Text

301 Final RO As-Given Written Exam
	ML15141A166
Person / Time
Site:	Mcguire, McGuire
Issue date:	05/20/2015
From:	; NRC/RGN-II
To:	; Duke Energy Carolinas
References
	Download: ML15141A166 (96)
	v • d • e

U.S. Nuclear Regulatory Commission Site-Specific RO 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. Examination papers will be collected 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after the examination begins.

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

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

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

Regarding the NC pump motor stator coolers,

1) cooling water is supplied from the system.

2) upon initiation of an signal, the cooling water supply will be isolated.

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

A. 1. RN

2. Ss (Safety Injection)

B. 1. RN

2. Sp (Phase B)

C. 1. KC

2. Ss (Safety Injection)

D. 1. KC

2. Sp (Phase B)

Page 1 of 75

McGuire Nuclear Station Question: 2 ILT-31 MNS RO NRC Examination (1 point)

Given the following initial conditions on Unit 1:

NCS Tavg is 215°F

NCS pressure is 250 PSIG

VCT pressure is 28 PSIG

The 1A NC pump is to be started for a unit heatup Subsequently:

The 1A2 Oil Lift pump is started

Oil Lift pressure is 580 PSIG In accordance with OP/1/A/6150/002A (REACTOR COOLANT PUMP OPERATION)

Enclosure 4.1 (STARTUP AND OPERATION), the MINIMUM required #1 Seal differential pressure for starting the NC pump (1) met.

Based on the conditions above, if the 1A NC PUMP SAFETY BKR "START" pushbutton is depressed, the pump (2) start.

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

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 2 of 75

McGuire Nuclear Station Question: 3 ILT-31 MNS RO NRC Examination (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:

2A1 KC pump trips Per OP/2/A/6100/SD-8 (WATER SOLID OPERATIONS) which ONE (1) of the following describes operator actions necessary to respond to the failure?

COMPONENT LEGEND:

2NV-121 (ND LETDOWN CONTROL) 2NV-241 (SEAL INJECTION FLOW CONTROL)

A. Throttle CLOSED 2NV-241 OR Throttle OPEN 2NV-121 B. Throttle OPEN 2NV-241 OR Throttle OPEN 2NV-121 C. Throttle CLOSED 2NV-241 OR Throttle CLOSED 2NV-121 D. Throttle OPEN 2NV-241 OR Throttle CLOSED 2NV-121 Page 3 of 75

McGuire Nuclear Station Question: 4 ILT-31 MNS RO NRC Examination (1 point)

Given the following initial conditions on Unit 1:

The unit is in MODE 5

NC temperature is 112°F

LTOP is in service

1B NV pump is running

1A NV pump is currently tagged out for maintenance

Both NI pumps are tagged out Subsequently:

Maintenance on the 1A NV pump is complete

A 30 minute run of the 1A NV pump must be performed for post-maintenance testing (PMT)

Per Technical Specification 3.4.12 (LTOP SYSTEM),

1) to meet the LCO requirements of the Tech Spec during 1A NV pump PMT, the crew must .

2) LCO relief valve requirements can be met by having two PORVs with a lift setting of less than or equal to PSIG.

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

A. 1. stop the 1B NV pump ONLY

2. 450 B. 1. stop the 1B NV pump and rack out its breaker

2. 450 C. 1. stop the 1B NV pump ONLY

2. 385 D. 1. stop the 1B NV pump and rack out its breaker

2. 385 Page 4 of 75

McGuire Nuclear Station Question: 5 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 2:

The unit is in Mode 4 with a cooldown in progress

Both ND trains are in operation

ND pump suction pressure is 30 PSIG

ND pump suction header temperature is 226°F Subsequently:

NC system and ND system temperatures begin to increase due to a reduction of KC flow to the ND heat exchangers Based on the indications above, ND pump cavitation will occur if ND pump suction temperature increases by a MINIMUM of (1) °F.

One indication that the ND pump is cavitating would be that motor amps are (2) .

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

REFERENCE PROVIDED A. 1. 25

2. high B. 1. 48

2. high C. 1. 25

2. fluctuating D. 1. 48

2. fluctuating Page 5 of 75

McGuire Nuclear Station Question: 6 ILT-31 MNS RO NRC Examination (1 point)

Given the following:

At time 08:10:00, an inadvertent Reactor Trip/Safety Injection occurs due to IAE testing At time 08:10:30, SI (1) be reset.

When the Safety Injection RESET pushbutton is depressed after the required time delay, any subsequent AUTOMATIC actuation signals (2) start safeguards equipment.

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

A. 1. can NOT

2. will B. 1. can NOT

2. will NOT C. 1. can

2. will D. 1. can

2. will NOT Page 6 of 75

McGuire Nuclear Station Question: 7 ILT-31 MNS RO NRC Examination (1 point)

The purpose of the LTOP System is to prevent a (1) concern.

In accordance with Tech Spec 3.4.12 (LTOP System), the LCO is applicable in MODE 4 if NC system temperature is less than (2) .

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

A. 1. Cold Overpressure

2. 300°F B. 1. Pressurized Thermal Shock (PTS)

2. 300°F C. 1. Cold Overpressure

2. 320°F D. 1. Pressurized Thermal Shock (PTS)

2. 320°F Page 7 of 75

McGuire Nuclear Station Question: 8 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

1NC-34A (U1 PZR PORV) has been identified as leaking

Over the last 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , PRT level has increased from 8% to 26%

PRT pressure is 65 PSIG Based on the conditions above, the Tech Spec 3.4.13 (RCS OPERATIONAL LEAKAGE) limit for IDENTIFIED leakage (1) been exceeded.

The PRT rupture disc will rupture if PRT pressure increases to a MINUMUM pressure of (2) .

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

REFERENCE PROVIDED A. 1. has

2. 85 PSIG B. 1. has

2. 100 PSIG C. 1. has NOT

2. 85 PSIG D. 1. has NOT

2. 100 PSIG Page 8 of 75

McGuire Nuclear Station Question: 9 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

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

B Train KC is aligned to supply Reactor and Aux Bldg Non-Essential Headers with both 1B1 and 1B2 pumps in operation

A Train KC is aligned to supply the A ND HX Header with both 1A1 and 1A2 pumps in operation

The 1A1 KC pump has just tripped In accordance with the Limits and Precautions of OP/1/A/6400/005 (Component Cooling Water System), KC flow through the 1A ND Heat Exchanger shall be throttled to less than a MAXIMUM of .

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

A. 2000 GPM B. 4000 GPM C. 5000 GPM D. 6000 GPM Page 9 of 75

McGuire Nuclear Station Question: 10 ILT-31 MNS RO NRC Examination (1 point)

The Pressurizer Pressure Master Controller soft controls indicate as follows:

With the current ERROR signal, "C" Pzr heaters will be energized (1) of the time.

The Pzr Backup heaters energize at a PRESSURE ERROR of (2) PSIG.

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

A. 1. 17%

2. (-) 25 B. 1. 17%

2. (-) 17 C. 1. 83%

2. (-) 25 D. 1. 83%

2. (-) 17 Page 10 of 75

McGuire Nuclear Station Question: 11 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 2:

The unit is at 100% RTP

The top row of SSPS bistable status lights simultaneously illuminate

Power Range Channel N-41 indication is lost

Intermediate Range Channel N-35 indication is lost Which ONE (1) of the following describes the failure that has occurred, AND the response of the Reactor Protection System?

A. Loss of 120 VAC Bus 2EKVB; Train A SSPS General Warning Alarm is received.

B. Loss of 120 VAC Bus 2EKVA; Train A SSPS General Warning Alarm is received.

C. Loss of 120 VAC Bus 2EKVD; Train B SSPS General Warning Alarm is received.

D. Loss of 120 VAC Bus 2EKVC; Train B SSPS General Warning Alarm is received.

Page 11 of 75

McGuire Nuclear Station Question: 12 ILT-31 MNS RO NRC Examination (1 point)

Given the following:

Unit 1 is at 100% power

A LBLOCA inside containment occurs

Containment pressure is 3.7 PSIG and stable

Safety Injection Train "B" fails to actuate Based on the conditions above AND PRIOR TO any operator actions,

1) Phase A, Train "B" containment isolation valves automatically CLOSE.

2) Phase B containment isolation valves on will automatically CLOSE.

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

A. 1. will

2. Train A ONLY B. 1. will

2. both Trains C. 1. will NOT

2. Train A ONLY D. 1. will NOT

2. both Trains Page 12 of 75

McGuire Nuclear Station Question: 13 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

A LOCA has occurred

Containment pressure peaked at 2.9 PSIG and now is 2.6 PSIG and stable Which ONE (1) of the following describes the operation of the Containment Cooling system based on these conditions?

A. All VU units have started and RV containment isolation valves are open.

B. All VU units have shunt tripped off and RV containment isolation valves are open.

C. All VU units have started and RV containment isolation valves are closed.

D. All VU units have shunt tripped off and RV containment isolation valves are closed.

Page 13 of 75

McGuire Nuclear Station Question: 14 ILT-31 MNS RO NRC Examination (1 point)

Given the following initial conditions on Unit 1:

Unit 1 is at 100% RTP

The Control Room has received Floor Cooling Glycol alarms on annunciator panel 1AD-9

An operator has been dispatched per the annunciator response procedure

Floor Cooling Glycol Temperature is 22°F

Ice bed temperature is 27°F Based on the conditions above,

1) the required actions per the annunciator response for Floor Cooling Glycol temperature, is to .

2) increased ice bed sublimation a concern.

A. 1. stop one Floor Cooling pump if both are running

2. is B. 1. stop one Floor Cooling pump if both are running

2. is NOT C. 1. start an additional Floor Cooling pump if available

2. is D. 1. start an additional Floor Cooling pump if available

2. is NOT Page 14 of 75

McGuire Nuclear Station Question: 15 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 2:

A Large Break LOCA has occurred

"B" train of NS has been aligned per ES-1.3 (TRANSFER TO COLD LEG RECIRC)

2NI-185A (2A ND PUMP SUCTION FROM CONT SUMP ISOL) failed to OPEN from the control room

The crew is aligning ND aux spray Based on the conditions above,

1) 2NS-43A (2A ND HX OUTLET TO NS CONT OUTSIDE ISOL) OPEN from the control room.

2) if 2NS-43A is OPEN, when containment pressure decreases to less than 0.35 PSIG, 2NS-43A .

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

A. 1. will

2. will CLOSE automatically B. 1. will

2. must be CLOSED manually C. 1. will NOT

2. will CLOSE automatically D. 1. will NOT

2. must be CLOSED manually Page 15 of 75

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

Given the following initial conditions on Unit 1:

Unit is at 75% RTP Subsequently,

A small steam leak develops on 1A S/G

NC system pressure is 2210 PSIG and STABLE Based on the conditions above,

1) a Main Steam Isolation will occur if the 1A S/G pressure decreases to less than a MINIMUM of PSIG.

2) if a Main Steam Isolation occurs, the SM PORVs .close.

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

A. 1. 775

2. will NOT B. 1. 875

2. will NOT C. 1. 775

2. will D. 1. 875

2. will Page 16 of 75

McGuire Nuclear Station Question: 17 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 2:

A loss of all feedwater has occurred

2A S/G is faulted inside Containment

Containment pressure has peaked at 2.8 PSIG and is stable

NO CA flow is available

FR-H.1 (RESPONSE TO LOSS OF SECONDARY HEAT SINK) has been implemented Given the following parameters:

TIME SG WR Level 1515 1530 2A S/G 10% 10%

2B S/G 37% 25%

2C S/G 33% 21%

2D S/G 35% 23%

Per FR-H.1 foldout page, the EARLIEST time that the crew is required to implement NC System Feed and Bleed is (1) .

Per FR-H.1, a MINIMUM of (2) PZR PORV(s) must be opened to establish NC system Feed and Bleed.

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

A. 1. 1515

2. ONE B. 1. 1515

2. TWO C. 1. 1530

2. ONE D. 1. 1530

2. TWO Page 17 of 75

McGuire Nuclear Station Question: 18 ILT-31 MNS RO NRC Examination (1 point)

Given the following initial conditions on Unit 1:

The unit is at 98% RTP

In preparation for a Unit 1 TDCA pump performance test the following flow control valves are positioned as follows:

1CA-64AB (TD CA PUMP TO 1A S/G) -- CLOSED 1CA-52AB (TD CA PUMP TO 1B S/G) -- CLOSED 1CA-48AB (TD CA PUMP TO 1C S/G) -- OPEN 1CA-36AB (TD CA PUMP TO 1D S/G) -- OPEN Subsequently,

An IAE technician inadvertently generates a U1 TDCA pump auto-start signal After the inadvertent auto-start signal is initiated, (1) of the U1 TDCA Flow Control valves will be OPEN.

In accordance with the Control Room Crew Expectations Manual, the crew will CLOSE any OPEN U1 TDCA Flow Control valves (2) .

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

A. 1. all four

2. as soon as practical B. 1. all four

2. when directed by OP/1/A/6250/002 (AUXILIARY FEEDWATER SYSTEM)

C. 1. only two

2. as soon as practical D. 1. only two

2. when directed by OP/1/A/6250/002 (AUXILIARY FEEDWATER SYSTEM)

Page 18 of 75

McGuire Nuclear Station Question: 19 ILT-31 MNS RO NRC Examination (1 point)

Given the following on Unit 2:

Unit 2 is at 100% RTP

2A D/G has been started per PT/2/A/4350/002 A (DIESEL GENERATOR 2A OPERABILITY TEST)

2A D/G has been running idle for 45 minutes Based on the conditions above, the 2A D/G should be loaded to a MINIMUM of 3000 kW AND run for one hour to ensure (1) .

The 2A D/G load limit for CONTINUOUS OPERATION is (2) kW.

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

A. 1. injector tips are clean

2. 4000 B. 1. burnout of excess fuel in cylinders

2. 4000 C. 1. injector tips are clean

2. 4400 D. 1. burnout of excess fuel in cylinders

2. 4400 Page 19 of 75

McGuire Nuclear Station Question: 20 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 2:

The unit is in MODE 3

All NCPs are running and powered from their normal sources

A Generator-Switchyard protective lockout occurs on 2A Bus Line

AUTO / MAN mode selector switches are in AUTO Based on the conditions above,

1) NCP 2A .

2) Bus 2TA automatically transfers to its alternate power supply.

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

A. 1. trips

2. slow B. 1. trips

2. fast C. 1. continues to run

2. slow D. 1. continues to run

2. fast Page 20 of 75

McGuire Nuclear Station Question: 21 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 2:

A BLACKOUT has occurred on 2ETB

D/G '2B' failed to start due to an 86N relay actuation

2AD-11 / F4 (BATT EVCD UNDERVOLTAGE) is in alarm

EVDD bus voltage is 113 VDC and lowering slowly In accordance with AP-07 (LOSS OF ELECTRICAL POWER), the action required to restore bus EVDD is to .

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

A. cross tie Bus EVDB to Bus EVDD B. align Battery Charger EVCS to Bus EVDD C. swap Battery Charger EVCD power supply to 1EMXB D. swap Battery Charger EVCD power supply to 2EMXH Page 21 of 75

McGuire Nuclear Station Question: 22 ILT-31 MNS RO NRC Examination (1 point)

Given the following initial conditions on Unit 2:

A loss of voltage has occurred on 2ETA

Blackout loading is in progress Subsequently:

A Safety Injection signal is received before Blackout loading is completed on 2ETA Based on the conditions above, the Blackout load sequence (1) , 2ETA is cleared of (2) loads, and the SI load sequence is actuated.

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

A. 1. stops

2. all B. 1. is completed

2. all C. 1. stops

2. all non-SI D. 1. is completed

2. all non-SI Page 22 of 75

McGuire Nuclear Station Question: 23 ILT-31 MNS RO NRC Examination (1 point)

Regarding Diesel Generator Auxiliaries:

1) Which ONE (1) of the following is a heat load that is cooled by the DG Cooling Water (KD) System?

2) Which ONE (1) of the following is the MIMIMUM KD Surge Tank level required to perform a MANUAL MODE start?

A. 1. VG After Coolers

2. 11.5 inches B. 1. Air Intake System Intercooler

2. 11.5 inches C. 1. VG After Coolers

2. 25 inches D. 1. Air Intake System Intercooler

2. 25 inches Page 23 of 75

McGuire Nuclear Station Question: 24 ILT-31 MNS RO NRC Examination (1 point)

Given the following initial conditions on Unit 1:

Unit is at 100% RTP

A leak on the RC piping in the turbine building basement has occurred

All TB Sump pumps are in Manual and ON, maintaining sump level stable Subsequently:

A detector failure occurs due to a failed power supply on 1EMF-31 (TURBINE BUILDING SUMP MONITOR)

Based on the conditions above,

1) the Unit 1TB Sump pumps trip automatically.

2) to continue with the leak mitigation, the crew will be required to .

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

A. 1. will NOT

2. open 1WP-35 (WMT & VUCDT TO RC CONTROL)

B. 1. will

2. clear the EMF-31 Trip 2 signal and restart the TB sump pumps C. 1. will NOT

2. open 1WP-6 (U1 TB SUMP PUMPS DISCH TO WC ISOL)

D. 1. will

2. place the HI RAD INH/BYP switch in BYP and restart the TB sump pumps Page 24 of 75

McGuire Nuclear Station Question: 25 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

I&E has requested that the 1A Nuclear Service Water Pump breaker be racked out for lubrication To which ONE (1) of the following locations should an Operator be dispatched to rack out the breaker?

A. 1TA B. 1TD C. 1ETA D. 1ETB Page 25 of 75

McGuire Nuclear Station Question: 26 ILT-31 MNS RO NRC Examination (1 point)

Concerning the VI System, 1VI-1812 (VI AIR DRYER BYPASS FILTER ISOL) solenoid will vent the actuator when VI system pressure decreases to less than a MAXIMUM of (1) PSIG.

RESET must be depressed on the local VI (2) to CLOSE 1VI-1812.

Which ONE of the following completes the statements above?

A. 1. 90

2. Sequencer Control Panel B. 1. 90

2. Reflash Panel C. 1. 85

2. Sequencer Control Panel D. 1. 85

2. Reflash Panel Page 26 of 75

McGuire Nuclear Station Question: 27 ILT-31 MNS RO NRC Examination (1 point)

Given the following initial conditions:

Both Units are at 100% RTP

VI (INSTRUMENT AIR) compressors are in a D, E, F alignment

VS (STATION AIR) is in a normal alignmment Subsequently:

A VI header rupture occurs

Annunciators 1AD-12 / C1 (VI/VS LO PRESSURE) AND 1AD-12 / D1 (VI/VS LO LO PRESSURE) are in alarm Based on the conditions above, 1VI-820 (VI TO VS CONTROL VALVE) will auto-close when VI system pressure decreases to less than a MAXIMUM of (1) PSIG AND the VS compressor (2) auto-start.

A. 1. 85

2. will B. 1. 90

2. will C. 1. 85

2. will NOT D. 1. 90

2. will NOT Page 27 of 75

McGuire Nuclear Station Question: 28 ILT-31 MNS RO NRC Examination (1 point)

Regarding Containment isolation signals,

1) the S/G CF Containment Isolation valves (CF-35, 30, 28, & 26) will close if Containment pressure increases to a MINIMUM of PSIG.

2) a Containment Phase A isolation will occur if NC system pressure decreases to less than a MAXIMUM of PSIG.

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

A. 1. 1.0

2. 1845 B. 1. 1.0

2. 1945 C. 1. 3.0

2. 1845 D. 1. 3.0

2. 1945 Page 28 of 75

McGuire Nuclear Station Question: 29 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 2:

The unit is at 100% RTP

Annunciator 1AD-2 / A10 (ROD CONTROL URGENT FAILURE) is LIT

I&E had determined that the alarm is the result of an urgent failure in the Logic Cabinet Based on the conditions above,

1) one of the possible causes of the Logic Cabinet urgent failure is a .

2) the Logic Cabinet Urgent Failure blocks rod motion in .

A. 1. Slave Cycler failure

2. AUTO ONLY B. 1. Slave Cycler failure

2. AUTO AND MANUAL C. 1. Phase failure

2. AUTO ONLY D. 1. Phase failure

2. AUTO AND MANUAL Page 29 of 75

McGuire Nuclear Station Question: 30 ILT-31 MNS RO NRC Examination (1 point)

Given the following initial conditions on Unit 1:

Unit is at 25% RTP

Power ascension to 50% RTP is in progress

"A" Pzr heaters are ON Subsequently,

A DCS malfunction occurs in the Pzr Level Median Select for Selected Pzr Level 1

Selected Pzr Level 1 fails at its current output

No operator action is taken Which ONE (1) of the following statements describes the plant response as the power ascension continues?

A. Charging flow decreases Letdown isolates B. Charging flow increases Pzr backup heaters energize C. Charging flow decreases Letdown will NOT isolate D. Charging flow increases Pzr backup heaters will NOT energize Page 30 of 75

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

Given the following conditions on Unit 1:

A Loss of Offsite Power has occurred

1ETA and 1ETB are energized from their respective DGs Based on the conditions above, power can be restored to Pressurizer Heater Group(s)

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

A. D ONLY B. C ONLY C. A and B ONLY D. C and D ONLY Page 31 of 75

McGuire Nuclear Station Question: 32 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

A malfunction occurs which results in a DATA A Failure for Control Rod H-6 on DRPI

At the time of the failure, the highest DRPI coil penetrated by Control Rod H-6 was a "B" Coil

The actual position of all control rods has remained the same After the failure, the DRPI indication for Control Rod H-6 .

In addition to the DATA A Failure alarm, a DRPI alarm will also be received.

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

A. 1. remains the same

2. Non-Urgent Failure B. 1. decreases

2. Non-Urgent Failure C. 1. remains the same

2. Urgent Failure D. 1. decreases

2. Urgent Failure Page 32 of 75

McGuire Nuclear Station Question: 33 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

A Large Break LOCA has occurred

Subcooling based on the 5 HI T/C AVG indicates negative (-) 4°F on the Inadequate Core Cooling Monitor (ICCM)

Based on the conditions above, ICCM indication of Subcooling based on the 5 HI T/C AVG (1) be displayed in reverse video.

The Core Exit Thermocouples (CETs) will indicate a MAXIMUM temperature of (2) .

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

A. 1. will

2. 1200°F B. 1. will NOT

2. 1200°F C. 1. will

2. 2300°F D. 1. will NOT

2. 2300°F Page 33 of 75

McGuire Nuclear Station Question: 34 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

PT/1/A/4450/003 A (ANNULUS VENTILATION SYSTEM TRAIN A OPERABILITY TEST) is being performed

During the test, a VE filter pre-heater malfunctions When the 1A VE Filter temperature rises to a MINIMUM of (1) °F, annunciator 0AD-12 / F2 (1A VE FILTER HI TEMP) will alarm.

As a result of this alarm, the (2) .

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

A. 1. 220

2. 1A VE pre-heaters trip ONLY B. 1. 220

2. 1A VE pre-heaters and 1A VE Fan trip C. 1. 325

2. 1A VE pre-heaters trip ONLY D. 1. 325

2. 1A VE pre-heaters and 1A VE Fan trip Page 34 of 75

McGuire Nuclear Station Question: 35 ILT-31 MNS RO NRC Examination (1 point)

Given the following initial conditions on Unit 2:

Unit is in Mode 6

VP (CONTAINMENT PURGE SYSTEM) is in service and refueling is in progress Subsequently:

A Trip 2 alarm on 2EMF-38(L) (CONTAINMENT PARTICULATE) is received Based on the conditions above,

1) the VP Supply and Exhaust .

2) to regain control of VP components, 2EMF-38 must be reset and the Containment Ventilation (SH) Reset push button located on must be depressed.

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

A. 1. fans will be "OFF" ONLY

2. 2MC-11 B. 1. fans will be "OFF" ONLY

2. Unit 2 HVAC panel C. 1. fans will be "OFF" AND dampers will be CLOSED

2. 2MC-11 D. 1. fans will be "OFF" AND dampers will be CLOSED

2. Unit 2 HVAC panel Page 35 of 75

McGuire Nuclear Station Question: 36 ILT-31 MNS RO NRC Examination (1 point)

Given the following on Unit 2:

The unit is at 100% RTP

The "SPENT FUEL POOL LEVEL LO" alarm is received on the Unit 2 OAC

1) Which ONE (1) of the following is the FIRST EMF that will alarm to confirm a leak on the Spent Fuel Pool Cooling system?

2) If a Trip 2 signal is received on 2EMF-42, what AUTOMATIC actions occur?

CONSIDER EACH QUESTION SEPARATELY.

COMPONENT LEGEND:

2EMF-4 (SPENT FUEL BLDG REFUEL BRDG) 2EMF-42 (UNIT 2 FUEL BUILDING VENTILATION)

A. 1. 2EMF-4

2. The VF Supply and Exhaust Fans will stop B. 1. 2EMF-42

2. The VF Supply and Exhaust Fans will stop C. 1. 2EMF-4

2. The Exhaust Filter Bypass Damper (D-5) will close D. 1. 2EMF-42

2. The Exhaust Filter Bypass Damper (D-5) will close Page 36 of 75

McGuire Nuclear Station Question: 37 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

The unit is at 47% RTP for repairs to the 1B CF Pump

The 1A CF Pump is in AUTOMATIC S/G NR Level (%)

1A 45 1B 51 1C 50 1D 47 Based on current conditions, a S/G LEVEL DEVIATION annunciator is LIT for S/G(s)

(1) .

In accordance with the Annunciator Response Procedure for S/G LEVEL DEVIATION, the crew will take manual control of the (2) to restore S/G levels to program.

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

A. 1. 1A ONLY

2. CF Control or Bypass Valves B. 1. 1A AND 1D

2. CF Control or Bypass Valves C. 1. 1A ONLY

2. 1A CF Pump D. 1. 1A AND 1D

2. 1A CF Pump Page 37 of 75

McGuire Nuclear Station Question: 38 ILT-31 MNS RO NRC Examination (1 point)

Regarding the CF&E (CONTAINMENT FLOOR AND EQUIPMENT) Sumps,

1) one input into the CF&E sumps is .

2) the CF&E sumps discharge is aligned to the .

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

A. 1. VU AHU drains

2. FDT (Floor Drain Tank)

B. 1. VU AHU drains

2. WMT (Waste Monitoring Tank)

C. 1. Ice Condenser Drains

2. FDT (Floor Drain Tank)

D. 1. Ice Condenser Drains

2. WMT (Waste Monitoring Tank)

Page 38 of 75

McGuire Nuclear Station Question: 39 ILT-31 MNS RO NRC Examination (1 point)

Given the following on Unit 1:

A Loss of Offsite power has occurred

1A and 1B D/Gs are supplying the 4160V busses

The crew has completed E-0 (REACTOR TRIP OR SAFETY INJECTION) and entered ES-0.1 (REACTOR TRIP RESPONSE)

NCS Tavg is 552°F and slowly lowering Based on the conditions above,

1) all Feedwater Isolation status lights on 1SI-4 be lit.

2) ES-0.1 will check NC system stable or trending to 557°F.

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

A. 1. will

2. Tavg B. 1. will NOT

2. Tavg C. 1. will

2. Tcolds D. 1. will NOT

2. Tcolds Page 39 of 75

McGuire Nuclear Station Question: 40 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 2:

The unit is operating at 100% RTP

One PZR PORV is leaking past its seat

Pressurizer pressure is 2235 PSIG

Pressurizer Steam Space temperature is 653°F

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

REFERENCE PROVIDED A. 220°F B. 240°F C. 250°F D. 300°F Page 40 of 75

McGuire Nuclear Station Question: 41 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 2:

Unit is at 100% RTP

2B KC surge tank level is slowly trending up

2EMF-46B (COMPONENT COOLING TRAIN B) is in a Trip 2 condition The indications above can be caused by a leak on the (1) heat exchanger.

When 2EMF-46B Trip 2 clears, 2KC-122 (KC SURGE TANK VENT VALVE)

(2) .automatically re-OPEN.

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

A. 1. Letdown

2. will NOT B. 1. Letdown

2. will C. 1. Seal Water Return

2. will NOT D. 1. Seal Water Return

2. will Page 41 of 75

McGuire Nuclear Station Question: 42 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

Unit was operating at 90% RTP

1NV-7B (L/D CONT OUTSIDE ISOL) failed CLOSED

The operators entered AP-12 (LOSS OF LETDOWN, CHARGING OR SEAL INJECTION)

Excess L/D has been placed in service 1NV-24B (C NC LOOP TO EXS L/D HX ISOL) and 1NV-25B (C NC LOOP TO EXS L/D HX ISOL) can be controlled from the C/R AND the (1) .

Per AP-12, when placing Excess L/D in service, 1NV-26B (U1 EXCESS L/D HX OUTLET CNTRL) is cycled OPEN for two minutes and then CLOSED to (2) .

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

A. 1. SSF

2. minimize possible reactivity excursions B. 1. ASP

2. minimize possible reactivity excursions C. 1. SSF

2. reduce the possibility of water hammers D. 1. ASP

2. reduce the possibility of water hammers Page 42 of 75

McGuire Nuclear Station Question: 43 ILT-31 MNS RO NRC Examination (1 point)

Given the following initial 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

The ND heat exchanger bypass valve (2ND-34) is throttled to 50% OPEN Subsequently:

A loss of Instrument Air (VI) occurs Based on the conditions above,

1) 2ND-14 and 2ND-29 fail .

2) 2ND-34 fails .

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

A. 1. open

2. closed B. 1. open

2. open C. 1. closed

2. closed D. 1. closed

2. open Page 43 of 75

McGuire Nuclear Station Question: 44 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

The Pressurizer Pressure Calculated Error observed on the Ovation Soft Panel has failed to +100 PSIG

1AD-2 / E8 (DCS TROUBLE) is in alarm

Actual Pressurizer Pressure is 2200 PSIG and decreasing Based on the conditions above, which ONE (1) of the following indicates the status of the Pressurizer Pressure Control system?

A. PORV 1NC-34A is OPEN PZR Spray Valves are OPEN B. PORV 1NC-34A is OPEN PZR Spray Valves are CLOSED C. PORV 1NC-34A is CLOSED PZR Spray Valves are OPEN D. PORV 1NC-34A is CLOSED PZR Spray Valves are CLOSED Page 44 of 75

McGuire Nuclear Station Question: 45 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 2:

A valid First Out annunciator is LIT on Annunciator Panel 2FO-1

Both Reactor Trip breakers indicate OPEN

IR SUR meters indicate +0.5 DPM

All WR Neutron flux indications are stable

The STA is manually evaluating the Critical Safety Function Status Trees (CSFSTs) because SPDS in not working Based on the conditions above, the CSFSTs require implementation of FR-S.1 (RESPONSE TO NUCLEAR GENERATION / ATWS) if indicated power is greater than a MINIMUM of (1) OR if WR Neutron Flux indicates greater than a MINIMUM of (2) .

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

A. 1. 5 %

2. 10-3 %

B. 1. 5 %

2. 10-5 %

C. 1. 10 %

2. 10-3 %

D. 1. 10 %

2. 10-5 %

Page 45 of 75

McGuire Nuclear Station Question: 46 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

The 1D S/G is ruptured

E-3 (STEAM GENERATOR TUBE RUPTURE) has been implemented

The first NC system depressurization was stopped with the following indications:

NC system pressure 1250 PSIG 1D S/G pressure 1050 PSIG

SI has been terminated and the crew is preparing for a second NC system depressurization In accordance with the SGTR mitigating strategy,

1) the second NC system depressurization is performed to .

2) the reason for initially establishing a minimum level in the ruptured S/G is to prevent .

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

A. 1. prevent S/G over-fill

2. ruptured S/G depressurization B. 1. establish indicated level in the PZR

2. ruptured S/G depressurization C. 1. prevent S/G over-fill

2. additional damage of ruptured S/G tubes D. 1. establish indicated level in the PZR

2. additional damage of ruptured S/G tubes Page 46 of 75

McGuire Nuclear Station Question: 47 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

A Steam line break has occurred

NC pressure is 1700 PSIG and slowly lowering

Tavg is 518°F and slowly lowering

Containment pressure is 2.9 PSIG and stable on channels 1, 2 and 4 and 3.1 PSIG and stable on channel 3

S/G 1A pressure is 755 PSIG on channels 1 and 2 and 765 PSIG on channel 4 and slowly lowering on all channels

NO operator actions have been taken Based on the conditions above,

1) MSIV and MSIV Bypass valves are .

2) The purpose of CLOSING MSIVs and MSIV Bypass valves in E-2 (FAULTED STEAM GENERATOR ISOLATION) is to .

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

A. 1. OPEN

2. terminate an uncontrolled cooldown B. 1. OPEN

2. isolate a faulted S/G from the non-faulted S/Gs C. 1. CLOSED

2. terminate an uncontrolled cooldown D. 1. CLOSED

2. isolate a faulted S/G from the non-faulted S/Gs Page 47 of 75

McGuire Nuclear Station Question: 48 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

A unit shutdown is in progress

0200 both Main Feedwater pumps trip Subsequently, the following conditions are observed:

TIME CONDITION 0200 0205 0210 0215 NCS Temp (°F) 557 558 558 559 NCS Press (PSIG) 1965 1960 1976 1991 NR SG A (%) 19 18 19 19 NR SG B (%) 20 18 17 16 NR SG C (%) 20 19 18 16 NR SG D (%) 18 16 18 19 Based on the conditions above,

1) the EARLIEST time that the MD CA pumps will be running is .

2) the EARLIEST time that the TD CA pump will be running is .

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

A. 1. 0200

2. 0205 B. 1. 0205

2. 0205 C. 1. 0200

2. 0215 D. 1. 0205

2. 0215 Page 48 of 75

McGuire Nuclear Station Question: 49 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions:

MNS has experienced a Station Blackout

The 1A D/G fails to start

The 1B D/G started and tripped on low lube oil pressure Based on the conditions above,

1) the vital DC batteries that should be monitored for decaying voltage are .

2) the battery discharge rate will on the vital DC batteries with decaying voltage, until the design battery capacity is exhausted.

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

A. 1. EVCA and EVCB

2. remain constant B. 1. EVCA and EVCB

2. increase steadily C. 1. EVCC and EVCD

2. remain constant D. 1. EVCC and EVCD

2. increase steadily Page 49 of 75

McGuire Nuclear Station Question: 50 ILT-31 MNS RO NRC Examination (1 point)

Given the following initial conditions on Unit 1:

A Loss of Offsite Power has occurred

The crew is verifying natural circulation flow per EP/1A/5000/ G-1 (Generic Enclosures) Enclosure 33 (NATURAL CIRCULATION PARAMETERS)

Given the following parameters:

1. NC system Subcooling > 0°F

2. NC system hot leg temperatures at saturation temperature for S/G pressure

3. NC system cold leg temperatures going up slowly

4. NC system hot leg temperatures going down

5. S/G pressure stable

6. NC system cold leg temperatures at saturation temperature for S/G pressure

7. NC system pressure stable

8. Core Exit T/C's stable Which ONE (1) of the following sets of conditions confirm that Natural Circulation exists and is effective in cooling the core in accordance with G-1, Enclosure 33?

A. 1, 3, 4, 5, 7 B. 2, 3, 5, 7, 8 C. 1, 4, 5, 6, 8 D. 1, 2, 5, 7, 8 Page 50 of 75

McGuire Nuclear Station Question: 51 ILT-31 MNS RO NRC Examination (1 point)

Given the following initial conditions on Unit 2:

Both CFPT's tripped causing a Rx Trip 15 minutes ago

The crew has completed E-0 (REACTOR TRIP OR SAFETY INJECTION) and transitioned to ES-0.1 (REACTOR TRIP RESPONSE)

Subsequently:

EVDA output breaker to 2EVIA inverter trips OPEN Based on the conditions above,

1) which ONE (1) of the following indicates the impact on the CA system flow instrumentation?

2) what alternate indication can be used to determine the status of CA flow to the affected S/G?

A. 1. 2A S/G CA flow fails low

2. 2A CA Pump amps and breaker indicating lights B. 1. 2B S/G CA flow fails low

2. 2B CA Pump amps and breaker indicating lights C. 1. 2C S/G CA flow fails low

2. 2A CA Pump amps and breaker indicating lights D. 1. 2D S/G CA flow fails low

2. 2B CA Pump amps and breaker indicating lights Page 51 of 75

McGuire Nuclear Station Question: 52 ILT-31 MNS RO NRC Examination (1 point)

Given the following on Unit 1:

Unit is at 100% RTP

125VDC Battery CXB is aligned for an "equalizing charge" Subsequently:

A fault on bus DCB causes the CXB Battery charger output breaker and the DCA -DCB cross tie breakers to OPEN Based on the conditions above and per AP-15 (LOSS OF VITAL OR AUX CONTROL POWER),

1) switch indication on any component powered from 6.9 kV switchgear will be DARK.

2) breakers powered from the affected 6.9 kV switchgear be remotely operated.

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

A. 1. 1TB ONLY

2. can B. 1. 1TB AND 1TD

2. can C. 1. 1TB ONLY

2. can NOT D. 1. 1TB AND 1TD

2. can NOT Page 52 of 75

McGuire Nuclear Station Question: 53 ILT-31 MNS RO NRC Examination (1 point)

Given the following initial conditions on Unit 1:

Unit power ascension is in progress

Unit is at 660 MW Subsequently:

MVARs are (-) 500 and slowly decreasing

The operating crew enters AP-05 (GENERATOR VOLTAGE AND ELECTRICAL GRID DISTURBANCES)

1) If the voltage regulator is placed in MANUAL, the voltage regulator under excitation limiter function to reduce leading MVARs.

2) Based on the conditions above and per AP-05, if unable to maintain MVARs within limits of the generator capability curve, then the crew will .

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

PROCEDURE LEGEND:

AP-02 (TURBINE TRIP)

E-0 (REACTOR TRIP OR SAFETY INJECTION)

A. 1. will

2. trip Unit 1 Turbine AND GO TO AP-02 B. 1. will

2. trip Unit 1 Reactor AND GO TO E-0 C. 1. will NOT

2. trip Unit 1 Turbine AND GO TO AP-02 D. 1. will NOT

2. trip Unit 1 Reactor AND GO TO E-0 Page 53 of 75

McGuire Nuclear Station Question: 54 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

ECA-1.2 (LOCA OUTSIDE CONTAINMENT) has been implemented

NC System pressure is 1700 psig and stable In accordance with ECA-1.2,

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

2) the overall mitigating strategy includes cooldown and depressurization of the NCS to allow the .

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

A. 1. ND

2. Cold Leg Accumulators to inject B. 1. NI

2. Cold Leg Accumulators to inject C. 1. ND

2. ND isolation valves (1NI-173A and 1NI-178B) to close D. 1. NI

2. ND isolation valves (1NI-173A and 1NI-178B) to close Page 54 of 75

McGuire Nuclear Station Question: 55 ILT-31 MNS RO NRC Examination (1 point)

Given the following condition on Unit 1:

S/G's 1C & 1D are indicating 30% Narrow Range Level

S/G's 1A & 1B are faulted and indicating <5% Wide Range Level

All CA is unavailable

Containment Pressure is 3.5 PSIG

E-0 (REACTOR TRIP OR SAFETY INJECTION) has been completed Based on the conditions above, which ONE (1) of the following indicates the NEXT procedure to be implemented AND the action(s) required?

PROCEDURE LEGEND:

E-2 (FAULTED S/G ISOLATION)

FR-H.1 (RESPONSE TO LOSS OF SECONDARY HEAT SINK)

A. Go to E-2; Isolate C & D S/G's B. Go to FR-H.1; Commence NCS feed and bleed C. Go to E-2; Close all MSIVs and MSIV bypasses D. Go to FR-H.1; Restore feed water flow to C & D S/G's Page 55 of 75

McGuire Nuclear Station Question: 56 ILT-31 MNS RO NRC Examination (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)

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. 95 B. 1. will NOT

2. 95 C. 1. will

2. 20 D. 1. will NOT

2. 20 Page 56 of 75

McGuire Nuclear Station Question: 57 ILT-31 MNS RO NRC Examination (1 point)

Given the following initial conditions on Unit 1:

A Unit runback has occurred

Rods are inserting in AUTO

Rod M-12 in Control Bank D is NOT inserting with its bank Subsequently:

A Rod Control Urgent Failure alarm is received

Unit1 Control Rod Bank Select is taken to MANUAL

I&E determines source of alarm is Power Cabinet 1BD Due to the Power Cabinet Rod Control Urgent Failure alarm, Group 1 rods in Control Banks B and D will NOT move in (1) .

When Unit 1 OATC attempts to continue control rod insertion, rods in all groups of the other banks (2) insert.

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

A. 1. AUTO ONLY

2. will B. 1. AUTO OR MANUAL

2. will C. 1. AUTO ONLY

2. will NOT D. 1. AUTO OR MANUAL

2. will NOT Page 57 of 75

McGuire Nuclear Station Question: 58 ILT-31 MNS RO NRC Examination (1 point)

Given the following initial conditions on Unit 2:

A loss of offsite power has occurred

The crew has commenced a cooldown and depressurization in accordance with ES-0.2 (NATURAL CIRCULATION COOLDOWN)

The following conditions are observed:

0220 0230 NC Pressure 1685 1635 (PSIG)

T-Colds (°F) 602 598 CETs (°F) 612 610

At time 0230 Pressurizer level begins increasing rapidly In accordance with ES-0.2, the MAXIMUM allowable cooldown rate is (1) .

The cause of the Pressurizer level increase is (2) .

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

A. 1. 50°F / Hr

2. voiding in the Reactor Vessel head B. 1. 50°F / Hr

2. an increase in flow from the NI pumps C. 1. 100°F / Hr

2. voiding in the Reactor Vessel head D. 1. 100°F / Hr

2. an increase in flow from the NI pumps Page 58 of 75

McGuire Nuclear Station Question: 59 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 2:

Shutdown Bank Rods are withdrawn in preparation for a Reactor startup

The startup is on hold while I&E completes an inspection of the Channel 1 Nuclear Instrument cabinet PROCEDURE LEGEND:

Tech Spec 3.3.1 (RTS INSTRUMENTATION)

In accordance with Tech Spec 3.3.1,

1) based on the conditions above, channel(s) of Source Range Nuclear Instrumentation is/are currently required to be OPERABLE.

2) if the I&E technician caused a a loss of power to Source Range Channel N31, the crew required to IMMEDIATELY open the Reactor Trip Breakers (RTBs).

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

REFERENCE PROVIDED A. 1. ONE

2. is B. 1. ONE

2. is NOT C. 1. BOTH

2. is D. 1. BOTH

2. is NOT Page 59 of 75

McGuire Nuclear Station Question: 60 ILT-31 MNS RO NRC Examination (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 increase to allow taking critical rod height data is in progress

Reactor power is 7X10-6 % (IR)

Subsequently:

The IR Signal Processor for detector channel N36 fails Based on the conditions above,

1) per Tech Spec 3.3.1 (RTS INSTRUMENTATION), the power increase

2) Reactor power indication on has been lost.

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

A. 1. can continue

2. N36 ONLY B. 1. must be suspended

2. N36 ONLY C. 1. can continue

2. N32 AND N36 D. 1. must be suspended

2. N32 AND N36 Page 60 of 75

McGuire Nuclear Station Question: 61 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 2:

2EMF-59 (EQUIPMENT STAGING BUILDING VENTILATION MONITOR) is in Trip 2 alarm due to a release in the building

The VK (EQUIPMENT STAGING BUILDING VENT) system selector switch is in the "ON" position Which ONE (1) of the following describes the actions, if any, that will occur as a result of the Trip 2 alarm on 2EMF-59?

A. The VK Supply fans ONLY will trip B. The VK Exhaust AND Supply fans will trip C. The VK exhaust filter bypass damper will CLOSE D. NO automatic actions will occur Page 61 of 75

McGuire Nuclear Station Question: 62 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

Unit 1 is at 100% RTP

1AD-13 / E3 (FIRE DET SYS ALERT) is in alarm

An electrical fire inside the auxiliary building cable spreading room has been reported

AP-45 (PLANT FIRE) has been implemented Fire suppression for the affected area will be accomplished by .

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

A. automatic halon actuation B. automatic sprinkler actuation C. an AO dispatched to open a MANUAL deluge valve D. an AO dispatched to actuate a manual Cardox system Page 62 of 75

McGuire Nuclear Station Question: 63 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 2:

The unit is at 100% RTP

2EMF-6 (REACTOR COOLANT FILTER 2B) is in Trip 2 alarm

2EMF-48 (REACTOR COOLANT HI RAD) is also in Trip 2 alarm

The crew has implemented AP-18 (HIGH ACTIVITY IN REACTOR COOLANT)

Chemistry has reported that the cause of the high activity is due to FAILED FUEL In accordance with the mitigating strategy for AP-18, the crew will (1) .

The reason for performing this action is because it (2) .

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

A. 1. ensure that a mixed bed demineralizer is in service

2. causes a pH change that prevents further fuel degradation B. 1. ensure that a mixed bed demineralizer is in service

2. facilitates the removal of fission products resulting from the failed fuel C. 1. increase letdown to 120 GPM

2. increases the effectiveness of the fission product gas removal by the VCT D. 1. increase letdown to 120 GPM

2. increases the removal rate of fission products by the demineralizer Page 63 of 75

McGuire Nuclear Station Question: 64 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

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

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

NC Cooldown rate was approximately 220°F/hr

NC System temperature is currently 240°F

The crew is performing a soak in accordance with FR-P.1 (RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION)

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

A. Energize PZR heaters B. Start an additional NV Pump C. Place Auxiliary Spray in service D. Increase CA flow to recover S/G NR level Page 64 of 75

McGuire Nuclear Station Question: 65 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 2:

Unit tripped from 100% RTP

A Loss of Off-Site Power has occurred

ES-0.2 (NATURAL CIRCULATION COOLDOWN) has been implemented Blocking automatic Safety Injection (1) required to be performed in ES-0.2 prior to implementing ES-0.3 (NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL).

The FIRST Major Action associated with ES-0.3 is (2) .

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

A. 1. is

2. initiate an NCS Cooldown B. 1. is

2. try to start an NC pump C. 1. is NOT

2. initiate an NCS Cooldown D. 1. is NOT

2. try to start an NC pump Page 65 of 75

McGuire Nuclear Station Question: 66 ILT-31 MNS RO NRC Examination (1 point)

Concerning AD-OP-ALL-0203 (REACTIVITY MANAGEMENT) during abnormal operating conditions,

1) a reactor trip should be initiated if the cause of a power change is not understood and reactor power level exceeds the pre-transient power level by greater than a MINIMUM of , or is not controllable.

2) the ROs shall inform the CRS of .

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

A. 1. 5%

2. all MANUAL control rod withdrawals B. 1. 5%

2. the first MANUAL control rod withdrawal ONLY C. 1. 10%

2. all MANUAL control rod withdrawals D. 1. 10%

2. the first MANUAL control rod withdrawal ONLY Page 66 of 75

McGuire Nuclear Station Question: 67 ILT-31 MNS RO NRC Examination (1 point)

When performing a normal fuel reload from the spent fuel pool to a core location, PT/0/A/4150/033 (TOTAL CORE RELOADING) requires the Reactor Building Crane operator to obtain permission from the to PLACE a fuel assembly into a core location.

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

A. Fuel Handling SRO B. Site Refueling Supervisor C. Fuel Handling Reactor Engineer D. Refueling Booth Support Reactor Operator Page 67 of 75

McGuire Nuclear Station Question: 68 ILT-31 MNS RO NRC Examination (1 point)

Given the following initial conditions on Unit 2:

Unit is at 4% RTP conducting a plant startup Subsequently:

One control bank A rod drops fully into the core

NCS temperature decreases to 550°F Based on the conditions above, the MOST limiting Tech Spec required action is to (1) within (2) .

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

A. 1. restore rod to within alignment limits

2. 30 minutes B. 1. be in MODE 2 with Keff less than 1.0

2. 30 minutes C. 1. restore rod to within alignment limits

2. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months D. 1. be in MODE 2 with Keff less than 1.0

2. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Page 68 of 75

McGuire Nuclear Station Question: 69 ILT-31 MNS RO NRC Examination (1 point)

Given the following initial plant conditions:

Both units are operating at 100% RTP

The following alarms are lit on each unit:

o 1AD-11 C-5 (XFMR A URGENT ALARM) o 2AD-11 C-5 (XFMR A URGENT ALARM)

Subsequently:

An AO reports a loss of BOTH Cooling Groups has occurred on each transformer To prevent a turbine runback to <56% RTP, cooling to the (1) Main Transformer must be restored within a MAXIMUM of (2) .

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

A. 1. 1A

2. 8 minutes, 45 seconds B. 1. 2A

2. 8 minutes, 45 seconds C. 1. 1A

2. 28 minutes, 45 seconds D. 1. 2A

2. 28 minutes, 45 seconds Page 69 of 75

McGuire Nuclear Station Question: 70 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

You are to perform a valve lineup in the Letdown Heat Exchanger Room

The dose rate in the room is 3000 mREM/HR

Your total exposure for the year is 1000 mREM In accordance with PD-RP-ALL-0001 (RADIATION PROTECTION):

The Letdown Heat Exchanger Room must be posted as a (1) Area.

The MAXIMUM amount of time you can spend in the room before reaching your EXCLUDE exposure limit is (2) minutes.

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

A. 1. Locked High Radiation

2. 12 B. 1. Locked High Radiation

2. 16 C. 1. Very High Radiation

2. 12 D. 1. Very High Radiation

2. 16 Page 70 of 75

McGuire Nuclear Station Question: 71 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions:

An RO is performing a valve lineup in the Unit 1 Auxiliary Building pipe chase

The RO receives a Dose Rate alarm on his Electronic Dosimeter (ED)

The possibility of Dose Rate alarms was discussed during the RP brief In accordance with PD-RP-ALL-0001 (RADIATION WORKER RESPONSIBILITIES),

1) the Dose Rate alarm will .

2) based on the conditions above, the RO .

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

A. 1. NOT clear until the ED is reset

2. must stop work and exit the area B. 1. NOT clear until the ED is reset

2. will reset the dose rate alarm and continue to work until two additional dose rate alarms are received C. 1. automatically clear when dose rate drops below 80% of alarm setpoint

2. must stop work and exit the area D. 1. automatically clear when dose rate drops below 80% of alarm setpoint

2. may continue to work until two additional dose rate alarms are received Page 71 of 75

McGuire Nuclear Station Question: 72 ILT-31 MNS RO NRC Examination (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 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

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

2. the general area dose rate is less than 500 mREM/hr C. 1. can

2. the radiation exposure for a single verification exceeds the allowable limit D. 1. can NOT

2. the radiation exposure for a single verification is within the allowable limit Page 72 of 75

McGuire Nuclear Station Question: 73 ILT-31 MNS RO NRC Examination (1 point)

Related to Emergency Operating Procedures (EOPs) rules of usage,

1) the step below is a (an) action step.

2) steps which may be performed in any order are designated by .

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

A. 1. immediate

2. asterisks B. 1. immediate

2. bullets C. 1. continuous

2. asterisks D. 1. continuous

2. bullets Page 73 of 75

McGuire Nuclear Station Question: 74 ILT-31 MNS RO NRC Examination (1 point)

Given the following plant conditions:

A fire has been reported on a small oil cooled transformer

The transformer may be energized Which ONE (1) of the following indicates the fire class ratings of the portable fire extinguishers that must be used in this situation?

A. A and B B. B and C C. C and D D. A and D Page 74 of 75

McGuire Nuclear Station Question: 75 ILT-31 MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

A Site Area Emergency has been declared

A Site Assembly is being conducted in accordance with RP/0/A/5700/011 (CONDUCTING A SITE ASSEMBLY, SITE EVACUATION, OR CONTAINMENT EVACUATION)

Per Enclosure 4.3 (OSM ACTIONS FOR SITE ASSEMBLY),

1) the announcement for the Site Assembly shall be repeated every

.minutes until notification that the Site Assembly has been completed.

2) the Site Assembly shall be completed within a MAXIMUM of minutes.

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

A. 1. 10

2. 30 B. 1. 20

2. 30 C. 1. 10

2. 60 D. 1. 20

2. 60 Page 75 of 75

Reference List for: ILT-31 MNS RO NRC Examination Steam Tables Unit 1 Plant Data Book, Curve 7.2 Tech Spec 3.3.1 (RTS Instrumentation) Pages 1-15 Printed 4/24/2015 12:10:32 PM

OP/1/A/6100/22 UNIT 1 ENCLOSURE 4.3 CURVE 7.2 PRESSURIZER RELIEF TANK (VOLUME vs. LEVEL) 14000 13000 100% LEVEL = 13,172 GALLONS 12000 11000 10000 9000 VOLUME (GALLONS) 8000 7000 6000 TOTAL VOLUME OF TANK = 13,488 GALLONS 5000 4000 3000 2000 1000 0% LEVEL = 317 GALLONS 0

0 10 20 30 40 50 60 70 80 90 100 110 PERCENT LEVEL INSTRUMENTATION INDICATION This data is also available on the OAC. UNIT 1

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

Examination KEY for: ILT-31 MNS RO NRC Examination Question Answer Number 1 B 2 B 3 A 4 D 5 D 6 B 7 A 8 D 9 B 10 C 11 B 12 D 13 B 14 C 15 D 16 C 17 D 18 A 19 A 20 D 21 C 22 C 23 B 24 D 25 C Printed 4/24/2015 1:48:32 PM Page 1 of 3

Examination KEY for: ILT-31 MNS RO NRC Examination Question Answer Number 26 D 27 D 28 A 29 B 30 D 31 C 32 A 33 C 34 A 35 C 36 C 37 A 38 C 39 C 40 C 41 B 42 D 43 B 44 A 45 B 46 A 47 D 48 C 49 B 50 C Printed 4/24/2015 1:48:32 PM Page 2 of 3

Examination KEY for: ILT-31 MNS RO NRC Examination Question Answer Number 51 A 52 D 53 B 54 C 55 D 56 C 57 B 58 A 59 D 60 D 61 D 62 C 63 B 64 C 65 B 66 A 67 D 68 B 69 B 70 B 71 D 72 D 73 B 74 B 75 A Printed 4/24/2015 1:48:32 PM Page 3 of 3

ML15141A166

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