Text

301 Final SRO Written Exam
	ML16119A429
Person / Time
Site:	McGuire, Mcguire
Issue date:	04/26/2016
From:	; NRC/RGN-II
To:	;
References
	Download: ML16119A429 (140)
	v • d • e

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

Date: Facility/Unit: MCGUIRE Region: I II III IV Reactor Type: W 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 ILT-16-1 MNS SRO NRC Examination Question: 1 (1 point)

Given the following initial conditions on Unit 1:

The unit is at 100% RTP

Train "B" equipment is in service Subsequently,

An 86 Lockout occurs on 1ETB

No operator actions have been taken Based on the conditions above, NC pumps currently have KC cooling.

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

A. NO B. ALL C. ONLY A and D D. ONLY B and C Page 1 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 2 (1 point)

To which ONE (1) of the following locations would you dispatch an Auxiliary Operator to rack out the breaker for the 1A ND pump?

A. SATA B. 1TA C. 1TC D. 1ETA Page 2 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 3 (1 point)

Given the following conditions on Unit 2:

The unit is in solid operations while cooling down

Both trains of ND are in service, A NV pump is in service

Letdown is through 2NV-121 Subsequently:

The Letdown Heat Exchanger Outlet temperature sensor fails causing 2KC-132 to go full OPEN Per OP/2/A/6100/SD-8 (WATER SOLID OPERATIONS), the operator action required is to throttle 2NV-241 (1) OR throttle 2NV-121 (2) .

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

COMPONENT LEGEND:

2NV-121 (ND LETDOWN CONTROL) 2KC-132 (U2 LD HX KC OUT TEMP CNTRL) 2NV-241 (SEAL INJECTION FLOW CONTROL)

A. 1. CLOSED

2. OPEN B. 1. OPEN

2. OPEN C. 1. CLOSED

2. CLOSED D. 1. OPEN

2. CLOSED Page 3 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 4 (1 point)

Given the following conditions on Unit 2:

Both trains of Residual Heat Removal (ND) are in service

ND Heat Exchanger outlet valves (2ND-14 & 2ND-29) are throttled to 2000 gpm each

NC Cooldown rate is 25°F/Hr

The instrument air line to Train "B ND Heat Exchanger outlet valve (2ND-14) breaks off Which ONE (1) of the following indicates the INITIAL ND System response to this event?

Total ND System Flow NC System Cooldown rate A. Goes UP Goes UP B. Goes UP Remains the Same C. Goes DOWN Goes DOWN D. Goes DOWN Remains the Same Page 4 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 5 (1 point)

Given the following conditions on Unit 2:

Unit is at 75% RTP

Several banks of FWST heaters have failed "ON"

Current FWST temperature is 91°F

FWST temperature is increasing at a rate of 0.5°F/min Based on the conditions above, FWST temperature will reach the T.S. 3.5.4 (REFUELING WATER STORAGE TANK) limit in (1) minutes.

Normally, Group 1 FWST heaters cycle automatically to maintain FWST temperature greater than a MINIMUM of (2) .

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

A. 1. 14

2. 72°F B. 1. 14

2. 75°F C. 1. 18

2. 72°F D. 1. 18

2. 75°F Page 5 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 6 (1 point)

Given the following initial conditions on Unit 1:

The unit is initially at 100% RTP

Safety Injection initiates due to a Large-Break LOCA inside Containment Approximately ONE (1) hour after the LOCA,

The 1B RN pump trips Based on the conditions above,

1) the temperature of will increase.

2) after transfer to cold leg recirculation, the length of time it takes to cooldown from 350°F to 140°F be affected.

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

(ASSUME THAT BOTH TRAINS OF ND REMAIN IN OPERATION DURING THE ENTIRE EVENT)

A. 1. 1B ND pump motor ONLY

2. will NOT B. 1. 1B ND pump motor ONLY

2. will C. 1. 1A AND 1B ND pump motors

2. will NOT D. 1. 1A AND 1B ND pump motors

2. will Page 6 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 7 (1 point)

Given the following initial conditions on Unit 2:

A reactor trip has occurred

The crew is performing E-0 (REACTOR TRIP OR SAFETY INJECTION)

Containment pressure is 0.1 PSIG and stable Subsequently,

ONE (1) PZR PORV fails partially open

PRT pressure rises to approximately 115 PSIG, and then suddenly drops and stabilizes at 2 PSIG

Containment pressure starts to rise at 0.1 PSIG per minute Based on the conditions above,

1) the PRT rupture discs operate as designed.

2) when Containment pressure rises above the Tech Spec 3.6.4 (CONTAINMENT PRESSURE) limit, action MUST be taken to restore Containment pressure to within the limit in a MAXIMUM of .

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

A. 1. did

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

2. 30 minutes C. 1. did NOT

2. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months D. 1. did NOT

2. 30 minutes Page 7 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 8 (1 point)

Given the following conditions on Unit 2:

The unit is in MODE 3

OP/1/A/6400/005 (COMPONENT COOLING WATER SYSTEM) Enclosure 4.20 (POST OUTAGE KC to NC PUMP FLOW BALANCE) is being performed

2A1 KC pump is running, 2A2 KC pump has been stopped for the flow test

2B1 and 2B2 KC pumps are available

The 2B sequencer is in TEST for surveillance testing

I&E inadvertently generates an SI signal on Unit 2 B Train ONLY Assuming no operator actions, which ONE (1) of the following indicates the Unit 2 KC pumps which are in service?

A. 2A1 KC pump ONLY B. 2A1 and 2A2 KC pumps ONLY C. 2A1, 2B1, and 2B2 KC pumps ONLY D. 2A1, 2A2, 2B1 and 2B2 KC pumps Page 8 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 9 (1 point)

Given the following conditions on Unit 2:

A unit runback has occurred

Steam Dump valves failed to modulate OPEN

The Pressurizer Pressure Calculated Error observed on the Ovation Soft Panel is +76 PSIG Based on the conditions above, the Pzr Spray Control valves will be (1) OPEN.

Pzr PORVs (2NC-32B and 2NC-36B) will OPEN if actual Pzr pressure increases to a MINIMUM of (2) PSIG.

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

A. 1. full

2. 2335 B. 1. throttled

2. 2335 C. 1. full

2. 2385 D. 1. throttled

2. 2385 Page 9 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 10 (1 point)

Given the following conditions on Unit 1:

NC system pressure is 1985 PSIG and slowly lowering due to a leaking Pressurizer Code Safety Valve (1NC-1)

PRT pressure is currently 65 PSIG

Discharge temperature downstream of 1NC-1 is 310°F

Containment pressure is currently 0.1 PSIG When the PRT rupture disc ruptures,

1) the rate of NC system depressurization will .

2) the temperature downstream of 1NC-1 will .

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

REFERENCE PROVIDED A. 1. increase

2. remain the same B. 1. remain the same

2. remain the same C. 1. remain the same

2. decrease D. 1. increase

2. decrease Page 10 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 11 (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

Train B SSPS testing is in progress

Reactor Trip Bypass breaker (BYB) is racked in and closed Based on the conditions above, a General Warning alarm for (1) train SSPS will be generated.

If Reactor Trip Bypass breaker (BYA) is racked in and closed, (2) would receive a trip open signal.

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

A. 1. A

2. RTA, RTB, BYA, and BYB breakers B. 1. A

2. RTA and RTB breakers ONLY C. 1. B

2. RTA, RTB, BYA, and BYB breakers D. 1. B

2. RTA and RTB breakers ONLY Page 11 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 12 (1 point)

Given the following conditions on Unit 1:

A Safety Injection has occurred on the unit Which ONE (1) of the following indicates the status of the VL (Lower Containment Ventilation) and VU (Upper Containment Ventilation) fans five (5) minutes after the Safety Injection signal?

VL VU A. Running in LOW speed Running in MAX COOL mode B. Running in HIGH speed Running in MAX COOL mode C. Running in LOW speed Shunt tripped OFF D. Running in HIGH speed Shunt tripped OFF Page 12 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 13 (1 point)

Given the following conditions on Unit 2:

A Large Break LOCA has occurred

The P between Lower Containment and Upper Containment is 0.3 PSID at 15 seconds into the event

6 minutes after the event initiation, an operator checks the status of the Containment Air Return Fans (CARFs)

Based on the conditions above,

1) the Containment Air Return Isolation dampers (RAF-D-2/4) are .

2) the Containment Air Return Fans are .

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

A. 1. CLOSED

2. OFF B. 1. CLOSED

2. ON C. 1. OPEN

2. OFF D. 1. OPEN

2. ON Page 13 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 14 (1 point)

Regarding the effect of prolonged operation with elevated Ice Condenser temperatures,

1) sublimation rates would .

2) if a high energy line break occurs inside Containment, peak Containment pressure would be .

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

A. 1. increase

2. higher B. 1. increase

2. unaffected C. 1. decrease

2. higher D. 1. decrease

2. unaffected Page 14 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 15 (1 point)

Given the following conditions on Unit 1:

The crew is performing ES-1.3 (TRANSFER TO COLD LEG RECIRC)

Containment Spray (NS) has been aligned for recirculation

FWST Level is 35 inches

Containment pressure is 3.2 PSIG and rising slowly Aligning NS for recirc in accordance with ES-1.3, requires (1) train(s) of NS to be aligned.

Based on the conditions above, if a loss of NS flow occurs, a Containment ORANGE path (2) occur.

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

A. 1. ONLY one

2. will NOT B. 1. both

2. will NOT C. 1. ONLY one

2. will D. 1. both

2. will Page 15 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 16 (1 point)

Given the following conditions on Unit 2:

I&E has requested that the 2B Containment Spray Pump breaker be racked out for an oil change.

To which ONE (1) of the following locations should an AO be dispatched to rack out the breaker?

A. SATB B. 2 ETB C. 2 TB D. 2 TD Page 16 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 17 (1 point)

Given the following conditions on Unit 1:

Unit is at 70% RTP

A steam leak has occurred

The crew has implemented AP-01 (STEAM LEAK)

If Pressurizer level is still GOING DOWN after crew actions to, OPEN 1NV-238 (CHARGING LINE FLOW CONTROL), (1) AP-01 will direct a Reactor trip.

If the main turbine fails to trip upon Reactor trip, AND can NOT be manually tripped, the NEXT action directed by E-0 (REACTOR TRIP OR SAFETY INJECTION), is to CLOSE (2) .

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

A. 1. and isolate Letdown ONLY

2. governor valves in FAST action B. 1. and isolate Letdown ONLY

2. all MSIVs and MSIV Bypass Valves C. 1. isolate Letdown AND start an additional NV pump

2. governor valves in FAST action D. 1. isolate Letdown AND start an additional NV pump

2. all MSIVs and MSIV Bypass Valves Page 17 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 18 (1 point)

Given the following Unit 2 initial conditions:

The Unit is at 100% RTP

2B MDCA Pump is tagged out Subsequently,

The 2B S/G Main Steam line breaks

The 2A MDCA Pump fails to start

E-2 (FAULTED STEAM GENERATOR ISOLATION) has been implemented In accordance with E-2, what valve(s) will be closed to isolate the steam supply to TD CA pump from 2B S/G?

COMPONENT LEGEND:

2SA-2 (2B S/G SM SUPPLY TO UNIT 2 TD CA PUMP TURB MAINT ISOL)

2SA-78 (2B S/G SM SUPPLY TO UNIT 2 TD CA PUMP TURB LOOP SEAL ISOL)

2SA-49AB (SM FRM S/G 2B TO TD CA PUMP ISOL)

A. 2SA2, 2SA-78, AND 2SA-49AB B. 2SA-2 AND 2SA-78 ONLY C. 2SA-49AB ONLY D. 2SA-2 ONLY Page 18 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 19 (1 point)

Given the following conditions on Unit 1:

The unit is at 12% RTP

Power increase is in progress DCS will maintain S/G Level Control for each S/G in the LO Power mode until a MAXIMUM Selected CF Flow of (1) is reached on each S/G.

With DCS in the LO Power mode, the CF Control Valves will start to OPEN when the CF Control Bypass Valves demand signal reaches a MINIMUM of (2) .

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

A. 1. 13%

2. 65%

B. 1. 13%

2. 75%

C. 1. 18%

2. 65%

D. 1. 18%

2. 75%

Page 19 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 20 (1 point)

Given the following conditions on Unit 1:

A Reactor trip has occurred

1A and 1B MDCA pumps are running

1A and 1B MDCA pump Discharge Flow Control valves are in MANUAL controlling S/G NR levels at program

1) If 1B MDCA pump Discharge Flow Control valves are closed, minimum flow protection will be provided by __ __ .

2) The 1B MDCA pump recirculation flow path will be to the __ __ .

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

A. 1. recirculation orifices

2. Upper Surge Tank B. 1. recirculation orifices

2. Auxiliary Feedwater Storage Tank (CAST)

C. 1. an automatic recirculation control valve

2. Upper Surge Tank D. 1. an automatic recirculation control valve

2. Auxiliary Feedwater Storage Tank (CAST)

Page 20 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 21 (1 point)

Given the following conditions on Unit 1:

1ETA Normal incoming breaker has opened

1A D/G started and loaded

While monitoring D/G parameters, the crew notes that D/G 1A VOLTS is at 4000 V When D/G 1A voltage is adjusted to NORMAL, how will 1A D/G Amps AND Power Factor indications respond to this adjustment?

AMPS Power Factor A. decrease more lagging B. decrease stay the same C. increase more lagging D. increase stay the same Page 21 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 22 (1 point)

Given the following conditions on Unit 2:

A Loss of Offsite Power has occurred

2B D/G started but subsequently tripped on overspeed

60 seconds have passed since the Loss of Offsite Power occurred Based on the conditions above,

1) 125 VDC Power Panel Board 2EVDD will be energized from .

2) this can be verified by checking control power available to 4160V pumps powered from .

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

A. 1. Battery EVCD

2. 2ETA B. 1. Battery EVCD

2. 2ETB C. 1. Standby Charger EVCS

2. 2ETA D. 1. Standby Charger EVCS

2. 2ETB Page 22 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 23 (1 point)

Given the following conditions:

Inverter KXB has experienced an overcurrent condition Based on the conditions above,

1) an indication used to determine that the backup power supply has been aligned is the light LIT.

2) when Inverter KXB overcurrent condition clears, the normal power supply be automatically realigned.

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

A. 1. In Sync

2. will NOT B. 1. In Sync

2. will C. 1. Alternate Source Supplying Load

2. will NOT D. 1. Alternate Source Supplying Load

2. will Page 23 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 24 (1 point)

Given the following initial conditions on Unit 1:

A switchyard transient causes a loss of offsite power on Unit 1

1A D/G starts and trips on overspeed

1B D/G starts

D/G Sequencers have not been reset Based on the conditions above, (1) of AP-07 (LOSS OF ELECTRICAL POWER) will be entered.

When desired, the 1B D/G (2) be secured from the control room.

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

PROCEDURE LEGEND:

AP-07, Case I (LOSS OF NORMAL POWER TO BOTH 1ETA AND 1ETB)

AP-07, Case II (LOSS OF NORMAL POWER TO EITHER 1ETA OR 1ETB)

A. 1. Case I

2. can B. 1. Case I

2. can NOT C. 1. Case II

2. can D. 1. Case II

2. can NOT Page 24 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 25 (1 point)

While performing the daily surveillance checks on 1EMF-33 (CONDENSER AIR EJECTOR EXHAUST), it is determined that the OPERATE light is OFF.

Which ONE (1) of the following actions is required in accordance with PT/1/A/4600/003 B (Daily Surveillance Items)?

COMPONENT LEGEND:

1EMF-36L (UNIT VENT GAS MONITOR)

A. Verify operability of 1EMF-36L.

B. Perform a source check of 1EMF-33.

C. Depress CLR (Clear) on the 1EMF-33 touch controls.

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

Page 25 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 26 (1 point)

Given the following initial conditions on Unit 1:

The Unit is at 100% RTP

B Train components in service Subsequently,

The 1B RN pump trips on overcurrent

The crew implements AP-20 (LOSS OF RN), and places the 1A RN pump in service

The remaining B Train components are still in operation

The BOP operator positions the manual loader for 1RN-190B (RN TO B KC HX CONTROL) to 10% open

The OATC, monitoring the OAC graphic for RN, notes 1RN-190B is indicating full open Which ONE (1) of the following identifies the reason for 1RN-190B indicating full open?

A. The manual loader is bypassed when the 1B RN pump breaker is open.

B. 1RN-190B is interlocked to open when the 1B RN pump breaker opens.

C. Minimum flow requirements for the 1B RN Pump are not met.

D. Minimum flow requirements for the 1A RN Pump are not met.

Page 26 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 27 (1 point)

Regarding the operation of 1VI-820 (VI TO VS SUPPLY VALVE),

1) the valve will automatically close if header pressure decreases to less than 90 PSIG.

2) if the 1VI-820 control switch is inadvertently left in the OPEN position, the valve close on decreasing pressure.

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

A. 1. VI

2. will NOT B. 1. VS

2. will NOT C. 1. VI

2. will D. 1. VS

2. will Page 27 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 28 (1 point)

In accordance with Tech. Spec. 3.6.5 (CONTAINMENT AIR TEMPERATURE),

Containment average temperature may be reduced to a MINIMUM of (1) in MODE(s) (2) .

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

A. 1. 60°F

2. 4 ONLY B. 1. 60°F

2. 2, 3 and 4 C. 1. 75°F

2. 4 ONLY D. 1. 75°F

2. 2, 3 and 4 Page 28 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 29 (1 point)

Given the following initial conditions on Unit 2:

Unit is stable at 25% RTP

Control Rods are in MANUAL Subsequently:

2D NCP trips on overcurrent Based on the conditions above,

1) an automatic reactor trip occur.

2) when steady-state conditions are achieved, in the UNAFFECTED loops will be .

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

A. 1. will NOT

2. higher B. 1. will NOT

2. lower C. 1. will

2. higher D. 1. will

2. lower Page 29 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 30 (1 point)

Given the following initial conditions on Unit 2:

A reactor startup is being performed per OP/2/A/6100/003 (CONTROLLING PROCEDURE FOR UNIT OPERATION)

Reactor power has increased into the IR and is currently at 5X10-6 % (IR)

Subsequently,

IR N-36 detector fails low Indication on Source Range N-32 (1) affected by the detector failure.

Based on the conditions above, per Tech Spec 3.3.1 (RTS INSTRUMENTATION), the power increase (2) .

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

REFERENCE PROVIDED A. 1. is

2. can continue B. 1. is

2. must be suspended C. 1. is NOT

2. can continue D. 1. is NOT

2. must be suspended Page 30 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 31 (1 point)

Given the following conditions on Unit 1:

The unit is stable at 45% RTP

Turbine Inlet Pressure is 400 PSIG Which ONE (1) of the following is the MINIMUM condition that would require entry into AP-03 (LOAD REJECTION)?

A. Buslines 1A AND 1B DEENERGIZE B. Busline 1A ONLY DEENERGIZES C. CF Pumps 1A AND 1B TRIP D. CF Pump 1A ONLY TRIPs Page 31 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 32 (1 point)

Given the following conditions on Unit 1:

A SGTR has occurred on 1A S/G

The crew has implemented E-3 (STEAM GENERATOR TUBE RUPTURE)

The OATC is performing the initial cooldown

1) Based on the conditions above, when NC system Tavg decreases to less than a MAXIMUM of , steam dumping will be blocked.

2) If a loss of vital bus occurs during the cooldown, all steam dump valves will CLOSE.

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

A. 1. 553°F

2. EVDB B. 1. 553°F

2. EVDA C. 1. 551°F

2. EVDB D. 1. 551°F

2. EVDA Page 32 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 33 (1 point)

Given the following conditions on Unit 1:

Makeup to the Spent Fuel Pool (SFP) is required

Chemistry sample results indicate SFP boron concentration at 2750 ppm In accordance with OP/1/A/6200/005 (SPENT FUEL COOLING SYSTEM) and based on the chemistry results above, (1) will be used for makeup to the SFP.

Assured makeup to the SFP is provided by the (2) system.

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

A. 1. YM

2. RN B. 1. YM

2. RF/RY C. 1. the FWST

2. RN D. 1. the FWST

2. RF/RY Page 33 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 34 (1 point)

Given the following conditions on Unit 1:

Unit 1 refueling is in progress

A fuel assembly is in the Reactor Building Manipulator Crane mast Subsequently, the following alarms are received:

1AD-13, B/6 (INCORE INSTRUMENT ROOM SUMP HI LEVEL)

1RAD-3, D/1 (1EMF 16 CONTAINMENT REFUELING BRIDGE)

Based on the conditions above,

1) the Tech Spec MINIMUM required refueling cavity water level is feet above the top of the reactor vessel flange.

2) the crew will implement to mitigate this event.

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

PROCEDURE LEGEND:

AP-25 (SPENT FUEL DAMAGE)

AP-40 (LOSS OF REFUELING CAVITY LEVEL)

A. 1. 23

2. AP-25 B. 1. 23

2. AP-40 C. 1. 33

2. AP-25 D. 1. 33

2. AP-40 Page 34 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 35 (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

While performing the RCCA movement test, Control Rod H-8 slips into the core to 200 steps withdrawn

All other Control Bank D control rods are at 216 steps withdrawn as indicated on DRPI and step demand counters

The crew is performing AP-14 (CONTROL ROD MALFUNCTION)

Based on the conditions above,

1) the MAXIMUM time allowed to restore Control Rod H-8 to within limits per Tech. Spec. 3.1.4 (ROD GROUP ALIGNMENT LIMITS) is .

2) in accordance with AP-14, the lift coil disconnect switches, located in the Rod Disconnect Panel, on will be placed in the disconnect position for all rods except H-8 when initially attempting to withdraw Control Rod H-8.

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

2. 1MC-5 C. 1. 30 minutes

2. Power Cabinet 2BD D. 1. 30 minutes

2. 1MC-5 Page 35 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 36 (1 point)

Given the following initial conditions on Unit 2:

Unit is in Mode 6

Fuel loading in progress Subsequently,

2EMF-39(L) (CONTAINMENT GAS-LO RANGE) Trip 2 alarm is received

2EMF-3 (CONTAINMENT REFUELING BRIDGE) Trip 2 alarm is received Based on the conditions above,

1) the Containment Evacuation alarm automatically actuate.

2) VP be automatically secured.

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

A. 1. will

2. will B. 1. will

2. will NOT C. 1. will NOT

2. will D. 1. will NOT

2. will NOT Page 36 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 37 (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

All Pressurizer heaters are energized in MANUAL

The SLIM for 1NV-238 (CHARGING FLOW CONTROL) has been placed in MANUAL due to a malfunction of the Pressurizer Level Master Controller

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

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

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

A. 1. INCREASING

2. OFF B. 1. INCREASING

2. ON C. 1. DECREASING

2. OFF D. 1. DECREASING

2. ON Page 37 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 38 (1 point)

Given the following conditions on Unit 1:

A Large Break LOCA has occurred

Subcooling based on Core Exit Thermocouples (CETs) indicates negative

(-) 4°F on the Inadequate Core Cooling Monitor (ICCM)

Based on the conditions above, ICCM indication of Subcooling based CETs (1) be displayed in reverse video.

Subsequently, if ONE Core Exit Thermocouple in Quadrant II fails LOW, indicated Subcooling on the ICCM will (2) .

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

A. 1. will

2. become less negative B. 1. will NOT

2. become less negative C. 1. will

2. NOT be affected D. 1. will NOT

2. NOT be affected Page 38 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 39 (1 point)

Given the following sequence of events on Unit 1:

0210 - reactor tripped due to a LOCA

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

0330 - crew enters ECA-1.1, (Loss of Emergency Coolant Recirc)

0350 - The crew is at step 18.b of ECA-1.1 Current conditions at time 0350:

1A NI pump is running, indicating 145 GPM

1B NI pump is running, indicating 185 GPM

Both NV pumps are running, indicating 340 GPM (Consider that the NV pumps have equal capacity)

Subcooling is +35°F Based on the conditions above, at time 0350:

1) the MINIMUM flow from the ECCS pumps which will match the decay heat removal requirements of ECA-1.1 is .

AND

2) to meet the ECCS requirements of ECA-1.1, the crew will .

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

REFERENCE PROVIDED A. 1. 310 GPM

2. stop both NI pumps B. 1. 310 GPM

2. stop the 1B NI pump AND one NV pump C. 1. 330 GPM

2. stop both NV pumps D. 1. 330 GPM

2. stop the 1A NI pump AND one NV pump Page 39 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 40 (1 point)

Given the following conditions on Unit 2:

A Small Break LOCA results in a Reactor Trip and Safety Injection

The crew has implemented E-1 (LOSS OF REACTOR OR SECONDARY COOLANT)

Subcooling is -2°F

Pressurizer level is 2%

Containment pressure is 2.5 PSIG and STABLE

CETs are 650°F and slowly increasing In accordance with E-1, the NCPs should (1) to (2) .

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

A. 1. be stopped

2. minimize NC system inventory loss B. 1. remain running

2. provide forced cooling flow through the core C. 1. be stopped

2. prevent pump damage due to loss of support systems D. 1. remain running

2. aid in refilling the pressurizer to satisfy SI termination criteria Page 40 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 41 (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

The following trends are observed on the 1A NCP:

Time 0200 0205 0210 0215 Pump #1 Seal D/P (PSID) 215 210 205 195 Lower pump bearing temp (°F) 221 224 228 231

1 seal outlet temp (°F) 222 237 246 253 Motor winding temp (°F) 303 310 316 323 At what time is 1A NCP trip criteria FIRST exceeded?

A. 0200 B. 0205 C. 0210 D. 0215 Page 41 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 42 (1 point)

In accordance with AP-12 (LOSS OF LETDOWN, CHARGING, or SEAL INJECTION),

After stabilizing the plant, what is the proper order of the major mitigation actions?

A. Restore Letdown, Charging, and Seal Injection B. Restore Letdown, Seal Injection, and Charging C. Restore Charging, Seal Injection, and Letdown D. Restore Charging, Letdown, and Seal Injection Page 42 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 43 (1 point)

Given the following initial conditions on Unit 1:

Unit is in MODE 5

'A' Train of ND, KC and RN are in service

The standby KC train is NOT available to start

NC system temperature is being maintained at 140°F Subsequently,

1A2 KC pump trips on overcurrent In accordance with AP-21 (LOSS OF KC OR KC SYSTEM LEAKAGE), the action which would maintain or restore the NC system to its INITIAL temperature is to throttle (1) OR throttle (2) .

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

(ASSUME THE ACTIONS LISTED DO NOT RESULT IN EXCEEDING ANY FLOW OR TEMPERATURE LIMITATIONS)

COMPONENT LEGEND:

1ND-34 (1A & 1B ND HX BYPASS)

1NV-459 (U1 VARIABLE L/D ORIFICE OUTLET FLOW CONTROL)

1KC-149 (1A KF HX OUTLET FLOW)

1RN-89A (RN TO A KC HX CONTROL)

A. 1. CLOSED 1NV-459

2. OPEN 1RN-89A B. 1. CLOSED 1KC-149

2. OPEN 1ND-34 C. 1. OPEN 1ND-34

2. OPEN 1RN-89A D. 1. OPEN 1KC-149

2. CLOSED 1NV-459 Page 43 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 44 (1 point)

Given the following conditions on Unit 2:

KC Surge Tank level is lowering slowly

The crew has implemented AP-21 (LOSS OF KC OR KC SYSTEM LEAKAGE)

Based on the conditions above, a possible location of the KC system leakage is into the (1) heat exchanger.

The assured supply of makeup water to the KC Surge tank is (2) .

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

A. 1. Letdown

2. YM B. 1. Letdown

2. RN C. 1. Seal Water Return

2. YM D. 1. Seal Water Return

2. RN Page 44 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 45 (1 point)

Given the following initial conditions:

Both units have experienced a Loss of Offsite Power

BOTH Diesel VI compressors are NOT available

ECA-0.0 (LOSS OF ALL AC POWER) was implemented on Unit 1 and the crew has just transitioned to ECA-0.1 (LOSS OF ALL AC POWER RECOVERY WITHOUT S/I REQUIRED)

Current conditions:

NC Thots are STABLE

S/G pressures are STABLE at 725 PSIG

S/G levels are decreasing and approaching 11% NR

NC Tcolds are 490°F and STABLE

VI header pressure is 0 PSIG Based on the conditions above,

1) Natural Circulation flow been established.

2) in accordance with ECA-0.1, the Operators will .

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

REFERENCE PROVIDED A. 1. HAS

2. increase CA flow using flow controllers in the control room B. 1. HAS

2. increase CA flow by notifying AO to throttle CA valves locally C. 1. HAS NOT

2. increase dumping steam using SM PORV controller on main control board AND increase CA flow using flow controllers in the control room D. 1. HAS NOT

2. dispatch an operator to locally increase flow from the SM PORV AND increase CA flow by notifying AO to throttle CA valves locally Page 45 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 46 (1 point)

Given the following initial conditions on Unit 1:

Unit is in Mode 6

NC System WR level is at +2 inches and lowering

AP-19 (LOSS OF ND OR ND SYSTEM LEAKAGE) has been implemented

The CRS has decided to makeup to the NC system using gravity feed through 1ND-35 (UNIT 1 ND to FWST ISOL) and 1NI-173A (1A ND to A & B COLD LEGS CONT OUTSIDE ISOL)

In accordance with AP-19,

1) flow to the NC system will be established by throttling 1ND-35 .

2) ND pump operation is not allowed with 1ND-35 OPEN because will occur.

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

A. 1. from the Control Room

2. a loss of NC system inventory outside containment B. 1. from the Control Room

2. ND pump runout conditions C. 1. locally

2. a loss of NC system inventory outside containment D. 1. locally

2. ND pump runout conditions Page 46 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 47 (1 point)

Given the following initial conditions on Unit 1:

The unit is at 10% RTP

The turbine is rolling at 1800 RPM in preparation for a unit startup

Status lights on 1SI-3 indicate the following:

Subsequently,

A steam line break occurs upstream of the 1D S/G MSIV

1D S/G pressure is 700 PSIG

The status lights on 1SI-3 currently indicate the following:

Based on the indications above:

1) the Main Steam Isolation valves operated as required.

2) the Main Steam Isolation Bypass valves operated as required.

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

(ASSUME NO OPERATOR ACTIONS HAVE BEEN TAKEN)

A. 1. have

2. have B. 1. have

2. have NOT C. 1. have NOT

2. have D. 1. have NOT

2. have NOT Page 47 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 48 (1 point)

Given the following initial conditions on Unit 1:

The crew is performing a Unit Startup and Power increase

Unit is holding at 2% RTP per OP/1/A/6100/003 (POWER INCREASE)

1A CF pump is out of service for emergent repairs Subsequently,

1B CF pump trips on low lube oil pressure

The crew enters AP/1/A/5500/006 (S/G FEEDWATER MALFUNCTION)

1) In accordance with AP-06, what is the MAXIMUM power level allowed, above which, a manual reactor trip is required?

2) What is the basis for manually tripping the reactor above that power level?

A. 1. 5%

2. to prevent an inadvertent mode change B. 1. 5%

2. to ensure CA can maintain adequate S/G levels C. 1. 3%

2. to prevent an inadvertent mode change D. 1. 3%

2. to ensure CA can maintain adequate S/G levels Page 48 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 49 (1 point)

Given the following conditions on Unit 2:

The unit is at 100% RTP

A loss of power occurs on 2EKVA Which ONE (1) of the following indicates the Power Range Nuclear Instrument channels that are still operable and can be used for backup indication of reactor power?

A. N-41, N-42, N-43 B. N-41, N-43, N-44 C. N-41, N-42, N-44 D. N-42, N-43, N-44 Page 49 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 50 (1 point)

Given the following conditions on Unit 1:

The 125VDC/120VAC Auxiliary Control Power System is in normal alignment

The supply breaker from DCA to Static Inverter KXA trips open Based on the conditions above,

1) Bus KXA automatically swap to its alternate power source.

2) the crew can verify power has been restored to KXA by observing that Which ONE (1) of the following completes the statements above?

COMPONENT LEGEND:

0RN-10AC (TRAIN 1B & 2B LLI SUPPLY)

A. 1. will

2. NC pump vibration monitors are IN SERVICE B. 1. will

2. the indicating light (control power) to 0RN-10AC is LIT C. 1. will NOT

2. the NC pump vibration monitors are IN SERVICE D. 1. will NOT

2. the indicating light (control power) to 0RN-10AC is LIT Page 50 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 51 (1 point)

Given the following initial conditions on Unit 1:

The unit is at 100% RTP

Both trains of KC and RN are in service Subsequently,

1A RN pump TRIPS

A Blackout occurs on 2ETB Based on the conditions above, the 1A KC HX (1) have cooling water because the RN essential headers (2) . (Assuming no operator actions)

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

A. 1. does

2. are always cross-connected B. 1. does

2. automatically cross-connected when the 1A RN pump tripped C. 1. does NOT

2. are always separated D. 1. does NOT

2. on both units automatically separate on any Blackout on either unit Page 51 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 52 (1 point)

Given the following plant conditions:

Both units are operating at 100% RTP

An instrument air system leak develops in the Unit 1 Turbine Building The following indications are observed in the Control Room:

Based on the indications above, the Diesel VI Compressors (1) receive an auto start signal .

If an auto start signal is received, the Diesel VI compressors (2) start AND load if the START/WARM-UP/RUN switch is selected to the WARM-UP position.

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

A. 1. will

2. will NOT B. 1. will

2. will C. 1. will NOT

2. will NOT D. 1. will NOT

2. will Page 52 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 53 (1 point)

Given the following conditions on Unit 1:

Turbine Load is 900 MWe

Generator Hydrogen Pressure is 60 PSIG

Generator Voltage is 22.8 KV According to the Main Generator Capability Curve the accepable range of reactive load is .

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

REFERENCE PROVIDED A. 860 MVAR (Lagging) to -640 MVAR (Leading)

B. 840 MVAR (Lagging) to -710 MVAR (Leading)

C. 710 MVAR (Lagging) to -560 MVAR (Leading)

D. 690 MVAR (Lagging) to -630 MVAR (Leading)

Page 53 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 54 (1 point)

Given the following conditions on Unit 2:

The crew has implemented ECA-1.2 (LOCA OUTSIDE CONTAINMENT)

U2 FWST level is slowly lowering

NC system pressure is 1600 PSIG and slowly lowering In accordance with ECA-1.2,

1) the crew will FIRST stop and isolate the pumps from the FWST.

2) an NC system depressurization and cooldown at will be required.

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

A. 1. NI

2. the maximum rate B. 1. NI

2. 100°F/hr C. 1. ND

2. the maximum rate D. 1. ND

2. 100°F/hr Page 54 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 55 (1 point)

Given the following initial conditions on Unit 1:

The crew has implemented FR-H.1 (RESPOND TO A LOSS OF SECONDARY HEAT SINK)

Feed and Bleed criteria is met

1) Which Cold Leg Accumulators (CLAs) provide backup motive force to open the PZR PORVs?

2) To establish adequate heat removal during Feed and Bleed, what is the MINIMUM number of PZR PORVs that must be opened? (Consider PORVs ONLY)

A. 1. A and B

2. 1 B. 1. A and B

2. 2 C. 1. C and D

2. 1 D. 1. C and D

2. 2 Page 55 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 56 (1 point)

Given the following conditions on Unit 1:

A Large Break LOCA has occurred inside Containment

A and B ND pumps are not available

The Control room crew has implemented ECA-1.1 (LOSS OF EMERGENCY COOLANT RECIRC) but, NO actions have been taken

Containment pressure is 8 PSIG and slowly rising

FWST level is 105 inches and lowering When the FWST Level LO setpoint is reached, 1NI-184B (1B ND PUMP SUCTION FROM CONT SUMP ISOL) AND 1NI-185A (1A ND PUMP SUCTIONFROM CONT SUMP ISOL) (1) automatically OPEN.

Per ECA-1.1 Foldout Page, when FWST level decreases to less than a MAXIMUM of (2) inches ALL ECCS pumps must be secured.

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

A. 1. will

2. 20 B. 1. will NOT

2. 20 C. 1. will

2. 95 D. 1. will NOT

2. 95 Page 56 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 57 (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

Control Rod P-8 (Control Bank C, Group 1) drops fully into the core due to a blown stationary gripper fuse

The crew implements AP-14 (CONTROL ROD MALFUNCTION)

Subsequently,

The blown fuse has been replaced and all requirements have been met for the operating crew to recover Control Rod P-8

As Control Rod P-8 begins to move, annunciator 1AD-2 / A10 (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. 1AC B. 2AC C. 1BD D. 2BD Page 57 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 58 (1 point)

Based on the indications above, the entry conditions of FR-H.2 (RESPONSE TO STEAM GENERATOR OVERPRESSURE) (1) met.

FR-H.2 is designed to address a failure of (2) .

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

A. 1. are

2. a S/G PORV ONLY B. 1. are NOT

2. a S/G PORV ONLY C. 1. are

2. a S/G PORV AND the Main Steam Line Code Safety valves D. 1. are NOT

2. a S/G PORV AND the Main Steam Line Code Safety valves Page 58 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 59 (1 point)

Given the following conditions on Unit 2:

The crew has implemented AP-10 (NC SYSTEM LEAKAGE), Case 1 (S/G TUBE LEAKAGE)

Pressurizer level has been stabilized

Letdown flow is 45 GPM

Charging flow is 110 GPM Based on the conditions above, the estimated leak rate is (1) GPM.

Per OP/1/A/6200/001 (NV System), letdown flow through Normal Letdown shall not exceed a MAXIMUM of (2) GPM.

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

A. 1. 65

2. 120 B. 1. 65

2. 185 C. 1. 53

2. 120 D. 1. 53

2. 185 Page 59 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 60 (1 point)

Given the following conditions on Unit 1:

Unit is at 85% RTP

Main condenser vacuum is 24.5" Hg and degrading at a rate of 0.5" Hg per minute

Crew has entered AP-23 (LOSS OF CONDENSER VACUUM)

Based on the conditions above, Control Interlock (C-9) will block the ability to dump steam to the condenser in a MINIMUM of (1) minutes.

The reason for the Main Turbine trip on loss of Condenser vacuum is to (2) .

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

A. 1. 3

2. prevent condenser damage due to over-pressurization B. 1. 3

2. minimize low pressure turbine blading damage due to low vacuum conditions C. 1. 9

2. prevent condenser damage due to over-pressurization D. 1. 9

2. minimize low pressure turbine blading damage due to low vacuum conditions Page 60 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 61 (1 point)

Given the following conditions on Unit 1:

A Ventilation Unit Condensate Drain Tank (VUCDT) release to the RC Discharge is in progress

A 1EMF-44(L) (CONTAINMENT VENTILATION DRAINS - LOW RANGE)

Trip 2 alarm is received Which ONE (1) of the following indicates the automatic response to the EMF alarm?

COMPONENT LEGEND:

1WP-35 (WMT/VUCDT to RC CNTRL)

1WL-320 (VUCDT RAD MONITOR OUTLET)

1WL-322B (CONT VENT DRN OTSD ISOL)

A. 1WP-35 ONLY CLOSES B. 1WL-320 AND 1WP-35 CLOSE C. 1WL-322B ONLY CLOSES D. 1WL-320 AND 1WL-322B CLOSE Page 61 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 62 (1 point)

Given the following conditions on Unit 2:

A Large Break LOCA has occurred

ES-1.3 (TRANSFER TO COLD LEG RECIRC) has been implemented

Containment pressure is 4 PSIG ES-1.3 directs the crew to start an NS pump if Containment pressure is greater than a MINIMUM of (1) PSIG.

The reason that ES-1.3 directs the crew to reset Safety Injection (SI) and the Sequencers prior to attempting to start an NS pump is that (2) .

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

A. 1. 3

2. the NS pumps are locked out until the Sequencers are reset B. 1. 3

2. the NS pump discharge valves cannot be opened unless SI is reset C. 1. 1

2. the NS pumps are locked out until the Sequencers are reset D. 1. 1

2. the NS pump discharge valves cannot be opened unless SI is reset Page 62 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 63 (1 point)

Given the following conditions on Unit 1:

A Loss of Off-Site Power (LOOP) has occurred

Due to multiple equipment failures, the crew has implemented FR-C.1 (RESPONSE TO INADEQUATE CORE COOLING)

"LOW PRESSURE STEAMLINE ISOL" has been blocked

Operators are preparing to depressurize intact steam generators to 190 PSIG Based on the conditions above,

1) the CRS will direct the operating crew to establish a cooldown rate.

2) the cooldown and depressurization will be performed using the .

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

A. 1. 100 °F/hour

2. steam dumps B. 1. 100 °F/hour

2. S/G PORVs C. 1. maximum

2. steam dumps D. 1. maximum

2. S/G PORVs Page 63 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 64 (1 point)

Given the following initial conditions on Unit 2:

A Small Break LOCA has occurred

The crew has entered ES-1.2 (POST LOCA COOLDOWN AND DEPRESSURIZATION) and began an NC system cooldown and depressurization Subsequently,

Annunciator 2AD-6 / A12 (PORV LO PRESS MODE NOT SELECTED) alarms For this alarm to be valid, NC system (1) ,.

AND the PORV OVERPRESS PROTECTION SELECT switch for 2NC-34A OR (2) must be in the NORM position.

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

COMPONENT LEGEND:

2NC-34A (U2 PZR PORV) 2NC-32B (U2 PZR PORV) 2NC-36B (U2 PZR PORV)

A. 1. temperature must be less than a setpoint of 320°F

2. 2NC-36B B. 1. pressure must be less than a setpoint of 380 PSIG

2. 2NC-36B C. 1. temperature must be less than a setpoint of 320°F

2. 2NC-32B D. 1. pressure must be less than a setpoint of 380 PSIG

2. 2NC-32B Page 64 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 65 (1 point)

Given the following on Unit 1:

A Large Break LOCA has occurred

Containment sump level is 7.5 feet and rising at a constant rate of 0.25 feet per minute

1) FR-Z.2 (RESPONSE TO CONTAINMENT FLOODING) entry conditions will be met in a MINIMUM of minutes.

2) Why is safe plant recovery not assured for a design-basis Large Break LOCA when Containment water level requires entry into FR Z.2?

A. 1. 24

2. Operation of critical ECCS components needed for safe recovery is endangered by submersion.

B. 1. 24

2. Operation of the hydrogen skimmer system is compromised by the suction line becoming submerged.

C. 1. 20

2. Operation of critical ECCS components needed for safe recovery is endangered by submersion.

D. 1. 20

2. Operation of the hydrogen skimmer system is compromised by the suction line becoming submerged.

Page 65 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 66 (1 point)

Given the following initial conditions on Unit 1:

Unit is at 30% RTP and STABLE

Control rods are in manual Subsequently,

1ETA normal incoming breaker trips OPEN

The 1A D/G starts and is carrying the 1ETA bus

The RO reports that reactor power has increased to 34% and is now STABLE Per AD-OP-ALL-0203 (REACTIVITY MANAGEMENT), what actions (if any) will the crew take in response to the power increase?

A. Move control rods as necessary to restore Tave = Tref.

B. No actions are required since power is less than 100% RTP.

C. Borate to establish power at or below the pre-transient power level.

D. Reduce turbine load to establish power at or below the pre-transient power level.

Page 66 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 67 (1 point)

Given the following conditions on Unit 1:

The unit is in Mode 6

"A" ND Train is in operation

"B" ND Train is available Which ONE (1) of the following conditions would prevent commencing fuel movement?

(Consider each individually)

A. The reactor has been subcritical for 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months .

B. The Equipment Hatch is closed with 2 bolts fastened.

C. The Refueling Cavity level is lowered to 370 on 1NCP-5990 (NC WR LEVEL).

D. MCB Annunciator 1AD10/F-1 (UPPER CONT AIRLOCK RX DOOR OPEN),

alarms.

Page 67 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 68 (1 point)

Given the following plant conditions:

The Main Control Room has been evacuated

AP-17 (LOSS OF CONTROL ROOM) has been implemented

Both Auxiliary Shutdown Panels (ASP) are manned The Operator at the Unit 1 ASP believes that the following indications at the Unit 1 ASP are not indicating correctly:

1. NC System Cold Leg Temperature

2. NC System Hot Leg Temperature

3. NC System WR Pressure

4. NC System Letdown Flow Which ONE (1) of the following indicates the parameters listed above that can be verified using redundant indications at the Safe Shutdown Facility (SSF)?

A. 1&4 B. 2&4 C. 1&3 D. 2&3 Page 68 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 69 (1 point)

Regarding Maintenance Rule Assessments,

1) NSD-403 (SHUTDOWN RISK MANAGEMENT) is the official tool for performing risk assessments in and below.

2) when using the Electronic Risk Assessment Tool (ERAT), the color .

is associated with a key safety function being in condition that is "REDUCED but still acceptable".

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

A. 1. MODE 3

2. ORANGE B. 1. MODE 4

2. ORANGE C. 1. MODE 3

2. YELLOW D. 1. MODE 4

2. YELLOW Page 69 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 70 (1 point)

Given the following conditions on Unit 2:

NC system temperature is 195°F

NC system pressure is 320 PSIG Based on the conditions above, the FWST (1) required to be OPERABLE per Technical Specification 3.5.4 (Refueling Water Storage Tank).

When the FWST is required to be operable, and level is less than the borated water volume required by Surveillance Requirement 3.5.4.2, (2) are required.

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

A. 1. is

2. immediate actions to restore the FWST to OPERABLE status B. 1. is

2. actions to restore the FWST to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months C. 1. is NOT

2. immediate actions to restore the FWST to OPERABLE status D. 1. is NOT

2. actions to restore the FWST to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Page 70 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 71 (1 point)

An Operator needs to access an area with a general area radiation dose rate of 1100 mREM/hr to hang a clearance tag.

In accordance with AD-RP-ALL-2017 (ACCESS CONTROLS FOR HIGH, LOCKED HIGH, AND VERY HIGH RADIATION AREAS),

1) the correct radiation posting for this area is a .

2) the Radiation Protection requirements for entry are .

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

A. 1. High Radiation Area

2. continuous RP coverage B. 1. High Radiation Area

2. a documented RP briefing ONLY C. 1. Locked High Radiation Area

2. continuous RP coverage D. 1. Locked High Radiation Area

2. a documented RP briefing ONLY Page 71 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 72 (1 point)

Given the following conditions on Unit 1:

Mode 4 valve checklist PT is being performed

The PT calls for independent verification of a single valve located in a room with a general area dose rate of 110 mREM/hr

Estimated time to independently verify the valve's position is 5 minutes 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. can NOT

2. the general area dose rate is less than 500 mREM/hr B. 1. can NOT

2. the radiation exposure for a single verification is within the allowable limit C. 1. can

2. the general area dose rate is greater than 100 mREM/hr D. 1. can

2. the radiation exposure for a single verification exceeds the allowable limit Page 72 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 73 (1 point)

Given the following initial conditions on Unit 1:

"B" Train equipment is in service Subsequently,

The 1B RN pump amps are swinging

The following annunciators alarm:

o 1AD-12 / A-4 (B RN PMP DISCHARGE LO PRESS) o 1AD-12 / C-4 (B RN PUMP SUCTION LO PRESS)

The crew implements AP-20 (LOSS OF RN)

PROCEDURE LEGEND:

AP-20, CASE I (LOSS OF OPERATING RN TRAIN)

AP-20, CASE II (LOSS OF LOW LEVEL OR RC SUPPLY CROSSOVER)

Based on the conditions above, the crew will enter AP-20, (1) .

In accordance with the AP-20 mitigating strategy for this event, the crew (2) ,

swap the RN pump suction to the SNSWP?

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

A. 1. Case I

2. will B. 1. Case I

2. will NOT C. 1. Case II

2. will D. 1. Case II

2. will NOT Page 73 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 74 (1 point)

Given the following plant conditions:

Fire Brigade has extinguished a fire in the Unit 2 Turbine Building

A Main Fire Pump is out-of-service

1A and 1B Jockey Pumps are OFF

B Main Fire Pump is running

C Main Fire Pump is OFF The automatic start setpoint for the "B" Main Fire Pump on decreasing fire header pressure is (1) PSIG.

In accordance with OP/1/A/6400/002A (FIRE PROTECTION SYSTEM), the sequence for returning the Fire Protection system to normal alignment is to (2) .

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

A. 1. 73

2. place the Jockey Pump to be started in MAN, START the Jockey Pump selected to MAN, and stop the B Main Fire Pump.

B. 1. 73

2. stop the B Main Fire Pump, place the Jockey Pump to be started in MAN, and START the Jockey Pump selected to MAN.

C. 1. 78

2. place the Jockey Pump to be started in MAN, START the Jockey Pump selected to MAN, and stop the B Main Fire Pump.

D. 1. 78

2. stop the B Main Fire Pump, place the Jockey Pump to be started in MAN, and START the Jockey Pump selected to MAN.

Page 74 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 75 (1 point)

Given the following conditions on Unit 1:

The unit is in MODE 4

"A" Train of ND is in service

Annunciator 1AD-9 / A1 (1ND-2A OPEN AND NC HI PRESS) has just come into alarm

NC WR pressure is indicating 460 PSIG Based on the conditions above,

1) 1ND-1B AUTO CLOSE.

2) the redundant indication which would be used to verify that this annunciator is valid is .

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

COMPONENT LEGEND:

1ND-2A (C HL SUCTION TO ND ISOLATION) 1ND-1B (C HL SUCTION TO ND ISOLATION)

A. 1. will

2. CF&E sump level rising B. 1. will

2. PRT level rising C. 1. will NOT

2. CF&E sump level rising D. 1. will NOT

2. PRT level rising Page 75 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 76 (1 point)

Given the following initial conditions on Unit 1:

The unit is increasing power following a Refueling Outage

At 42% reactor power, the P-8 permissive bistable fails "AS IS" Subsequently,

Reactor power is currently 52%

1A NCP trips Based on the conditions above, an automatic Reactor trip signal (1) be generated.

If subsequent conditions require implementation of FR-S.1 (RESPONSE TO NUCLEAR GENERATION / ATWS), the crew will transition from FR-S.1 to E-0 (REACTOR TRIP OR SAFETY INJECTION) (2) .

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

A. 1. will

2. after FR-S.1 is performed to completion B. 1. will NOT

2. after FR-S.1 is performed to completion C. 1. will

2. immediately upon a successful Reactor trip D. 1. will NOT

2. immediately upon a successful Reactor trip Page 76 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 77 (1 point)

Given the following conditions on Unit 2:

The unit is in MODE 3

A cooldown is in progress to comply with TS 3.0.3

NC system pressure is 1980 PSIG

NC system temperature is 500°F

An inadvertent actuation of SI Train B occurs Based on the conditions above,

1) Ice Bed temperatures will .

2) the optimal procedure flowpath to mitigate this event is to implement .

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

PROCEDURE LEGEND:

E-0 (REACTOR TRIP OR SAFETY INJECTION)

ES-1.1 (SI TERMINATION)

AP-35 (ECCS ACTUATION DURING PLANT SHUTDOWN)

A. 1. increase

2. AP-35 B. 1. remain the same

2. AP-35 C. 1. increase

2. E-0 and then transition to ES-1.1 D. 1. remain the same

2. E-0 and then transition to ES-1.1 Page 77 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 78 (1 point)

Given the following conditions on Unit 1:

The unit is at 8% RTP preparing to roll the main turbine

M1A1276 (U1 CA Temp at Chk Vlv 1CA-37) alarms on the OAC Based on the conditions above, in accordance with OP/1/A/6250/002 (AUXILIARY FEEDWATER SYSTEM), the method that will FIRST be used to reduce the temperature at the check valve is to (1) .

In accordance with Tech Spec 3.7.5 (AFW SYSTEM), actions taken to reduce the temperature at the check valve (2) the TD CA pump to be declared INOPERABLE.

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

COMPONENT LEGEND:

1CA-37 (#1 TD CA TO S/G D) 1CA-36AB (U1 TD CA PUMP DISCH TO 1D S/G CONTROL) 1CA-38B (U1 TD CA PUMP DISCH TO 1D S/G ISOL)

REFERENCE PROVIDED A. 1. close 1CA-36AB and monitor temperature for 15 minutes

2. requires B. 1. close 1CA-36AB and monitor temperature for 15 minutes

2. does NOT require C. 1. close 1CA-38B and start the U1 TD CA pump aligned for recirculation to the UST

2. requires D. 1. close 1CA-38B and start the U1 TD CA pump aligned for recirculation to the UST

2. does NOT require Page 78 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 79 (1 point)

Given the following initial conditions on Unit 1:

Unit is in Mode 4 with a plant cooldown in progress

B Train in service Subsequently,

Containment Pressure begins rising

The SAFETY INJECTION ACTUATED status light on 1SI-18 is LIT

The crew implements AP-34 (SHUTDOWN LOCA)

The following indications are observed on 1SI-14:

Based on the conditions and indications above,

1) the will overheat due to loss of RN cooling.

2) the crew will be directed to to mitigate this event.

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

PROCEDURE LEGEND:

AP-10 (NC SYTEM LEAKAGE WITHIN THE CAPACITY OF BOTH NV PUMPS)

A. 1. NC pumps

2. GO TO AP-10 B. 1. running DG

2. GO TO AP-10 C. 1. NC Pumps

2. remain in AP-34 D. 1. running DG

2. remain in AP-34 Page 79 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 80 (1 point)

Given the following plant conditions:

Both units are at 100% RTP

A malfunction of the VI Air Dryers has resulted in rapidly decreasing VI Header pressures

Both units have implemented AP-22 (LOSS OF VI)

In accordance with AP-22,

1) what is the MAXIMUM VI Header pressure which requires implementation of Enclosure 7 (RN ALIGNMENT DURING LOSS OF VI EVENT)?

2) which of the following conditions will FIRST require the crew to initiate a manual reactor trip?

A. Pressurizer level begins INCREASING in an uncontrolled manner B. S/G levels begin DECREASING in an uncontrolled manner A. 1. 60 PSIG

2. A B. 1. 85 PSIG

2. A C. 1. 60 PSIG

2. B D. 1. 85 PSIG

2. B Page 80 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 81 (1 point)

Given the following initial conditions on Unit 2:

A unit load increase in on hold at 35% RTP

Control Bank D rod M-4 is at 160 steps by DRPI

Control Bank D Group Step Counters indicate 170 steps Subsequently,

I&E determines that rod M-4 will not move because the lift coil disconnect switch has failed The rod alignment limits of Tech Spec 3.1.4 (ROD GROUP ALIGNMENT LIMITS)

(1) met.

In accordance with Tech Spec 3.1.7 (ROD POSITION INDICATION) Bases, the basis for the operability of the Rod Position Indication system is to verify that the assumptions in the plant's safety analysis which are directly related to (2) .

distribution are being met.

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

A. 1. are

2. core power B. 1. are NOT

2. core power C. 1. are

2. fuel burnup D. 1. are NOT

2. fuel burnup Page 81 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 82 (1 point)

Given the following conditions on Unit 1:

Containment Pressure Channel 3 has failed low due to a failed power supply

The failed channel has NOT been removed from service by I&E Based on the conditions above, the current Containment Pressure channel logic for the remaining Containment Pressure channels which will cause a Safety Injection actuation is (1) .

In accordance with Tech Spec 3.3.2 (ESFAS INSTRUMENTATION) LCO actions, when the failed channel is removed from service, I&E will place the Containment Pressure Hi-Hi Bistable in (2) .

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

A. 1. 1/2

2. TRIP B. 1. 2/2

2. TRIP C. 1. 1/2

2. BYPASS D. 1. 2/2

2. BYPASS Page 82 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 83 (1 point)

Given the following conditions on Unit 2:

The unit is at 100% RTP

The 2A SM PORV is leaking

The 2A SM PORV Block valve has been CLOSED Based on the conditions above,

1) in accordance with Tech Spec 3.7.4 (SG PORVs) Basis, the 2A SM PORV is

2) Tech Spec 3.7.4 requires SM PORVs to be OPERABLE.

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

A. 1. OPERABLE

2. three B. 1. OPERABLE

2. two C. 1. INOPERABLE

2. three D. 1. INOPERABLE

2. two Page 83 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 84 (1 point)

Given the following initial conditions on Unit 1:

A Reactor startup is in progress

Shutdown Bank rods are fully withdrawn

Control Bank A is at 100 steps

All NCPs are in service Subsequently, the following indications are observed:

OAC Point M1A0698 (1D NC PUMP LOWER RADIAL BRG TMP) alarm

OAC Point M1A0744 (1D NC PUMP MOTOR UPPER BEARING TEMP) alarm

OAC Point M1A0720 (1D NC PUMP MOTOR LOWER BEARING TEMP) alarm

1D NC pump lower radial bearing temperature = 200°F and increasing slowly

1D NC pump motor upper bearing temperature = 200°F and increasing slowly

1D NC pump motor lower bearing temperature = 180°F and increasing slowly The crew has implemented AP-08 (REACTOR COOLANT PUMP MALFUNCTION)

Based on the conditions above,

1) the CRS will implement .

2) if stopping the 1D NC pump is required, the procedure flowpath will be to Which ONE (1) of the following completes the statements above?

PROCEDURE LEGEND:

AP-08 Case I (NC PUMP SEAL OR PUMP LOWER BEARING MALFUNCTION)

AP-08 Case II (NC PUMP MOTOR OR MOTOR BEARING MALFUNCTION)

E-0 (REACTOR TRIP OR SAFETY INJECTION)

A. 1. AP-08, Case I

2. stop the 1D NC pump and continue in AP-08 B. 1. AP-08, Case I

2. trip the reactor, stop 1D NC pump, and transition to E-0 C. 1. AP-08, Case II

2. stop the 1D NC pump and continue in AP-08 D. 1. AP-08, Case II

2. trip the reactor, stop 1D NC pump, and transition to E-0 Page 84 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 85 (1 point)

Given the following conditions on Unit 2:

The unit is at 100% RTP

A DCS malfunction causes the Selected Pressurizer Pressure 1 input to the Pressurizer Master Controller to fail HIGH

In accordance with AP-11 (PRESSURIZER PRESSURE ANOMALIES), the BOP has manually closed 2NC-34A (PZR PORV) and 2NC-27C and 29C (PRESSURIZER SPRAY VALVES)

The Pressurizer Pressure Master Controller is in MANUAL

1) In accordance with Tech Spec 3.4.11 (PRESSURIZER PORVs), in what MODES are the Pressurizer PORVs required to be OPERABLE?

2) In accordance with Tech Spec 3.4.11 Bases, is 2NC-34A OPERABLE?

A. 1. 1, 2, and 3 ONLY

2. No B. 1. 1, 2, 3, and 4

2. No C. 1. 1, 2, and 3 ONLY

2. Yes D. 1. 1, 2, 3, and 4

2. Yes Page 85 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 86 (1 point)

Given the following initial conditions on Unit 1:

The unit is at 30% RTP

NC pump 1C trips due to an error during I&E testing Subsequently,

A lockout occurs on 1A Busline due to a fault

The Reactor Trip breakers remain closed Based on the conditions above,

1) an ATWS in progress.

2) the crew will .

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

PROCEDURE LEGEND:

Technical Specification 3.4.4 (RCS LOOPS MODES 1 & 2)

REFERENCE PROVIDED A. 1. is

2. manually trip the turbine to conserve SG inventory B. 1. is

2. manually trip the turbine to generate a redundant reactor trip signal C. 1. is NOT

2. restart 1C NC pump within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to comply with TS 3.4.4 D. 1. is NOT

2. place the unit in MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to comply with TS 3.4.4 Page 86 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 87 (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

1EMF-33 (CONDENSER AIR EJECTOR EXHAUST) is INOPERABLE

The crew is performing PT/1/A/4150/001 B (REACTOR COOLANT LEAKAGE CALCULATION)

During the surveillance, S/G Primary-to-Secondary leakage was determined to be:

S/G Leakage (GPD) 1A 125 1B 50 1C 75 1D 40 Based on the conditions above,

1) in accordance with PT/1/A/4150/001 B, 1EMF 71-74 indications a valid method to evaluate whether the requirements of Technical Specification Surveillance SR 3.4.13.2 (Primary-to-Secondary Leakage) are met.

2) Primary-to-Secondary leakage within the limits of Technical Specification 3.4.13 (RCS OPERATIONAL LEAKAGE).

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

COMPONENT LEGEND:

1EMF-71 thru 74 (N16 LEAKAGE)

A. 1. are NOT

2. is B. 1. are NOT

2. is NOT C. 1. are

2. is D. 1. are

2. is NOT Page 87 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 88 (1 point)

In accordance with Tech Spec 3.6.6 (CONTAINMENT SPRAY SYSTEM) Bases:

1) the Containment Spray System is designed to work in conjunction with the Ice Condensers to limit peak Containment Pressure and peak Containment Temperature during a Design-Basis ,

AND

2) a Design-Basis LOCA will result in peak Containment .

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

A. 1. LOCA ONLY

2. pressure B. 1. Steam Line Break ONLY

2. temperature C. 1. LOCA OR Steam Line Break

2. temperature D. 1. LOCA OR Steam Line Break

2. pressure Page 88 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 89 (1 point)

Given the following sequence of events on Unit 1:

A LOCA has occurred

The crew has implemented ECA-1.1 (LOSS OF EMERGENCY COOLANT RECIRC)

Containment pressure is currently 3.2 PSIG In accordance with ECA-1.1, while attempting to establish recirculation flow the crew will cool the core by (1) .

While performing ECA-1.1, if a RED Path occurs on Core Cooling the crew (2) transition to FR-C.1 (RESPONSE TO INADEQUATE CORE COOLING).

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

A. 1. aligning the NC system for Feed and Bleed

2. will B. 1. aligning the NC system for Feed and Bleed

2. will NOT C. 1. dumping steam from intact Steam Generators

2. will D. 1. dumping steam from intact Steam Generators

2. will NOT Page 89 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 90 (1 point)

Given the following conditions on Unit 1:

The unit is at 60% RTP

A unit load increase is on hold due to a potentially stuck Control Bank D rod

The incore thermocouple map indicates the following:

1. Based on the indications above, which Control Bank D rod is stuck?

2. What surveillances (if any) are required per Technical Specification 3.1.4 (ROD GROUP ALIGNMENT LIMITS) to allow continued power operation in MODE 1?

A. 1. Rod D-12

2. RCCA Movement Test B. 1. Rod D-12

2. FNH(X,Y) and FQ(X,Y,Z)

C. 1. Rod M-4

2. RCCA Movement Test D. 1. Rod M-4

2. FNH(X,Y) and FQ(X,Y,Z)

Page 90 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 91 (1 point)

Given the following conditions on Unit 2:

The unit is currently in MODE 5

Source Range Nuclear Instrument count rates begin increasing

The CRS suspects an inadvertent dilution is in progress

Boric Acid Tank (BAT) temperature is 68°F

The crew implements AP-038 (EMERGENCY BORATION AND RESPONSE TO INADVERTENT DILUTION)

2NV-265B (U2 NV PUMP BORIC ACID SUP ISOL) will NOT open In accordance with AP-038, the crew will FIRST attempt to establish emergency boration using .

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

COMPONENT LEGEND:

2NV-269 (UNIT 2 NV PUMP BORIC ACID SUPPLY ISOL (EMERGENCY BORATION VALVE))

2NV-267A (BORIC ACID TO BLENDER CONTROL)

A. NV from the BAT after locally aligning 2NV-269 and 2NV-267 because it is the preferred flow path B. NI from the FWST because it is the preferred flowpath with and INOPERABLE BAT C. NV from the FWST because it is the preferred flowpath D. NV from the FWST because the BAT is INOPERABLE Page 91 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 92 (1 point)

Given following conditions on Unit 1:

0800 A Reactor trip occurred from 100% RTP due to a large steam break 1045 The steam break has been isolated and the unit stabilized with the following conditions:

o NC system temperature = 240°F o NC system pressure = 1000 PSIG Based on the conditions above,

1) as part of the subsequent recovery actions, the crew perform an NC system soak.

2) after NC system pressure is reduced, the next cooldown performed will be at a MAXIMUM rate of per hour.

Which ONE (1) of the following completes the statements above? (CONSIDER EACH QUESTION SEPARATELY)

A. 1. will

2. 50°F B. 1. will

2. 100°F C. 1. will NOT 2 50°F D. 1. will NOT

2. 100°F Page 92 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 93 (1 point)

Given the following conditions on Unit 1:

Chemistry has confirmed two leaking fuel rods

A Large Break LOCA occurs

ES-1.2 (POST LOCA COOLDOWN AND DEPRESSURIZATION) has been implemented

All Red and Orange Paths have been addressed

1EMF-51A = 39 R/Hr

Pressurizer level = 20% and STABLE

Reactor Vessel Upper Range Level = 98% and STABLE

The CRS is currently considering implementing Yellow Path procedures Based on the conditions above, the CRS will direct the crew to .

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

PROCEDURE LEGEND:

FR-I.3 (RESPONSE TO VOIDS IN THE REACTOR VESSEL)

FR-Z.3 (RESPONSE TO HIGH CONTAINMENT RADIATION LEVEL)

A. transition from ES-1.2 to FR-I.3 B. remain in ES-1.2 and implement FR-I.3 concurrently C. transition from ES-1.2 to FR-Z.3 D. remain in ES-1.2 and implement FR-Z.3 concurrently Page 93 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 94 (1 point)

Given the following conditions on Unit 1:

The unit is in MODE 6 with core alterations in progress

It is determined that a Fuel Handling interlock must be bypassed to insert the next fuel assembly into the core

The interlock which must be bypassed is NOT specified in a procedure In accordance with AD-NS-ALL-1001 (CONDUCT OF REFUELING), which individual(s) listed below is/are allowed to approve bypassing the interlock?

1. Refueling SRO

2. Reactor Engineering

3. Shift Manager - Operations A. 1 ONLY B. 1 AND 2 ONLY C. 1 AND 3 ONLY D. 1, 2, AND 3 Page 94 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 95 (1 point)

Regarding Tech Spec 3.7.12 (FUEL HANDLING VENTILATION EXHAUST SYSTEM (FHVES) and its Bases,

1) 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) the design basis assumes that a total system failure could result in the atmospheric release from the fuel handling building exceeding the 10 CFR limits at the site exclusion area boundary in the event of a fuel handling accident.

PROCEDURE LEGEND:

10 CFR PART 20 (STANDARDS FOR PROTECTION AGAINST RADIATION) 10 CFR PART 100 (REACTOR SITE CRITERIA)

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

A. 1. is

2. 20 B. 1. is

2. 100 C. 1. is NOT

2. 20 D. 1. is NOT

2. 100 Page 95 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 96 (1 point)

Given the following conditions on Unit 1:

The 1A Annulus Ventilation (VE) train has been placed in service for a test run after fan lubrication

During the test run, Annunciator 0AD-12 / F-2 (1A VE Filter Hi Temp) alarms due to a malfunction of the filter heater Based on the conditions above, it is expected that 1A VE heaters (1) .

automatically tripped.

In accordance with Technical Specification 3.6.10 (Annulus Ventilation System (AVS))

Bases, after the 1A VE heaters are declared INOPERABLE and tagged for repairs, the 1A Annulus Ventilation train is (2) .

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

A. 1. have

2. OPERABLE B. 1. have NOT

2. OPERABLE C. 1. have

2. INOPERABLE D. 1. have NOT

2. INOPERABLE Page 96 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 97 (1 point)

Given the following conditions on Unit 1:

The unit startup is in progress

A site level Operating Procedure (OP) is to be performed on back-shift

The OATC identifies that a technical change to the procedure is needed because it cannot be performed as written

The change is to be processed as a TEMPORARY change since Procedure Group support is NOT available In accordance with AD-DC-ALL-0201 (DEVELOPMENT AND MAINTENANCE OF CONTROLLED PROCEDURE MANUAL PROCEDURES),

1) the lowest level of approval for the change to the procedure is the

2) temporary changes to FLEET level technical procedures .

allowed.

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

A. 1. Assistant Operations Manager - Shift

2. are NOT B. 1. Assistant Operations Manager - Shift

2. are C. 1. Shift Manager - Operations

2. are NOT D. 1. Shift Manager - Operations

2. are Page 97 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 98 (1 point)

Given the following conditions on Unit 2:

The unit is shutdown in preparation for refueling

NC system temperature is currently 190°F

An entry into Containment is planned for an inspection Based on the conditions above, in accordance with MSD-585 (REACTOR BUILDING PERSONNEL ACCESS AND MATERIAL CONTROL),

1) is permission from the WCC SRO required for the entry?

2) is use of the "buddy system" required for the entry?

A. 1. YES

2. NO B. 1. NO

2. NO C. 1. YES

2. YES D. 1. NO

2. YES Page 98 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 99 (1 point)

Given the following Unit 1 conditions:

The crew is responding to a large LOCA with 10% failed fuel

1NI-184B (1B ND PUMP SUCTION FROM CONT SUMP ISOL) would NOT open during FWST swap-over

1NI-184B breaker has tripped and will NOT reset

Manual alignment of 1NI-184B is required to protect the health and safety of the general public

Expected dose rates in the area of the valve may exceed 150 REM/hr

It will take 12 minutes to open 1NI-184B In accordance with the Emergency Response Procedures (RP) requirements for planned Emergency Exposures,

1) who, by title, is allowed to approve the Emergency Exposure?

2) and based on the conditions above, is a volunteer required to be used to open 1NI-184B?

A. 1. Site Vice President

2. NO B. 1. Site Vice President

2. YES C. 1. Emergency Coordinator

2. NO D. 1. Emergency Coordinator

2. YES Page 99 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 100 (1 point)

Given the following initial plant conditions:

A large break LOCA has occurred on Unit 1

At 0220, the SM, acting as the Emergency Coordinator (EC), declares a General Emergency and makes the following initial Protective Action Recommendations (PARs):

o Evacuate - Zones B, C, L, M, D, N, O, R o Shelter - Zones P, Q, S At 0230, the following conditions are observed:

Conditions which resulted in the General Emergency on Unit 1 remain unchanged

Wind direction has changed and is now from 100° In accordance with the Response Procedures (RP), the Emergency Coordinator (1) allowed to delegate APPROVAL of PARs.

Based on the conditions at 0230, the Emergency Coordinator (2) recommend suspending evacuation of Zone D.

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

REFERENCE PROVIDED A. 1. is

2. will B. 1. is

2. will NOT C. 1. is NOT

2. will D. 1. is NOT

2. will NOT Page 100 of 100

Reference List for: ILT-16-1 MNS SRO NRC Examination ECA-1.1 (Step 18)

ECA-1.1 (Enclosure 9)

Generator Capability Curve 3.1.1 Generator Capability Curve 3.1.2 Generic Enclosure 33 RP/0/B/5700/029 Enclosure 4.4 (Offsite Protective Action Recommendations)

Steam Tables Tech Spec 3.3.1 (RTS Instrumentation)

Tech Spec 3.4.4. (RCS Loops Modes 1 & 2)

Tech Spec 3.7.5 (AFW SYSTEM)

Printed 3/10/2016 6:13:08 AM

RTS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1-1.

ACTIONS

NOTE----------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one or more referenced in Table 3.3.1-1 required channels for the channel(s).

inoperable.

B. One Manual Reactor B.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Trip channel inoperable. OPERABLE status.

OR B.2 Be in MODE 3. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months C. One channel or train C.1 Restore channel or train to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable. OPERABLE status.

OR C.2 Open reactor trip breakers 49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months (RTBs).

(continued)

McGuire Units 1 and 2 3.3.1-1 Amendment Nos. 184/166

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One channel inoperable. ------------------NOTE-------------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing and setpoint adjustment.

D.1.1 ------------NOTE---------------

Only required to be performed when the Power Range Neutron Flux input to QPTR is inoperable Perform SR 3.2.4.2 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from discovery of THERMAL POWER

> 75% RTP AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND D.1.2 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR D.2 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months (continued)

McGuire Units 1 and 2 3.3.1-2 Amendment Nos. 248/228

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One channel inoperable. ------------------NOTE-------------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

E.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR E.2 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months F. THERMAL POWER F.1 Reduce THERMAL 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

> P-6 and < P-10, one POWER to < P-6.

Intermediate Range Neutron Flux channel OR inoperable.

F.2 Increase THERMAL 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months POWER to > P-10.

NOTE----------------

Limited boron concentration changes associated with RCS inventory control or limited plant temperature changes are allowed.

G. THERMAL POWER G.1 Suspend operations Immediately

> P-6 and < P-10, two involving positive reactivity Intermediate Range additions.

Neutron Flux channels inoperable. AND G.2 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to < P-6.

H. THERMAL POWER H.1 Restore channel(s) to Prior to increasing

< P-6, one or two OPERABLE status. THERMAL POWER Intermediate Range to > P-6 Neutron Flux channels inoperable.

(continued)

McGuire Units 1 and 2 3.3.1-3 Amendment Nos. 248/228

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

NOTE-----------------

Limited boron concentration changes associated with RCS inventory control or limited plant temperature changes are allowed.

I. One Source Range I.1 Suspend operations Immediately Neutron Flux channel involving positive reactivity inoperable. additions.

J. Two Source Range J.1 Open RTBs. Immediately Neutron Flux channels inoperable.

K. One Source Range K.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Neutron Flux channel OPERABLE status.

inoperable.

OR K.2 Open RTBs. 49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months

NOTE-----------------

Plant temperature changes are allowed provided that SDM is maintained and Keff remains <

0.99.

L. Required Source Range L.1 Suspend operations Immediately Neutron Flux channel involving positive reactivity inoperable. additions.

AND L.2 Close unborated water 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months source isolation valves.

AND L.3 Perform SR 3.1.1.1. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter (continued)

McGuire Units 1 and 2 3.3.1-4 Amendment Nos. 216 / 197

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME M. One channel inoperable. ------------------NOTE-------------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

M.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR M.2 Reduce THERMAL 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months POWER to < P-7.

N. One Reactor Coolant -----------------NOTE--------------------

Flow - Low (Single One channel may be bypassed for Loop) channel up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance inoperable. testing.

N.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR N.2 Reduce THERMAL 76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months POWER to < P-8.

(continued)

McGuire Units 1 and 2 3.3.1-5 Amendment Nos. 250/230

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME O. One Turbine Trip - Low ------------------NOTE-------------------

Fluid Oil Pressure One channel may be bypassed for channel inoperable. up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

O.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR O.2 Reduce THERMAL 76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months POWER to < P-8.

P. One or more Turbine P.1 Place channel(s) in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Trip - Turbine Stop Valve Closure channels OR inoperable.

P.2 Reduce THERMAL 76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months POWER to < P-8.

Q. One train inoperable. ------------------NOTE-------------------

One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing provided the other train is OPERABLE.

Q.1 Restore train to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

OR Q.2 Be in MODE 3. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months (continued)

McGuire Units 1 and 2 3.3.1-6 Amendment Nos. 248/228

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME R. One RTB train ------------------NOTE------------------

inoperable. One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing, provided the other train is OPERABLE.

R.1 Restore train to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

OR R.2 Be in MODE 3. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months S. One or more channel(s) S.1 Verify interlock is in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. required state for existing unit conditions.

OR S.2 Be in MODE 3. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months (continued)

McGuire Units 1 and 2 3.3.1-7 Amendment Nos. 248/228

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME T. One or more channel(s) T.1 Verify interlock is in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. required state for existing unit conditions.

OR T.2 Be in MODE 2. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months U. One trip mechanism U.1 Restore inoperable trip 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable for one RTB. mechanism to OPERABLE status.

OR U.2 Be in MODE 3. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months V. Two RTS trains V.1 Enter LCO 3.0.3. Immediately inoperable.

McGuire Units 1 and 2 3.3.1-8 Amendment Nos. 184/166

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS

NOTE-------------------------------------------------------------

Refer to Table 3.3.1-1 to determine which SRs apply for each RTS Function.

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.1.2 ------------------------------NOTES----------------------------------

1. Adjust NIS channel if absolute difference is > 2%

RTP.

2. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER is > 15% RTP.

Compare results of calorimetric heat balance calculation In accordance with to Nuclear Instrumentation System (NIS) channel output. the Surveillance Frequency Control Program SR 3.3.1.3 ------------------------------NOTES----------------------------------

1. Adjust NIS channel if absolute difference is > 3%

AFD.

2. Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is > 15% RTP.

Compare results of the incore detector measurem In accordance with ents to NIS AFD. the Surveillance Frequency Control Program (continued)

McGuire Units 1 and 2 3.3.1-9 Amendment Nos. 261/241

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.4 ------------------------------NOTES----------------------------------

This Surveillance must be performed on the reactor trip bypass breaker prior to placing the bypass breaker in service.

Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.5 Perform ACTUATION LOGIC TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.6 ------------------------------NOTES----------------------------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is > 75% RTP.

Calibrate excore channels to agree with incore detector In accordance with measurements. the Surveillance Frequency Control Program SR 3.3.1.7 ------------------------------NOTES----------------------------------

Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after entry into MODE 3.

Perform COT. In accordance with the Surveillance Frequency Control Program (continued)

McGuire Units 1 and 2 3.3.1-10 Amendment Nos. 261/241

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.8 ------------------------------NOTES----------------------------------

This Surveillance shall include verification that interlocks P-6 (for the Intermediate Range channels) and P-10 (for the Power Range channels) are in their required state for existing unit conditions.

Perform COT. ---------NOTE-------

Only required when not performed within the Frequency specified in the Surveillance Frequency Control Program or previous 184 days Prior to reactor startup AND Four hours after reducing power below P-10 for power and intermediate range instrumentation AND Four hours after reducing power below P-6 for source range instrumentation AND In accordance with the Surveillance Frequency Control Program (continued)

McGuire Units 1 and 2 3.3.1-11 Amendment Nos. 261/241

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.9 ------------------------------NOTES----------------------------------

Verification of setpoint is not required.

Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.10 ------------------------------NOTES----------------------------------

This Surveillance shall include verification that the time constants are adjusted to the prescribed values.

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.1.11 ------------------------------NOTES----------------------------------

1. Neutron detectors are excluded from CHANNEL CALIBRATION.

2. Power Range Neutron Flux high voltage detector saturation curve verification is not required to be performed prior to entry into MODE 1 or 2.

3. Intermediate Range Neutron Flux detector plateau voltage verification is not required to be performed prior to entry into MODE 1 or 2.* In accordance with

the Surveillance Frequency Control Perform CHANNEL CALIBRATION. Program SR 3.3.1.12 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program (continued)

This note applies to the Westinghouse-supplied compensated ion chamber neutron detectors. The compensated ion chamber neutron detectors are being replaced with Thermo Scientific-supplied fission chamber neutron detectors which do not require detector plateau voltage verification. Therefore, this note does not apply to the fission chamber neutron detectors.

McGuire Units 1 and 2 3.3.1-12 Amendment Nos. 261/241

RTS Instrumentation 3.3.1 SURVEILLANCE FREQUENCY SR 3.3.1.13 Perform COT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.14 ------------------------------NOTES----------------------------------

Verification of setpoint is not required.

Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.15 ------------------------------NOTES---------------------------------- --------NOTE--------

Verification of setpoint is not required. Only required

when not performed within previous 31 days Perform TADOT. Prior to reactor startup SR 3.3.1.16 ------------------------------NOTES----------------------------------

Neutron detectors are excluded from response time testing.

Verify RTS RESPONSE TIME is within limits. In accordance with the Surveillance Frequency Control Program SR 3.3.1.17 Verify RTS RESPONSE TIME for RTDs is within limits. In accordance with the Surveillance Frequency Control Program McGuire Units 1 and 2 3.3.1-13 Amendment Nos. 261/241

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 7)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

1. Manual Reactor Trip 1,2 2 B SR 3.3.1.14 NA NA 3(a), 4(a), 5(a) 2 C SR 3.3.1.14 NA NA

2. Power Range Neutron Flux

a. High 1,2 4 D SR 3.3.1.1 < 110% RTP 109% RTP SR 3.3.1.2 SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.16

b. Low 1(b),2 4 E SR 3.3.1.1 < 26% RTP 25% RTP SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.16

3. Power Range Neutron Flux Rate High Positive Rate 1,2 4 D SR 3.3.1.7 < 5.5% RTP 5% RTP SR 3.3.1.11 with time with time constant constant

> 2 sec > 2 sec

4. Intermediate Range 1(b), 2(c) 2 F,G SR 3.3.1.1 < 30% RTP* 25% RTP Neutron Flux SR 3.3.1.8(j)(k) < 38% RTP SR 3.3.1.11(j)(k) 2(d) 2 H SR 3.3.1.1 < 30% RTP*

25% RTP

< 38% RTP SR 3.3.1.8(j)(k)

SR 3.3.1.11(j)(k)

(continued)

The < 30% RTP Allowable Value applies to the Westinghouse-supplied compensated ion chamber Intermediate Range neutron detectors. The compensated ion chamber neutron detectors are being replaced with Thermo Scientific-supplied fission chamber neutron detectors. The < 38% Allowable Value applies to the replacement fission chamber Intermediate Range neutron detectors.

(a) With Reactor Trip Breakers (RTBs) closed and Rod Control System capable of rod withdrawal.

(b) Below the P-10 (Power Range Neutron Flux) interlocks.

(c) Above the P-6 (Intermediate Range Neutron Flux) interlocks.

(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

(j) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(k) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The methodologies used to determine the as-found and the as-left tolerances are specified in the UFSAR.

McGuire Units 1 and 2 3.3.1-14 Amendment Nos. 257/237

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 7)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

5. Source Range 2(d) 2 I,J SR 3.3.1.1 < 1.3 E5 cps** 1.0 E5 cps Neutron Flux SR 3.3.1.8(j)(k) < 1.44 E5 cps SR 3.3.1.11(j)(k) 3(a), 4(a), 5(a) 2 J,K SR 3.3.1.1 < 1.3 E5 cps** 1.0 E5 cps SR 3.3.1.7(j)(k) < 1.44 E5 cps SR 3.3.1.11(j)(k) 3(e), 4(e), 5(e) 1 L SR 3.3.1.1 N/A N/A SR 3.3.1.11

6. Overtemperature T 1,2 4 E SR 3.3.1.1 Refer to Note 1 Refer to SR 3.3.1.3 (Page Note 1 (Page SR 3.3.1.6 3.3.1-18) 3.3.1-18)

SR 3.3.1.7 SR 3.3.1.12 SR 3.3.1.16 SR 3.3.1.17

7. Overpower T 1,2 4 E SR 3.3.1.1 Refer to Note 2 Refer to SR 3.3.1.3 (Page Note 2 (Page SR 3.3.1.6 3.3.1-19) 3.3.1-19)

SR 3.3.1.7 SR 3.3.1.12 SR 3.3.1.16 SR 3.3.1.17

8. Pressurizer Pressure

a. Low 1(f) 4 M SR 3.3.1.1 > 1935 psig 1945 psig SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16

b. High 1,2 4 E SR 3.3.1.1 < 2395 psig 2385 psig SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16 (continued)

- The < 1.3 E5 cps Allowable Value applies to the Westinghouse-supplied boron triflouride (BF3) Source Range neutron detectors. The BF3 neutron detectors are being replaced with Thermo Scientific-supplied fission chamber neutron detectors. The < 1.44 E5 cps Allowable Value applies to the replacement fission chamber Source Range neutron detectors.

(a) With Reactor Trip Breakers (RTBs) closed and Rod Control System capable of rod withdrawal.

(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

(e) With the RTBs open. In this condition, source range Function does not provide reactor trip but does provide indication.

(f) Above the P-7 (Low Power Reactor Trips Block) interlock.

(j) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(k) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The methodologies used to determine the as-found and the as-left tolerances are specified in the UFSAR.

McGuire Units 1 and 2 3.3.1-15 Amendment Nos. 257/237

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 3 of 7)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

9. Pressurizer Water 1(f) 3 M SR 3.3.1.1 < 93% 92%

Level - High SR 3.3.1.7 SR 3.3.1.10

10. Reactor Coolant Flow - Low

a. Single Loop 1(g) 3 per loop N SR 3.3.1.1 > 87% 88%

SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16

b. Two Loops 1(h) 3 per loop M SR 3.3.1.1 > 87% 88%

SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16

11. Undervoltage RCPs 1(f) 1 per bus M SR 3.3.1.9 > 5016 V 5082 V SR 3.3.1.10 SR 3.3.1.16

12. Underfrequency 1(f) 1 per bus M SR 3.3.1.9 > 55.9 Hz 56.4 Hz RCPs SR 3.3.1.10 SR 3.3.1.16

13. Steam Generator 1,2 4 per SG E SR 3.3.1.1 > 15% 16.7%

(SG) Water Level - SR 3.3.1.7 Low Low SR 3.3.1.10 SR 3.3.1.16

14. Turbine Trip

a. Low Fluid Oil 1(g) 3 O SR 3.3.1.10 > 42 psig 45 psig Pressure SR 3.3.1.15

b. Turbine Stop 1(g) 4 P SR 3.3.1.10 > 1% open > 1% open Valve Closure SR 3.3.1.15

15. Safety Injection (SI) 1,2 2 trains Q SR 3.3.1.5 NA NA Input from SR 3.3.1.14 Engineered Safety Feature Actuation System (ESFAS)

(continued)

(f) Above the P-7 (Low Power Reactor Trips Block) interlock.

(g) Above the P-8 (Power Range Neutron Flux) interlock.

(h) Above the P-7 (Low Power Reactor Trips Block) interlock and below the P-8 (Power Range Neutron Flux) interlock.

McGuire Units 1 and 2 3.3.1-16 Amendment Nos. 257/237

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 4 of 7)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

16. Reactor Trip System Interlocks

a. Intermediate 2(d) 2 S SR 3.3.1.11 > 4E-11 amp*** 1E-10 amp***

Range Neutron SR 3.3.1.13 > 6.6E-6% RTP 1E-5% RTP Flux, P-6

b. Low Power 1 1 per train T SR 3.3.1.5 NA NA Reactor Trips Block, P-7

c. Power Range 1 4 T SR 3.3.1.11 < 49% RTP 48% RTP Neutron Flux, SR 3.3.1.13 P-8

d. Power Range 1,2 4 S SR 3.3.1.11 > 7% RTP and 10% RTP Neutron Flux, SR 3.3.1.13 < 11% RTP P-10

e. Turbine Inlet 1 2 T SR 3.3.1.12 < 11% turbine 10% turbine Pressure, P-13 SR 3.3.1.13 inlet pressure inlet pressure equivalent equivalent

17. Reactor Trip 1,2 2 trains R, V SR 3.3.1.4 NA NA (i)

Breakers 3(a), 4(a), 5(a) 2 trains C SR 3.3.1.4 NA NA

18. Reactor Trip Breaker 1,2 1 each per U SR 3.3.1.4 NA NA Undervoltage and RTB Shunt Trip Mechanisms 3(a), 4(a), 5(a) 1 each per C SR 3.3.1.4 NA NA RTB

19. Automatic Trip Logic 1,2 2 trains Q, V SR 3.3.1.5 NA NA 3(a), 4(a), 5(a) 2 trains C SR 3.3.1.5 NA NA

- - The > 4E-11 amp Allowable Value and the 1E-10 amp NOMINAL TRIP SETPOINT value apply to the Westinghouse-supplied compensated ion chamber Intermediate Range neutron detectors. The compensated ion chamber neutron detectors are being replaced with Thermo Scientific-supplied fission chamber neutron detectors. The > 6.6E-6% RTP Allowable Value and the 1E-5% RTP NOMINAL TRIP SETPOINT value apply to the replacement fission chamber Intermediate Range neutron detectors.

(a) With RTBs closed and Rod Control System capable of rod withdrawal.

(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

(i) Including any reactor trip bypass breakers that are racked in and closed for bypassing on RTP.

McGuire Units 1 and 2 3.3.1-17 Amendment Nos. 268/248

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 5 of 7)

Reactor Trip System Instrumentation Note 1: Overtemperature T The Overtemperature T Function Allowable Value shall not exceed the following NOMINAL TRIP SETPOINT by more than 4.3 % of RTP.

(1 + 1s ) 1 (1 + 4 s ) 1 T K 1 K 2 T + K 3 (P P ) f1 ( I )

(1 + 2 s ) 1 + s T0 T

(1 + 5 s ) (1 + 6 s )

3 Where: T is measured RCS T by loop narrow range RTDs, °F.

T0 is the indicated T at RTP, °F.

s is the Laplace transform operator, sec-1.

T is the measured RCS average temperature, °F.

T' is the nominal Tavg at RTP, < the value specified in the COLR.

P is the measured pressurizer pressure, psig P' is the nominal RCS operating pressure, = the value specified in the COLR.

K1 = Overtemperature T reactor NOMINAL TRIP SETPOINT, as presented in the COLR, K2 = Overtemperature T reactor trip heatup setpoint penalty coefficient, as presented in the COLR, K3 = Overtemperature T reactor trip depressurization setpoint penalty coefficient, as presented in the COLR, 1,2 = Time constants utilized in the lead-lag controller for T, as presented in the COLR, 3 = Time constants utilized in the lag compensator for T, as presented in the COLR, 4, 5 = Time constants utilized in the lead-lag controller for Tavg, as presented in the COLR, 6 = Time constants utilized in the measured Tavg lag compensator, as presented in the COLR, and, f1(I) = a function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:

(i) for qt - qb between the "positive" and "negative" f1(I) breakpoints as presented in the COLR; f1(I) = 0, where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL POWER in percent of RATED THERMAL POWER; (continued)

McGuire Units 1 and 2 3.3.1-18 Amendment Nos. 219 / 201

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 6 of 7)

Reactor Trip System Instrumentation (ii) for each percent imbalance that the magnitude of qt - qb is more negative than the f1(I) "negative" breakpoint presented in the COLR, the T Trip Setpoint shall be automatically reduced by the f1(I) "negative" slope presented in the COLR; and (iii) for each percent imbalance that the magnitude of qt - qb is more positive than the f1(I) "positive" breakpoint presented in the COLR, the T Trip Setpoint shall be automatically reduced by the f1(I)

"positive" slope presented in the COLR.

Note 2: Overpower T The Overpower T Function Allowable Value shall not exceed the following NOMINAL TRIP SETPOINT by more than 2.6% of RTP.

(1 + 1 s ) 1 7 s 1 1 T K 4 K 5 T K 6 T (1 + 2 s 1 + s T0 7 s 1 + s T f 2 ( I )

3 1 + 6 1+ 6 s Where: T is measured RCS T by loop narrow range RTDs, °F.

T0 is the indicated T at RTP, °F.

s is the Laplace transform operator, sec-1.

T is the measured RCS average temperature, °F.

T" is the nominal Tavg at RTP, < the value specified in the COLR.

K4 = Overpower T reactor NOMINAL TRIP SETPOINT as presented in the COLR, K5 = The value specified in the COLR for increasing average temperature and the value specified in the COLR for decreasing average temperature, K6 = Overpower T reactor trip heatup setpoint penalty coefficient as presented in the COLR for T > T" and K6 = the value specified in the COLR for T < T",

1, 2 = Time constants utilized in the lead-lag controller for T, as presented in the COLR, 3 = Time constants utilized in the lag compensator for T, as presented in the COLR, 6 = Time constants utilized in the measured Tavg lag compensator, as presented in the COLR, 7 = Time constant utilized in the rate-lag controller for Tavg, as presented in the COLR, and f2(I) = a function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:

(continued)

McGuire Units 1 and 2 3.3.1-19 Amendment Nos. 219 / 201

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 7 of 7)

Reactor Trip System Instrumentation (i) for qt - qb between the "positive" and "negative" f2(I) breakpoints as presented in the COLR; f2(I) = 0, where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL POWER in percent of RATED THERMAL POWER; (ii) for each percent imbalance that the magnitude of qt - qb is more negative than the f2(I) "negative" breakpoint presented in the COLR, the T Trip Setpoint shall be automatically reduced by the f2(I) "negative" slope presented in the COLR; and (iii) for each percent imbalance that the magnitude of qt - qb is more positive than the f2(I) "positive" breakpoint presented in the COLR, the T Trip Setpoint shall be automatically reduced by the f2(I) "positive" slope presented in the COLR.

McGuire Units 1 and 2 3.3.1-20 Amendment Nos. 184/166

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. 184/166

AFW System 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 --------------------------------NOTE----------------------------------

Not applicable to automatic valves when THERMAL POWER is < 10% RTP.

Verify each AFW manual, power operated, and automatic In accordance valve in each water flow path, and in both steam supply with the flow paths to the steam turbine driven pump, that is not Surveillance locked, sealed, or otherwise secured in position, is in the Frequency correct position. Control Program 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, In accordance sealed, or otherwise secured in position, actuates to the with the correct position on an actual or simulated actuation Surveillance signal. Frequency Control Program (continued)

McGuire Units 1 and 2 3.7.5-3 Amendment Nos. 261/241

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 In accordance or simulated actuation signal. with the Surveillance Frequency Control Program McGuire Units 1 and 2 3.7.5-4 Amendment Nos. 261/241

RCS Loops - MODES 1 and 2 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Loops MODES 1 and 2 LCO 3.4.4 Four RCS loops shall be OPERABLE and in operation.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of LCO A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RCS loop is in operation. In accordance with the Surveillance Frequency Control Program McGuire Units 1 and 2 3.4.4-1 Amendment Nos. 261/241

Enclosure 4.4 RP/0/B/5700/029 Protective Action Recommendations Page 1 of 4 INITIAL PAR Determination GE Has Been Note 1: Protective Action Zones (PAZs) are defined in Table 1 on page 3. SIP is Shelter in Place.

Declared Note 2: Offsite Agencies have provided prior knowledge of offsite impediments to evacuation (such as flooding, bridge/road closures, adverse weather, traffic control not in place, etc.) AND specifically requested that site NOT issue an evacuation PAR.

Note 3: RPSA criteria: Only Applicable to First PAR after GE Declaration AND two of the following exist from Is this a Rapidly No RP/0/A/5700/000: (IF RPSA conditions can NOT be confirmed, THEN answer NO)

Progressing Severe Accident (RPSA) 1. LOSS of Containment Barrier per Enclosure 4.1.

(See Note 3) AND

2. POTENTIAL LOSS of Containment Barrier per Containment Radiation Monitor EMF51A or 51B per Yes Enclosure 4.1.

OR (See Note 1)

P There is a significant radiological release projected to exceed 4.3.G.1 EAL at the site boundary within an hour.

Evacuate 2-mile Radius A

Evacuate 2-5 miles Downwind

SIP 5-10 miles Downwind R

Is there a Hostile Is there a known No No Action Based event offsite impediment to in progress? evacuation?

(See Note 2)

(See Note 1) P Are offsite dose

Evacuate 2-mile Radius A No Yes Yes R projections or field

Evacuate 2-5 miles Downwind measurements 5 rem CDE Thyroid?

(See Note 1) P

SIP 2-mile Radius A

SIP 2-5 miles Downwind R Yes Are offsite dose Recommend the P Yes projections or field No P A Recommend the consideration of A consideration of KI measurements 5 KI use by the public. R use by the public R rem CDE Thyroid?

GO TO Page 2 for EXPANDED PAR

Enclosure 4.4 RP/0/B/5700/029 Protective Action Recommendations Page 2 of 4 EXPANDED PAR Determination Note 1: Protective Action Zones (PAZs) are defined in Table 1 on page 3. SIP is Shelter in Place.

(IF a PAZ has been accurately selected for evacuation, it shall remain selected.) From INITIAL PAR Note 2: Offsite Agencies have provided prior knowledge of offsite impediments to evacuation (such as flooding, bridge/road closures, adverse weather, traffic control not in place, etc.) AND specifically requested that site NOT issue an evacuation PAR.

Note 3: A short-term release is one that can be accurately projected to be < three hours and controlled Continuous Assessment by the licensee. This consideration would typically apply to controlled venting of containment. Evaluate PAR based on changes in any of the following:

Increase in dose assessment projected values.

Note 4: Plant conditions exist which would require the classification of a General Emergency per the

Increase in field team measured values.

EALs. This does NOT include consideration of offsite dose-based EALs.

Shift in 15-minute average wind direction resulting in additional sectors being affected. (Table 3 on page 3)

Offsite Agencies provides information that offsite impediments no longer exist.

Hostile action based event has been terminated.

No Is there a known No Is there a Hostile

IF RPSA, when safer to do so consider evacuation of offsite impediment to Action Based event SIP PAZs based upon radiological assessment and evacuation?

in progress? discussions with Offsite Agencies.

(See Note 2)

Is there a short-term No Yes release in progress?

Yes (See Note 3) No Offsite Projected Dose GE Conditions? projections or field No Yes (See Note 4) measurements exceed PAGs?

Table 2 Yes Yes Evacuate PAZ(s) that exceed P (See Note 1) P PAGs. If projected dose exceeds A (See Note 1) P

SIP 2-mile Radius A A 5-Rem Thyroid CDE then R

Evacuate 2-mile Radius recommend the consideration of R

SIP 2-5 miles Downwind R

SIP additional PAZ(s) that exceed PAGs

Evacuate 2-5 miles Downwind KI use by the public.

Enclosure 4.4 RP/0/B/5700/029 Offsite Protective Action Recommendations Page 3 of 4 Table 1 Protective Action Zones Wind Direction 2 Mile 2-5 Miles 5-10 Miles Radius Downwind Downwind 0.1 - 22.5 B,C,L,M D,O,R E,F,S 22.6 - 45.0 B,C,L,M D,O,R E,Q,S 45.1 - 67.5 B,C,L,M D,N,O,R E,P,Q,S 67.6 - 90.0 B,C,L,M D,N,O,R P,Q,S 90.1 - 112.5 B,C,L,M N,O,R K,P,Q,S 112.6 - 135.0 B,C,L,M A,N,O,R I,K,P,Q,S 135.1 - 157.5 B,C,L,M A,N,O I,K,P,Q 157.6 - 180.0 B,C,L,M A,N H,I,J,K,P 180.1 - 202.5 B,C,L,M A,N G,H,I,J,K,P 202.6 - 225.0 B,C,L,M A,D,N G,H,I,J,K,P 225.1 - 247.5 B,C,L,M A,D F,G,H,I,J 247.6 - 270.0 B,C,L,M A,D F,G,H,I,J 270.1 - 292.5 B,C,L,M A,D E,F,G,H,J 292.6 - 315.0 B,C,L,M A,D,R E,F,G 315.1 - 337.5 B,C,L,M D,R E,F,G,S 337.6 - 360.0 B,C,L,M D,R,O E,F,S Table 2 PROTECTIVE ACTION GUIDES (PAGs)

(Projected Dose or Field Measurements)

Total Effective Dose Committed Dose Equivalent (TEDE) Equivalent (CDE)

Thyroid

> 1 Rem > 5 Rem Table 3 WIND SPEED/DIRECTION ENF Line 9 Radiation Protection Manager McGuire SDS Group Display ERORD5 DPC Meteorological Lab 704-382-0139 704-373-7896 National Weather Service 864-879-1085 Greer, S.C 800-268-7785

Enclosure 4.4 RP/0/B/5700/029 Offsite Protective Action Recommendations Page 4 of 4 McGUIRE PROTECTIVE ACTION ZONES (2 and 5 mile radius, inner circles) 10-MILE EPZ

Examination KEY for: ILT-16-1 MNS SRO NRC Examination Question Answer Number 1 A 2 D 3 D 4 A 5 D 6 B 7 C 8 C 9 A 10 D 11 C 12 D 13 C 14 A 15 C 16 B 17 C 18 B 19 C 20 D 21 B 22 B 23 D 24 B 25 B Printed 4/18/2016 5:48:33 AM Page 1 of 4

Examination KEY for: ILT-16-1 MNS SRO NRC Examination Question Answer Number 26 C 27 C 28 B 29 A 30 B 31 A 32 B 33 C 34 B 35 B 36 A 37 A 38 C 39 B 40 A 41 B 42 C 43 A 44 D 45 B 46 C 47 B 48 D 49 D 50 A Printed 4/18/2016 5:48:33 AM Page 2 of 4

Examination KEY for: ILT-16-1 MNS SRO NRC Examination Question Answer Number 51 D 52 A 53 C 54 C 55 B 56 A 57 B 58 C 59 C 60 D 61 B 62 A 63 D 64 C 65 C 66 D 67 B 68 C 69 D 70 D 71 C 72 B 73 C 74 C 75 D Printed 4/18/2016 5:48:33 AM Page 3 of 4

Examination KEY for: ILT-16-1 MNS SRO NRC Examination Question Answer Number 76 B 77 C 78 B 79 C 80 C 81 A 82 D 83 A 84 D 85 C 86 A 87 C 88 D 89 C 90 DELETED 91 A 92 A 93 D 94 A 95 B 96 A 97 C 98 B 99 D 100 D Printed 4/18/2016 5:48:33 AM Page 4 of 4

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

Date: Facility/Unit: MCGUIRE Region: I II III IV Reactor Type: W 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 ILT-16-1 MNS SRO NRC Examination Question: 1 (1 point)

Given the following initial conditions on Unit 1:

The unit is at 100% RTP

Train "B" equipment is in service Subsequently,

An 86 Lockout occurs on 1ETB

No operator actions have been taken Based on the conditions above, NC pumps currently have KC cooling.

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

A. NO B. ALL C. ONLY A and D D. ONLY B and C Page 1 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 2 (1 point)

To which ONE (1) of the following locations would you dispatch an Auxiliary Operator to rack out the breaker for the 1A ND pump?

A. SATA B. 1TA C. 1TC D. 1ETA Page 2 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 3 (1 point)

Given the following conditions on Unit 2:

The unit is in solid operations while cooling down

Both trains of ND are in service, A NV pump is in service

Letdown is through 2NV-121 Subsequently:

The Letdown Heat Exchanger Outlet temperature sensor fails causing 2KC-132 to go full OPEN Per OP/2/A/6100/SD-8 (WATER SOLID OPERATIONS), the operator action required is to throttle 2NV-241 (1) OR throttle 2NV-121 (2) .

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

COMPONENT LEGEND:

2NV-121 (ND LETDOWN CONTROL) 2KC-132 (U2 LD HX KC OUT TEMP CNTRL) 2NV-241 (SEAL INJECTION FLOW CONTROL)

A. 1. CLOSED

2. OPEN B. 1. OPEN

2. OPEN C. 1. CLOSED

2. CLOSED D. 1. OPEN

2. CLOSED Page 3 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 4 (1 point)

Given the following conditions on Unit 2:

Both trains of Residual Heat Removal (ND) are in service

ND Heat Exchanger outlet valves (2ND-14 & 2ND-29) are throttled to 2000 gpm each

NC Cooldown rate is 25°F/Hr

The instrument air line to Train "B ND Heat Exchanger outlet valve (2ND-14) breaks off Which ONE (1) of the following indicates the INITIAL ND System response to this event?

Total ND System Flow NC System Cooldown rate A. Goes UP Goes UP B. Goes UP Remains the Same C. Goes DOWN Goes DOWN D. Goes DOWN Remains the Same Page 4 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 5 (1 point)

Given the following conditions on Unit 2:

Unit is at 75% RTP

Several banks of FWST heaters have failed "ON"

Current FWST temperature is 91°F

FWST temperature is increasing at a rate of 0.5°F/min Based on the conditions above, FWST temperature will reach the T.S. 3.5.4 (REFUELING WATER STORAGE TANK) limit in (1) minutes.

Normally, Group 1 FWST heaters cycle automatically to maintain FWST temperature greater than a MINIMUM of (2) .

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

A. 1. 14

2. 72°F B. 1. 14

2. 75°F C. 1. 18

2. 72°F D. 1. 18

2. 75°F Page 5 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 6 (1 point)

Given the following initial conditions on Unit 1:

The unit is initially at 100% RTP

Safety Injection initiates due to a Large-Break LOCA inside Containment Approximately ONE (1) hour after the LOCA,

The 1B RN pump trips Based on the conditions above,

1) the temperature of will increase.

2) after transfer to cold leg recirculation, the length of time it takes to cooldown from 350°F to 140°F be affected.

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

(ASSUME THAT BOTH TRAINS OF ND REMAIN IN OPERATION DURING THE ENTIRE EVENT)

A. 1. 1B ND pump motor ONLY

2. will NOT B. 1. 1B ND pump motor ONLY

2. will C. 1. 1A AND 1B ND pump motors

2. will NOT D. 1. 1A AND 1B ND pump motors

2. will Page 6 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 7 (1 point)

Given the following initial conditions on Unit 2:

A reactor trip has occurred

The crew is performing E-0 (REACTOR TRIP OR SAFETY INJECTION)

Containment pressure is 0.1 PSIG and stable Subsequently,

ONE (1) PZR PORV fails partially open

PRT pressure rises to approximately 115 PSIG, and then suddenly drops and stabilizes at 2 PSIG

Containment pressure starts to rise at 0.1 PSIG per minute Based on the conditions above,

1) the PRT rupture discs operate as designed.

2) when Containment pressure rises above the Tech Spec 3.6.4 (CONTAINMENT PRESSURE) limit, action MUST be taken to restore Containment pressure to within the limit in a MAXIMUM of .

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

A. 1. did

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

2. 30 minutes C. 1. did NOT

2. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months D. 1. did NOT

2. 30 minutes Page 7 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 8 (1 point)

Given the following conditions on Unit 2:

The unit is in MODE 3

OP/1/A/6400/005 (COMPONENT COOLING WATER SYSTEM) Enclosure 4.20 (POST OUTAGE KC to NC PUMP FLOW BALANCE) is being performed

2A1 KC pump is running, 2A2 KC pump has been stopped for the flow test

2B1 and 2B2 KC pumps are available

The 2B sequencer is in TEST for surveillance testing

I&E inadvertently generates an SI signal on Unit 2 B Train ONLY Assuming no operator actions, which ONE (1) of the following indicates the Unit 2 KC pumps which are in service?

A. 2A1 KC pump ONLY B. 2A1 and 2A2 KC pumps ONLY C. 2A1, 2B1, and 2B2 KC pumps ONLY D. 2A1, 2A2, 2B1 and 2B2 KC pumps Page 8 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 9 (1 point)

Given the following conditions on Unit 2:

A unit runback has occurred

Steam Dump valves failed to modulate OPEN

The Pressurizer Pressure Calculated Error observed on the Ovation Soft Panel is +76 PSIG Based on the conditions above, the Pzr Spray Control valves will be (1) OPEN.

Pzr PORVs (2NC-32B and 2NC-36B) will OPEN if actual Pzr pressure increases to a MINIMUM of (2) PSIG.

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

A. 1. full

2. 2335 B. 1. throttled

2. 2335 C. 1. full

2. 2385 D. 1. throttled

2. 2385 Page 9 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 10 (1 point)

Given the following conditions on Unit 1:

NC system pressure is 1985 PSIG and slowly lowering due to a leaking Pressurizer Code Safety Valve (1NC-1)

PRT pressure is currently 65 PSIG

Discharge temperature downstream of 1NC-1 is 310°F

Containment pressure is currently 0.1 PSIG When the PRT rupture disc ruptures,

1) the rate of NC system depressurization will .

2) the temperature downstream of 1NC-1 will .

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

REFERENCE PROVIDED A. 1. increase

2. remain the same B. 1. remain the same

2. remain the same C. 1. remain the same

2. decrease D. 1. increase

2. decrease Page 10 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 11 (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

Train B SSPS testing is in progress

Reactor Trip Bypass breaker (BYB) is racked in and closed Based on the conditions above, a General Warning alarm for (1) train SSPS will be generated.

If Reactor Trip Bypass breaker (BYA) is racked in and closed, (2) would receive a trip open signal.

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

A. 1. A

2. RTA, RTB, BYA, and BYB breakers B. 1. A

2. RTA and RTB breakers ONLY C. 1. B

2. RTA, RTB, BYA, and BYB breakers D. 1. B

2. RTA and RTB breakers ONLY Page 11 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 12 (1 point)

Given the following conditions on Unit 1:

A Safety Injection has occurred on the unit Which ONE (1) of the following indicates the status of the VL (Lower Containment Ventilation) and VU (Upper Containment Ventilation) fans five (5) minutes after the Safety Injection signal?

VL VU A. Running in LOW speed Running in MAX COOL mode B. Running in HIGH speed Running in MAX COOL mode C. Running in LOW speed Shunt tripped OFF D. Running in HIGH speed Shunt tripped OFF Page 12 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 13 (1 point)

Given the following conditions on Unit 2:

A Large Break LOCA has occurred

The P between Lower Containment and Upper Containment is 0.3 PSID at 15 seconds into the event

6 minutes after the event initiation, an operator checks the status of the Containment Air Return Fans (CARFs)

Based on the conditions above,

1) the Containment Air Return Isolation dampers (RAF-D-2/4) are .

2) the Containment Air Return Fans are .

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

A. 1. CLOSED

2. OFF B. 1. CLOSED

2. ON C. 1. OPEN

2. OFF D. 1. OPEN

2. ON Page 13 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 14 (1 point)

Regarding the effect of prolonged operation with elevated Ice Condenser temperatures,

1) sublimation rates would .

2) if a high energy line break occurs inside Containment, peak Containment pressure would be .

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

A. 1. increase

2. higher B. 1. increase

2. unaffected C. 1. decrease

2. higher D. 1. decrease

2. unaffected Page 14 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 15 (1 point)

Given the following conditions on Unit 1:

The crew is performing ES-1.3 (TRANSFER TO COLD LEG RECIRC)

Containment Spray (NS) has been aligned for recirculation

FWST Level is 35 inches

Containment pressure is 3.2 PSIG and rising slowly Aligning NS for recirc in accordance with ES-1.3, requires (1) train(s) of NS to be aligned.

Based on the conditions above, if a loss of NS flow occurs, a Containment ORANGE path (2) occur.

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

A. 1. ONLY one

2. will NOT B. 1. both

2. will NOT C. 1. ONLY one

2. will D. 1. both

2. will Page 15 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 16 (1 point)

Given the following conditions on Unit 2:

I&E has requested that the 2B Containment Spray Pump breaker be racked out for an oil change.

To which ONE (1) of the following locations should an AO be dispatched to rack out the breaker?

A. SATB B. 2 ETB C. 2 TB D. 2 TD Page 16 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 17 (1 point)

Given the following conditions on Unit 1:

Unit is at 70% RTP

A steam leak has occurred

The crew has implemented AP-01 (STEAM LEAK)

If Pressurizer level is still GOING DOWN after crew actions to, OPEN 1NV-238 (CHARGING LINE FLOW CONTROL), (1) AP-01 will direct a Reactor trip.

If the main turbine fails to trip upon Reactor trip, AND can NOT be manually tripped, the NEXT action directed by E-0 (REACTOR TRIP OR SAFETY INJECTION), is to CLOSE (2) .

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

A. 1. and isolate Letdown ONLY

2. governor valves in FAST action B. 1. and isolate Letdown ONLY

2. all MSIVs and MSIV Bypass Valves C. 1. isolate Letdown AND start an additional NV pump

2. governor valves in FAST action D. 1. isolate Letdown AND start an additional NV pump

2. all MSIVs and MSIV Bypass Valves Page 17 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 18 (1 point)

Given the following Unit 2 initial conditions:

The Unit is at 100% RTP

2B MDCA Pump is tagged out Subsequently,

The 2B S/G Main Steam line breaks

The 2A MDCA Pump fails to start

E-2 (FAULTED STEAM GENERATOR ISOLATION) has been implemented In accordance with E-2, what valve(s) will be closed to isolate the steam supply to TD CA pump from 2B S/G?

COMPONENT LEGEND:

2SA-2 (2B S/G SM SUPPLY TO UNIT 2 TD CA PUMP TURB MAINT ISOL)

2SA-78 (2B S/G SM SUPPLY TO UNIT 2 TD CA PUMP TURB LOOP SEAL ISOL)

2SA-49AB (SM FRM S/G 2B TO TD CA PUMP ISOL)

A. 2SA2, 2SA-78, AND 2SA-49AB B. 2SA-2 AND 2SA-78 ONLY C. 2SA-49AB ONLY D. 2SA-2 ONLY Page 18 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 19 (1 point)

Given the following conditions on Unit 1:

The unit is at 12% RTP

Power increase is in progress DCS will maintain S/G Level Control for each S/G in the LO Power mode until a MAXIMUM Selected CF Flow of (1) is reached on each S/G.

With DCS in the LO Power mode, the CF Control Valves will start to OPEN when the CF Control Bypass Valves demand signal reaches a MINIMUM of (2) .

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

A. 1. 13%

2. 65%

B. 1. 13%

2. 75%

C. 1. 18%

2. 65%

D. 1. 18%

2. 75%

Page 19 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 20 (1 point)

Given the following conditions on Unit 1:

A Reactor trip has occurred

1A and 1B MDCA pumps are running

1A and 1B MDCA pump Discharge Flow Control valves are in MANUAL controlling S/G NR levels at program

1) If 1B MDCA pump Discharge Flow Control valves are closed, minimum flow protection will be provided by __ __ .

2) The 1B MDCA pump recirculation flow path will be to the __ __ .

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

A. 1. recirculation orifices

2. Upper Surge Tank B. 1. recirculation orifices

2. Auxiliary Feedwater Storage Tank (CAST)

C. 1. an automatic recirculation control valve

2. Upper Surge Tank D. 1. an automatic recirculation control valve

2. Auxiliary Feedwater Storage Tank (CAST)

Page 20 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 21 (1 point)

Given the following conditions on Unit 1:

1ETA Normal incoming breaker has opened

1A D/G started and loaded

While monitoring D/G parameters, the crew notes that D/G 1A VOLTS is at 4000 V When D/G 1A voltage is adjusted to NORMAL, how will 1A D/G Amps AND Power Factor indications respond to this adjustment?

AMPS Power Factor A. decrease more lagging B. decrease stay the same C. increase more lagging D. increase stay the same Page 21 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 22 (1 point)

Given the following conditions on Unit 2:

A Loss of Offsite Power has occurred

2B D/G started but subsequently tripped on overspeed

60 seconds have passed since the Loss of Offsite Power occurred Based on the conditions above,

1) 125 VDC Power Panel Board 2EVDD will be energized from .

2) this can be verified by checking control power available to 4160V pumps powered from .

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

A. 1. Battery EVCD

2. 2ETA B. 1. Battery EVCD

2. 2ETB C. 1. Standby Charger EVCS

2. 2ETA D. 1. Standby Charger EVCS

2. 2ETB Page 22 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 23 (1 point)

Given the following conditions:

Inverter KXB has experienced an overcurrent condition Based on the conditions above,

1) an indication used to determine that the backup power supply has been aligned is the light LIT.

2) when Inverter KXB overcurrent condition clears, the normal power supply be automatically realigned.

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

A. 1. In Sync

2. will NOT B. 1. In Sync

2. will C. 1. Alternate Source Supplying Load

2. will NOT D. 1. Alternate Source Supplying Load

2. will Page 23 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 24 (1 point)

Given the following initial conditions on Unit 1:

A switchyard transient causes a loss of offsite power on Unit 1

1A D/G starts and trips on overspeed

1B D/G starts

D/G Sequencers have not been reset Based on the conditions above, (1) of AP-07 (LOSS OF ELECTRICAL POWER) will be entered.

When desired, the 1B D/G (2) be secured from the control room.

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

PROCEDURE LEGEND:

AP-07, Case I (LOSS OF NORMAL POWER TO BOTH 1ETA AND 1ETB)

AP-07, Case II (LOSS OF NORMAL POWER TO EITHER 1ETA OR 1ETB)

A. 1. Case I

2. can B. 1. Case I

2. can NOT C. 1. Case II

2. can D. 1. Case II

2. can NOT Page 24 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 25 (1 point)

While performing the daily surveillance checks on 1EMF-33 (CONDENSER AIR EJECTOR EXHAUST), it is determined that the OPERATE light is OFF.

Which ONE (1) of the following actions is required in accordance with PT/1/A/4600/003 B (Daily Surveillance Items)?

COMPONENT LEGEND:

1EMF-36L (UNIT VENT GAS MONITOR)

A. Verify operability of 1EMF-36L.

B. Perform a source check of 1EMF-33.

C. Depress CLR (Clear) on the 1EMF-33 touch controls.

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

Page 25 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 26 (1 point)

Given the following initial conditions on Unit 1:

The Unit is at 100% RTP

B Train components in service Subsequently,

The 1B RN pump trips on overcurrent

The crew implements AP-20 (LOSS OF RN), and places the 1A RN pump in service

The remaining B Train components are still in operation

The BOP operator positions the manual loader for 1RN-190B (RN TO B KC HX CONTROL) to 10% open

The OATC, monitoring the OAC graphic for RN, notes 1RN-190B is indicating full open Which ONE (1) of the following identifies the reason for 1RN-190B indicating full open?

A. The manual loader is bypassed when the 1B RN pump breaker is open.

B. 1RN-190B is interlocked to open when the 1B RN pump breaker opens.

C. Minimum flow requirements for the 1B RN Pump are not met.

D. Minimum flow requirements for the 1A RN Pump are not met.

Page 26 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 27 (1 point)

Regarding the operation of 1VI-820 (VI TO VS SUPPLY VALVE),

1) the valve will automatically close if header pressure decreases to less than 90 PSIG.

2) if the 1VI-820 control switch is inadvertently left in the OPEN position, the valve close on decreasing pressure.

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

A. 1. VI

2. will NOT B. 1. VS

2. will NOT C. 1. VI

2. will D. 1. VS

2. will Page 27 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 28 (1 point)

In accordance with Tech. Spec. 3.6.5 (CONTAINMENT AIR TEMPERATURE),

Containment average temperature may be reduced to a MINIMUM of (1) in MODE(s) (2) .

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

A. 1. 60°F

2. 4 ONLY B. 1. 60°F

2. 2, 3 and 4 C. 1. 75°F

2. 4 ONLY D. 1. 75°F

2. 2, 3 and 4 Page 28 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 29 (1 point)

Given the following initial conditions on Unit 2:

Unit is stable at 25% RTP

Control Rods are in MANUAL Subsequently:

2D NCP trips on overcurrent Based on the conditions above,

1) an automatic reactor trip occur.

2) when steady-state conditions are achieved, in the UNAFFECTED loops will be .

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

A. 1. will NOT

2. higher B. 1. will NOT

2. lower C. 1. will

2. higher D. 1. will

2. lower Page 29 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 30 (1 point)

Given the following initial conditions on Unit 2:

A reactor startup is being performed per OP/2/A/6100/003 (CONTROLLING PROCEDURE FOR UNIT OPERATION)

Reactor power has increased into the IR and is currently at 5X10-6 % (IR)

Subsequently,

IR N-36 detector fails low Indication on Source Range N-32 (1) affected by the detector failure.

Based on the conditions above, per Tech Spec 3.3.1 (RTS INSTRUMENTATION), the power increase (2) .

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

REFERENCE PROVIDED A. 1. is

2. can continue B. 1. is

2. must be suspended C. 1. is NOT

2. can continue D. 1. is NOT

2. must be suspended Page 30 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 31 (1 point)

Given the following conditions on Unit 1:

The unit is stable at 45% RTP

Turbine Inlet Pressure is 400 PSIG Which ONE (1) of the following is the MINIMUM condition that would require entry into AP-03 (LOAD REJECTION)?

A. Buslines 1A AND 1B DEENERGIZE B. Busline 1A ONLY DEENERGIZES C. CF Pumps 1A AND 1B TRIP D. CF Pump 1A ONLY TRIPs Page 31 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 32 (1 point)

Given the following conditions on Unit 1:

A SGTR has occurred on 1A S/G

The crew has implemented E-3 (STEAM GENERATOR TUBE RUPTURE)

The OATC is performing the initial cooldown

1) Based on the conditions above, when NC system Tavg decreases to less than a MAXIMUM of , steam dumping will be blocked.

2) If a loss of vital bus occurs during the cooldown, all steam dump valves will CLOSE.

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

A. 1. 553°F

2. EVDB B. 1. 553°F

2. EVDA C. 1. 551°F

2. EVDB D. 1. 551°F

2. EVDA Page 32 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 33 (1 point)

Given the following conditions on Unit 1:

Makeup to the Spent Fuel Pool (SFP) is required

Chemistry sample results indicate SFP boron concentration at 2750 ppm In accordance with OP/1/A/6200/005 (SPENT FUEL COOLING SYSTEM) and based on the chemistry results above, (1) will be used for makeup to the SFP.

Assured makeup to the SFP is provided by the (2) system.

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

A. 1. YM

2. RN B. 1. YM

2. RF/RY C. 1. the FWST

2. RN D. 1. the FWST

2. RF/RY Page 33 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 34 (1 point)

Given the following conditions on Unit 1:

Unit 1 refueling is in progress

A fuel assembly is in the Reactor Building Manipulator Crane mast Subsequently, the following alarms are received:

1AD-13, B/6 (INCORE INSTRUMENT ROOM SUMP HI LEVEL)

1RAD-3, D/1 (1EMF 16 CONTAINMENT REFUELING BRIDGE)

Based on the conditions above,

1) the Tech Spec MINIMUM required refueling cavity water level is feet above the top of the reactor vessel flange.

2) the crew will implement to mitigate this event.

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

PROCEDURE LEGEND:

AP-25 (SPENT FUEL DAMAGE)

AP-40 (LOSS OF REFUELING CAVITY LEVEL)

A. 1. 23

2. AP-25 B. 1. 23

2. AP-40 C. 1. 33

2. AP-25 D. 1. 33

2. AP-40 Page 34 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 35 (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

While performing the RCCA movement test, Control Rod H-8 slips into the core to 200 steps withdrawn

All other Control Bank D control rods are at 216 steps withdrawn as indicated on DRPI and step demand counters

The crew is performing AP-14 (CONTROL ROD MALFUNCTION)

Based on the conditions above,

1) the MAXIMUM time allowed to restore Control Rod H-8 to within limits per Tech. Spec. 3.1.4 (ROD GROUP ALIGNMENT LIMITS) is .

2) in accordance with AP-14, the lift coil disconnect switches, located in the Rod Disconnect Panel, on will be placed in the disconnect position for all rods except H-8 when initially attempting to withdraw Control Rod H-8.

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

2. 1MC-5 C. 1. 30 minutes

2. Power Cabinet 2BD D. 1. 30 minutes

2. 1MC-5 Page 35 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 36 (1 point)

Given the following initial conditions on Unit 2:

Unit is in Mode 6

Fuel loading in progress Subsequently,

2EMF-39(L) (CONTAINMENT GAS-LO RANGE) Trip 2 alarm is received

2EMF-3 (CONTAINMENT REFUELING BRIDGE) Trip 2 alarm is received Based on the conditions above,

1) the Containment Evacuation alarm automatically actuate.

2) VP be automatically secured.

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

A. 1. will

2. will B. 1. will

2. will NOT C. 1. will NOT

2. will D. 1. will NOT

2. will NOT Page 36 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 37 (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

All Pressurizer heaters are energized in MANUAL

The SLIM for 1NV-238 (CHARGING FLOW CONTROL) has been placed in MANUAL due to a malfunction of the Pressurizer Level Master Controller

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

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

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

A. 1. INCREASING

2. OFF B. 1. INCREASING

2. ON C. 1. DECREASING

2. OFF D. 1. DECREASING

2. ON Page 37 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 38 (1 point)

Given the following conditions on Unit 1:

A Large Break LOCA has occurred

Subcooling based on Core Exit Thermocouples (CETs) indicates negative

(-) 4°F on the Inadequate Core Cooling Monitor (ICCM)

Based on the conditions above, ICCM indication of Subcooling based CETs (1) be displayed in reverse video.

Subsequently, if ONE Core Exit Thermocouple in Quadrant II fails LOW, indicated Subcooling on the ICCM will (2) .

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

A. 1. will

2. become less negative B. 1. will NOT

2. become less negative C. 1. will

2. NOT be affected D. 1. will NOT

2. NOT be affected Page 38 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 39 (1 point)

Given the following sequence of events on Unit 1:

0210 - reactor tripped due to a LOCA

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

0330 - crew enters ECA-1.1, (Loss of Emergency Coolant Recirc)

0350 - The crew is at step 18.b of ECA-1.1 Current conditions at time 0350:

1A NI pump is running, indicating 145 GPM

1B NI pump is running, indicating 185 GPM

Both NV pumps are running, indicating 340 GPM (Consider that the NV pumps have equal capacity)

Subcooling is +35°F Based on the conditions above, at time 0350:

1) the MINIMUM flow from the ECCS pumps which will match the decay heat removal requirements of ECA-1.1 is .

AND

2) to meet the ECCS requirements of ECA-1.1, the crew will .

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

REFERENCE PROVIDED A. 1. 310 GPM

2. stop both NI pumps B. 1. 310 GPM

2. stop the 1B NI pump AND one NV pump C. 1. 330 GPM

2. stop both NV pumps D. 1. 330 GPM

2. stop the 1A NI pump AND one NV pump Page 39 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 40 (1 point)

Given the following conditions on Unit 2:

A Small Break LOCA results in a Reactor Trip and Safety Injection

The crew has implemented E-1 (LOSS OF REACTOR OR SECONDARY COOLANT)

Subcooling is -2°F

Pressurizer level is 2%

Containment pressure is 2.5 PSIG and STABLE

CETs are 650°F and slowly increasing In accordance with E-1, the NCPs should (1) to (2) .

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

A. 1. be stopped

2. minimize NC system inventory loss B. 1. remain running

2. provide forced cooling flow through the core C. 1. be stopped

2. prevent pump damage due to loss of support systems D. 1. remain running

2. aid in refilling the pressurizer to satisfy SI termination criteria Page 40 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 41 (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

The following trends are observed on the 1A NCP:

Time 0200 0205 0210 0215 Pump #1 Seal D/P (PSID) 215 210 205 195 Lower pump bearing temp (°F) 221 224 228 231

1 seal outlet temp (°F) 222 237 246 253 Motor winding temp (°F) 303 310 316 323 At what time is 1A NCP trip criteria FIRST exceeded?

A. 0200 B. 0205 C. 0210 D. 0215 Page 41 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 42 (1 point)

In accordance with AP-12 (LOSS OF LETDOWN, CHARGING, or SEAL INJECTION),

After stabilizing the plant, what is the proper order of the major mitigation actions?

A. Restore Letdown, Charging, and Seal Injection B. Restore Letdown, Seal Injection, and Charging C. Restore Charging, Seal Injection, and Letdown D. Restore Charging, Letdown, and Seal Injection Page 42 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 43 (1 point)

Given the following initial conditions on Unit 1:

Unit is in MODE 5

'A' Train of ND, KC and RN are in service

The standby KC train is NOT available to start

NC system temperature is being maintained at 140°F Subsequently,

1A2 KC pump trips on overcurrent In accordance with AP-21 (LOSS OF KC OR KC SYSTEM LEAKAGE), the action which would maintain or restore the NC system to its INITIAL temperature is to throttle (1) OR throttle (2) .

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

(ASSUME THE ACTIONS LISTED DO NOT RESULT IN EXCEEDING ANY FLOW OR TEMPERATURE LIMITATIONS)

COMPONENT LEGEND:

1ND-34 (1A & 1B ND HX BYPASS)

1NV-459 (U1 VARIABLE L/D ORIFICE OUTLET FLOW CONTROL)

1KC-149 (1A KF HX OUTLET FLOW)

1RN-89A (RN TO A KC HX CONTROL)

A. 1. CLOSED 1NV-459

2. OPEN 1RN-89A B. 1. CLOSED 1KC-149

2. OPEN 1ND-34 C. 1. OPEN 1ND-34

2. OPEN 1RN-89A D. 1. OPEN 1KC-149

2. CLOSED 1NV-459 Page 43 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 44 (1 point)

Given the following conditions on Unit 2:

KC Surge Tank level is lowering slowly

The crew has implemented AP-21 (LOSS OF KC OR KC SYSTEM LEAKAGE)

Based on the conditions above, a possible location of the KC system leakage is into the (1) heat exchanger.

The assured supply of makeup water to the KC Surge tank is (2) .

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

A. 1. Letdown

2. YM B. 1. Letdown

2. RN C. 1. Seal Water Return

2. YM D. 1. Seal Water Return

2. RN Page 44 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 45 (1 point)

Given the following initial conditions:

Both units have experienced a Loss of Offsite Power

BOTH Diesel VI compressors are NOT available

ECA-0.0 (LOSS OF ALL AC POWER) was implemented on Unit 1 and the crew has just transitioned to ECA-0.1 (LOSS OF ALL AC POWER RECOVERY WITHOUT S/I REQUIRED)

Current conditions:

NC Thots are STABLE

S/G pressures are STABLE at 725 PSIG

S/G levels are decreasing and approaching 11% NR

NC Tcolds are 490°F and STABLE

VI header pressure is 0 PSIG Based on the conditions above,

1) Natural Circulation flow been established.

2) in accordance with ECA-0.1, the Operators will .

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

REFERENCE PROVIDED A. 1. HAS

2. increase CA flow using flow controllers in the control room B. 1. HAS

2. increase CA flow by notifying AO to throttle CA valves locally C. 1. HAS NOT

2. increase dumping steam using SM PORV controller on main control board AND increase CA flow using flow controllers in the control room D. 1. HAS NOT

2. dispatch an operator to locally increase flow from the SM PORV AND increase CA flow by notifying AO to throttle CA valves locally Page 45 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 46 (1 point)

Given the following initial conditions on Unit 1:

Unit is in Mode 6

NC System WR level is at +2 inches and lowering

AP-19 (LOSS OF ND OR ND SYSTEM LEAKAGE) has been implemented

The CRS has decided to makeup to the NC system using gravity feed through 1ND-35 (UNIT 1 ND to FWST ISOL) and 1NI-173A (1A ND to A & B COLD LEGS CONT OUTSIDE ISOL)

In accordance with AP-19,

1) flow to the NC system will be established by throttling 1ND-35 .

2) ND pump operation is not allowed with 1ND-35 OPEN because will occur.

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

A. 1. from the Control Room

2. a loss of NC system inventory outside containment B. 1. from the Control Room

2. ND pump runout conditions C. 1. locally

2. a loss of NC system inventory outside containment D. 1. locally

2. ND pump runout conditions Page 46 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 47 (1 point)

Given the following initial conditions on Unit 1:

The unit is at 10% RTP

The turbine is rolling at 1800 RPM in preparation for a unit startup

Status lights on 1SI-3 indicate the following:

Subsequently,

A steam line break occurs upstream of the 1D S/G MSIV

1D S/G pressure is 700 PSIG

The status lights on 1SI-3 currently indicate the following:

Based on the indications above:

1) the Main Steam Isolation valves operated as required.

2) the Main Steam Isolation Bypass valves operated as required.

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

(ASSUME NO OPERATOR ACTIONS HAVE BEEN TAKEN)

A. 1. have

2. have B. 1. have

2. have NOT C. 1. have NOT

2. have D. 1. have NOT

2. have NOT Page 47 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 48 (1 point)

Given the following initial conditions on Unit 1:

The crew is performing a Unit Startup and Power increase

Unit is holding at 2% RTP per OP/1/A/6100/003 (POWER INCREASE)

1A CF pump is out of service for emergent repairs Subsequently,

1B CF pump trips on low lube oil pressure

The crew enters AP/1/A/5500/006 (S/G FEEDWATER MALFUNCTION)

1) In accordance with AP-06, what is the MAXIMUM power level allowed, above which, a manual reactor trip is required?

2) What is the basis for manually tripping the reactor above that power level?

A. 1. 5%

2. to prevent an inadvertent mode change B. 1. 5%

2. to ensure CA can maintain adequate S/G levels C. 1. 3%

2. to prevent an inadvertent mode change D. 1. 3%

2. to ensure CA can maintain adequate S/G levels Page 48 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 49 (1 point)

Given the following conditions on Unit 2:

The unit is at 100% RTP

A loss of power occurs on 2EKVA Which ONE (1) of the following indicates the Power Range Nuclear Instrument channels that are still operable and can be used for backup indication of reactor power?

A. N-41, N-42, N-43 B. N-41, N-43, N-44 C. N-41, N-42, N-44 D. N-42, N-43, N-44 Page 49 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 50 (1 point)

Given the following conditions on Unit 1:

The 125VDC/120VAC Auxiliary Control Power System is in normal alignment

The supply breaker from DCA to Static Inverter KXA trips open Based on the conditions above,

1) Bus KXA automatically swap to its alternate power source.

2) the crew can verify power has been restored to KXA by observing that Which ONE (1) of the following completes the statements above?

COMPONENT LEGEND:

0RN-10AC (TRAIN 1B & 2B LLI SUPPLY)

A. 1. will

2. NC pump vibration monitors are IN SERVICE B. 1. will

2. the indicating light (control power) to 0RN-10AC is LIT C. 1. will NOT

2. the NC pump vibration monitors are IN SERVICE D. 1. will NOT

2. the indicating light (control power) to 0RN-10AC is LIT Page 50 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 51 (1 point)

Given the following initial conditions on Unit 1:

The unit is at 100% RTP

Both trains of KC and RN are in service Subsequently,

1A RN pump TRIPS

A Blackout occurs on 2ETB Based on the conditions above, the 1A KC HX (1) have cooling water because the RN essential headers (2) . (Assuming no operator actions)

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

A. 1. does

2. are always cross-connected B. 1. does

2. automatically cross-connected when the 1A RN pump tripped C. 1. does NOT

2. are always separated D. 1. does NOT

2. on both units automatically separate on any Blackout on either unit Page 51 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 52 (1 point)

Given the following plant conditions:

Both units are operating at 100% RTP

An instrument air system leak develops in the Unit 1 Turbine Building The following indications are observed in the Control Room:

Based on the indications above, the Diesel VI Compressors (1) receive an auto start signal .

If an auto start signal is received, the Diesel VI compressors (2) start AND load if the START/WARM-UP/RUN switch is selected to the WARM-UP position.

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

A. 1. will

2. will NOT B. 1. will

2. will C. 1. will NOT

2. will NOT D. 1. will NOT

2. will Page 52 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 53 (1 point)

Given the following conditions on Unit 1:

Turbine Load is 900 MWe

Generator Hydrogen Pressure is 60 PSIG

Generator Voltage is 22.8 KV According to the Main Generator Capability Curve the accepable range of reactive load is .

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

REFERENCE PROVIDED A. 860 MVAR (Lagging) to -640 MVAR (Leading)

B. 840 MVAR (Lagging) to -710 MVAR (Leading)

C. 710 MVAR (Lagging) to -560 MVAR (Leading)

D. 690 MVAR (Lagging) to -630 MVAR (Leading)

Page 53 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 54 (1 point)

Given the following conditions on Unit 2:

The crew has implemented ECA-1.2 (LOCA OUTSIDE CONTAINMENT)

U2 FWST level is slowly lowering

NC system pressure is 1600 PSIG and slowly lowering In accordance with ECA-1.2,

1) the crew will FIRST stop and isolate the pumps from the FWST.

2) an NC system depressurization and cooldown at will be required.

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

A. 1. NI

2. the maximum rate B. 1. NI

2. 100°F/hr C. 1. ND

2. the maximum rate D. 1. ND

2. 100°F/hr Page 54 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 55 (1 point)

Given the following initial conditions on Unit 1:

The crew has implemented FR-H.1 (RESPOND TO A LOSS OF SECONDARY HEAT SINK)

Feed and Bleed criteria is met

1) Which Cold Leg Accumulators (CLAs) provide backup motive force to open the PZR PORVs?

2) To establish adequate heat removal during Feed and Bleed, what is the MINIMUM number of PZR PORVs that must be opened? (Consider PORVs ONLY)

A. 1. A and B

2. 1 B. 1. A and B

2. 2 C. 1. C and D

2. 1 D. 1. C and D

2. 2 Page 55 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 56 (1 point)

Given the following conditions on Unit 1:

A Large Break LOCA has occurred inside Containment

A and B ND pumps are not available

The Control room crew has implemented ECA-1.1 (LOSS OF EMERGENCY COOLANT RECIRC) but, NO actions have been taken

Containment pressure is 8 PSIG and slowly rising

FWST level is 105 inches and lowering When the FWST Level LO setpoint is reached, 1NI-184B (1B ND PUMP SUCTION FROM CONT SUMP ISOL) AND 1NI-185A (1A ND PUMP SUCTIONFROM CONT SUMP ISOL) (1) automatically OPEN.

Per ECA-1.1 Foldout Page, when FWST level decreases to less than a MAXIMUM of (2) inches ALL ECCS pumps must be secured.

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

A. 1. will

2. 20 B. 1. will NOT

2. 20 C. 1. will

2. 95 D. 1. will NOT

2. 95 Page 56 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 57 (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

Control Rod P-8 (Control Bank C, Group 1) drops fully into the core due to a blown stationary gripper fuse

The crew implements AP-14 (CONTROL ROD MALFUNCTION)

Subsequently,

The blown fuse has been replaced and all requirements have been met for the operating crew to recover Control Rod P-8

As Control Rod P-8 begins to move, annunciator 1AD-2 / A10 (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. 1AC B. 2AC C. 1BD D. 2BD Page 57 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 58 (1 point)

Based on the indications above, the entry conditions of FR-H.2 (RESPONSE TO STEAM GENERATOR OVERPRESSURE) (1) met.

FR-H.2 is designed to address a failure of (2) .

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

A. 1. are

2. a S/G PORV ONLY B. 1. are NOT

2. a S/G PORV ONLY C. 1. are

2. a S/G PORV AND the Main Steam Line Code Safety valves D. 1. are NOT

2. a S/G PORV AND the Main Steam Line Code Safety valves Page 58 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 59 (1 point)

Given the following conditions on Unit 2:

The crew has implemented AP-10 (NC SYSTEM LEAKAGE), Case 1 (S/G TUBE LEAKAGE)

Pressurizer level has been stabilized

Letdown flow is 45 GPM

Charging flow is 110 GPM Based on the conditions above, the estimated leak rate is (1) GPM.

Per OP/1/A/6200/001 (NV System), letdown flow through Normal Letdown shall not exceed a MAXIMUM of (2) GPM.

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

A. 1. 65

2. 120 B. 1. 65

2. 185 C. 1. 53

2. 120 D. 1. 53

2. 185 Page 59 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 60 (1 point)

Given the following conditions on Unit 1:

Unit is at 85% RTP

Main condenser vacuum is 24.5" Hg and degrading at a rate of 0.5" Hg per minute

Crew has entered AP-23 (LOSS OF CONDENSER VACUUM)

Based on the conditions above, Control Interlock (C-9) will block the ability to dump steam to the condenser in a MINIMUM of (1) minutes.

The reason for the Main Turbine trip on loss of Condenser vacuum is to (2) .

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

A. 1. 3

2. prevent condenser damage due to over-pressurization B. 1. 3

2. minimize low pressure turbine blading damage due to low vacuum conditions C. 1. 9

2. prevent condenser damage due to over-pressurization D. 1. 9

2. minimize low pressure turbine blading damage due to low vacuum conditions Page 60 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 61 (1 point)

Given the following conditions on Unit 1:

A Ventilation Unit Condensate Drain Tank (VUCDT) release to the RC Discharge is in progress

A 1EMF-44(L) (CONTAINMENT VENTILATION DRAINS - LOW RANGE)

Trip 2 alarm is received Which ONE (1) of the following indicates the automatic response to the EMF alarm?

COMPONENT LEGEND:

1WP-35 (WMT/VUCDT to RC CNTRL)

1WL-320 (VUCDT RAD MONITOR OUTLET)

1WL-322B (CONT VENT DRN OTSD ISOL)

A. 1WP-35 ONLY CLOSES B. 1WL-320 AND 1WP-35 CLOSE C. 1WL-322B ONLY CLOSES D. 1WL-320 AND 1WL-322B CLOSE Page 61 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 62 (1 point)

Given the following conditions on Unit 2:

A Large Break LOCA has occurred

ES-1.3 (TRANSFER TO COLD LEG RECIRC) has been implemented

Containment pressure is 4 PSIG ES-1.3 directs the crew to start an NS pump if Containment pressure is greater than a MINIMUM of (1) PSIG.

The reason that ES-1.3 directs the crew to reset Safety Injection (SI) and the Sequencers prior to attempting to start an NS pump is that (2) .

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

A. 1. 3

2. the NS pumps are locked out until the Sequencers are reset B. 1. 3

2. the NS pump discharge valves cannot be opened unless SI is reset C. 1. 1

2. the NS pumps are locked out until the Sequencers are reset D. 1. 1

2. the NS pump discharge valves cannot be opened unless SI is reset Page 62 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 63 (1 point)

Given the following conditions on Unit 1:

A Loss of Off-Site Power (LOOP) has occurred

Due to multiple equipment failures, the crew has implemented FR-C.1 (RESPONSE TO INADEQUATE CORE COOLING)

"LOW PRESSURE STEAMLINE ISOL" has been blocked

Operators are preparing to depressurize intact steam generators to 190 PSIG Based on the conditions above,

1) the CRS will direct the operating crew to establish a cooldown rate.

2) the cooldown and depressurization will be performed using the .

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

A. 1. 100 °F/hour

2. steam dumps B. 1. 100 °F/hour

2. S/G PORVs C. 1. maximum

2. steam dumps D. 1. maximum

2. S/G PORVs Page 63 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 64 (1 point)

Given the following initial conditions on Unit 2:

A Small Break LOCA has occurred

The crew has entered ES-1.2 (POST LOCA COOLDOWN AND DEPRESSURIZATION) and began an NC system cooldown and depressurization Subsequently,

Annunciator 2AD-6 / A12 (PORV LO PRESS MODE NOT SELECTED) alarms For this alarm to be valid, NC system (1) ,.

AND the PORV OVERPRESS PROTECTION SELECT switch for 2NC-34A OR (2) must be in the NORM position.

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

COMPONENT LEGEND:

2NC-34A (U2 PZR PORV) 2NC-32B (U2 PZR PORV) 2NC-36B (U2 PZR PORV)

A. 1. temperature must be less than a setpoint of 320°F

2. 2NC-36B B. 1. pressure must be less than a setpoint of 380 PSIG

2. 2NC-36B C. 1. temperature must be less than a setpoint of 320°F

2. 2NC-32B D. 1. pressure must be less than a setpoint of 380 PSIG

2. 2NC-32B Page 64 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 65 (1 point)

Given the following on Unit 1:

A Large Break LOCA has occurred

Containment sump level is 7.5 feet and rising at a constant rate of 0.25 feet per minute

1) FR-Z.2 (RESPONSE TO CONTAINMENT FLOODING) entry conditions will be met in a MINIMUM of minutes.

2) Why is safe plant recovery not assured for a design-basis Large Break LOCA when Containment water level requires entry into FR Z.2?

A. 1. 24

2. Operation of critical ECCS components needed for safe recovery is endangered by submersion.

B. 1. 24

2. Operation of the hydrogen skimmer system is compromised by the suction line becoming submerged.

C. 1. 20

2. Operation of critical ECCS components needed for safe recovery is endangered by submersion.

D. 1. 20

2. Operation of the hydrogen skimmer system is compromised by the suction line becoming submerged.

Page 65 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 66 (1 point)

Given the following initial conditions on Unit 1:

Unit is at 30% RTP and STABLE

Control rods are in manual Subsequently,

1ETA normal incoming breaker trips OPEN

The 1A D/G starts and is carrying the 1ETA bus

The RO reports that reactor power has increased to 34% and is now STABLE Per AD-OP-ALL-0203 (REACTIVITY MANAGEMENT), what actions (if any) will the crew take in response to the power increase?

A. Move control rods as necessary to restore Tave = Tref.

B. No actions are required since power is less than 100% RTP.

C. Borate to establish power at or below the pre-transient power level.

D. Reduce turbine load to establish power at or below the pre-transient power level.

Page 66 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 67 (1 point)

Given the following conditions on Unit 1:

The unit is in Mode 6

"A" ND Train is in operation

"B" ND Train is available Which ONE (1) of the following conditions would prevent commencing fuel movement?

(Consider each individually)

A. The reactor has been subcritical for 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months .

B. The Equipment Hatch is closed with 2 bolts fastened.

C. The Refueling Cavity level is lowered to 370 on 1NCP-5990 (NC WR LEVEL).

D. MCB Annunciator 1AD10/F-1 (UPPER CONT AIRLOCK RX DOOR OPEN),

alarms.

Page 67 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 68 (1 point)

Given the following plant conditions:

The Main Control Room has been evacuated

AP-17 (LOSS OF CONTROL ROOM) has been implemented

Both Auxiliary Shutdown Panels (ASP) are manned The Operator at the Unit 1 ASP believes that the following indications at the Unit 1 ASP are not indicating correctly:

1. NC System Cold Leg Temperature

2. NC System Hot Leg Temperature

3. NC System WR Pressure

4. NC System Letdown Flow Which ONE (1) of the following indicates the parameters listed above that can be verified using redundant indications at the Safe Shutdown Facility (SSF)?

A. 1&4 B. 2&4 C. 1&3 D. 2&3 Page 68 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 69 (1 point)

Regarding Maintenance Rule Assessments,

1) NSD-403 (SHUTDOWN RISK MANAGEMENT) is the official tool for performing risk assessments in and below.

2) when using the Electronic Risk Assessment Tool (ERAT), the color .

is associated with a key safety function being in condition that is "REDUCED but still acceptable".

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

A. 1. MODE 3

2. ORANGE B. 1. MODE 4

2. ORANGE C. 1. MODE 3

2. YELLOW D. 1. MODE 4

2. YELLOW Page 69 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 70 (1 point)

Given the following conditions on Unit 2:

NC system temperature is 195°F

NC system pressure is 320 PSIG Based on the conditions above, the FWST (1) required to be OPERABLE per Technical Specification 3.5.4 (Refueling Water Storage Tank).

When the FWST is required to be operable, and level is less than the borated water volume required by Surveillance Requirement 3.5.4.2, (2) are required.

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

A. 1. is

2. immediate actions to restore the FWST to OPERABLE status B. 1. is

2. actions to restore the FWST to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months C. 1. is NOT

2. immediate actions to restore the FWST to OPERABLE status D. 1. is NOT

2. actions to restore the FWST to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Page 70 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 71 (1 point)

An Operator needs to access an area with a general area radiation dose rate of 1100 mREM/hr to hang a clearance tag.

In accordance with AD-RP-ALL-2017 (ACCESS CONTROLS FOR HIGH, LOCKED HIGH, AND VERY HIGH RADIATION AREAS),

1) the correct radiation posting for this area is a .

2) the Radiation Protection requirements for entry are .

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

A. 1. High Radiation Area

2. continuous RP coverage B. 1. High Radiation Area

2. a documented RP briefing ONLY C. 1. Locked High Radiation Area

2. continuous RP coverage D. 1. Locked High Radiation Area

2. a documented RP briefing ONLY Page 71 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 72 (1 point)

Given the following conditions on Unit 1:

Mode 4 valve checklist PT is being performed

The PT calls for independent verification of a single valve located in a room with a general area dose rate of 110 mREM/hr

Estimated time to independently verify the valve's position is 5 minutes 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. can NOT

2. the general area dose rate is less than 500 mREM/hr B. 1. can NOT

2. the radiation exposure for a single verification is within the allowable limit C. 1. can

2. the general area dose rate is greater than 100 mREM/hr D. 1. can

2. the radiation exposure for a single verification exceeds the allowable limit Page 72 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 73 (1 point)

Given the following initial conditions on Unit 1:

"B" Train equipment is in service Subsequently,

The 1B RN pump amps are swinging

The following annunciators alarm:

o 1AD-12 / A-4 (B RN PMP DISCHARGE LO PRESS) o 1AD-12 / C-4 (B RN PUMP SUCTION LO PRESS)

The crew implements AP-20 (LOSS OF RN)

PROCEDURE LEGEND:

AP-20, CASE I (LOSS OF OPERATING RN TRAIN)

AP-20, CASE II (LOSS OF LOW LEVEL OR RC SUPPLY CROSSOVER)

Based on the conditions above, the crew will enter AP-20, (1) .

In accordance with the AP-20 mitigating strategy for this event, the crew (2) ,

swap the RN pump suction to the SNSWP?

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

A. 1. Case I

2. will B. 1. Case I

2. will NOT C. 1. Case II

2. will D. 1. Case II

2. will NOT Page 73 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 74 (1 point)

Given the following plant conditions:

Fire Brigade has extinguished a fire in the Unit 2 Turbine Building

A Main Fire Pump is out-of-service

1A and 1B Jockey Pumps are OFF

B Main Fire Pump is running

C Main Fire Pump is OFF The automatic start setpoint for the "B" Main Fire Pump on decreasing fire header pressure is (1) PSIG.

In accordance with OP/1/A/6400/002A (FIRE PROTECTION SYSTEM), the sequence for returning the Fire Protection system to normal alignment is to (2) .

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

A. 1. 73

2. place the Jockey Pump to be started in MAN, START the Jockey Pump selected to MAN, and stop the B Main Fire Pump.

B. 1. 73

2. stop the B Main Fire Pump, place the Jockey Pump to be started in MAN, and START the Jockey Pump selected to MAN.

C. 1. 78

2. place the Jockey Pump to be started in MAN, START the Jockey Pump selected to MAN, and stop the B Main Fire Pump.

D. 1. 78

2. stop the B Main Fire Pump, place the Jockey Pump to be started in MAN, and START the Jockey Pump selected to MAN.

Page 74 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 75 (1 point)

Given the following conditions on Unit 1:

The unit is in MODE 4

"A" Train of ND is in service

Annunciator 1AD-9 / A1 (1ND-2A OPEN AND NC HI PRESS) has just come into alarm

NC WR pressure is indicating 460 PSIG Based on the conditions above,

1) 1ND-1B AUTO CLOSE.

2) the redundant indication which would be used to verify that this annunciator is valid is .

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

COMPONENT LEGEND:

1ND-2A (C HL SUCTION TO ND ISOLATION) 1ND-1B (C HL SUCTION TO ND ISOLATION)

A. 1. will

2. CF&E sump level rising B. 1. will

2. PRT level rising C. 1. will NOT

2. CF&E sump level rising D. 1. will NOT

2. PRT level rising Page 75 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 76 (1 point)

Given the following initial conditions on Unit 1:

The unit is increasing power following a Refueling Outage

At 42% reactor power, the P-8 permissive bistable fails "AS IS" Subsequently,

Reactor power is currently 52%

1A NCP trips Based on the conditions above, an automatic Reactor trip signal (1) be generated.

If subsequent conditions require implementation of FR-S.1 (RESPONSE TO NUCLEAR GENERATION / ATWS), the crew will transition from FR-S.1 to E-0 (REACTOR TRIP OR SAFETY INJECTION) (2) .

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

A. 1. will

2. after FR-S.1 is performed to completion B. 1. will NOT

2. after FR-S.1 is performed to completion C. 1. will

2. immediately upon a successful Reactor trip D. 1. will NOT

2. immediately upon a successful Reactor trip Page 76 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 77 (1 point)

Given the following conditions on Unit 2:

The unit is in MODE 3

A cooldown is in progress to comply with TS 3.0.3

NC system pressure is 1980 PSIG

NC system temperature is 500°F

An inadvertent actuation of SI Train B occurs Based on the conditions above,

1) Ice Bed temperatures will .

2) the optimal procedure flowpath to mitigate this event is to implement .

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

PROCEDURE LEGEND:

E-0 (REACTOR TRIP OR SAFETY INJECTION)

ES-1.1 (SI TERMINATION)

AP-35 (ECCS ACTUATION DURING PLANT SHUTDOWN)

A. 1. increase

2. AP-35 B. 1. remain the same

2. AP-35 C. 1. increase

2. E-0 and then transition to ES-1.1 D. 1. remain the same

2. E-0 and then transition to ES-1.1 Page 77 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 78 (1 point)

Given the following conditions on Unit 1:

The unit is at 8% RTP preparing to roll the main turbine

M1A1276 (U1 CA Temp at Chk Vlv 1CA-37) alarms on the OAC Based on the conditions above, in accordance with OP/1/A/6250/002 (AUXILIARY FEEDWATER SYSTEM), the method that will FIRST be used to reduce the temperature at the check valve is to (1) .

In accordance with Tech Spec 3.7.5 (AFW SYSTEM), actions taken to reduce the temperature at the check valve (2) the TD CA pump to be declared INOPERABLE.

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

COMPONENT LEGEND:

1CA-37 (#1 TD CA TO S/G D) 1CA-36AB (U1 TD CA PUMP DISCH TO 1D S/G CONTROL) 1CA-38B (U1 TD CA PUMP DISCH TO 1D S/G ISOL)

REFERENCE PROVIDED A. 1. close 1CA-36AB and monitor temperature for 15 minutes

2. requires B. 1. close 1CA-36AB and monitor temperature for 15 minutes

2. does NOT require C. 1. close 1CA-38B and start the U1 TD CA pump aligned for recirculation to the UST

2. requires D. 1. close 1CA-38B and start the U1 TD CA pump aligned for recirculation to the UST

2. does NOT require Page 78 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 79 (1 point)

Given the following initial conditions on Unit 1:

Unit is in Mode 4 with a plant cooldown in progress

B Train in service Subsequently,

Containment Pressure begins rising

The SAFETY INJECTION ACTUATED status light on 1SI-18 is LIT

The crew implements AP-34 (SHUTDOWN LOCA)

The following indications are observed on 1SI-14:

Based on the conditions and indications above,

1) the will overheat due to loss of RN cooling.

2) the crew will be directed to to mitigate this event.

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

PROCEDURE LEGEND:

AP-10 (NC SYTEM LEAKAGE WITHIN THE CAPACITY OF BOTH NV PUMPS)

A. 1. NC pumps

2. GO TO AP-10 B. 1. running DG

2. GO TO AP-10 C. 1. NC Pumps

2. remain in AP-34 D. 1. running DG

2. remain in AP-34 Page 79 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 80 (1 point)

Given the following plant conditions:

Both units are at 100% RTP

A malfunction of the VI Air Dryers has resulted in rapidly decreasing VI Header pressures

Both units have implemented AP-22 (LOSS OF VI)

In accordance with AP-22,

1) what is the MAXIMUM VI Header pressure which requires implementation of Enclosure 7 (RN ALIGNMENT DURING LOSS OF VI EVENT)?

2) which of the following conditions will FIRST require the crew to initiate a manual reactor trip?

A. Pressurizer level begins INCREASING in an uncontrolled manner B. S/G levels begin DECREASING in an uncontrolled manner A. 1. 60 PSIG

2. A B. 1. 85 PSIG

2. A C. 1. 60 PSIG

2. B D. 1. 85 PSIG

2. B Page 80 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 81 (1 point)

Given the following initial conditions on Unit 2:

A unit load increase in on hold at 35% RTP

Control Bank D rod M-4 is at 160 steps by DRPI

Control Bank D Group Step Counters indicate 170 steps Subsequently,

I&E determines that rod M-4 will not move because the lift coil disconnect switch has failed The rod alignment limits of Tech Spec 3.1.4 (ROD GROUP ALIGNMENT LIMITS)

(1) met.

In accordance with Tech Spec 3.1.7 (ROD POSITION INDICATION) Bases, the basis for the operability of the Rod Position Indication system is to verify that the assumptions in the plant's safety analysis which are directly related to (2) .

distribution are being met.

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

A. 1. are

2. core power B. 1. are NOT

2. core power C. 1. are

2. fuel burnup D. 1. are NOT

2. fuel burnup Page 81 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 82 (1 point)

Given the following conditions on Unit 1:

Containment Pressure Channel 3 has failed low due to a failed power supply

The failed channel has NOT been removed from service by I&E Based on the conditions above, the current Containment Pressure channel logic for the remaining Containment Pressure channels which will cause a Safety Injection actuation is (1) .

In accordance with Tech Spec 3.3.2 (ESFAS INSTRUMENTATION) LCO actions, when the failed channel is removed from service, I&E will place the Containment Pressure Hi-Hi Bistable in (2) .

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

A. 1. 1/2

2. TRIP B. 1. 2/2

2. TRIP C. 1. 1/2

2. BYPASS D. 1. 2/2

2. BYPASS Page 82 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 83 (1 point)

Given the following conditions on Unit 2:

The unit is at 100% RTP

The 2A SM PORV is leaking

The 2A SM PORV Block valve has been CLOSED Based on the conditions above,

1) in accordance with Tech Spec 3.7.4 (SG PORVs) Basis, the 2A SM PORV is

2) Tech Spec 3.7.4 requires SM PORVs to be OPERABLE.

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

A. 1. OPERABLE

2. three B. 1. OPERABLE

2. two C. 1. INOPERABLE

2. three D. 1. INOPERABLE

2. two Page 83 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 84 (1 point)

Given the following initial conditions on Unit 1:

A Reactor startup is in progress

Shutdown Bank rods are fully withdrawn

Control Bank A is at 100 steps

All NCPs are in service Subsequently, the following indications are observed:

OAC Point M1A0698 (1D NC PUMP LOWER RADIAL BRG TMP) alarm

OAC Point M1A0744 (1D NC PUMP MOTOR UPPER BEARING TEMP) alarm

OAC Point M1A0720 (1D NC PUMP MOTOR LOWER BEARING TEMP) alarm

1D NC pump lower radial bearing temperature = 200°F and increasing slowly

1D NC pump motor upper bearing temperature = 200°F and increasing slowly

1D NC pump motor lower bearing temperature = 180°F and increasing slowly The crew has implemented AP-08 (REACTOR COOLANT PUMP MALFUNCTION)

Based on the conditions above,

1) the CRS will implement .

2) if stopping the 1D NC pump is required, the procedure flowpath will be to Which ONE (1) of the following completes the statements above?

PROCEDURE LEGEND:

AP-08 Case I (NC PUMP SEAL OR PUMP LOWER BEARING MALFUNCTION)

AP-08 Case II (NC PUMP MOTOR OR MOTOR BEARING MALFUNCTION)

E-0 (REACTOR TRIP OR SAFETY INJECTION)

A. 1. AP-08, Case I

2. stop the 1D NC pump and continue in AP-08 B. 1. AP-08, Case I

2. trip the reactor, stop 1D NC pump, and transition to E-0 C. 1. AP-08, Case II

2. stop the 1D NC pump and continue in AP-08 D. 1. AP-08, Case II

2. trip the reactor, stop 1D NC pump, and transition to E-0 Page 84 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 85 (1 point)

Given the following conditions on Unit 2:

The unit is at 100% RTP

A DCS malfunction causes the Selected Pressurizer Pressure 1 input to the Pressurizer Master Controller to fail HIGH

In accordance with AP-11 (PRESSURIZER PRESSURE ANOMALIES), the BOP has manually closed 2NC-34A (PZR PORV) and 2NC-27C and 29C (PRESSURIZER SPRAY VALVES)

The Pressurizer Pressure Master Controller is in MANUAL

1) In accordance with Tech Spec 3.4.11 (PRESSURIZER PORVs), in what MODES are the Pressurizer PORVs required to be OPERABLE?

2) In accordance with Tech Spec 3.4.11 Bases, is 2NC-34A OPERABLE?

A. 1. 1, 2, and 3 ONLY

2. No B. 1. 1, 2, 3, and 4

2. No C. 1. 1, 2, and 3 ONLY

2. Yes D. 1. 1, 2, 3, and 4

2. Yes Page 85 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 86 (1 point)

Given the following initial conditions on Unit 1:

The unit is at 30% RTP

NC pump 1C trips due to an error during I&E testing Subsequently,

A lockout occurs on 1A Busline due to a fault

The Reactor Trip breakers remain closed Based on the conditions above,

1) an ATWS in progress.

2) the crew will .

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

PROCEDURE LEGEND:

Technical Specification 3.4.4 (RCS LOOPS MODES 1 & 2)

REFERENCE PROVIDED A. 1. is

2. manually trip the turbine to conserve SG inventory B. 1. is

2. manually trip the turbine to generate a redundant reactor trip signal C. 1. is NOT

2. restart 1C NC pump within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to comply with TS 3.4.4 D. 1. is NOT

2. place the unit in MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to comply with TS 3.4.4 Page 86 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 87 (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

1EMF-33 (CONDENSER AIR EJECTOR EXHAUST) is INOPERABLE

The crew is performing PT/1/A/4150/001 B (REACTOR COOLANT LEAKAGE CALCULATION)

During the surveillance, S/G Primary-to-Secondary leakage was determined to be:

S/G Leakage (GPD) 1A 125 1B 50 1C 75 1D 40 Based on the conditions above,

1) in accordance with PT/1/A/4150/001 B, 1EMF 71-74 indications a valid method to evaluate whether the requirements of Technical Specification Surveillance SR 3.4.13.2 (Primary-to-Secondary Leakage) are met.

2) Primary-to-Secondary leakage within the limits of Technical Specification 3.4.13 (RCS OPERATIONAL LEAKAGE).

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

COMPONENT LEGEND:

1EMF-71 thru 74 (N16 LEAKAGE)

A. 1. are NOT

2. is B. 1. are NOT

2. is NOT C. 1. are

2. is D. 1. are

2. is NOT Page 87 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 88 (1 point)

In accordance with Tech Spec 3.6.6 (CONTAINMENT SPRAY SYSTEM) Bases:

1) the Containment Spray System is designed to work in conjunction with the Ice Condensers to limit peak Containment Pressure and peak Containment Temperature during a Design-Basis ,

AND

2) a Design-Basis LOCA will result in peak Containment .

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

A. 1. LOCA ONLY

2. pressure B. 1. Steam Line Break ONLY

2. temperature C. 1. LOCA OR Steam Line Break

2. temperature D. 1. LOCA OR Steam Line Break

2. pressure Page 88 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 89 (1 point)

Given the following sequence of events on Unit 1:

A LOCA has occurred

The crew has implemented ECA-1.1 (LOSS OF EMERGENCY COOLANT RECIRC)

Containment pressure is currently 3.2 PSIG In accordance with ECA-1.1, while attempting to establish recirculation flow the crew will cool the core by (1) .

While performing ECA-1.1, if a RED Path occurs on Core Cooling the crew (2) transition to FR-C.1 (RESPONSE TO INADEQUATE CORE COOLING).

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

A. 1. aligning the NC system for Feed and Bleed

2. will B. 1. aligning the NC system for Feed and Bleed

2. will NOT C. 1. dumping steam from intact Steam Generators

2. will D. 1. dumping steam from intact Steam Generators

2. will NOT Page 89 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 90 (1 point)

Given the following conditions on Unit 1:

The unit is at 60% RTP

A unit load increase is on hold due to a potentially stuck Control Bank D rod

The incore thermocouple map indicates the following:

1. Based on the indications above, which Control Bank D rod is stuck?

2. What surveillances (if any) are required per Technical Specification 3.1.4 (ROD GROUP ALIGNMENT LIMITS) to allow continued power operation in MODE 1?

A. 1. Rod D-12

2. RCCA Movement Test B. 1. Rod D-12

2. FNH(X,Y) and FQ(X,Y,Z)

C. 1. Rod M-4

2. RCCA Movement Test D. 1. Rod M-4

2. FNH(X,Y) and FQ(X,Y,Z)

Page 90 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 91 (1 point)

Given the following conditions on Unit 2:

The unit is currently in MODE 5

Source Range Nuclear Instrument count rates begin increasing

The CRS suspects an inadvertent dilution is in progress

Boric Acid Tank (BAT) temperature is 68°F

The crew implements AP-038 (EMERGENCY BORATION AND RESPONSE TO INADVERTENT DILUTION)

2NV-265B (U2 NV PUMP BORIC ACID SUP ISOL) will NOT open In accordance with AP-038, the crew will FIRST attempt to establish emergency boration using .

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

COMPONENT LEGEND:

2NV-269 (UNIT 2 NV PUMP BORIC ACID SUPPLY ISOL (EMERGENCY BORATION VALVE))

2NV-267A (BORIC ACID TO BLENDER CONTROL)

A. NV from the BAT after locally aligning 2NV-269 and 2NV-267 because it is the preferred flow path B. NI from the FWST because it is the preferred flowpath with and INOPERABLE BAT C. NV from the FWST because it is the preferred flowpath D. NV from the FWST because the BAT is INOPERABLE Page 91 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 92 (1 point)

Given following conditions on Unit 1:

0800 A Reactor trip occurred from 100% RTP due to a large steam break 1045 The steam break has been isolated and the unit stabilized with the following conditions:

o NC system temperature = 240°F o NC system pressure = 1000 PSIG Based on the conditions above,

1) as part of the subsequent recovery actions, the crew perform an NC system soak.

2) after NC system pressure is reduced, the next cooldown performed will be at a MAXIMUM rate of per hour.

Which ONE (1) of the following completes the statements above? (CONSIDER EACH QUESTION SEPARATELY)

A. 1. will

2. 50°F B. 1. will

2. 100°F C. 1. will NOT 2 50°F D. 1. will NOT

2. 100°F Page 92 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 93 (1 point)

Given the following conditions on Unit 1:

Chemistry has confirmed two leaking fuel rods

A Large Break LOCA occurs

ES-1.2 (POST LOCA COOLDOWN AND DEPRESSURIZATION) has been implemented

All Red and Orange Paths have been addressed

1EMF-51A = 39 R/Hr

Pressurizer level = 20% and STABLE

Reactor Vessel Upper Range Level = 98% and STABLE

The CRS is currently considering implementing Yellow Path procedures Based on the conditions above, the CRS will direct the crew to .

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

PROCEDURE LEGEND:

FR-I.3 (RESPONSE TO VOIDS IN THE REACTOR VESSEL)

FR-Z.3 (RESPONSE TO HIGH CONTAINMENT RADIATION LEVEL)

A. transition from ES-1.2 to FR-I.3 B. remain in ES-1.2 and implement FR-I.3 concurrently C. transition from ES-1.2 to FR-Z.3 D. remain in ES-1.2 and implement FR-Z.3 concurrently Page 93 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 94 (1 point)

Given the following conditions on Unit 1:

The unit is in MODE 6 with core alterations in progress

It is determined that a Fuel Handling interlock must be bypassed to insert the next fuel assembly into the core

The interlock which must be bypassed is NOT specified in a procedure In accordance with AD-NS-ALL-1001 (CONDUCT OF REFUELING), which individual(s) listed below is/are allowed to approve bypassing the interlock?

1. Refueling SRO

2. Reactor Engineering

3. Shift Manager - Operations A. 1 ONLY B. 1 AND 2 ONLY C. 1 AND 3 ONLY D. 1, 2, AND 3 Page 94 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 95 (1 point)

Regarding Tech Spec 3.7.12 (FUEL HANDLING VENTILATION EXHAUST SYSTEM (FHVES) and its Bases,

1) 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) the design basis assumes that a total system failure could result in the atmospheric release from the fuel handling building exceeding the 10 CFR limits at the site exclusion area boundary in the event of a fuel handling accident.

PROCEDURE LEGEND:

10 CFR PART 20 (STANDARDS FOR PROTECTION AGAINST RADIATION) 10 CFR PART 100 (REACTOR SITE CRITERIA)

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

A. 1. is

2. 20 B. 1. is

2. 100 C. 1. is NOT

2. 20 D. 1. is NOT

2. 100 Page 95 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 96 (1 point)

Given the following conditions on Unit 1:

The 1A Annulus Ventilation (VE) train has been placed in service for a test run after fan lubrication

During the test run, Annunciator 0AD-12 / F-2 (1A VE Filter Hi Temp) alarms due to a malfunction of the filter heater Based on the conditions above, it is expected that 1A VE heaters (1) .

automatically tripped.

In accordance with Technical Specification 3.6.10 (Annulus Ventilation System (AVS))

Bases, after the 1A VE heaters are declared INOPERABLE and tagged for repairs, the 1A Annulus Ventilation train is (2) .

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

A. 1. have

2. OPERABLE B. 1. have NOT

2. OPERABLE C. 1. have

2. INOPERABLE D. 1. have NOT

2. INOPERABLE Page 96 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 97 (1 point)

Given the following conditions on Unit 1:

The unit startup is in progress

A site level Operating Procedure (OP) is to be performed on back-shift

The OATC identifies that a technical change to the procedure is needed because it cannot be performed as written

The change is to be processed as a TEMPORARY change since Procedure Group support is NOT available In accordance with AD-DC-ALL-0201 (DEVELOPMENT AND MAINTENANCE OF CONTROLLED PROCEDURE MANUAL PROCEDURES),

1) the lowest level of approval for the change to the procedure is the

2) temporary changes to FLEET level technical procedures .

allowed.

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

A. 1. Assistant Operations Manager - Shift

2. are NOT B. 1. Assistant Operations Manager - Shift

2. are C. 1. Shift Manager - Operations

2. are NOT D. 1. Shift Manager - Operations

2. are Page 97 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 98 (1 point)

Given the following conditions on Unit 2:

The unit is shutdown in preparation for refueling

NC system temperature is currently 190°F

An entry into Containment is planned for an inspection Based on the conditions above, in accordance with MSD-585 (REACTOR BUILDING PERSONNEL ACCESS AND MATERIAL CONTROL),

1) is permission from the WCC SRO required for the entry?

2) is use of the "buddy system" required for the entry?

A. 1. YES

2. NO B. 1. NO

2. NO C. 1. YES

2. YES D. 1. NO

2. YES Page 98 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 99 (1 point)

Given the following Unit 1 conditions:

The crew is responding to a large LOCA with 10% failed fuel

1NI-184B (1B ND PUMP SUCTION FROM CONT SUMP ISOL) would NOT open during FWST swap-over

1NI-184B breaker has tripped and will NOT reset

Manual alignment of 1NI-184B is required to protect the health and safety of the general public

Expected dose rates in the area of the valve may exceed 150 REM/hr

It will take 12 minutes to open 1NI-184B In accordance with the Emergency Response Procedures (RP) requirements for planned Emergency Exposures,

1) who, by title, is allowed to approve the Emergency Exposure?

2) and based on the conditions above, is a volunteer required to be used to open 1NI-184B?

A. 1. Site Vice President

2. NO B. 1. Site Vice President

2. YES C. 1. Emergency Coordinator

2. NO D. 1. Emergency Coordinator

2. YES Page 99 of 100

McGuire Nuclear Station ILT-16-1 MNS SRO NRC Examination Question: 100 (1 point)

Given the following initial plant conditions:

A large break LOCA has occurred on Unit 1

At 0220, the SM, acting as the Emergency Coordinator (EC), declares a General Emergency and makes the following initial Protective Action Recommendations (PARs):

o Evacuate - Zones B, C, L, M, D, N, O, R o Shelter - Zones P, Q, S At 0230, the following conditions are observed:

Conditions which resulted in the General Emergency on Unit 1 remain unchanged

Wind direction has changed and is now from 100° In accordance with the Response Procedures (RP), the Emergency Coordinator (1) allowed to delegate APPROVAL of PARs.