. close the MSIVs AND MSIV bypasses C. 1. IR SUR ZERO OR NEGATIVE

2. place the turbine in MANUAL AND close the governor valves in fast action D. 1. IRAMPS-GOING DOWN

2. place the turbine in MANUAL AND close the governor valves in fast action Page 39 of 100

McGuire Nuclear Station Question:

40 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

The unit is operating at 100% RTP

One PZR PORV is leaking past its seat

Pressurizer pressure is 2235 PSIG

Pressurizer Steam Space temperature is 653° F

PRT pressure is 15 PSIG Which ONE (1) of the following is the approximate expected temperature downstream of the leaking PZR PORV?

REFERENCE PROVIDED A. 220°F B. 240°F o 250°F D. 300°F Page 40 of 100

McGuire Nuclear Station Question:

41 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

. The operating crew initiated a manual SI due to a small break LOCA.

Equipment failures resulted in a RED condition on the Integrity CSF Status Tree.

NC Cooldown rate was approximately 220°F per hour

NC System temperature is currently 240°F

The crew is performing a soak in accordance with FR-P.1 (Response to Imminent Pressurized Thermal Shock Condition).

Based on the conditions given, which ONE (1) of the following actions is permitted by FR-P.1 during the soak?

A. Energize PZR heaters B. Start an additional NV Pump C. Place Auxiliary Spray in service D. Initiate a cooldown at less than 50°F per hour Page 41 of 100

McGuire Nuclear Station Question: 42 2012 MNS SRO NRC Examination (1 point)

Unit I was operating at 100% RTP when a Large-Break LOCA occurred.

1) What is the MINIMUM time following the LOCA that E-1 (Loss of Reactor or Secondary Coolant) directs an initiation of hot leg recirculation?

2) Which ECCS pumps are CAPABLE of being aligned to inject into the hot legs per ES-1.4 (Transfer to Hot Leg Recirculation)?

A. 1. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

2. NI ONLY B. 1. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

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

2. NDandNI D. 1. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

2. NI ONLY Page 42 of 100

McGuire Nuclear Station Question:

43 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

A load rejection from 100% RTP has occurred due to the trip of 2A CF pump

Pressurizer level is greater than setpoint

2NV-238 (Charging Line Flow Control) is in AUTOMATIC and CLOSING

Annunciator 2AD-7, J/1 (NC PUMP SEAL INJ LO FLOW) is LIT The setpoint forAnnunciator2AD-7, J/l is (1) GPM.

To clearthe Annunciator, the BOP must throttle 2NV-241 (Seal Injection Flow Control) in the (2) direction.

Which ONE of the following completes the statements above?

A. 1.6

2. OPEN B. 1.6

2. CLOSED C. 1.7

2. OPEN D. 1.7

2. CLOSED Page 43 of 100

McGuire Nuclear Station Question:

44 2012 MNS SRO NRC Examination (1 point)

Unit I was operating at I 00%. Given the following events and conditions:

. 021 0 reactor tripped due to a LOCA

. 0300 crew enters ECA-1.2, (LOCA Outside Containment)

. 0320 crew enters ECA-1 I (Loss of Emergency Coolant Recirc)

. 0330 The crew is atstep 18.b of ECA-1 .1

. Current conditions:

0 IA NI pump is running, indicating 185 GPM 0 lB NI pump is running, indicating 165 GPM o Both NV pumps are running, indicating 340 GPM (Consider that the NV pumps have equal capacity) o Subcooling is +35° F Based on the conditions above, at time 0330:

1) Which ONE (I) of the following describes the actions that will meet JJ, requirements of ECA-I.I?

AND

2) Flow from the remaining ECCS pumpswill be greaterthan the MINIMUM required flow rate of________

REFERENCE PROVIDED A. I. StopbothNVpumps.

2. 345 GPM B. I Stop the I B NI pump AND one NV pump.

2. 345 GPM C. I. Stop the IA NI pump AND one NV pump.

2. 330 GPM D. I. Stopboth NI pumps.

2. 330 GPM Page 44 of 100

McGuire Nuclear Station Question:

45 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

. The unit is in HOT SHUTDOWN on ND Cooling (Both Train A and B)

. B Train KC is aligned to supply Reactor and Aux Bldg Non-Essential Headers with both IBI and 1B2 pumps in operation

A Train KC is aligned to supply the A ND HX Header with both IAI and 1A2 pumps in operation

The IAI KC pump has just tripped In accordance with the Limits and Precautions of OPIIIA/6400/005 (Component Cooling Water System), KC flow through the IA ND Heat Exchanger shall be throttled to less than a MAXIMUM of Which ONE (I) of the following completes the statement above?

A. 2000 GPM B. 4000 GPM C. 5000 GPM D. 6000 GPM Page 45 of 100

McGuire Nuclear Station Question:

46 2012 MNS SRO NRC Examination (1 point)

Given the foIIowng conditions on Unit 2:

. A failure ofthe Pressurizer Pressure Master Controller occurs

. All Pressurizer heaters energize due to the failure

NC system pressure is currently 2310 PSIG

All Pressurizer Pressure control components are in AUTO Based on the given conditions, if NO operator actions are taken, which ONE (1) of the following is the effect on the PZR Surge Line temperature AND the position of the Pressurizer Spray valves, as compared to the conditions before the Pressurizer Pressure Master Controller failure?

PZR Surge Line Temperature PZR Spray Valve Position A. INCREASED CLOSED B. DECREASED CLOSED C. INCREASED OPEN D. DECREASED OPEN Page 46 of 100

McGuire Nuclear Station Question:

47 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

. An ATWS has occurred

. FR-S. I (Response to Nuclear Power Generation I ATWS) has been rn pleme nted

1) When the turbine is tripped, the amount of negative reactivity added will be greater ifthe unit is at

2) The basis for immediately tripping the turbine during an ATWS event is to Which ONE (1) of the following completes the statements above?

A. 1. EOLascomparedtoBOL

2. generate a redundant reactor trip signal B. 1. BOLascomparedtoEOL

2. generate a redundant reactor trip signal C. 1. EOLascomparedtoBOL

2. maintain SIG inventory if the initiating event is a simultaneous loss of all fee dwate r D. 1. BOLascomparedtoEOL

2. maintain SIG inventory if the initiating event is a simultaneous loss of all fee dwate r Page 47 of 100

McGuire Nuclear Station Question:

48 2012 MNS SRO NRC Examination (1 point)

Given the following initial conditions on Unit 2:

. A SGTR has occurred on the 2D SG

. A Steam Line break occurred on the 2B SG

Containment pressure peaked at 3.1 PSIG Current conditions:

Containment pressure is 0.9 PSIG and STABLE Based on the current conditions, E3 (Steam Generator Tube Rupture) requires that 2D SG NR level be maintained greater than a MINIMUM of (1)

AND E-3 will require the crew to FIRST attempt to depressunze the NC system using (2)

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

A. 1. 11%

2. one PZR PORV B. 1. 32%

2. one PZR PORV C. 1. 11%

2. Auxiliary Spray D. 1. 32%

2. Auxiliary Spray Page 48 of 100

McGuire Nuclear Station Question:

49 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The unit was initially at 100% RTP

A steam line break occurs inside Containment

Containment pressure is currently 3.5 PSIG Based on the conditions above, with no operator action:

Both CF Pumpsare (1)

AND The CF to CA Nozzle Valves are (2)

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

A. 1. tripped

2. CLOSED B. 1. tripped

2. OPEN C. 1. running at 2800 RPM

2. CLOSED D. 1. running at 2800 RPM

2. OPEN Page 49 of 100

McGuire Nuclear Station Question:

50 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

UnitisatlOO%RTP Regarding the operation of the CA system:

1) ONLY the Motor-D nven CA pump(s) will sta ft if a occurs.

2) The CA system is capable of supplying sufficient flow to maintain S/G inventory provided reactor power is less than a MAXIMUM of Which ONE (1) of the following completes the statements above?

A. 1. Blackout signal on I ETA and/or I ETB

2. 3%

B. I. Tripofboth CF pumps

2. 3%

C. I. Blackoutsignalon IETAand/orIETB

2. 5%

D. I. Trip of both CF pumps

2. 5%

Page 50 of 100

McGuire Nuclear Station Question:

51 2012 MNS SRO NRC Examination (1 point)

Given the following conditions:

. A Loss ofAIIAC power has occurred on Unit I

. Crew has implemented ECA-O.O (Loss ofAll AC Power)

. The Unit I Standby Make Up pump has failed

. Subcooling Margin Monitor indicates subcooling is 5°F In accordance with ECA-O.O:

I) What is the reason for depressurizing the S/Gs to 290 PSIG?

2) What is the reason for NOT allowing S/Gs to depressurize to less than 190 PSIG?

A. I . Reduce NC system pressure to initiate Cold Leg Accumulator injection to restore subcooling

2. Prevent excessive thermal shock of Reactor Vessel cold leg nozzles B. I . Reduce NC system temperature and pressure to reduce NC pump seal leakage and minimize NC system inventory loss

2. Prevent excessive thermal shock of Reactor Vessel cold leg nozzles C. I. Reduce NC system pressure to initiate Cold Leg Accumulator injection to restore subcooling

2. Prevent nitrogen from the Cold Leg Accumulators from injecting into the NC system D. 1. Reduce NC system temperature and pressure to reduce NC pump seal leakage and minimize NC system inventory loss

2. Prevent nitrogen from the Cold Leg Accumulators from injecting into the NC system Page 51 of 100

McGuire Nuclear Station Question:

52 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

. A Loss of Offsite Power has occurred

During the recovery, it is determined that a natural circulation cooldown needs to be performed Which ONE (1) of the following indicates that natural circulation is occurring per Generic Enclosure 33 (Natural Circulation Parameters)?

NC System Cold Leg NC System Hot Leg Temperatures: Temperatures:

A. Going DOWN At saturation temperature for SIG pressure B. At saturation temperature for Going DOWN S/G pressure C. Going DOWN Going DOWN D. At saturation temperature for At saturation temperature for S/G pressure SIG pressure Page 52 of 100

McGuire Nuclear Station Question: 53 2012 MNS SRO NRC Examination (1 point)

A sustained loss of power to Vital AC Panelboard will require that operators manually transfer NV Pump suction from the VCT to the FWST per AP-1 5 (Loss of Vital or Aux Control Power).

Which ONE of the following completes the statement above?

A. IEKVA B. IEKVB C. IEKVC D. IEKVD Page 53 of 100

McGuire Nuclear Station Question:

54 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The I B DG is running due to an inadvertent Blackout signal during testing

IRN-171B (B DG HX Supply Isolation Valve) did NOT open

1) Based on the conditions above, if the Lube Oil High Temperature trip setpoint is reached, will the DG trip?

2) What is the DG Lube Oil High Temperature trip setpoint?

A. 1. Yes

2. 190°F B. I.No

2. 190°F C. 1. Yes

2. 200°F D. 1.No

2. 200°F Page 54 of 100

McGuire Nuclear Station Question:

55 2012 MNS SRO NRC Examination (1 point)

Unit I was initially at 100% RTP:

. A Safety Injection has occurred due to a LOCA on IA Train of ND

. ECA-1 .2 (LOCA Outside Containment) has been implemented The overall mitigating strategy of ECA-1 .2 includes:

Cooldown the NCS (1 ) and then depressurize the NCS to allow the (2)

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

A. I while maintaining a cooldown rate in NC Tcolds less than 100°F/hr

2. Cold Leg Accumulators to inject B. 1. at maximum rate while attempting to avoid a Main Steam Isolation

2. Cold Leg Accumulators to inject C. 1. while maintaining a cooldown rate in NC Tcolds less than 100°F/hr

2. ND isolation valves (INI-l73Aand INI-178B)to close D. 1. at maximum rate while attempting to avoid a Main Steam Isolation

2. ND isolation valves (INI-173A and INI-178B) to close Page 55 of 100

McGuire Nuclear Station Question:

56 2012 MNS SRO NRC Examination (1 point)

Unit 1 has tripped from 100% RTP with the following conditions:

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

All attempts to restore CA flow have been unsuccessful Which ONE (1) of the following identifies the next source of feedwater that FR-H.1 will prioritize for restoration AND when attempts to restore feedwater will be terminated?

A. Condensate (CM); AND When Feed and Bleed has been established.

B. Condensate (CM); AND When a Secondary Heat Sink is restored.

C. Main Feedwater (CF); AND When Feed and Bleed has been established.

D. Main Feedwater(CF); AND When a Secondary Heat Sink is restored.

Page 56 of 100

McGuire Nuclear Station Question:

57 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

. The Reactor is shutdown

. Tave is 556°F and STABLE

. OATC is moving Shutdown Ban k A rods for testing Current Conditions:

. Shutdown rod B4 drops halfway into the core

. The OATC immediately stops moving rods

. DRPI for rod B4 reads 30 steps

. DRPI and Group Step Counters for all other rods in Shutdown Bank A read 66 steps

Except for Shutdown Bank A, all other rod bottom lights are LIT Based on the current conditions, Technical Specification (TS) 3.1 .4 (Rod Group Alignment Limits) LCO actions (I) required to be taken.

OP/I /A/61001003 (Controlling Procedure for Unit Operation) states that MODE 2 may be declared when (2) Banks are initially withdrawn from the fully inserted position.

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

A. I.ARENOT

2. Control B. I. ARE NOT

2. Shutdown C. I. ARE

2. Control D. I. ARE

2. Shutdown Page 57 of 100

McGuire Nuclear Station Question:

58 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

. Afterwithdrawing Control Bank D, the RO identifies that Control Rod M-4 (Control Bank D, Group 2) indicates 92 steps on DRPI

Bank D Group Step Counters indicate 100 steps on both banks

l&E has determined that Control Rod M-4 stopped moving due to a failed Lift Coil Disconnect switch

The failed switch has been replaced and the Operating crew is ready to realign Control Rod M-4

As Control Rod M-4 begins to move, annunciator IAD-2, All 0 (Rod Control Urgent Failure) alarms The cause of this alarm is an Urgent Failure in Power Cabinet Which ONE (1) of the following completes the statement above?

A. IAC B. 2AC C. IBD D. 2BD Page 58 of 100

McGuire Nuclear Station Question:

59 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

An ATVVS has occurred on the unit

FR-S.1 (Response to Nuclear Power Generation I ATWS) has been implemented

Emergency Boration has been initiated FR-S. I requires the operator to:

1) verify a MINIMUM Emergency Boration flow of________

AND

2) check that charging flow Which ONE (1) of the following completes the statements above?

A. 1. 2OGPM

2. isgreaterthan boration flow B. 1. 3OGPM

2. isgreaterthan boration flow C. I. 2OGPM

2. does not exceed VCT makeup capability D. I. 3OGPM

2. does not exceed VCT makeup capability Page 59 of 100

McGuire Nuclear Station Question:

60 2012 MNS SRO NRC Examination (1 point)

Unit I is operating at 97% RTP when a Reactor Trip occurs.

Given the following conditions:

Channel Flux Level SUR SRN3I OCPS ODPM SRN32 OCPS 0DPM 1RN35 AMPS 10 1.IxIO -1/3DPM IR N36 11 AMPS 9.5x10 -1/3 DPM PRN41 12%

PR N42 0%

PR N43 0%

PR N44 0%

Which ONE (1) of the following statements descnbes 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-10 (Nuclear at Power) status light is DARK.

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

Page 60 of 100

McGuire Nuclear Station Question:

61 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

A Reactor startup is in progress

Based on the following indications, the startup has been placed on hold:

o N-31 indicates 3.1x10 cps 4

o N-32 indicates 4 cps 3.0x10 o N-35 indicates 9 amps 1.5x10 o N-36 indicates ° amps 1

1.OxlcY

Rods are in manual with no rod motion

SR and IR NIs are slowly increasing

Tave is holding steady Which ONE of the following is the reason for placing the startup on hold?

A. N-35 compensating voltage is set too high B. N-35 compensating voltage is set too low C. N-36 compensating voltage is set too high D. N-36 compensating voltage is set too low Page 61 of 100

McGuire Nuclear Station Question:

62 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

. EPI2IAI5000IFR-C.2 (Response to Degraded Core Cooling) is in progress

. Reactor coolant pumps (NCP) 2A and 2C are in service

. Reactor vessel dynamic DIP is decreasing and is 3% less than required

. The crew has just completed depressurizing the S/Gs to 190 PSIG What is the mitigation strategy in accordance with EPI2IAI5000IFR-C.2?

A. Shutdown all NCPs. Depressurize the NC system by depressurizing the steam generators to atmospheric pressure.

B. Shutdown all NCPs. Do not depressurize the steam generators further.

C. Continue to run both NCPs. Depressurize the NC system by depressurizing the steam generators to atmospheric pressure.

D. Continue to run both NCPs. Do not depressurize the steam generators further.

Page 62 of 100

McGuire Nuclear Station Question:

63 2012 MNS SRO NRC Examination (1 point)

Given the following on Unit 1:

. The Fire Detection system computer indicates a fire in Zone 70 (AB 716 Unit I M/D CA Pump Room)

. An Operator dispatched to the area reports that there is smoke and some cables with glowing embers but, NO visible flames I) In accordance with AP-45 (Plant Fire) and the conditions above, this classified as an ACTIVE fire.

2) In accordance with RP-25 (Fire Brigade Response), in addition to making an announcement on the Fire Brigade Radio AND activating the Fire Brigade Pagers, a Plant PA announcement required when dispatching the Fire Brigade.

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

A. I.is

2. is B. I. is

2. is NOT C. I. is NOT

2. is D. I. is NOT

2. is NOT Page 63 of 100

McGuire Nuclear Station Question:

64 2012 MNS SRO NRC Examination (1 point)

Given the following sequence of events on Unit I:

Time = 1000 Unit I was operating at 100% RTP Time = 1001 A technician setting up poles for temporary lighting in the Control Room inadvertently actuates Train B of Containment Isolation PhaseA Time = 1002 An automatic Reactor trip occurs when the A MSIV spuriously closes Time = 1003 Unit I loses all offsite power Current conditions at Time = I 010:

. SlisNOTactuated

. Train B of Phase A has NOT been reset

. Buses I ETA and I ETB are powered from their respective D/Gs

Operators are implementing FR-H.2 (Response to S/G Overpressure)

S/Gstatus:

A S/G B S/G C S/G D S/G NR Level [%]: 77 67 65 70 S/GPressure[PSIG]: 1270 1180 1176 1182 Based on the current conditions, in accordance with FR-H.2, which ONE (I) of the following will be required to mitigate the overpressure condition?

A. Start the TDCA pump B. Open the A SM PORV C. Place the S/G Blowdown system (BB) in service D. Commence a 100°F/hr NC system cooldown using condenser steam dumps Page 64 of 100

McGuire Nuclear Station Question: 65 2012 MNS SRO NRC Examination (1 point)

Which ONE (1) of the following is NOT a major action category of procedure FR-Z.3 (Response to High Containment Radiation)?

A. Place VE (Annulus Ventilation) system in operation.

B. Place VX (Containment Air Return) system in operation.

C. Check Containment Ventilation Isolation.

D. Notify Station Management of Containment Radiation levels.

Page 65 of 100

McGuire Nuclear Station Question:

66 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

. The crew has implemented E-O (Reactor Trip or Safety Injection) due to a LOCA

. The OATC is performing supplementary action steps in E-O

. The BOP is manually adjusting CA flow to the S/Gs

. An alarm annunciates on the electrical relay back panel behind the main control boards (IADI 1-E8, Transfer Trip System B Trouble)

In accordance with SOMP 01 -04 (Conduct of Operations) Attachment 7.6 (Reactor Operator Responsibilities), which ONE (1) ofthe following is the correct response by the OATC regarding the annunciator alarm?

A. The OATC can investigate the alarm, because the requirements for remaining in the surveillance area do not apply dunng implementation of EOPs.

B. The OATC can investigate the alarm because the electrical relay panel is within the OATC defined surveillance area.

C. The OATC is required to remain within the surveillance area during implementation of EOPs. The annunciator alarm can NOT be investigated by the OATC, another operator must investigate the alarm.

D. The OATC is allowed to momentarily leave the surveillance area to investigate the alarm in the event of an emergency affecting the safety of plant operations.

Page 66 of 100

McGuire Nuclear Station Question: 67 2012 MNS SRO NRC Examination (1 point)

SOMP 01-04 (Conduct of Operations), Attachment 7.15 (Control Room Conduct)

Step 2 (Starting or Operating Large Components) specifically requires an announcement using the plant paging system prior to initiation of Which ONE (1) of the following completes the statement above?

A. Excess Letdown B. Normal Letdown C. Steam Generator Blowdown D. Radioactive Waste Liquid Release Page 67 of 100

McGuire Nuclear Station Question:

68 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

. The WCC SRO has dispatched two NEOs (Doer I Documenter) to perform valve manipulations inside a contaminated area in accordance with an Operating Procedure

. The Doer is inside the contaminated area and is in direct communication with the Documenter outside the contaminated area

. The Documenter is reading each procedure step sequentially

. The Documenter can NOT see the valve manipulations being performed If the Doer does NOT have the procedure in hand as he performs the steps, what are the requirements of NSD 704 (Technical Procedure Use and Adherence), regarding the sign off for each step?

A. The Documenter checks off each step as the step is completed. The Doer initials each step upon completion of the task.

B. The Doer signs off the steps using his own initials upon completion of the task after leaving the contaminated area.

C. The Documenter signs off each step as the step is completed using his own initials AND the initials of the Doer.

D. The Documenter signs off each step as the step is completed using his own initials ONLY.

Page 68 of 100

McGuire Nuclear Station Question:

69 2012 MNS SRO NRC Examination (1 point)

With Unit I conducting a plant startup the following conditions exist:

. Reactorisat4O%RTP

. Impulse Pressure Channel I is 295 PSIG

. Impulse Pressure Channel 2 is 305 PSIG

. All AMSAC S/G LOW FLOW status lights are DARK

. The S/G PATH CLSD > 30 SEC annunciator is DARK

. The AMSAC UNBLOCK light is DARK Which ONE (1) ofthe following describes the operation ofthe AMSAC System, AND describes the action that should be taken in accordance with OP/11N61 00/003, Enclosure 4.1 (Power Increase)?

A. AMSAC has NOT failed to automatically unblock; Continue with the power increase and AMSAC will automatically unblock when BOTH Impulse Pressure channels rise above a MINIMUM of 360 P51G.

B. AMSAC has NOT failed to automatically unblock; Continue with the power increase and AMSAC will automatically unblock when Impulse Pressure Channel I rises above a MINIMUM of 300 PSIG.

C. AMSAC has failed to automatically unblock; Suspend the power increase until the failure has been resolved.

D. AMSAC has failed to automatically unblock; Depress the AMSAC Unblock Pushbutton, verify the Unblock light is jJI, and continue with the power increase.

Page 69 of 100

McGuire Nuclear Station Question: 70 2012 MNS SRO NRC Examination (1 point)

Given the following plant conditions:

. It is the end of a shift and there is an outstanding Configuration Control Card (CCC) that is being maintained in the Control Room

. The component being tracked on the CCC can NOT be returned to its AS FOUND position before the end of shift In accordance with SOMP 02-01 (Safety Tagging and Configuration Control), which ONE (1) of the foIlovAng describes the required disposition of the CCC?

A. Document the CCC as part of your turnover at shift relief.

B. Return the CCC to the OSM. An R&R will be issued prior to shift turnover.

C. Return the CCC to the CRS to determine whether it should be turned over, or if a procedure change will be required.

D. Return the CCC to the WCC SRO. The CCC will be tracked as open until the component can be repositioned to its AS FOUND position.

Page 70 of 100

McGuire Nuclear Station Question:

71 2012 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. clear after pressing and holding the Dose/Dose Rate toggle button on the ED for 10 seconds

2. clear when the dose rate drops below the alarm setpoint D. 1. clear after pressing and holding the Dose/Dose Rate toggle button on the ED for 10 seconds

2. not clear until the ED is reset Page 71 of 100

McGuire Nuclear Station Question:

72 2012 MNS SRO NRC Examination (1 point)

A radiation worker is repairing a valve in a contaminated area, which has the following radiological characteristics:

. The workers present exposure is 1938 MREM for the year

. The RWP states:

0 General area dose rate = 30 MREM/hr C Airborne contamination concentration = I 0. 0 DAC The job will take 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months if the worker wears a full-face respirator. The 2-hour time for work with a respirator includes the respirator-induced inefficiency factor. It will only take I hour ifthe worker does notwear the respirator.

Ifthe RP Managergrants all applicable dose extensions, which ONE (1) of the following choices for completing this job would maintain the workers exposure within the station administrative requirements and the principles of ALARA AND why is that action appropriate?

A. The worker must wear the respirator.

He will exceed DAC limits if he does NOT wear one.

B. The worker must wear the respirator.

The calculated TEDE dose received will be less than if he does NOT wear one.

C. The worker should NOT wear the respirator.

The calculated TEDE dose received will be less than if he does wear one.

D. The worker should NOT wear the respirator.

The dose received wearing a respirator will exceed site annual personnel dose limits.

Page 72 of 100

McGuire Nuclear Station Question: 73 2012 MNS SRO NRC Examination (1 point)

Unit 1 is operating at 8% RTP.

Which ONE (I) of the following conditions will result in an automatic Reactor trip signal? (Consider each indication separately)

A. Intermediate Range channel N-35 indicates i0 4 AMPS B. IA NC Loop Flow I NCP-5000 (Channel 1) indicates 90%

C. Pressurizer Level INCP-5160 (Channel 1) and INCP-5151 (Channel 2) indicate 100%

D. IC S/G NR Level ICFP-5560 (Channel 3) and ICFP-5550 (Channel 4) indicate 82%

Page 73 of 100

McGuire Nuclear Station Question:

74 2012 MNS SRO NRC Examination (1 point)

Given the following plant conditions:

. Chlorine gas is entering the Control Room due to a dropped gas cylinder

. AP-17 (Loss of Control Room) has been implemented

. I ETA and I ETB are energized In accordance with AP-17:

The RO dispatched to the CA Pump panels is first directed to (1)

At the CA Pump panels, the RO is directed to control S/G WR levels between (2)

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

A. 1. locally stop the Reactor Makeup Water pumps if a dilution is in progress

2. 80-90%

B. 1. locally stop the Reactor Makeup Water pumps if a dilution is in progress

2. 55-65%

C. 1. close the MSIVs by opening the breakers in the vital battery room if a coold own is occurring

2. 80-90%

D. 1. close the MSIVs by opening the breakers in the vital battery room if a coold own is occurring

2. 55-65%

Page 74 of 100

McGuire Nuclear Station Question:

75 2012 MNS SRO NRC Examination (1 point)

Given the following initial conditions on Unit 1:

. Theunitisat45% RTP Current conditions:

. IAD-4 I A3 (SIG C FLOW MISMATCH LO STM FLOW) LIT -

. IAD-4 I B3 (S/G C LEVEL DEVIATION) LIT -

. IAD-6 I BlO (T-REFIT-AVG ABNORMAL) LIT -

. I AD-6 I D1O (LOOP T-AVG DEVIATION) LIT -

. IAD-6 I ElO (LOOP D/T DEVIATION) LIT -

. IAD-6 I F3 (C NC PUMP LO FLO ALERT) LIT -

. IAD-6 I Eli (NC PUMP HI VIBRATION) LIT -

. IAD-61 Fli (NC PUMP HI HI VIBRATION)- LIT

. The Safety breakerAND the Feeder breakerfor IC NC pump indicate CLOSED

. The unit remains at 45% RTP Based on the above conditions, which ONE (I) of the following actions is required to be performed?

A. Immediately trip the IC NC pump and THEN shutdown the unit in accordance with OP/I /A/6100/003 (Controlling Procedure for Unit Operation).

B. Place the I C S/G CF Control valve in Manual and reduce feed flow.

C. Manually trip the reactor, stop the I C NCP, and then go to E-O (Reactor Trip or Safety Injection).

D. Place the Unit I D/T DEFEAT switch to the I C position per the Annunciator Response Procedure for IAD-6 / ElO.

Page 75 of 100

McGuire Nuclear Station Question:

76 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

. The unit is performing a normal NC system cooldown for refueling

. Current NC temperature is 400° F Per the Selected Licensee Commitments (SLC) for Borated Water Sources, as a minimum, the Boric Acid Tank (BAT) (1) the Refueling Water Storage Tank (FWST) shall be OPERABLE.

Per Tech Spec 3.5.4 (RWST) Bases, the basis for the MINIMUM FWST boron concentration limit is to prevent Post-LOCA (2)

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

A. 1. AND

2. caustic stress corrosion damage to various systems and components during containment sump recirc B. 1. AND

2. boron precipitation hindering core cooling prior to transferring to Hot Leg Recirc C. 1. OR

2. caustic stress corrosion damage to various systems and components during containment sump recirc D. 1.OR

2. boron precipitation hindering core cooling prior to transferring to Hot Leg Recirc Page 76 of 100

McGuire Nuclear Station Question: 77 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

A Loss of Offsite Power occurred, resulting in a stuck open PZR safety valve

Reactor tripped automatically and SI actuated automatically

I B DIG failed to start

Actions of E-0 (Reactor Trip or Safety Injection) are complete at Time = 0645 Conditions at Time = 0700: Conditions at Time = 0720:

I B D/G will not start

lB D/G will not start

NC pressure=1650 PSIG

NC pressure=1610 PSIG

RVLIS Lower Range level = 35%

RVLIS Lower Range level = 33%

PZR safety valve is stuck open

PZR safety valve is stuck open

I NI-9A (NC Cold Leg nj from NV)

INI-9Aisclosed is closed

CETs=715°F

CETs=705°F

Subcooling Monitor= -35° F

Subcooling Mon itor= -35° F Based on the conditions at 0720, which ONE (I) of the following is the classification for this event? (For the purposes of this question, do NOT consider Emergency Coodinatorjudgement as a basis of classification)

REFERENCE PROVIDED A. Notification of Unusual Event (NOUE)

B. Alert C. Site Area Emergency D. General Emergency Page 77 of 100

McGuire Nuclear Station Question:

78 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

. Todays date is September 5th

. PT111A144501006 B (VX System Train I B Performance Test) is in progress

At 1100, the test is stopped due to high vibration on the lB VX Fan and I B VX Train is declared INOPERABLE

At 1230, IA DG is declared INOPERABLE due to a fuel oil leak In order to NOT declare both trains of VX INOPERABLE, the crew must restore either lB VX Train or IA DG to OPERABLE status no later than Which ONE of the following completes the statement above?

REFERENCE PROVIDED A. 1500 on September 5th B. 1630 on September 5th C. 1100 on September 8th D. 1230 on September 8th Page 78 of 100

McGuire Nuclear Station Question:

79 2012 MNS SRO NRC Examination (1 point)

Given the following Unit I conditions:

. The unit experienced a total loss of Feedwater and subsequent reactor trip

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

. Subsequently, the IA CF Pump was restored to service per Enclosure 8 (Reestablishing CF Flow) and Feedwater flow has been established

. All SG Wide Range (WR) levels are 8% and INCREASING slowly

. Core exitthermocouple temperatures are 560°F and STABLE

. Containment pressure peaked at 0.6 PSIG In accordance with FR-HI, (Loss of Secondary Heat Sink) Enclosure 8 (Re-establishing CF Flow) Feedwater flow to the respective generators may be increased further to reduce CET temperatures when Steam Generator WR Level is greater than aMINIMUMof (1)

In accordance with the FR-H.1 Background document, to ensure an adequate, maintainable heat sink exists, Narrow Range (NR) level in at least one S/G shall be greaterthanaMiNiMUMof (2)

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

A. 1. 12%

2. 11%

B. 1. 17%

2. 11%

C. 1. 12%

2. 17%

D. 1. 17%

2. 17%

Page 79 of 100

McGuire Nuclear Station Question:

80 2012 MNS SRO NRC Examination (1 point)

Unit I is at 100% powerwhen the Control Room receives the following alarms:

. OAC Alarm M1A1590, IAI VG HEADER PRESS, Lo-Lo

. Annunciator IADI 1-A/6, DG A PANEL TROUBLE A NEO dispatched to the IA DG Room reports the following:

. Annunciator IADI9-C/5 (STARTING AIR PRESS LOW) is in alarm

. No other annunciators are lit at the local panel

. The VG Starting Air Tank I Al is 208 psig and going down slowly

VG compressor IAI cannot be started

The lAl VG Starting Air Tank has been isolated Based on the conditions above, the IA Emergency Diesel Generator is (I)

Per Tech Spec 3.8.3 (Diesel Fuel Oil and Starting Air) Bases, for the Starting Air system to be considered OPERABLE it must be capable of a MINIMUM of (2) start attempts without recharging the air start receivers.

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

A. I. OPERABLE

2. three B. I. OPERABLE

2. five C. I. INOPERABLE

2. three D. I. INOPERABLE

2. five Page 80 of 100

McGuire Nuclear Station Question:

81 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

. Unit I has implemented AP-14 (Rod Control Malfunction) in response to a dropped control rod

. The dropped rod has not yet been recovered

. The crew hasjustcalled up OAC point M1P1385 (ReactorThermal Power, Best Estimate) to determine reactor power The unit isat9O%TPBE

QPTRisI.05

AFD has exceeded the limits of Tech Specs Based on the conditions above, which ONE (1) of the following describes the NEXT action required by AP-14?

A. Reduce power to comply with Tech Spec 3.2.4 (QPTR) within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

B. Reduce power to less than 75% to comply with Tech Spec 3.1.4 (Rod Group Alignment) within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

C. Reduce power to less than 50% using AP-04 (Rapid Down power) within 30 minutes.

D. Trip the reactor and transition to E-0 (Reactor Trip or Safety Injection).

Page 81 of 100

McGuire Nuclear Station Question:

82 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

NC system heatup is in progress following a forced outage

NC system temperature is 500° F

All ReactorTrip and Bypass breakers are OPEN Based on the conditions above, Technical Specifications (TS) require that a MINIMUM of (1) NC loops shall be OPERABLE.

For an NC loop to be considered OPERABLE, Technical Specifications require that its associated S/G NarrowRange(NR)levelshall begreaterthan aMINIMUMof (2)

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

A. 1.2

2. 12%

B. 1.2

2. 17%

C. 1.3

2. 12%

D. 1.3

2. 17%

Page 82 of 100

McGuire Nuclear Station Question:

83 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

. PT/11A144501003 A (Annulus Ventilation System Train A Operability Test) is being performed.

. During the test, Annunciator OAD-12 I F-2 (IA VE Filter Hi Temp) alarms

. The IA VE Filter temperature is 222 °F

The cause of the high temperature is a malfunction of the filter heater

1) What automatic action(s) is(are) expected as a result of this alarm?

2) In accordance with Technical Specification 3.6.10 (Annulus Ventilation System (AVS)) Bases, with the heater INOPERABLE, the IA Annulus Ventilation train is Which ONE (1) of the following completes the statements above?

A. 1. IA Heaters trip ONLY

2. INOPERABLE B. 1. IA Heaters AND IA VE Fan trip

2. INOPERABLE C. 1. lAHeaterstrip ONLY

2. OPERABLE D. 1. lAHeatersANDlAVEFantrip

2. OPERABLE Page 83 of 100

McGuire Nuclear Station Question:

84 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

. The unit is at I 00% RTP

. I D NC Pump Lower Motor Bearing temperature is 205°F and increasing

. Lower Bearing KC Outlet Flow is slowly decreasing

. 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 5%, then stop the I D NCP.

B. Trip the Reactor, verify reactor power less than 10%, then stop the I D NCP.

C. Reduce reactor power to less than 5% using AP-04 (Rapid Downpower), then stop the ID NCP.

D. Reduce reactor power to less than 10% using AP-04 (Rapid Down power), then stop the ID NCP.

Page 84 of 100

McGuire Nuclear Station Question:

85 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

. The unit is operating at I 00% RTP

. The IA NV pump is tagged out for maintenance

. The lB NV pump trips

. The PD pump cannot be started

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

Per AP-12, the crew is evaluating placing the Standby Makeup pump in service

Currently, Pressurizer level is 40% and decreasing at a rate of 1%/mm Based on the current Pressurizer level and rate of decrease, the evaluation for placing the Standby Makeup pump in service must be completed within (1) minutes.

After normal seal injection is restored, the MINIMUM seal injection flow rate required byAP-l2is (2)

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

A. 1.20

2. 6GPM B. 1.36

2. 6GPM C. 1.20

2. 8GPM D. 1.36

2. 8GPM Page 85 of 100

McGuire Nuclear Station Question:

86 2012 MNS SRO NRC Examination (1 point)

Given the following initial conditions on Unit 1:

. The crew implemented E-O (ReactorTrip or Safety Injection) due to a valid Reactor trip signal

. Subsequently, the crew transitioned to FR-S.1 (Response to Nuclear Power Generation I ATWS) due to a failure of the Reactor to trip automatically or manually Current conditions:

. The crew has just completed the step in FR-SI to check NC T-colds stable or going up, and is now evaluating plant conditions for a potential procedural transition

. hR SUR is positive

. W/R Neutron Flux is 7%

. CETs are 1220°F and increasing Based on the current conditions, which ONE (1) of the following describes the NEXT procedural implementation, in accordance with FR-SI?

A. Complete the actions of FR-SI, and THEN implement FR-C.1 (Response to Inadequate Core Cooling).

B. Perform ONLY those actions of FR-C. I that do not cool down the NC system or add positive reactivity to the core, in parallel with F R-S. I.

C. Perform j, actions of FR-C. I including those that coo down the NC system or add positive reactivity to the core, in parallel with FR-S. I.

D. GO TO EG/1/NMSAM/SACRGI (Severe Accident Control Room Guideline Initial Response).

Page 86 of 100

McGuire Nuclear Station Question:

87 2012 MNS SRO NRC Examination (1 point)

Given the following initial conditions on Unit 2:

. A SGTR has occurred on 20 S/G

. Prior to initiating NC system cooldown, all NC pumps were stopped due to loss of subcooling Subsequently, the following conditions exist:

. NC system cooldown and depressurization is COMPLETE

. NC subcooling is 25°F

. The crew has reached the step in E-3 (SGTR) to check NCP status In accordance with the EOP background document for E-3, the principal reason for restarting an NC pump at this point in E-3 is to (1 ) during the subsequent recovery.

In accordance with E-3, Enclosure 7 (NC Pump Start), the reason for checking Reactor Vessel Upper Range level pnor to the NC pump start is to ensure sufficient inventory to (2)

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

A. 1. reduce S/G tube thermal stress

2. accommodate void collapse B. 1. provide normal Pressurizer spray flow

2. accommodate void collapse C. 1. reduceS/Gtubethermal stress

2. provide adequate NC pump NPSH D. 1. provide normal Pressurizer spray flow

2. provide adequate NC pump NPSH Page 87 of 100

McGuire Nuclear Station Question:

88 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

. Battery Charger EVCS is currently out-of-service for preventive maintenance

. During rounds, the Unit I Auxiliary Building Operator reports that Battery Charger EVCA has tripped and can NOT be restarted

. A NEO is stationed at EVDA to continuously monitor bus voltage and report to the Control Room

. AP-15 (Loss of Vital or Aux Control Power) Enclosure I (Response to Degraded DC Bus Voltage) has been implemented

The NEO reports that EVDA is 110.5 VDC and lowering Based on the conditions above, AP-15 requires that the inverters associated with EVDA be swapped to an alternate source prior to EVDA reaching a MINIMUM voltage of (1)

In accordance with the Design Basis, Battery EVCA must be capable of carrying its design loadsforaMlNlMUMof (2)

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

A. 1. 110

2. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. 1. 107

2. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C. 1. 107

2. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months D. 1. 110

2. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Page 88 of 100

McGuire Nuclear Station Question:

89 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

. A LOCA has occurred

. ECA-1 .1 (Loss of Emergency Coolant Recirculation) has been implemented

. The crew has transitioned to Enclosure 5 (NS Alignment to Containment Sump)

. Containment sump level is 3.5 FT

. Containment pressure is 3.2 PSIG

. Both NS pumps areOFF

. The crew hasjust opened INS-18A (IA NS Pump Suction from Cont Sump Isol) as directed by Enclosure 5

. Before the crew attempts to start the NS pump, the STA announces thatthere is an ORANGE path on the Containment CSFST Based on the conditions above:

1) The NEXT action the crew is required to take is to

2) What is the basis for this action?

A. I . enter FR-Z.1 (Response to High Containment Pressure)

2. RED or ORANGE Path FRPs must be implemented immediately while in ECA-1.1.

B. I . enter FR-Z.1 (Response to High Containment Pressure)

2. FR-Z.1 contains more restrictive requirements on NS pump operation under these conditions than ECA-1 .1.

C. 1. continue aligning NS for recirc per ECA-1 .1, Enclosure 5

2. A Containment ORANGE Path may briefly exist between opening the NS sump valve and starting the NS pump, therefore FR-Z.1 is NOT required to be implemented at this time.

D. 1. continue aligning NS for recirc per ECA-1 .1, Enclosure 5

2. FR-Z. I is not required to be entered because CSF status trees are monitored for information only while in ECA-I .1.

Page 89 of 100

McGuire Nuclear Station Question:

90 2012 MNS SRO NRC Examination (1 point)

Loading of a Dry Storage Cask is complete, the cask lid has been welded shut, and the crew is preparing to move the cask to the Vertical Concrete Cask (VCC).

1) Per Tech Spec 3.7.12 (Fuel Handling Ventilation Exhaust System (FHVES)), is the VF System required to be OPERABLE and in operation in the Filter Mode when the cask is moved using the 125 -Ton Overhead Crane with the rollup door closed?

2) Per Tech Spec 3.7.12 Bases, total system failure could result in the atmospheric release from the fuel handling building exceeding the limits in the event of a fuel handling accident.

A. 1.No

2. IOCFR 100 B. 1.No

2. IOCFR5O C. 1. Yes

2. IOCFR 100 D. 1. Yes

2. IOCFR5O Page 90 of 100

McGuire Nuclear Station Question:

91 2012 MNS SRO NRC Examination (1 point)

A release of Waste Monitor Tank (WMT) A has been planned.

A radioactive Hquid release permit has been prepared with the following data:

=== RC PUMP DATA =======================================:

RC pumps running 3.00 RC pumps assigned to RELEASE 3.00 Total RC pumps required (all concurrent releases) 4.00

RECOMME NDED RELEAS E RATE ==========================

Allowable release rate (gpm) I .61E+01 Recommended release rate (gpm) I .20E--02

SETPOINT DATA ============

EMF49L in Service Yes Monitor Background (cpm) 4.49 E--03 Cs-I 37 Equivalence (uCi/ML). . . 7.23E-06 Expected CPM 4.50E+03 Trip I setpoint (cpm) 8.97E+03 Trip 2 setpoint (cpm) I .42E+04 Which ONE (I) of the following actions is correct for approval of this release permit?

A. The release may NOT be approved due to inadequate number of RC pumps.

Recommended Release Rate information is correct.

B. The release may NOT be approved due to incorrect Recommended Release Rate. RC Pump Data information is adequate.

C. The release may NOT be approved due to inadequate number of RC Pumps AND incorrect Recommended Release Rate.

D. The release MAY be approved as presented.

Page 91 of 100

McGuire Nuclear Station Question:

92 2012 MNS SRO NRC Examination (1 point)

Given the following plant conditions:

. Both units are operating at 100% RTP

. A fire occurs in the Control Room

AP-45 (Plant Fire) has been implemented

Enclosure 22 (Control Room Fire Unit I and 2 Actions) has just been implemented In accordance with AP-45, the assured Safe Shutdown Train(s) for this event is (are)

(1)

In accordance with the AP-45 Background document, for a fire in the Control Room, the PZR PORVs Block valves must be closed within (2) minutes of the start of the fire.

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

A. 1. the SSF

2. 10 B. I. the SSF

2. 30 C. 1. Train AorB

2. 10 D. I. Train AorB

2. 30 Page 92 of 100

McGuire Nuclear Station Question: 93 2012 MNS SRO NRC Examination (1 point)

Given the initial conditions on Unit I:

. A LOCA occurred

. Containment pressure peaked at 5 PSIG and is slowly decreasing Current conditions:

. ECCS suctions have been swapped to the Cold Leg Recirculation alignment

. FWST level is 7%

. NC pressure is 2 PSIG

. CETsare600°F

. Reactor Vessel Lower Range level is 49% and slowly decreasing

. ContainmentSump level is 13.1 feetand increasing Based on the current conditions, which ONE (1) of the following states the required procedure transition AND the reason for implementation of this procedure?

A. Implement FR-C.2 (Response to Degraded Core Cooling).

The level ofwater in the core region has been reduced such that a challenge exists to core cooling.

B. Implement FR-C.2 (Response to Degraded Core Cooling).

Core exit temperatures and NC pump status indicate that a challenge exists to core cooling.

C. Implement FR-Z.2 (Response to Containment Flooding).

Containment sump levels are higher than expected, indicating a potential for a ruptured RN or KC pipe inside containment.

D. Implement FR-Z.2 (Response to Containment Flooding).

Containment sump levels are higher than expected, indicating a potential secondary line (feedwater or main steam) break inside containment along with the input from the NC system and the FWST.

Page 93 of 100

McGuire Nuclear Station Question:

94 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

. Power is 50% RTP for maintenance on 2B CF pump

. Chemistryjust reported that NC Dose Equivalentl-131 was 100 pCi/gm based upon a sample taken I hour ago Based on the given conditions and in accordance with Technical Specification (TS) 3.4.16 (RCS SpecificActivity), a valid REQUIRED ACTION is to (1)

AND I n acco rd an ce with th e bases of TS 3.4. 16 the LCO Iim its o n th e specific activity of the NC system ensures the resulting 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months doses (2)

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

REFERENCE PROVIDED A. I . restore DOSE EQUIVALENT 1-131 to within limit in 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months

2. at the site boundary will not exceed a small fraction of the IOCFRIOO dose guideline following a SGTR accident B. I . restore DOSE EQUIVALENT 1-131 to within limit in 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months

2. to the whole body and thyroid of radiation workers will not exceed the I OCFR20 dose guideline following a SGTR accident with a stuck open main steam safety valve on the ruptured SG C. 1. be in MODE 3 with Tave< 500 °F in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

2. at the site boundary will not exceed a small fraction of the IOCFRI 00 dose guideline following a SGTR accident D. I. be in MODE 3 with Tave< 500 °F in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

2. to the whole body and thyroid of radiation workers will not exceed the I 0CFR20 dose guideline following a SGTR accident with a stuck open main steam safety valve on the ruptured SG Page 94 of 100

McGuire Nuclear Station Question:

95 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

. Annunciator 2RAD-1 / E-5 (2 EMF 38 CONTAINMENT PART ALERT) alarms

The crew observes that 2EMF-38L (Containment Particulate Monitor) is in Trip I In accordance with Tech Spec 3.4.15 (RCS Leakage Detection Instrumentation)

Bases, which ONE (1) of the following is required by the LCO to be capable of identifying a I GPM Reactor Coolant system leak in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or less after leakage has reached the sumps?

A. Containment Floor and Equipment (CFAE) sump level B. 2EMF-39 (Unit 2 Containment Gas Monitor)

C. Incore Instrument sump level D. Volume Control Tank level Page 95 of 100

McGuire Nuclear Station Question:

96 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

. The unit is operating at I 00% RTP

. A loss of Battery C harger EVCA occurred

. Battery EVCA voltage lowered to I 09 VDC Following restoration, conditions are:

. Battery EVCA voltage is currently I 29 VDC

. For two connected cells, the Specific Gravity is I I 80

. For all connected cells, the average Specific Gravity is I .202

Electrolyte temperature is 76°F Based on the conditions following restoration given above, per Tech Spec (TS) 3.8.6 (Battery Cell Parameters), Battery EVCA (1) INOPERABLE.

The basis of TS 3.8.6 states that the operability of the DC subsystems includes maintaining at least ONE (2) of DC sources OPERABLE during accident condition s.

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

REFERENCE PROVIDED A. lis

2. train B. 1. is NOT

2. train C. lis

2. channel D. 1. is NOT

2. channel Page 96 of 100

McGuire Nuclear Station Question:

97 2012 MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

A LOCA has occurred

The TSC is fully staffed and has been activated

An individual is needed for activities needed to protect valuable property during which 7 R EM of TED E exposure is expected to be received In accordance with RP-004 (General Emergency) Enclosure 4.4 (Request for Emergency Exposure):

1) Is the individual required to be a volunteer?

2) The Operations Shift Manager (OSM) approve (authorize) the exposure for this activity.

A. 1. Yes

2. can B. 1. Yes

2. can NOT C. 1.No

2. can NOT D. 1.No

2. can Page 97 of 100

McGuire Nuclear Station Question:

98 2012 MNS SRO NRC Examination (1 point)

Given the following plant conditions:

. You are tasked to evaluate four available teams of NEOs to perform a valve lineup in a 1500 mREM/hr radiation field Given the following available teams:

TEAMA TEAM C NEO A 200 mREM YTD NEO A-4700 mREM YTD NEOB-4375mREM YTD NEOB-200mREM YTD NEOC-25OmREM YTD Team A can complete the alignment in 30 minutes. Team C can complete the alignment 15 minutes.

TEAMB TEAMD NEO A 500 mREM YTD NEO A 4000 mREM YTD NEO B -3500 mREM YTD NEO B -1000 mREM YTD NEOC-500mREM YTD Team B can complete the alignment in 45 minutes. Team D can complete the alignment in 20 minutes.

In accordance with the Duke Energy Fleet ALARA Manual, which ONE (1) of the available teams should be selected?

Consider that the members of each team receive an equal dose and are approved for exposures up to Federal limits.

A. Team A B. Team B C. Team C D. Team D Page 98 of 100

McGuire Nuclear Station Question:

99 2012 MNS SRO NRC Examination (1 point)

Given the following plant conditions:

. A Notification of Unusual Event (NOUE) has been declared

. The initial notification to the State and Counties has been made using the Selective Signaling System In accordance with RP-029 (Notifications to Offsite Agencies from the Control Room):

1) if plant conditions remain the same, follow-up notifications are required every until the emergency is terminated.

2) if the Selective Signal System fails, the FIRST backup system that is used to contact the State and Counties is the Which ONE (1) of the following completes the statement above?

A. 1. hour

2. Standard Phone Lines B. 1. four hours

2. Standard Phone Lines C. 1. hour

2. Wireless Radio System D. 1. four hours

2. Wireless Radio System Page 99 of 100

McGuire Nuclear Station Question: 100 2012 MNS SRO NRC Examination (1 point)

In accordance with RP-004 (General Emergency) and RP-029 (Notifications to Offsite Agencies from the Control Room), irrespective of the event in progress, the INITIAL notification to offsite agencies of a General Emergency (1) ALWAYS require a Protective Action Recommendation (PAR) to be made.

AND If a PAR is required, regardless of wind speed, the MINIMUM geographic radius that requires evacuation is a (2)

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

A. 1. does

2. 2 mile radius B. 1. doesNOT

2. 2 mile radius C. 1. does

2. 5 mile radius D. 1. doesNOT

2. 5 mile radius Page 100 of 100

Reference Listfor: 2012 MNS SRO NRC Examination Steam Tables EP/1/A/5000/ECA-1.1 (Step 18)

EP/1/A/5000/ECA-1 I (Enclosure 9)

RPIOIAI5700I000, Classification of Emergency Tech Spec 3.8.1 AC Sources Operating Tech Spec 3.6.11 Air Return System Tech Spec 3.4.16 Tech Spec 3.8.6 Printed 8/28/2012 8:44:23 AM Page 1 of 1

Examination KEYfor: 2012 MNS SRO NRC Examination Question Answer Number A

2 B 3 B 4 C 5 A 6 D 7 C 8 C 9 A 10 B 11 B 12 C 13 B 14 B 15 B 16 C 17 B 18 C 19 D 20 D 21 B 22 C 23 B 24 A 25 A Printed 8/28/2012 8:44:55AM Page 1 of 4

Examination KEYfor: 2012 MNS SRO NRC Examination Question Answer Number 26 C 27 B 28 D 29 A 30 A 31 B 32 C 33 A 34 B 35 B 36 B 37 A 38 D 39 D 40 C 41 C 42 B 43 D 44 C 45 B 46 A 47 C 48 B 49 A 50 B Printed 8/28/2012 8:44:56AM Page 2 of 4

Examination KEYfor: 2012 MNS SRO NRC Examination Question Answer Number 51 D 52 B 53 A 54 B 55 D 56 D 57 A 58 C 59 B 60 B 61 B 62 A 63 C 64 B 65 B 66 D 67 C 68 C 69 D 70 B 71 A 72 C 73 A 74 B 75 C Printed 8/28/2012 8:44:56AM Page 3 of4

Examination KEYfor: 2012 MNS SRO NRC Examination Question Answer Number 76 A 77 D 78 B 79 A 80 B 81 D 82 C 83 C 84 A 85 A 86 D 87 B 88 C 89 C 90 C 91 C 92 A 93 C 94 A 95 A 96 A 97 C 98 D 99 B 100 A Printed 8/28/2012 8:44:56 AM Page 4 of 4

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