Text

Initial Exam 2013-301 Final SRO Written Exam
	ML14014A063
Person / Time
Site:	Mcguire, McGuire
Issue date:	01/14/2014
From:	; Division of Nuclear Materials Safety II
To:	; Duke Energy Carolinas
References
	Download: ML14014A063 (106)
	v • d • e

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

Date: Facility/Unit: MCGUIRE Region: I Ill IV Reactor Type: CE 8W GE Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to complete the combined examination, and 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months if you are only taking the SRO portion.

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

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

McGuire Nuclear Station Question:

I 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

Unit is operating at 100% RTP

Ops Test Group is performing a slave relay test and a procedural error results in the inadvertent closure of 1RN-277B (RB NON ESS RET CONT OUTSIDE ISOL)

At 1400, the following NC pumps indications are noted:

NC Pump IA lB IC ID Current Stator 250.5°F 259.5°F 265°F 253.6°F Winding Temp.

Temp. Increase 1.8°F/mm 1.5°F/mm 1.2°F/mm 1.7°F/mm Based on the conditions above, which ONE (1) of the following indicates the FIRST NC pump that would have to be manually secured in accordance with AP-08, (MALFUNCTION OF NC PUMP)?

A. 1A B. lB C. IC D. ID Page 1 of 100

McGu ire Nuclear Station Question:

2 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

Unit is operating at 90% RTP

The controller for I KC-1 32 (LETDOWN HX OUTLET TEMP CTRL) has been placed in MANUAL due to erratic operation

Letdown Heat Exchanger outlet temperature is initially 100°F

Subsequently, NV letdown flow is increased by 10 GPM as requested by Chemistry Based on the conditions above, reactor power will initially (1)

If Letdown Heat Exchanger outlet temperature increases to a maximum of (2)

I NV-I 27A (LD HX OUTLET 3-WAY TEMP CNTRL) will automatically divert letdown to the VCT.

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

A. I. INCREASE

2. 120°F B. 1. INCREASE

2. 138°F C. I. DECREASE

2. 120°F D. 1. DECREASE

2. 138°F Page 2 of 100

McGu ire Nuclear Station Question: 3 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

A power decrease from 100% RTP was in progress

The following indications were observed:

o Pressurizer level = 51%

o Reactor power = 75%

The power decrease is halted when the crew notes that I NV-238 (CHARGING LINE FLOW CONTROL VALVE) is NOT maintaining pressurizer level at program level

1 NV-238 is placed in manual and adjusted to restore pressurizer level to program level

1) When the crew discovered I NV-238 was not maintaining program level, how did actual level compare to program level?

2) When 1 NV-238 is repaired, what operator action(s) will be recwired to restore automatic pressurizer level control?

A. 1. Actual level was higher than program level

2. Place 1 NV-238 in automatic AND restore the Pressurizer Level Master to automatic using the DCS soft controls B. 1. Actual level was higher than program level

2. Place INV-238 in automatic ONLY C. 1. Actual level was lower than program level

2. Place 1 NV-238 in automatic AND restore the Pressurizer Level Master to automatic using the DCS soft controls D. 1. Actual level was lower than program level

2. Place INV-238 in automatic ONLY Page 3 of 100

McGuire Nuclear Station Question: 4 2013A MNS SRO 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

2A NV pump is in service

Letdown is through 2NV-121 (ND LETDOWN CONTROL)

Based on the conditions above, a loss of Vito would cause NC system pressure to increase? (Consider each separately)

Which ONE of the following completes the statement above?

A. 2ND-29 (2A ND Hx Outlet)

B. 2ND-34 (A & B ND Hx Bypass)

C. 2NV-459 (Letdown Flow Control valve)

D. 2KC-57 (2A ND Heat Exchanger Cooling Water Control)

Page 4 of 100

McGu ire Nuclear Station Question: 5 2013A MNS SRO NRC Examination (1 point)

Concerning the operation of Engineering Safeguards Modulating Control Valves:

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

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

A. 1. Safety Injection ONLY

2. align Vito B. 1. Safety injection Q, Blackout

2. align Vito C. 1. Safety injection ONLY

2. ventairoff D. 1. Safety Injection OR Blackout

2. ventairoff Page 5 of 100

McGu ire Nuclear Station Question: 6 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

Containment pressure is initially NEGATIVE 0.1 PSIG and stable

ONE (I) PZR safety valve sticks partially open

After the PRT rupture disc relieves, Containment pressure begins to rise at 0.1 PSIG per minute

1) How long will it be before the upper limit of Technical Specification 3.6.4 (CONTAINMENT PRESSURE), is reached?

2) How long will it be before the Lower Containment Ventilation (VL) AHUs automatically switch to HIGH speed?

A. 1. 3 minutes

2. 5 minutes B. 1. 3 minutes

2. 4 minutes C. 1. 4 minutes

2. 5 minutes D. 1. 4 minutes

2. 6 minutes Page 6 of 100

McGuire Nuclear Station Question: 7 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

A Small Break LOCA occurred in Containment

SI has actuated on both trains

1 B NV pump tripped on overcurrent

Containment pressure is 3.5 PSIG Based on the above conditions, ALL cooling would be lost to the NC pump .

A. motor bearings AND pump lower bearings.

B. seals AND pump lower bearings.

C. motor bearings ONLY.

D. seals ONLY.

Page 7 of 100

McGu ire Nuclear Station Question:

8 2013A MNS SRO NRC Examination (1 point)

Given the following initial conditions on Unit I:

The unit is at 100% RTP

A loss of offsite power occurs Current Conditions:

Natural Circulation established

NC system pressure is 2000 PSIG and STABLE

All Tcolds 550° F and STABLE

Pressurizer level is 32% and STABLE

Pressurizer temperature is 630° F

The IA, lB and ID PZR HTR MODE SELECT switches on IMC-10 have been placed in MAN Based on the conditions above:

The Pressurizeris (1)

When the BOP closes the PZR HTR Group Supply breakers from 1 MC-5, the Pressurizer Backup Heaters (2) automatically energize.

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

REFERENCE PROVIDED A. 1. saturated

2. WILL B. 1. subcooled

2. WILL C. 1. saturated

2. WILL NOT D. I. subcooled

2. WILL NOT Page 8 of 100

McGu ire Nuclear Station Question: 9 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The unit is increasing power following a Refueling Outage

At 45% reactor power, the P-8 permissive failed AS IS

Reactor power is currently at 50%

Based on the conditions above:

The P-8 HI PWR LO FLO RX TRIP BLOCK status light on lSl-18 is (1)

If one NC pump were to trip, an automatic reactor trip (2) occur.

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

A. 1. DARK

2. WILL NOT B. 1. DARK

2. WILL C. 1. LIT

2. WILL NOT D. 1. LIT

2. WILL Page 9 of 100

McGuire Nuclear Station Question: 10 2013A MNS SRO NRC Examination (1 point)

Which ONE (1) of the following indicates the power supplies to the DIG Sequencers?

A. 1EVDA;1EVDD B. IEVDA;IEVDB C. IEVDC;IEVDD D. 1EVDB;1EVDC Page 10 of 100

McGu ire Nuclear Station Question:

11 2013A MNS SRO NRC Examination (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?

A. Running n HIGH speed Running in MAX COOL mode B. Running in LOW speed Running in MAX COOL mode C. Running in HIGH speed Shunt tripped OFF D. Running in LOW speed Shunt tripped OFF Page 11 of 100

McGu ire Nuclear Station Question:

12 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The Unit is operating at 100% RTP

Train B components are in service

An Inadvertent SI is initiated by Maintenance performing testing Based on these conditions:

Lower Containment Ventilation Cooling will be supplied from (1)

Containment Ventilation System Supply Isolation valves ORN-3O1AC and ORN-302B will be (2)

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

A. 1. RVpumps

2. CLOSED B. 1. RVpumps

2. OPEN C. 1. RN non essential header

2. CLOSED D. 1. RN non essential header

2. OPEN Page 12 of 100

McGu ire Nuclear StatIon Question: 13 2013A MNS SRO NRC Examination (1 point)

Given the following signals:

1. Low-Low Glycol Tank level

2. Floor Cooling Glycol Low temperature

3. Phase A Containment Isolation

4. Phase B Containment Isolation Which ONE (1) of the following indicates the signals above that will close 1 NF-228A (NF Supply Containment Isolation Valve)?

A. l&4 B. 2&4 C. 1&3 D. 2&3 Page 13 of 100

McGu ire Nuclear Station Question: 14 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

A LOCA has occurred inside Containment

The crew has implemented E-0 (REACTOR TRIP OR SAFETY INJECTION)

All Containment Spray (NS) pump discharge valves are OPEN

Safety Injection has been RESET Based on the conditions above, to manually start a Containment Spray (NS) pump, the crew must verify that CPCS pressure is greater than a MINIMUM of (1) PSIG AND must depress the (2)

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

A. 1. 0.35

2. NS pump START pushbutton ONLY B. 1. 0.50

2. NS pump START pushbutton ONLY C. 1. 0.35

2. DG Sequencer RESET pushbutton AND NS pump START pushbutton D. 1. 0.50

2. DG Sequencer RESET pushbutton AND NS pump START pushbutton Page 14 of 100

McGu ire Nuclear Station Question: 15 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The unit is at 75% RTP

A small steam leak has developed on 1A SIG

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

A Main Steam Isolation will occur if the IA SIG pressure decreases to less than a MINIMUM of (1) PSIG.

If a Main Steam Isolation occurs, in addition to closing the MSIVs, the (2) will also close.

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

A. 1. 775

2. MSIV Bypasses ONLY B. 1. 875

2. MSIV Bypasses ONLY C. 1. 775

2. MSIV Bypass AND SM PORVs D. 1. 875

2. MSIV Bypass AND SM PORVs Page 15 of 100

McGuire Nuclear Station Question: 16 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The Main Generator is tied to the grid with both Generator breakers CLOSED

Turbine Inlet pressure is 510 PSIG

Both CF pumps are running Based on the conditions above, the entry conditions of AP-03 (LOAD REJECTION)

(1) be met if EITHER CF pump trips.

(2) be met if EITHER Busline de-energizes.

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

A. 1. WILL

2. WILL B. 1. WILL NOT

2. WILL C. 1. WILL

2. WILL NOT D. 1. WILL NOT

2. WILL NOT Page 16 of 100

McGu ire Nuclear Station Question:

17 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

Unit is in Mode 3

The crew is performing unit heatup and pressurization

NC pressure is 1900 PSIG

The CA PUMP AUTO START DEFEAT light is LIT Based on the conditions above:

If both Main Feedwater pumps trip, the MD CA pumps (1) auto start.

If a Safety Injection occurs, the MD CA pumps (2) auto start.

Which ONE (I) 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 17 of 100

McGu ire Nuclear Station Question: 18 2013A MNS SRO NRC Examination (1 point)

Given the following initial conditions on Unit 1:

FR-Hi (RESPONSE TO LOSS OF SECONDARY HEAT SINK) has been implemented and the crew is performing a feed and bleed

CA flow has been restored using the TDCA pump

Containment pressure = 2.1 PSIG In accordance with FR-H.1, which ONE (1) of the following indicates the MINIMUM heat sink requirements that must be met to allow termination of NC system feed and bleed?

A. NR level in at least ONE S/G> 11%

B. NR level in at least ONE S/G > 32%

C. WR level in at least THREE S/Gs> 24%

D. WR level in at least THREE S/Gs> 36%

Page 18 of 100

McGu ire Nuclear Station Question:

19 2013A MNS SRO NRC Examination (1 point)

Given the following on Unit 1:

A reactor trip from 100% RTP has occurred

The TD CA pump tripped on overspeed upon starting

Bus 1 ETA locked out due to a ground fault on the bus Based on the conditions above, which ONE (1) of the following describes which SIGs are currently being fed and the associated flow rates? (ASSUME NO OPERATOR ACTION)

A. IA and I B S/Gs at 450 GPM total flow B. 1C and 1 D S/Gs at 450 GPM total flow C. 1A and lB S/Gs at 150 GPM to each SIG D. IC and 1D S/Gs at 150 GPM to each SIG Page 19 of 100

McGu ire Nuclear Station Question: 20 2013A MNS SRO NRC Examination (1 point)

Given the following plant conditions:

. An electrical grid disturbance has resulted in degrading grid frequency

. AP-05 (GENERATOR VOLTAGE AND ELCTRIC GRID DISTURBANCES) has been implemented

. The crew is monitoring frequency on the OAC and notes the following trend:

Frequency (Hz) vs. Time 61 6O 59i 58 Frequency 57 56 55 14:00 14:10 14:20 14:30 14:40 14:50 15:00 15:10 15:20 15:30 15:40 Assuming that both units remain tied to the grid AND that the current frequency trend continues, what is the EARLIEST time that the units will meet the NC Pump Bus Underfrequency trip setpoint?

A. 14:50 B. 15:00 C. 15:30 D. 15:40 Page 20 of 100

McGuire Nuclear Station Question:

21 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The unit is operating at 100% RTP

The IA DIG has just been declared inoperable due to an oil leak on the Woodward governor Which ONE (I) of the following describes ALL checks which must be performed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to ensure compliance with TS 3.8.1 (AC SOURCES OPERATING)?

A. Flowpaths through which 1 ETA AND I ETB are being supplied by offsite power AND operability of I B D/G.

B. Flowpath through which I ETA is being supplied by offsite power AND determine that I ETA is being supplied independently from 1 ETB.

C. Flowpath through which I ETA OR 1 ETB is being supplied by offsite power AND determine that IETA and IETB are being supplied independently.

D. Flowpaths through which I ETA AND I ETB are being supplied by offsite power AND determine that I ETA and I ETB are being supplied independently.

Page 21 of 100

McGu ire Nuclear Station Question:

22 2013A MNS SRO NRC Examination (1 point)

Given the following plant conditions:

An equalizing charge of Battery I DP is in progress (1) What is the alignment of the 25OVDC Auxiliary Power system battery chargers?

(2) What is the position of the Unit I & 2 Distribution Center bus tie breakers?

A. I. The normal charger charges battery I DP separately from the distribution center while the standby charger supplies the distribution center loads.

2. OPEN B. 1. The normal charger supplies the distribution center loads while the standby charger charges battery I DP separately from the distribution center.

2. CLOSED C. 1. The normal charger charges battery 1 DP separately from the distribution center while the standby charger supplies the distribution center loads.

2. CLOSED D. 1. The normal charger supplies the distribution center loads while the standby charger charges battery I DP separately from the distribution center.

2. OPEN Page 22 of 100

McGu ire Nuclear Station Question:

23 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

A Slow Start of the IA DG is being performed

The IA DG is declared inoperable

The operator places the IA DG Mode Select switch in the LOCAL position Before the engine is started, a loss of normal power occurs on I ETA.

Which ONE (1) of the following describes the action (if any) that must be taken by the Control Room Operator?

A. No action is necessary; The IA DG will start automatically.

B. Place the IA DG Mode Select switch to AUTO; THEN, the IA DG will start automatically.

C. Place the IA DG Mode Select switch to C/R; THEN, the IA DG will start automatically.

D. Place the IA DG Mode Select switch to C/R; THEN, press the 1A DG start pushbutton.

Page 23 of 100

McGuire Nuclear Station Question: 24 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

The unit is operating at 100% RTP

Train A equipment is in operation

The power supply to 2EMF46A (TRAIN A COMPONENT COOLING) has failed

1) What is the impact of the power supply failure?

2) What procedure will be used to address the situation?

A. 1. Alarm on Annunciator Panel 2RAD-1 ONLY

2. Annunciator Response for 2RAD-1/A-4 2EMF 46A Train A KC Hi Rad B. 1. Alarm on Annunciator Panel 2RAD-1 ONLY

2. OP/2/A/6400/005 (COMPONENT COOLING WATER SYSTEM)

C. 1. Alarm on Annunciator Panel 2RAD-1 AND 2KC-122 (COMPONENT COOLING WATER SURGE TANK VENT) will auto close

2. Annunciator Response for 2RAD-1/A-4 2EMF 46A Train A KC Hi Rad D. 1. AlarmonAnnunciatorPanel2RAD-1 AND 2KC-122 (COMPONENT COOLING WATER SURGE TANK VENT) will auto close

2. OP/2/A/6400/005 (COMPONENT COOLING WATER SYSTEM)

Page 24 of 100

McGu ire Nuclear Station Question:

25 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The Unit was initially operating at 100% RTP with B Train components in service

The 1 B RN pump tripped on overcurrent

The crew implemented AP-20 (LOSS OF RN), and has placed the IA RN pump in service

The remaining B Train components are still in operation

The BOP positions the manual loader for I RN-I 90B (RN TO B KC HX CONTROL) to 10% open

The RO was reviewing the OAC graphic for RN and noted 1 RN-i 90B is indicating full open Which ONE (I) of the following describes the reason for this?

A. IRN-I9OB control power is not supplied unless the lB RN Pump breaker is closed.

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

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

D. The manual loader has mechanically failed.

Page 25 of 100

McGuire Nuclear Station Question: 26 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

B Train equipment is in service

The IA DG sequencer is in TEST

A Blackout occurs on the unit

lBDGfaNstostart Assuming no operator actions, which Unit I KC pumps (if any) are in service?

A. IAI and 1A2 KC pumps only B. 1BI and 1B2 KC pumps only C. IAI, IA2, IBI and 1B2 KC pumps D. NO Unit 1 KC pumps are in service Page 26 of 100

McGu ire Nuclear Station Question: 27 2013A MNS SRO NRC Examination (1 point)

The Diesel Generator Starting Air system (VG) can be used to supply the Auxiliary Building Instrument Air system (VI) provided:

Diesel Generator speed is greater than a MINIMUM of (1)

AND a (2) signal is present.

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

A. 1. 97%

2. Blackout ONLY B. 1. 95%

2. Blackout ONLY C. 1. 97%

2. Blackout OR Safety Injection D. 1. 95%

2. Blackout OR Safety Injection Page 27 of 100

McGu ire Nuclear Station Question: 28 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

Unit 2 is in Mode 6 loading fuel

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

2EMF-3 (CONTAINMENT REFUELING BRIDGE) Trip 2 alarm Procedure Legend:

AP-25 (SPENT FUEL DAMAGE)

AP-40 (LOSS OF REFUELING CANAL LEVEL)

The Containment Evacuation alarm (1) automatically actuate.

Based on the above conditions, the crew will be required to implement (2) to mitigate the event.

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

A. 1. WILL

2. AP-25 B. 1. WILL NOT

2. AP-25 C. 1. WILL

2. AP-40 D. 1. WILLNOT

2. AP-40 Page 28 of 100

McGuire Nuclear Station Question:

29 2013A MNS SRO NRC Examination (1 point)

Regarding Control Rod Insertion Limits:

The reason from maintaining Control Rods above a minimum insertion limit is to ensure (1)

If the annunciator IAD-2 / B8 (CONTROL ROD BANK LO LIMIT) is received as the result of a RUNBACK, the crew will (2)

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

Procedure legend:

AP-38 (EMERGENCY BORATION AND RESPONSE TO INADVERTENT DILUTION)

A. 1. adequate Shutdown Margin is maintained

2. ensure the alarm clears as Xenon builds in B. 1. adequate Shutdown Margin is maintained

2. initiate Emergency Boration in accordance with AP-38 C. I. axial flux distribution limits are maintained

2. ensure the alarm clears as Xenon builds in D. I. axial flux distribution limits are maintained

2. initiate Emergency Boration in accordance with AP-38 Page 29 of 100

McGu ire Nuclear Station Question: 30 2013A MNS SRO NRC Examination (1 point)

The WCC SRO has requested a Safety Tag be hung on the breaker for the Unit 2 Reciprocating Charging Pump (PD).

Which ONE (1) of the following electrical panels will the operator need to go to in order to hang this Tag?

A. LC2ELXD B. MCC2MXJ C. MCC2MXK D. MCC2EMXB Page 30 of 100

McGuire Nuclear Station Question:

31 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

A Large Break LOCA has occurred

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

On the ICCM, Subcooling based on the 5 HI T/C AVG (1) be displayed in reverse video.

The range of indication for 5 HI T/C AVG is (2)

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

A. 1. WILL

2. O°Fto2300°F B. 1. WILL NOT

2. O°Fto2300°F C. 1. WILL

2. 32°Fto2300°F D. 1. WILL NOT

2. 32°Fto2300°F Page 31 of 100

McGu ire Nuclear Station Question:

32 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

VF in Filter Mode

1EMF-42 (FUEL BLDG VENT HI RAD) is in service

Loaded Dry Cask movement is in progress in Unit I SFP

Control Room receives a I RAD 3 Cabinet Trouble Alarm due to a loss of power to 1EMF-17 (SPENT FUEL BLDG REFUEL BRDG)

Based on the conditions above, which one of the following states the required Selected Licensee Commitments (SLC) action (if any)?

A. Dry Cask movement may continue since I EMF-42 is in service.

B. Dry Cask movement may continue since this is not movement of recently irradiated fuel assemblies.

C. Suspend all fuel movement operations in the fuel handling area being monitored IMMEDIATELY.

D. Suspend all fuel movement operations in the fuel handling area being monitored WITHIN 1 HOUR.

Page 32 of 100

McGuire Nuclear Station Question: 33 2013A MNS SRO NRC Examination (1 point)

Concerning the Steam Dump Control System:

The P-i 2 LO-LO Tavg setpoint is (1)

In the Load Rejection Mode, the setpoint at which the Bank 1 Steam Dump valves receive a trip open signal is at a (Tavg Tref) difference of

- (2)

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

A 1 551°F 2 8i°F B 1 553°F 2 81°F C 1 551°F 2 144°F D 1 553°F

2. 14.4°F Page 33 of 100

McGuire Nuclear Station Question: 34 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

A turbine load increase was is in progress following a Refueling Outage with IA CF pump in service

The I B CF pump was placed in service and Main Generator electrical load increased to 700 MWe

The load increase was placed on hold at 700 MWe while troubleshooting a problem with the I B CF pump Low Pressure (LP) governor

Control Rods were placed in MANUAL to maintain AFD at current levels Based on the conditions above, the crew will have to initially (1) the NC system to maintain stable plant conditions.

After the I B CF pump is repaired and the unit load increase is recommenced, the withdrawal of control rods (2) be restricted by fuel maneuvering limits.

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

REFERENCE PROVIDED A. I. BORATE

2. WILL B. 1. DILUTE

2. WILL C. 1. BORATE

2. WILL NOT D. I. DILUTE

2. WILL NOT Page 34 of 100

McGuire Nuclear Station Question:

35 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

Unit is at 40% RTP

Exhaust Hood temperature is 160°F

Condenser vacuum is 26 inches HG and DEGRADING slowly

(1ZJP5000) CSAE steam pressure is reading 100 PSIG Which ONE (1) of the following actions is directed by AP-23 (LOSS OF CONDENSER VACUUM) to mitigate this event?

A. Dispatch operator to increase CSAE steam pressure B. Open the Exhaust Hood Spray valves C. Start additional RC pumps D. Reduce turbine load Page 35 of 100

McGuire Nuclear Station Question: 36 2013A MNS SRO NRC Examination (1 point)

Both Main Feedwater (OF) pumps will trip if (1) Condensate Booster pumps trip.

An individual CF pump will trip if its suction pressure decreases to less than a minimum of (2)

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

A. 1. 2/3

2. 230 PSIG B. 1. 3/3

2. 230 PSIG C. 1. 2/3

2. 280 PSIG D. 1. 3/3

2. 280 PSIG Page 36 of 100

McGu ire Nuclear Station Question: 37 2013A MNS SRO NRC Examination (1 point)

Given the following plant conditions:

Both units are at 100% RTP

The B WMT is being released in accordance with an approved LWR Permit

This is the first attempt to release this tank using this permit Subsequently:

Annunciator I RAD-1 / C5 (EMF-49 LIQUID WASTE DISCH HI RAD) alarms in the Control Room

IWP-35 (WMT & VUCDT TO RC CNTRL) indicates OPEN

1WP-37 (LIQUID WASTE TO RC CNTRL) indicates OPEN Based on the conditions above, (1) has/have failed to automatically close.

The FIRST action directed by the Alarm Response Procedure for 1 RAD-1 / C5 is to (2)

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

A. 1. WP-35 ONLY

2. ensure 1WP-35 is closed B. 1. WP-35 ONLY

2. direct Radwaste to close IWM-45 (EMF49 Outlet Isol to RC)

C. 1. BOTH WP-35 and WP-37

2. ensure IWP-35 is closed D. 1. BOTH WP-35 and WP-37

2. direct Radwaste to close IWM-45 (EMF49 Outlet Isol to RC)

Page 37 of 100

McGu ire Nuclear Station Question:

38 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

2EMF-59 (EQUIPMENT STAGING BUILDING VENTILATION MONITOR) s in Trip 2 alarm IfVK(EQUIPMENTSTAGINGBUILDINGVENT)isin (1) ,THEN (2)

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

A. 1. AUTO

2. the Supply fans ONLY will trip B. 1. AUTO

2. the Exhaust AND Supply fans will trip C. 1.ON

2. the Supply fans ONLY will trip D. 1.ON

2. the Exhaust AND Supply fans will trip Page 38 of 100

McGu ire Nuclear Station Question:

39 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

AReactorTriphasoccurred

E-O (REACTOR TRIP OR SAFETY INJECTION) has been implemented In accordance with E-O, if the turbine has not automatically tripped and can NOT be manually tripped, the crew will NEXT attempt to (1)

The E-O basis for the required actions above is to (2)

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

A. 1. close the MSIVs AND MSIV bypasses

2. Prevent an uncontrolled cooldown B. 1. place the turbine in MANUAL AND close the governor valves

2. Prevent an uncontrolled cooldown C. 1. place the turbine in MANUAL AND close the governor valves

2. Maintain steam generator inventory D. 1. close the MSIVs AND MSIV bypasses

2. Maintain steam generator inventory Page 39 of 100

McGu ire Nuclear Station Question:

40 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

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

The crew has just completed the actions of E-0 (REACTOR TRIP OR SAFETY INJECTION)

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

NC system pressure is 1350 PSIG and STABLE

SG pressures are 1092 PSIG and STABLE

NC system subcooling on the ICCM is 22°F and STABLE Which ONE (1) of the following describes plant conditions upon transition to E-1 (LOSS OF REACTOR OR SECONDARY COOLANT)?

SGs NC Pumps Required for Running? Heat Removal?

A. NO YES B. NO NO C. YES YES D. YES NO Page 40 of 100

McGuire Nuclear Station Question:

41 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

The unit is at 100% RTP

The BOP observes that vibration reading on the 1 C NCP are INCREASING

The following is the vibration trend for the IC NCP:

Time 2100 2105 2110 2115 Motor Shaft 5 15 19 22 Vibration Frame Vibration 2 4 6 8 Based on the vibration trend above, which ONE (1) of the following indicates the EARLIEST time that the IC NCP must be secured?

A. 2100 B. 2105 C. 2110 D. 2115 Page 41 of 100

McGu ire Nuclear Station Question:

42 2013A MNS SRO NRC Examination (1 point)

Given the following initial conditions:

Unit I is in Mode 6

NC system is mid-loop at +10

Both ND trains are in operation

NC system temperature is 268° F Based on the indications above, ND pump cavitation will occur if ND pump suction pressure decreases below a MINIMUM of (1) PSIG.

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. fluctuating B. 1.40

2. fluctuating C. 1.25

2. high D. 1.40

2. high Page 42 of 100

McGu ire Nuclear Station Question:

43 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

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

2A Train KC is aligned to supply Reactor and Aux Bldg Non-Essential Headers with both A train KC pumps in operation

2B Train KC is aligned to supply the B ND HX Header with both B tam KC pumps in operation

The 2B2 KC pump has just tripped

2A KC Surge Tank level is slowly decreasing due to a leak In accordance with the Limits and Precautions of 0P121A164001005 (COMPONENT COOLING WATER SYSTEM), KC flow through the 2B ND Heat Exchanger shall be throttled to less than a MAXIMUM of (1) GPM.

In accordance with AP-21 (LOSS OF KC OR KC SYSTEM LEAKAGE), the Operators will take action to isolate flow to the Auxiliary Building Non-Essential Header if the 2A KC Surge Tank level decreases below a MINIMUM of (2)

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

A. 1. 4000

2. 1 foot B. 1. 2000

2. 1 foot C. 1. 4000

2. 2 feet D. 1. 2000

2. 2 feet Page 43 of 100

McGuire Nuclear Station Question: 44 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

A SBLOCA occurred coincident with a loss of Off-site power (LOOP)

ES-I .2 (POST LOCA COOLDOWN AND DEPRESSURIZATION) has been entered and the NCS has been cooled down to 510°F

NC System Pressure is 1600 PSIG

PZR level is 2%

Containment pressure peaked at 3.1 PSIG and is now STABLE at 1.9 psig Which ONE (I) of the following identifies:

(I) the method of NC System depressurization directed by ES-I .2 AND (2) when the depressurization can be stopped?

A. 1. Normal PZR Spray

2. Depressurization can be stopped as soon as pressurizer level exceeds 25%

B. 1. Normal PZR Spray

2. Depressurization can be stopped as soon as pressurizer level exceeds 50%

C. I. One PZR PORV

2. Depressurization can be stopped as soon as pressurizer level exceeds 25%

D. 1. One PZR PORV

2. Depressurization can be stopped as soon as pressurizer level exceeds 50%

Page 44 of 100

McGu ire Nuclear Station Question:

45 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

A SGTR has occurred on the 1 A SG

E-3 (STEAM GENERATOR TUBE RUPTURE) has been implemented When P-12 (LO-LO Tavg) status light on 1SI-18 is lit, the operator will be required to (1) to continue NC system cooldown.

Maximum cooldown rate will be achieved when open status lights are lit for steam dump valves (2)

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

A. 1. Place Steam Dump Select switch to Bypass Interlock

2. 3, 6 and 9 B. 1. Place Steam Pressure Controller in Manual

2. 3, 6 and 9 C. 1. Place Steam Dump Select switch to Bypass Interlock

2. 3,l2and2l D. 1. Place Steam Pressure Controller in Manual

2. 3,l2and2l Page 45 of 100

McGu ire Nuclear Station Question: 46 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

Unit I has established feed and bleed while performing the actions of FR-H.I (RESPONSE TO LOSS OF SECONDARY HEAT SINK)

The TDCA pump has been started and is available to feed the S/Gs

CETsareSTABLE

All S/G WR levels are indicating 0%

1) Based on the conditions described above the criteria for restoration of CA flow is to restore cooling to at a rate not to exceed 100 GPM.

2) The basis for the restoration of flow criteria is to minimize Which ONE (1) of the following completes the statements above?

A. 1. ONE intact S/G

2. the thermal stress on the S/G to prevent failure of S/G components B. I. ONE intact SIG

2. additional NC cooldown causing thermal stress to the reactor vessel C. 1. ALL intact S/Gs

2. the thermal stress on the S/G to prevent failure of S/G components D. 1. ALL intact S/Gs

2. additional NC cooldown causing thermal stress to the reactor vessel Page 46 of 100

McGu ire Nuclear Station Question:

47 2013A MNSSRONRCExamination (1 point)

Given the following initial conditions:

Both units have experiences a Loss of Offsite Power

BOTH Diesel VI compressors are unavailable

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 ThQt are STABLE

S/G pressures are STABLE at 725 PSIG

S/G levels are decreasing and approaching 11% NR

NC T Id are 490°F and STABLE 0

VI header pressure is 0 PSIG Based on the indications above:

Natural Circulation flow (1) been established.

In accordance with ECA-0.1, the Operators will (2)

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 NEO 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 NEO to throttle CA valves locally Page 47 of 100

McGuire Nuclear Station Question: 48 2013A MNS SRO NRC Examination (1 point)

In accordance with ECA-O.O (Loss of All AC Power):

Vital Batteries are sized to supply their design loads for a MINIMUM of (1)

If Channel I SIG Pressure indication for B & C SIG5 is lost, alternate indication is available in the (2) doghouses.

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

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

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

2. interior Page 48 of 100

McGu ire Nuclear Station Question:

49 2013A MNS SRO NRC Examination (1 point)

Given the following on Unit 1:

A loss of EVDD has occurred

The Control Room team has entered AP-1 5 (LOSS OF VITAL OR AUX CONTROL POWER)

In accordance with AP-1 5, the operating crew will be required to respond to rising containment pressure due to isolation of (1)

Containment pressure will be controlled by maintaining Upper Containment temperature within the TS 3.6.5 (Containment Air Temperature) LCO limits of (2)

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

A. 1. the VQ (Containment Air Addition and Release) system

2. 75-100°F B. 1. RV (Containment Cooling) to Upper Containment

2. 75-100°F C. 1. the VQ (Containment Air Addition and Release) system

2. 100-120°F D. 1. RV (Containment Cooling) to Upper Containment

2. 100-120°F Page 49 of 100

McGu ire Nuclear Station Question: 50 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The I25VDC/I2OVAC Auxiliary Control Power System is in normal alignment

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

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

The crew can verify power has been restored to KXA by observing that (2)

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

A. 1. WILL NOT

2. NC pump vibration monitors are IN SERVICE B. 1. WILL NOT

2. the indicating light (control power) to ORN-IOAC (TRAIN lB & 2B LLI SUPPLY) is LIT C. 1. WILL

2. the NC pump vibration monitors are IN SERVICE D. 1. WILL

2. the indicating light (control power) to ORN-IOAC (TRAIN lB & 2B LLI SUPPLY) is LIT Page 50 of 100

McGuire Nuclear Station Question:

51 2013A MNS SRO NRC Examination (1 point)

Given the following indications on Unit 1:

The Unit is operating at 100% RTP

IAD8 I D2 (SUMP B GROUNDWATER DRAINAGE HI HI LVL) just alarmed

An AO has been dispatched to investigate reports that the B Groundwater sump is overflowing Which ONE (1) of the following describes the source of the flooding?

A. 2A RN strainer basket shaft seal failure B. 2B RN Pump Suction piping weld failure C. RE piping break in the Unit 1 CA pump Room D. I B RN strainer automatic backwash valve has failed open Page 51 of 100

McGuire Nuclear Station Question:

52 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

The air line for 1NV-241 (Seal Injection Flow Control) blows off Based on the conditions above, Seal Injection flow to the NC pumps will (1)

The reason for the Seal Injection flow response above is that I NV-241 fails (2) on a loss of instrument air.

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

A. 1. INCREASE

2. OPEN B. 1. DECREASE

2. OPEN C. 1. INCREASE

2. CLOSED D. 1. DECREASE

2. CLOSED Page 52 of 100

McGuire Nuclear Station Question:

53 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The unit is responding to a LOCA Outside Containment

The crew has implemented ECA-1 .2 (LOCA OUTSIDE CONTAINMENT)

In accordance with ECA-1 .2:

The crew will FIRST attempt to isolate the leak by isolating the (1) system from the NC system.

If an NC system cooldown is required, the crew will be directed to use (2)

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

A. 1.NI

2. NC feed and bleed B. 1.ND

2. NC feed and bleed C. 1.Nl

2. the Steam Generators D. 1.ND

2. the Steam Generators Page 53 of 100

McGu ire Nuclear Station Question: 54 2013A MNS SRO NRC Examination (1 point)

An ECA-1.1 (LOSS OF EMERGENCY COOLANT RECIRC) major action requires further depressurization of S/Gs to cooldown and depressurize the NC system.

Which ONE (1) of the following lists ALL the reasons for the major action?

List of Reasons

1. Minimize NC subcooling

2. Reach RHR system conditions

3. Minimize break flow from the LOCA

4. Allow Cold Leg Accumulators to inject A. I and 4 ONLY B. 2and3ONLY C. 2, 3, and 4 ONLY D. I,2,and3ONLY Page 54 of 100

McGu ire Nuclear Station Question:

55 2013A MNS SRO NRC Examination (1 point)

Given the following initial conditions on Unit 1:

The crew has implemented FR-Hi (RESPONSE TO LOSS OF SECONDARY HEAT SINK)

All attempts to restore CA flow have been unsuccessful

SG IA is faulted inside Containment

Containment pressure peaked at 3.2 PSIG and is currently 1 .8 PSIG In accordance with FR-H.1:

The first source of feedwater which is prioritized for restoration is (I)

If feedwater cannot be restored, NC system feed and bleed must be initiated when the required SG WR levels decrease to a MINIMUM of (2)

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

A. 1. Condensate (CM)

2. 24%

B. 1. Condensate (CM)

2. 36%

C. 1. Main Feedwater (CF)

2. 24%

D. 1. Main Feedwater (CF) 2.36%

Page 55 of 100

McGuire Nuclear Station Question:

56 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP with Main Generator power factor at 0.99 lagging

Operators are controlling the Main Generator Voltage Regulator in MANUAL because the voltage regulator is not controlling properly in AUTO

A major grid disturbance causes power factor to become slightly leading

1. Which button on the voltage regulator is operated to bring power factor back to its original value?

2. What part of the generator is susceptible to overheating should power factor be erroneously adjusted to 0.8 lagging?

REFERNCE PROVIDED A. 1. RAISE button

2. Generator Field Windings B. 1. RAISE button

2. Generator Armature Core End C. 1. LOWER button

2. Generator Field Windings D. 1. LOWER button

2. Generator Armature Core End Page 56 of 100

McGu ire Nuclear Station Question: 57 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

AP-14 (ROD CONTROL MALFUNCTION) has been implemented due to a misaligned control rod

Control Rod P8 (Control Bank C) indicates 215 Steps

The remaining rods in Control Bank C indicate 228 Steps Based on the conditions above:

The URGENT ALARM on the RPI panel (1) be illuminated.

The color displayed on the RPI indicator for Rod P-8 will be (2)

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

A. 1. WILL

2. GREEN B. 1. WILL

2. ORANGE C. 1. WILL NOT

2. GREEN D. 1. WILL NOT

2. ORANGE Page 57 of 100

McGu ire Nuclear Station Question: 58 2013A MNS SRO NRC Examination (1 point)

The setpoint for the overload cutoff limit for the Reactor Building Manipulator crane is less than or equal to (1) pounds.

The reason for the manipulator crane overload limits it to prevent damage to the (2)

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

A. 1. 2900

2. Core Internals B. 1. 3250

2. Core Internals C. 1. 2900

2. Refueling Bridge D. 1. 3250

2. Refueling Bridge Page 58 of 100

McGu ire Nuclear Station Question: 59 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

A Steam Generator Tube Leak has occurred

All NC pumps are running Which ONE (1) of the following sets of operating conditions will result in the least Primary-to-Secondary leakage?

REFERENCE PROVIDED NCS Temperature NCS Pressure A. 505°F 775 PSIG B. 511°F 815PSIG C. 517°F 855 PSIG D. 523°F 895 PSIG Page 59 of 100

McGuire Nuclear Station Question: 60 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

The unit is operating at 100% RTP

Main condenser vacuum is degrading slowly

AP-23 (LOSS OF CONDENSER VACUUM) has been implemented In accordance with AP-23, a turbine trip is required if Main Condenser vacuum is less thanaMAXIMUMof (1)

After the Main Turbine reaches its trip setpoint and is tripped, decay heat removal will be via the (2)

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

A. 1. 20HG

2. SMPORVs B. 1. 23HG

2. SMPORVs C. 1. 20HG

2. Steam Dumps D. 1. 23HG

2. Steam Dumps Page 60 of 100

McGu ire Nuclear Station Question: 61 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The Control Room has been evacuated due to toxic gas

AP-17 (LOSS OF CONTROL ROOM) has been implemented In accordance with AP-17:

A local operator will ensure an adequate heat sink is maintained by monitoring SIG (1) level indication.

The local operator maintains SIG levels within the specified range by (2)

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

A. 1. Narrow-Range

2. manually throttling the motor operated isolation valves in the Doghouses B. 1. Wide-Range

2. manually throttling the motor operated isolation valves in the Doghouses C. 1. Narrow-Range

2. adjusting the manual loaders at the local CA pump panels D. 1. Wide-Range

2. adjusting the manual loaders at the local CA pump panels Page 61 of 100

McGu ire Nuclear Station Question: 62 2013A MNS SRO NRC Examination (1 point)

I EMF-48 ( Reactor Coolant Monitor) is located downstream of the Reactor Coolant (I) Sample Hx.

Related to its capability to identify a failed fuel event, I EMF-48 detects (2)

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

A. 1. Cold Leg

2. N16 gamma B. 1. Cold Leg

2. total gamma flux C. I. HotLeg

2. N16 gamma D. I. HotLeg

2. total gamma flux Page 62 of 100

McGu ire Nuclear Station Question:

63 2013A MNS SRO NRC Examination (1 point)

Given the following on Unit 1:

The unit is initially at 100% RTP

At 1100 a Large Break LOCA occurs

At 1215, the crew is in E-1 (LOSS OF REACTOR OR SECONDARY COOLANT), waiting for the time to transfer to Hot Leg Recirc

Containment sump level is 7.5 feet and slowly increasing

1) If Containment Sump level is increasing at a constant rate of 0.25 feet per minute, at what time is entry into FR-Z.2 (RESPONSE TO CONTAINMENT FLOODING),

FIRST required?

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. 1225

2. Operation of the hydrogen skimmer system is compromised by loss of direct access to the containment atmosphere.

B. 1. 1235

2. Operation of the hydrogen skimmer system is compromised by loss of direct access to the containment atmosphere.

C. 1. 1225

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

D. 1. 1235

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

Page 63 of 100

McGu ire Nuclear Station Question: 64 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

A Small-Break LOCA has occurred

ES-I .2 (POST LOCA COOLDOWN AND DEPRESSURIZATION) has been implemented

Containment pressure is 2.8 PSIG and STABLE In accordance with ES-1.2:

The crew will FIRST attempt to establish an NC system cooldown using the (I)

The crew will coold own (2)

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

A. 1. SMPORVs

2. as close as possible without exceeding 100°F in an hour B. 1. SMPORVs

2. at the maximum rate C. 1. Condenser Dumps

2. as close as possible without exceeding 100° F in an hour D. 1. CondenserDumps

2. at the maximum rate Page 64 of 100

McGu ire Nuclear Station Question: 65 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

A Small-Break LOCA has occurred

Containment pressure is 1 .2 PSIG

NC system pressure is 400 PSIG

FR-RI (RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK) has been implemented

SI Termination criteria per FR-P.1 has been met To terminate Safety Injection, FR-P.I directs the operator to reset (I) and stop (2)

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

A. I. Safety Injection ONLY

2. both NI pumps and all but one NV pump ONLY B. 1. Safety Injection AND the Sequencers

2. both NI pumps, both ND pumps and all but one NV pump C. I. Safety Injection AND the Sequencers

2. both NI pumps and all but one NV pump ONLY D. I. Safety Injection ONLY

2. both NI pumps, both ND pumps and all but one NV pump Page 65 of 100

McGu ire Nuclear Station Question:

66 2013A MNS SRO NRC Examination (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 1 NCP-5990 (NC WR LEVEL).

D. MCB Annunciator IADI 0/F-I (UPPER CONT AIRLOCK RX DOOR OPEN),

alarms.

Page 66 of 100

McGuire Nuclear Station Question:

67 2013A MNS SRO NRC Examination (1 point)

Given the following plant conditions:

The Main Control Room has been evacuated due to toxic gas

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

Both Auxiliary Shutdown Panels (ASP) are manned The Operator at the Unit I ASP believes that the following indications at the Unit I 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. l&3ONLY B. 2&3ONLY C. l,3,&4 D. 2,3,&4 Page 67 of 100

McGuire Nuclear Station Question: 68 2013A MNS SRO NRC Examination (1 point)

Regarding Maintenance Rule Assessments:

NSD-403 (SHUTDOWN RISK MANAGEMENT) is the official tool for performing risk assessment in MODES (1)

When using the Electronic Risk Assessment Tool (ERAT), the color associated with a condition where the capability of the ERAT software has been exceeded is (2)

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

A. 1. 4, 5, 6, and No MODE ONLY

2. RED B. 1. 3,4,5,6andNoMODE

2. RED C. 1. 4, 5, 6, and No MODE ONLY

2. WHITE D. I. 3, 4, 5, 6 and No MODE

2. WHITE Page 68 of 100

McGuire Nuclear Station Question:

69 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

A unit startup is in progress

The reactor is a 108 AMPS in the Intermediate Range In accordance with Tech Spec 2.1.2 (RCS Pressure Safety Limit), NC system pressure shall be less than or equal to a MAXIMUM of (1) PSIG.

Based on the conditions above, if the NC system Safety Limit is exceeded, NC system pressure must be restored to within limits in a MAXIMUM of (2)

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

A. 1. 2485

2. 5 minutes B. 1. 2735

2. 5 minutes C. 1. 2485

2. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months D. 1. 2735

2. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Page 69 of 100

McGuire Nuclear Station Question: 70 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

Letdown Heat Exchanger Room dose rate = 3000 mREM/HR In accordance with NSD-507 (RADIATION PROTECTION):

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

Access to the room is controlled by requiring the entrance to be (2)

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

A. 1. Locked High Radiation

2. locked OR guarded B. 1. Locked High Radiation

2. locked at all times C. 1. Very High Radiation

2. locked OR guarded D. 1. Very High Radiation

2. locked at all times Page 70 of 100

McGuire Nuclear Station Question:

71 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The unit is at 75% RTP

An engineer needs to enter the Reactor Building pipechase area to perform some scoping work for a future modification In accordance with MSD 585 (Reactor Building Personnel Access and Material Control):

1. What operational modes require the use of the buddy system for entry into the Reactor Building Annulus or Containment?

2. What is a responsibility of the Operations Control Room personnel for this evolution?

A. 1. Modes 1 and 2 only

2. Performance of PT101A147001062 (Daily Surveillance of Reactor Building Entries)

B. 1. Modes I and 2 only

2. Ensure proper VE airlock door operation C. 1. Modes I,2,3and4

2. Performance of PT101A147001062 (Daily Surveillance of Reactor Building Entries)

D. 1. Modes 1,2,3and4

2. Ensure proper VE airlock door operation Page 71 of 100

McGu ire Nuclear Station Question:

72 2013A MNS SRO NRC Examination (1 point)

Given the following conditions:

A worker will be replacing a valve in the Unit 2 Auxiliary Building

The workers current dose for the year is 1400 mREM

The dose rate in the area where he will be working is 50 mREM/HR The worker can take up to (I) to complete the job before exceeding the Duke Energy annual ALERT exposure limit.

To exceed the ALERT exposure limit, the worker must (2)

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

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

2. notify their supervisor B. 1. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

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

2. obtain a dose extension D. 1. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

2. obtain a dose extension Page 72 of 100

McGuire Nuclear Station Question: 73 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

A loss of Instrument Air (VI) has occurred

The crew has implemented AP-22 (LOSS OF VI)

Which ONE (1) of the following conditions would IMMEDIATELY require tripping the reactor in accordance with AP-22?

A. Pressurizer level going up in an uncontrolled manner.

B. Reactor Coolant Pump stator temperatures are 301 °F and going up.

C. Reactor coolant system temperature less than 557°F and going down.

D. FRV controllers indicate 100% demand and S/G levels are going down.

Page 73 of 100

McGu ire Nuclear Station Question: 74 2013A MNS SRO NRC Examination (1 point)

Given the following plant conditions:

A fire has occurred in the Unit 2 Turbine Building basement

The A Main Fire Pump auto-started due to a low fire header pressure signal

The fire brigade has extinguished the fire after forty-five minutes

IA and IB Jockey Pumps are OFF

A Main Fire Pump is running

B and C Main Fire Pumps are OFF (I) The automatic start setpoint for the A Main Fire Pump on decreasing fire header pressure is PSIG.

(2) In accordance with OP/11A16400/002A (FIRE PROTECTION SYSTEM), the sequence for returning the Fire Protection system to normal alignment is to 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 A Main Fire Pump.

B. 1.83

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

C. 1.73

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

D. 1.83

2. Stop the A 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 Question:

75 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

A BLACKOUT has occurred on I ETA

DIG 1A failed to start due to an 86N relay actuation

Annunciator lAD-I 1/ B4 (BATTERY EVCA UNDERVOLTAGE) is in alarm Per the Annunciator Response Procedure, which ONE (1) of the following addresses the Battery EVCA under voltage condition?

A. Cross tie EVDC to EVDA B. Swap EVDA to Battery Charger EVCS C. Swap Battery Charger Connection box to 2EMXH D. Swap Battery Charger Connection box to 2EM)(A Page 75 of 100

McGu ire Nuclear Station Question:

76 2013A MNS SRO NRC Examination (1 point)

Unit I is operating at 100% RTP. Given the following:

I EMF-33 (CONDENSER AIR EJECTOR EXHAUST) is in Trip 2 alarm

IEMF-71 (S/G A LEAKAGE) is in Trip 2 alarm

Pressurizer level has been stabilized using AP-lO (NC LEAKAGE WITHIN THE CAPACITY OF BOTH NV PUMPS)

Letdown flow is 45 GPM

Charging flow is 78 GPM The MAXIMUM time that AP-lO allows for the unit to reach MODE 3 for the conditions specified is (1)

In accordance with SLC 16.9.7 (STBY S/D SYSTEM) Condition C (LEAKAGE), the Standby Makeup Pump is (2)

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

A. 1. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

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

2. OPERABLE C. 1. 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months

2. INOPERALBE D. 1. 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months

2. OPERABLE Page 76 of 100

McGu ire Nuclear Station Question:

77 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

Train B SSPS testing is in progress In accordance with OMP 5-3 (TSAIL) entry into Tech Spec 3.3.1 (RTS INSTRUMENTATION) for One Rx Trip Breaker Train Inoperable must be made when the (I)

If the RTA Bypass (BYA) breaker is racked in and closed while RTB Bypass (BYB) breaker is racked in and closed, (2) would receive a trip open signal.

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

A. 1. BYB breaker is racked in ONLY

2. RTA and RTB breakers ONLY B. 1. BYB breaker is racked in AND closed

2. RTA and RTB breakers ONLY C. 1. BYB breaker is racked in ONLY

2. RTA, RTB, BYA, and BYB breakers D. 1. BYB breaker is racked in AND closed

2. RTA, RTB, BYA, and BYB breakers Page 77 of 100

McGuire Nuclear Station Question: 78 2013A MNS SRO NRC Examination (1 point)

Unit 1 was operating at 100% RTP when a steam line rupture occurred. Given the following events and conditions:

The operators transitioned from E-0 (Reactor Trip or Safety Injection) to FR-P.1 (Response to Imminent Thermal Shock Condition) due to a RED path on NC Integrity

NCPs 1A and I B were tripped due to high vibration

NCPs IC and I D continue to operate

The operator are at step 16 of FR-RI, which requires isolating the cold leg accumulators

Given the following parameters:

Time 0200 0205 0210 0215 Pzr Pressure (psig) 750 700 650 600 NC Subcooling (°F) +50 +75 +60 +40 RVLIS D/P indication Train A (%) 21 23 24 26 Train B (%) 42 44 51 57 In accordance with FR-P.I, which ONE (1) of the following describes:

I. the earliest time that the CLAs can be isolated?

2. the reason for isolating the CLAs based on current conditions?

REFERENCE PROVIDED A. 1. 0205

2. To prevent injecting CLA water into the reactor vessel and increasing the thermal stress on the vessel.

B. 1. 0205

2. To prevent injecting the CLA nitrogen bubble into the reactor, creating a gas bubble in the vessel head region.

C. 1. 0210

2. To prevent injecting CLA water into the reactor vessel and increasing the thermal stress on the vessel.

D. 1. 0210

2. To prevent injecting the CLA nitrogen bubble into the reactor, creating a gas bubble in the vessel head region.

Page 78 of 100

McGu ire Nuclear Station Question: 79 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

A fault has occurred on the IA Main Steam (SM) line upstream of the MSIV

A Reactor Trip and Safety Injection have occurred due to low NC system pressure

At Step 7 of E-.O (REACTOR TRIP OR SAFETY INJECTION) the OATC reports that the Feedwater Isolation status lights on 1SI-4 are NOT LIT

Narrow Range (NR) levels in IB, IC, and 1D S/Gs are 78% and INCREASING Procedure Legend:

FR-H.3 (RESPONSE TO STEAM GENERATOR HIGH LEVEL)

Based on the conditions above, a YELLOW PATH on Heat Sink will occur if NR level in the intact S/Gs exceeds a MAXIMUM of (I)

In accordance with the Background Document for FR-H.3, the reason for preventing S/G levels from going above the NR level span is to (2)

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

A. 1. 83%

2. prevent an NC system overcooling event B. 1. 83%

2. ensure each S/G remains effective for secondary heat removal C. 1. 92%

2. prevent an NC system overcooling event D. 1. 92%

2. ensure each S/G remains effective for secondary heat removal Page 79 of 100

McGu ire Nuclear Station Question:

80 2013A MNS SRO NRC Examination (1 point)

Given the following plant conditions:

The VI system on Unit 1 has become heavily contaminated with oil due to a maintenance problem

The VI Air Dryer packages rapidly clog Based on the conditions above, the impact to VI system operation is that (I)

AP-22 (LOSS OF VI) directs the CRS to dispatch Operators to locally (2)

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

A. 1. 1VI-1812 (VI Air Dryer Bypass Filter Isol) automatically opens at 85 PSIG

2. bypass the air dryers at 82 PSIG B. 1. lVl-1812 (VI Air Dryer Bypass Filter Isol) automatically opens at 90 PSIG

2. bypass the air dryers at 85 PSIG C. 1. VI Dryer Purge Exhaust Valves automatically close at 85 PSIG

2. close VI Dryer Purge Exhaust Valves at 82 PSIG D. I. VI Dryer Purge Exhaust Valves automatically close at 90 PSIG

2. close VI Dryer Purge Exhaust Valves at 85 PSIG Page 80 of 100

McGu ire Nuclear Station Question:

81 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

The unit is currently in MODE 6 in preparation for fuel movement

Refueling Cavity level is 373 inches Based on the conditions above:

In accordance with Technical Specifications, a MINIMUM of (1) RHR loops shall be OPERABLE.

In accordance with Technical Specification surveillance requirements, an RHR loop which is in operation shall have a flow rate of greater than or equal to a MINIMUM of (2) GPM.

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

A. 1. ONE

2. 500 B. 1. TWO

2. 500 C. 1. ONE

2. 1000 D. 1. TWO

2. 1000 Page 81 of 100

McGu ire Nuclear Station Question: 82 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

An inadvertent Safety Injection has occurred

The crew has implemented ES-I .1 (SAFETY INJECTION TERMINATION)

All NC pumps are running

Reactor Vessel D/P is 100%

The BOP operator informs the CRS that I NC-27C (1A LOOP PZR SPRAY CONTROL) indicates intermediate

PZR level is 85% and INCREASING Based on the above conditions, the entry conditions of FR-I.l (RESPONSE TO HIGH PRESSURIZER LEVEL) will be met if PZR level increases to a MAXIMUM of (1)

In accordance with FR-I.I, if INC-27C cannot be closed the crew will stop (2)

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

A. 1. 92%

2. IA and 1 B NC pumps ONLY B. 1. 96%

2. 1A and I B NC pumps ONLY C. 1. 92%

2. IA and 1 B NC pumps AND one additional NC pump D. 1. 96%

2. IA and 1 B NC pumps AND one additional NC pump Page 82 of 100

McGu ire Nuclear Station Question:

83 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

A DCS malfunction occurs and 1A CF Pump is not controlling properly in AUTO

All SIG NR levels are decreasing slowly due to a mismatch between steam flow and feed flow Procedure Legend:

AP-03 (LOAD REJECTION)

E-0 (REACTOR TRIP OR SAFETY INJECTION)

In accordance with AP-06 (S/G FEEDWATER MALFUNCTION):

The crew will FIRST attempt to gain control of the IA CF pump by (1)

If flow from the IA CF Pump is completely lost, the crew will be directed to (2)

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

A. 1. adjusting the LP governor controls in manual

2. immediately trip the reactor and enter E-0 B. I. selecting Speed Set mode and adjusting the LP governor setpoint

2. immediately trip the reactor and enter E-0 C. 1. adjusting the LP governor controls in manual

2. trip the IA CF pump AND implement AP-03 D. 1. selecting Speed Set mode and adjusting the LP governor setpoint

2. trip the 1A CF pump AND implement AP-03 Page 83 of 100

McGuire Nuclear Station Question:

84 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

A reactor trip has occurred

Safety Injection is actuated

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

NC pumps have been secured

NC System pressure is 1700 PSIG and lowering slowly

Pzr level is off-scale low

Containment pressure is 1 .7 PSIG and rising slowly

FWST level is 185 inches and lowering at 2 inches per minute

SG pressures are 1050 PSIG and stable

CAflowis600GPM

The operators have just transitioned to E-1 (LOSS OF REACTOR OR SECONDARY COOLANT)

Procedure Legend:

ES-I .2 (POST LOCA COOLDOWN AND DEPRESSURIZATION)

ES-I .3 (TRANSFER TO COLD LEG RECIRCULATION)

The basis for stopping NC pumps in E-0 is to (I)

Based on the conditions above, the next procedure transition will be to (2)

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

A. I. minimize heat input into the NC system

2. ES-I.2 B. 1. minimize mass loss from the NC system

2. ES-l.2 C. I. minimize heat input into the NC system

2. ES-I.3 D. I. minimize mass loss from the NC system

2. ES-I.3 Page 84 of 100

McGu ire Nuclear Station Question:

85 2013A MNS SRO NRC Examination (1 point)

Unit 1 is operating at 100% RTP when the following alarms are received:

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

IAD-7 /12 (REGEN HX LETDN HI TEMP)

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

The crew has implemented AP-12 (LOSS OF LETDOWN, CHARGING, OR SEAL INJECTION).

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

2. What actions are directed by AP-12 regarding the restoration of letdown during the subsequent recovery?

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

2. Pressurize the letdown system locally.

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

2. Pressurize the letdown system locally.

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

2. Pressurize the letdown system from the Control Room.

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

2. Pressurize the letdown system from the Control Room.

Page 85 of 100

McGu ire Nuclear Station Question:

86 2013A MNS SRO NRC Examination (1 point)

Given the following initial conditions on Unit 1:

A unit shutdown and cooldown is in progress

NC system pressure is 1900 PSIG

NC system temperature is 51 0°F

B Train components are in service The following sequence of events occur:

1. A Main Steam line ruptures inside containment

2. I2OVAC Vital panel board EKVD de-energizes due to an electrical fault

3. Pressurizer pressure is 1850 PSIG and lowering

4. Containment pressure is 2.8 PSIG and rising slowly Based on the condition above, the MSIVs (1) close when a Main Steam Isolation Signal is received.

In accordance with the surveillance requirements of Tech Spec 3.7.2 (MSIVs), the Main Steam Isolation Valves must be capable of closing in less than or equal to a MAXIMUM of (2) seconds.

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

A. 1. WILL

2. 8 B. 1. WILL

2. 10 C. 1. WILL NOT

2. 8 D. 1. WILL NOT

2. 10 Page 86 of 100

McGu ire Nuclear Station Question: 87 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

A Loss of Offsite Power has occurred

The supply breaker for I EKVA trips and cannot be re-closed In accordance with AP-15 (LOSS OF VITAL OR AUX CONTROL POWER)

Enclosure 29 (IA DIG Room Local Actions with Loss of I EKVA):

The VG Air Compressors breakers must be manually cycled to maintain D/G VG Tank pressure; the VG Air Compressors will (I) on a loss of I EKVA.

The IA D/G Fuel Oil Transfer pump control switch must be operated at the D/G Panel to maintain IA D/G Fuel Oil Day Tank level; the Fuel Oil Transfer pump will (2) on a loss of 1EKVA.

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

A. 1. run continuously

2. run continuously B. I. notruninauto

2. run continuously C. 1. run continuously

2. not run in auto D. 1. notrun in auto

2. not run in auto Page 87 of 100

McGu ire Nuclear Station Question:

88 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The unit is at 25% RTP

The crew receives a report of flooding in the Unit 1 B DIG Room

It is determined to be a major piping failure of the RN System Procedure Legend:

AP-20 (LOSS OF RN)

AP-44 (PLANT FLOODING)

Based on the conditions above, (1) would be used to isolate the piping failure.

Upon completion of the isolation procedure, the KD HX Inlet and Outlet Isolation Valves (1RN-171B and 1RN-174B) will be (2)

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

A. 1. AP-20

2. CLOSED ONLY B. 1. AP-20

2. CLOSED with their motor breakers OPEN C. 1. AP-44

2. CLOSED ONLY D. 1. AP-44

2. CLOSED with their motor breakers OPEN Page 88 of 100

McGuire Nuclear Station Question:

89 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

A loss of all Feedwater has occurred

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

NC system Feed and Bleed is in progress

The Shift Manager has assumed the role of Emergency Coordinator

The TSC is not manned

The EOF is activated Based on the conditions above, this event will be classified as a/an (1)

In accordance with the Emergency Response (RP) procedures, if emergency conditions prevent manning the TSC within 75 minutes of declaration, responsibility for classification and notification will (2)

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

REFERENCE PROVIDED A. 1. Site Area Emergency

2. remain with the Shift Manager B. 1. Site Area Emergency

2. be turned over to the EOF C. 1. Alert

2. remain with the Shift Manager D. 1. Alert

2. be turned overto the EOF Page 89 of 100

McGu ire Nuclear Station Question:

90 2013A MNSSRONRCExamination (1 point)

Given the following conditions on Unit 1:

A unit startup is in progress

Reactor power is 4%

The crew determines that Control Rod M-4 is misaligned by greater than 12 steps In accordance with AP-14 (ROD CONTROL MALFUNCTION) Enclosure 1 (RESPONSE TO DROPPED OR MISALIGNED ROD):

The crew will use (1) to determine reactor power during implementation of Enclosure 1.

Based on current plant conditions, the crew is required to (2)

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

A. 1. Excore Nuclear Instruments

2. shutdown to MODE 3 B. 1. Thermal Power Best Estimate

2. shutdown to MODE 3 C. 1. Excore Nuclear Instruments

2. maintain power stable until the cause of the misaligned rod is corrected D. 1. Thermal Power Best Estimate

2. maintain power stable until the cause of the misaligned rod is corrected Page 90 of 100

McGuire Nuclear Station Question:

91 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

A unit startup in progress

All Power Ranges indicate 6%

Both Source Range channels are de-energized In accordance with Tech Spec 3.3.1 (RTS INSTRUMENTATION), if BOTH Intermediate Range channels fail LOW, the crew will be required to (1)

Based on the conditions above, in accordance with AP-16 (MALFUNCTION OF NUCLEAR INSTRUMENTATION), if an Intermediate Range channel Control Power fuses are removed, a reactor trip (1) occur.

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

A. 1. reduce power to less than P-6 ONLY

2. WILL B. 1. reduce power to less than P-6 OR increase power to greater than P-1O

2. WILL C. 1. reduce power to less than P-6 ONLY

2. WILL NOT D. 1. reduce power to less than P-6 OR increase power to greater than P-1O

2. WILL NOT Page 91 of 100

McGu ire Nuclear Station Question: 92 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

At 0815 a Reactor Ttip and SI actuated automatically due to a Large-Break LOCA

Actions of E-0 (REACTOR TRIP OR SAFETY INJECTION) were completed at 0845 Conditions at Time = 0900: Conditions at Time = 0920:

NC pressure = 4 PSIG

NC pressure = 3 PSIG

RVLIS Lower Range level 35%

RVLIS Lower Range level = 33%

CETs=705°F

CETs=715°F

Subcooling Monitor = -35°F

Subcooling Monitor = -35°F

Containment pressure = 3.5 PSIG

Containment pressure = 2.5 PSIG

I EMF-51A = 35 RJhr

1EMF-51A=3ORIhr

All S/G NR levels offscale low with

All S/G NR levels offscale low with no CA flow no CA flow Based on the conditions at 0920, which ONE (1) of the following is the classification and associated EAL number for this event? (For the purposes of this question, do NOT consider Emergency Coodinatorjudgement as a basis of classification)

REFERENCE PROVIDED A. Site Area Emergency based on EAL # 4.1.S.1 B. General Emergency based on EAL #4.1.G.1 C. Site Area Emergency based on EAL # 4.1.S.2 D. General Emergency based on EAL#4.1.G.2 Page 92 of 100

McGu ire Nuclear Station Question:

93 2013A MNS SRO NRC Examination (1 point)

Given the following initial conditions on Unit 1:

The unit was at 100% RTP

A fault occurs on 1C SIG inside Containment

Containment pressure rapidly rises to 3.2 PSIG Procedure Legend:

E-0 (REACTOR TRIP OR SAFETY INJECTION)

FR-Si (RESPONSE TO NUCLEAR POWER GENERATION I ATWS)

E-1 (LOSS OR REACTOR OR SECONDARY COOLANT)

The following sequence of events occurs:

0200 - Crew implements E-0 due to a valid Reactor Trip condition 0201 - Crew transitions to FR-S.1 due to failure of reactor to trip in AUTOMATIC or MANUAL 0203 - Crew manually initiates Safety Injection 0205 - OATC reports that the reactor is tripped 0209 - Crew completes FR-S.1 and transitions back to E-0 0215 - Crew completes E-0 actions and transitions to E-1 Which ONE (1) of the following indicates the EARLIEST time that the crew could have transitioned to ES-0.0 (REDIAGNOSIS)?

A. 0201 B. 0203 C. 0209 D. 0215 Page 93 of 100

McGuire Nuclear Station Question:

94 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

You are the Control Room Supervisor

An explosion occurs resulting in significant damage in the unit

The Shift Manager was seriously injured in the explosion and is incapacitated.

A significant radioactive release is occurring from the Aux Building

To regain control of the unit, the crew must cross-tie power supplies NOT allowed by Technical Specifications

The cross-tie operation is NOT defined in EPs or APs

Immediate action is required Which ONE (1) of the following describes the MINIMUM requirements for applying 1 OCFR5O.54(X) (CONDITIONS OF LICENSES) in accordance with OMP 4-3 (USE OF ABNORMAL AND EMERGENCY PROCEDURES)?

A. You may approve this action without any additional concurrence.

B. You must obtain concurrence from one other SRO prior to performing the action.

C. The Plant Manager must be notified prior to the action and must approve the action to be taken.

D. The NRC must be notified prior to the action and must approve the action to be taken.

Page 94 of 100

McGu ire Nuclear Station Question:

95 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

A unit startup is in progress

Theunitisatl5%RTP

A Steam Generator Tube Leak occurs Indications:

S/G NR Level going up in an uncontrolled manner

S/G or Steam Line EMFs above normal

Comparison of S!G Secondary Chemistry samples

1. Comparison of RP frisk of main steam lines

2. S/G CF Flow comparison

3. Comparison of RP frisk of S/G cation columns In accordance with AP-lO (NC SYSTEM LEAKAGE WITHIN THE CAPACITY OF BOTH NV PUMPS) Case I (STEAM GENERATOR TUBE LEAKAGE), ALL of the redundant indications that will be used to identify the leaking S/G are the bulleted indications and Which ONE (1) of the following completes the statement above?

A. I ONLY B. 3 ONLY C. 1AND2 D. 2AND3 Page 95 of 100

McGu ire Nuclear Station Question:

96 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 2:

The unit is at 100% RTP

The Shift Manager has directed the OTG to perform PT/2/A14209/013A (2A BORIC ACID TRANSFER PUMP PERFORMANCE TEST) to observe the evolution

2A Boric Acid Pump is placed in recirc as required During the performance of PT/21A142091013A, the Boration Flow Path from the Boric Acid Tank is (1)

If the performance test determines that bearing vibration levels are in the ALERT Range, the pump (2)

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

A. 1. OPERABLE

2. must be declared inoperable B. 1. OPERABLE

2. is OPERABLE and surveillance frequency is doubled C. 1. INOPERABLE

2. must be declared inoperable D. 1. INOPERABLE

2. is OPERABLE and surveillance frequency is doubled Page 96 of 100

McGuire Nuclear Station Question:

97 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

The following alarms are received:

o 1 EMF-48 (REACTOR COOLANT HIGH RAD) o IEMF-18(REACTOR COOLANT FILTER IA)

The crew has implemented AP-018 (HIGH ACTIVITY IN REACTOR COOLANT)

Chemistry sample indicates that the high activity is due to failed fuel

Dose-Equivalent lodine-131 is approximately 5 jCi/gm In accordance with AP-Ol 8, the crew will (1)

In accordance with Tech Spec 3.4.16 (RCS SPECIFIC ACTIVITY) (2)

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

A. 1. raise Letdown flow to 120 GPM

2. a plant shutdown and coold own to less than 500° F must be performed B. 1. raise Letdown flow to 120 GPM;

2. plant operation may continue for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months with sampling NC system every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C. 1. ensure Mixed Bed Demin is in service AND place a Cation Bed Demin in service if requested by Chemistry

2. a plant shutdown and cooldown to less than 500°F must be performed D. 1. ensure Mixed Bed Demin is in service AND place a Cation Bed Demin in service if requested by Chemistry

2. plant operation may continue for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months with sampling NC system every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Page 97 of 100

McGu ire Nuclear Station Question:

98 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit 1:

The unit is in MODE 5 in preparation for refueling

The crew is preparing to place the Containment Purge (VP) system in service

The Gaseous Waste Release (GWR) is ready for Operations review Procedure legend:

SLC 16.11.6 (DOSE RATE GASEOUS EFFLUENTS)

Which ONE (1) of the following must the CRS verify prior to authorizing the VP release?

A. Source check has been performed B. Operability of I EMF-36 (UNIT VENT GAS)

C. 1 EMF-36 Trip 1 and Trip 2 setpoints D. The release will not exceed the limits of SLC 16.11.6 Page 98 of 100

McGu ire Nuclear Station Question:

99 2013A MNS SRO NRC Examination (1 point)

With Unit 1 at 100% RTP the following conditions exist:

The IC SIG develops a 10 GPM tube leak

AP-lO (NC SYSTEM LEAKAGE WITHIN THE CAPACITY OF BOTH NV PUMPS), Case I (STEAM GENERATOR TUBE LEAKAGE) has been implemented

Plant load is reduced using AP-04 (RAPID DOWNPOWER), and manually tripped at 15% power

The crew has just transitioned to ES-0.1 (REACTOR TRIP RESPONSE)

Subsequently:

NCS Pressure is 2210 PSIG, and slowly DECREASING

The crew arrives at Step 23.a of ES-0.1 and is directed to Maintain Pzr pressure AT 2235 PSIG

Simultaneously, the crew arrives at Step 18.a of AP-lO and is directed to Depressurize to between 1900-1 955 PSIG using normal Pzr spray.

Which ONE (1) of the following describes how the implementation of AP-lO and ES-0.1 is coordinated?

A. Suspend actions in AP-lO until ES-0.1 is complete; THEN Return to AP-lO and complete all required actions.

B. Continue simultaneous implementation of ES-0.1 and AP-lO; ONLY AP-lO actions directed by CRS may be performed.

C. Continue simultaneous implementation of ES-0.1 and AP-lO; If conflicting guidance is provided, AP-lO actions will have priority.

D. Continue simultaneous implementation of ES-0.1 and AP-lO; If conflicting guidance is provided, ES-0.1 actions will have priority.

Page 99 of 100

McGuire Nuclear Station Question: 100 2013A MNS SRO NRC Examination (1 point)

Given the following conditions on Unit I:

Mode4

Cold Leg Accumulators are isolated

In process of cooling down and depressurizing the NC System

1 NC-I (Pressurizer Code Safety Valve) begins to leak

NC Pressure is slowly going down

PRT level and pressure are going up

Containment Pressure is 0.15 PSIG and STABLE Procedure Legend:

AP-35 (ECCS ACTUATION DURING PLANT SHUTDOWN)

E-0 (REACTOR TRIP OR SAFETY INJECTION)

AP-lO (NC SYSTEM LEAKAGE WITHIN THE CAPACITY OF BOTH NV PUMPS) Case II (NC SYSTEM LEAKAGE)

AP-34 (SHUTDOWN LOCA)

Which one of the following describes the proper procedure flowpath to mitigate the conditions above?

A. Enter AP-35 and then go to AP-34 B. Enter AP-35 and then go to E-0 C. Enter AP-lO and then go to AP-34 D. Enter AP-I0 and then go to AP-35 Page 100 of 108

Reference Listfor: 2013A MNS SRO NRC Examination Steam Tables UI Data Book Enclosure 4.3, Fuel Maneuvering Limits Generic Enclosure 33 Generator Capability Curve FR-RI (Response to Imminent Pressurized Thermal Shock Condition)

Step 16.

RP-000 (Classification of Emergency)

Printed 12/3/2013 5:39:12 PM Page 1 of 1

Examination KEYfor: 2013A MNS SRO NRC Examination Question Answer Number 1 A 2 D 3 A 4 B 5 C 6 D 7 C 8 D 9 C 10 A 11 C 12 B 13 C 14 C 15 C 16 A 17 C 18 A 19 B 20 D 21 D 22 B 23 A 24 C 25 C Printed 12/3/2013 5:42:18 PM Page 1 of 4

Examination KEYfor: 2013A MNS SRO NRC Examination Question Answer Number 26 A 27 B 28 A 29 A 30 C 31 C 32 C 33 B 34 B 35 A 36 B 37 A 38 B 39 B 40 C 41 C 42 A 43 C 44 D 45 C 46 A 47 B 48 C 49 A 50 C Printed 12/3/2013 5:42:18 PM Page 2 of 4

Examination KEYfor: 2013A MNS SRO NRC Examination Question Answer Number 51 B 52 B 53 D 54 C 55 D 56 A 57 A 58 A 59 D 60 A 61 D 62 D 63 D 64 C 65 B 66 B 67 A 68 C 69 D 70 A 71 D 72 A 73 D 74 B 75 D Printed 12/3/2013 5:42:18 PM Page 3 of 4

Examination KEYfor: 2013A MNS SRO NRC Examination Question Answer Number 76 C 77 D 78 C 79 8 80 A 81 C 82 C 83 D 84 B 85 C 86 A 87 C 88 D 89 B 90 B 91 A 92 D 93 D 94 A 95 D 96 D 97 D 98 A 99 C 100 C Printed 12/3/2013 5:42:18 PM Page 4 of 4

ML14014A063

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