ML14014A062

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Initial Exam 2013-301 Final RO Written Exam
ML14014A062
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 01/14/2014
From:
Division of Nuclear Materials Safety II
To:
References
50-369/13-301, 50-370/13-301
Download: ML14014A062 (80)
v • d • e


Text

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

Date: Facility/Unit: MCGUIRE Region: I Ill IV Reactor Type: (V 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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

McGu ire Nuclear Station Question:

  • I 2013A MNS RO 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. 1D Page 1 of 75

McGu ire Nuclear Station Question:

  • 2 2013A MNSRONRCExamination (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 (I) of the following completes the statements above?

A. I. INCREASE

2. 120°F B. I. INCREASE
2. 138°F C. I. DECREASE
2. 120°F D. I. DECREASE
2. 138°F Page 2 of 75

McGu ire Nuclear Station Question: 3 2013A MNS RO 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 I NV-238 is repaired, what operator action(s) will be reQuired to restore automatic pressurizer level control?

A. 1. Actual level was higher than program level

2. Place I 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 I 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 1NV-238 in automatic ONLY Page 3 of 75

McGu ire Nuclear Station Question: 4 2013A 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
  • 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 75

McGu ire Nuclear Station Question: 5 2013A MNS RO 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 Qj, Blackout
2. align Vito C. 1. Safety injection ONLY
2. vent air off D. 1. Safety injection OR Blackout
2. ventairoff PageS of 75

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

Given the following conditions on Unit 2:

  • Containment pressure is initially NEGATIVE 0.1 PSIG and stable
  • ONE (1) 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 75

McGu ire Nuclear Station Question:

  • 7 2013A MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

  • A Small Break LOCA occurred in Containment
  • SI has actuated on both trains
  • I 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 75

McGu ire Nuclear Station Question:

  • 8 2013A MNS RO NRC Examination (1 point)

Given the following initial conditions on Unit 1:

  • 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 75

McGu ire Nuclear Station Question:

  • 9 2013A MNSRONRCExamination (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 1 SI-i 8 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 75

McGu ire Nuclear Station Question: 10 2013A MNS RO NRC Examination (1 point)

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

A. 1EVDA;1EVDD B. 1EVDA;IEVDB C. 1EVDC;IEVDD D. 1EVDB;1EVDC Page 10 of 75

McGu ire Nuclear Station Question: 11 2013A MNS RO 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 in 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 75

McGu ire Nuclear Station Question: 12 2013A MNS RO 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-3OIAC and ORN-302B will be (2)

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

A. 1. RV pumps

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 75

McGu ire Nuclear Station Question: 13 2013A MNSRONRCExamination (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. 1&4 B. 2&4 C. 1&3 D. 2&3 Page 13 of 75

McGuire Nuclear Station Question:

  • 14 2013A MNSRONRCExamination (1 point)

Given the following conditions on Unit 1:

  • A LOCA has occurred inside Containment
  • 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 75

McGu ire Nuclear Station Question:

  • 15 2013A MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

  • The unit is at 75% RTP
  • A small steam leak has developed on IA SIG
  • NC system pressure is 2210 PSIG and STABLE Based on the conditions above:

A Main Steam Isolation will occur if the IA S/G 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 75

McGuire Nuclear Station Question:

  • 16 2013A MNS RO 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 (1) 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 75

McGu ire Nuclear Station Question:

  • 17 2013A MNS RO 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 (1) of the following completes the statements above?

A. 1. WILL

2. WILL B. 1. WILL
2. WILL NOT C. 1. WILL NOT
2. WILL D. 1. WILL NOT
2. WILL NOT Page 17 of 75

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

Given the following initial conditions on Unit 1:

  • FR-H.1 (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 75

McGuire Nuclear Station Question: 19 2013A MNS RO NRC Examination (1 point)

Given the following on Unit 1:

  • The TD CA pump tripped on overspeed upon starting
  • Bus 1ETA locked out due to a ground fault on the bus Based on the conditions above, which ONE (I) of the following describes which S/Gs are currently being fed and the associated flow rates? (ASSUME NO OPERATOR ACTION)

A. 1A and 1 B S/Gs at 450 GPM total flow B. IC and ID S/Gs at 450 GPM total flow C. 1A and lB S/Gs at 150 GPM to each S/G D. 1C and ID S/Gs at 150 GPM to each S/G Page 19 of 75

McGu ire Nuclear Station Question: 20 2013A MNS RO 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 60 59 58 Frequency 57 I 56 1  :

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 75

McGu ire Nuclear Station Question: 21 2013A MNS RO 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 (1) of the following describes ALL checks which must be performed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to ensure compliance with TS 3.8.1 (AC SOURCES OPERATING)?

A. Flowpaths through which 1 ETA AND 1 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 I ETB is being supplied by offsite power AND determine that I ETA and I ETB 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 75

McGu ire Nuclear Station Question:

  • 22 2013A MNS RO 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. 1. 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. I. The normal charger charges battery 1 DP separately from the distribution center while the standby charger supplies the distribution center loads.
2. CLOSED D. I. 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 75

McGu ire Nuclear Station Question:

  • 23 2013A MNS RO 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 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 1A DG Mode Select switch to AUTO; THEN, the 1A 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 IA DG start pushbutton.

Page 23 of 75

McGu ire Nuclear Station Question:

  • 24 2013A MNS RO NRC Examination (1 point)

Given the following conditions on Unit 2:

  • The unit is operating at 1 00% 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. AlarmonAnnunciatorPanel2RAD-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. Alarm on Annunciator Panel 2RAD-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 75

McGu ire Nuclear Station Question: 25 2013A MNS RO NRC Examination (1 point)

Given the following conditions on Unit I:

  • The Unit was initially operating at 100% RTP with B Train components in service
  • The I 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 1 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-l 90B is indicating full open Which ONE (I) of the following describes the reason for this?

A. IRN-190B control power is not supplied unless the lB RN Pump breaker is closed.

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

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

D. The manual loader has mechanically failed.

Page 25 of 75

McGuire Nuclear Station Question:

  • 26 2013A MNS RO 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
  • IBDGfailstostart Assuming no operator actions, which Unit I KC pumps (if any) are in service?

A. IAI and 1A2 KC pumps only B. IBI and 1B2 KC pumps only C. IAI, 1A2, IBI and IB2 KC pumps D. NO Unit I KC pumps are in service Page 26 of 75

McGu ire Nuclear Station Question: 27 2013A MNS RO 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 75

McGuire Nuclear Station Question:

  • 28 2013A MNS RO 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. WILLNOT
2. AP-25 C. 1. WILL
2. AP-40 D. 1. WILLNOT
2. AP-40 Page 28 of 75

McGuire Nuclear Station Question: 29 2013A MNSRONRCExamination (1 point)

Regarding Control Rod Insertion Limits:

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

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. 1. axial flux distribution limits are maintained
2. ensure the alarm clears as Xenon builds in D. 1. axial flux distribution limits are maintained
2. initiate Emergency Boration in accordance with AP-38 Page 29 of 75

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

The WOO 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. MOO 2MXJ C. MOO 2MXK D. MOO 2EMXB Page 30 of 75

McGu ire Nuclear Station Question:

  • 31 2013A 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 TIC AVG indicates negative (-) 4°F on the Inadequate Core Cooling Monitor (lOOM)

On the 10CM, 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. 0°F to 2300° F B. 1. WILL NOT
2. 0°Fto2300°F C. 1. WILL
2. 32°Fto2300°F D. 1. WILL NOT
2. 32°Fto2300°F Page 31 of75

McGu ire Nuclear Station Question: 32 2013A MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

  • VF in Filter Mode
  • 1 EMF-42 (FUEL BLDG VENT HI RAD) is in service
  • Loaded Dry Cask movement is in progress in Unit I SFP
  • Control Room receives a 1 RAD 3 Cabinet Trouble Alarm due to a loss of power to IEMF-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 75

McGu ire Nuclear Station Question: 33 2013A MNS RO NRC Examination (1 point)

Concerning the Steam Dump Control System:

The P-12 LO-LO Tavg setpoint is (I)

In the Load Rejection Mode, the setpoint at which the Bank I 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 81°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 75

McGu ire Nuclear Station Question: 34 2013A MNS RO 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 1 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. 1. BORATE

2. WILL B. 1. DILUTE
2. WILL C. 1. BORATE
2. WILL NOT D. 1. DILUTE
2. WILL NOT Page 34 of 75

McGu ire Nuclear Station Question:

  • 35 2013A MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

  • Unitisat40%RTP
  • Exhaust Hood temperature is 160°F
  • Condenser vacuum is 26 inches HG and DEGRADING slowly
  • (IZJP5000) 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 75

McGu ire Nuclear Station Question: 36 2013A MNS RO NRC Examination (1 point)

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

An individual CE 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 75

McGu ire Nuclear Station Question: 37 2013A MNS RO 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 1 RAD-1 I C5 (EMF-49 LIQUID WASTE DISCH HI RAD) alarms in the Control Room
  • 1WP-35 (WMT & VUCDT TO RC CNTRL) indicates OPEN
  • IWP-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 I 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 75

McGu ire Nuclear Station Question:

  • 38 2013A MNSRONRCExamination (1 point)

Given the following conditions on Unit 2:

  • 2EMF-59 (EQUIPMENT STAGING BUILDING VENTILATION MONITOR) is in Trip 2 alarm If VK (EQUIPMENT STAGING BUILDING VENT) is in (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.
2. the Supply fans ONLY will trip D. 1.ON
2. the Exhaust AND Supply fans will trip Page 38 of 75

McGu ire Nuclear Station Question: 39 2013A MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

  • 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 75

McGu ire Nuclear Station Question:

  • 40 2013A MNS RO 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 75

McGu ire Nuclear Station Question: 41 2013A MNS RO 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 IC NCP are INCREASING
  • The following is the vibration trend for the 1 C 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 75

McGu ire Nuclear Station Question:

  • 42 2013A MNS RO NRC Examination (1 point)

Given the following initial conditions:

  • Unit us 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 (I) 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 75

McGu ire Nuclear Station Question: 43 2013A MNS RO 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. 2feet D. 1. 2000
2. 2feet Page 43 of 75

McGu ire Nuclear Station Question:

  • 44 2013A MNS RO 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:

(1) 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. 1. One PZR PORV

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

D. 1. OnePZRPORV

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

Page 44 of 75

McGu ire Nuclear Station Question: 45 2013A MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

  • E-3 (STEAM GENERATOR TUBE RUPTURE) has been implemented When P-I2 (LO-LO Tavg) status light on lSl-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 75

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

Given the following conditions on Unit 1:

  • Unit 1 has established feed and bleed while performing the actions of FR-H.1 (RESPONSE TO LOSS OF SECONDARY HEAT SINK)
  • The TDCA pump has been started and is available to feed the S/Gs
  • 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. 1. ONE intact S/G
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 75

McGu ire Nuclear Station Question: 47 2013A MNS RO NRC Examination (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 I and the crew has just transitioned to ECA-0.1 (LOSS OF ALL AC POWER RECOVERY WITHOUT S/I REQUIRED)

Current conditions:

NC Th t are STABLE 0

S/G pressures are STABLE at 725 PSIG S/G levels are decreasing and approaching 11 % NR NC Tjd are 490° F and STABLE 0

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

Natural Circulation flow (I) 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. I. 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 75

McGu ire Nuclear Station Question: 48 2013A MNSRONRCExamination (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 SIGs 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

2. exterior B. 1. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
2. exterior C. 1. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
2. interior D. 1. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
2. interior Page 48 of 75

McGu ire Nuclear Station Question:

  • 49 2013A MNSRONRCExamination (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-15, 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 75

McGu ire Nuclear Station Question:

  • 50 2013A MNSRONRCExamination (1 point)

Given the following conditions on Unit 1:

  • The 125VDC/12OVAC 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-1OAC (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 75

McGu ire Nuclear Station Question: 51 2013A MNS RO NRC Examination (1 point)

Given the following indications on Unit 1:

  • The Unit is operating at 100% RTP
  • 1AD8 / 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 75

McGu ire Nuclear Station Question: 52 2013A MNS RO NRC Examination (1 point)

Given the following conditions on Unit 1:

  • The unit is at 100% RTP
  • The air line for INV-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 1 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 75

McGu ire Nuclear Station Question: 53 2013A MNS RO 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.NI
2. the Steam Generators D. 1.ND
2. the Steam Generators Page 53 of 75

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

An ECA-1 .1 (LOSS OF EMERGENCY COOLANT RECIRC) major action requires further depressurization of SIGs 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. 1 and 4 ONLY B. 2 and 3 ONLY C. 2, 3, and 4 ONLY D. 1,2,and3ONLY Page 54 of 75

McGu ire Nuclear Station Question:

  • 55 2013A MNSRONRCExamination (1 point)

Given the following initial conditions on Unit 1:

  • The crew has implemented FR-H.1 (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-Hi:

The first source of feedwater which is prioritized for restoration is (1)

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 75

McGu ire Nuclear Station Question: 56 2013A MNSRONRCExamination (1 point)

Given the following conditions on Unit 1:

  • 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 Wind ings B. 1. RAISE button
2. Generator Armature Core End C. 1. LOWER button
2. Generator Field Wind ings D. 1. LOWER button
2. Generator Armature Core End Page 56 of 75

McGu ire Nuclear Station Question:

  • 57 2013A MNS RO 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
  • 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 75

McGu ire Nuclear Station Question: 58 2013A MNS RO 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 75

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

Given the following conditions on Unit 2:

  • 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 75

McGu ire Nuclear Station Question: 60 2013A MNS RO NRC Examination (1 point)

Given the following conditions on Unit 2:

  • The unit is operating at 100% RTP

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 75

McGu ire Nuclear Station Question:

  • 61 2013A MNSRONRCExamination (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 75

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

I EMF-48 ( Reactor Coolant Monitor) is located downstream of the Reactor Coolant (1) Sample Hx.

Related to its capability to identify a failed fuel event, 1 EMF-48 detects (2)

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

A. 1. Cold Leg

2. N16 gamma B. 1. Cold Leg
2. total gamma flux C. 1. HotLeg
2. N16 gamma D. 1. HotLeg
2. total gammaflux Page 62 of 75

McGu ire Nuclear Station Question:

  • 63 2013A MNS RO 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 75

McGu ire Nuclear Station Question: 64 2013A MNS RO 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-i.2:

The crew will FIRST attempt to establish an NC system cooldown using the (1)

The crew will cooldown (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. Condenser Dumps
2. at the maximum rate Page 64 of 75

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

Given the following conditions on Unit 1:

  • A Small-Break LOCA has occurred
  • Containment pressure is 1 .2 PSIG
  • NC system pressure is 400 PSIG
  • FR-P.1 (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.1 directs the operator to reset (I) and stop (2)

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

A. 1. 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. 1. Safety Injection AND the Sequencers
2. both NI pumps and all but one NV pump ONLY D. 1. Safety Injection ONLY
2. both NI pumps, both ND pumps and all but one NV pump Page 65 of 75

McGu ire Nuclear Station Question:

  • 66 2013A MNS RO 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 <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />.

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

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

D. MCB Annunciator IADIOIF-I (UPPER CONT AIRLOCK RX DOOR OPEN),

alarms.

Page 66 of 75

McGu ire Nuclear Station Question: 67 2013A MNS RO 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 1 ASP are not indicating correctly:
1. NC System Cold Leg Temperature
2. NC System Hot Leg Temperature
3. NC System WR Pressure
4. NC System Letdown Flow Which ONE (I) of the following indicates the parameters listed above that can be verified using redundant indications at the Safe Shutdown Facility (SSF)?

A. 1&3ONLY B. 2&3ONLY C. 1,3,&4 D. 2,3,&4 Page 67 of 75

McGu ire Nuclear Station Question: 68 2013A MNS RO 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, 5,6and No MODE
2. RED C. 1. 4, 5, 6, and No MODE ONLY
2. WHITE D. 1. 3, 4,5, 6 and No MODE
2. WHITE Page 68 of 75

McGu ire Nuclear Station Question:

  • 69 2013A MNS RO 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 (1) 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D. 1. 2735
2. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Page 69 of 75

McGuire Nuclear Station Question: 70 2013A MNSRONRCExamination (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 75

McGu ire Nuclear Station Question: 71 2013A MNS RO 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 I and 2 only

2. Performance of PT/O/A147001062 (Daily Surveillance of Reactor Building Entries)

B. 1. Modes 1 and 2 only

2. Ensure proper VE airlock door operation C. 1. Modes 1,2,3and4
2. Performance of PTIO/N4700/062 (Daily Surveillance of Reactor Building Entries)

D. 1. Modes 1,2,3and4

2. Ensure proper VE airlock door operation Page 71 of 75

McGu ire Nuclear Station Question:

  • 72 2013A MNS RO 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

2. notify their supervisor B. 1. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
2. notify their supervisor C. 1. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
2. obtain a dose extension D. 1. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
2. obtain a dose extension Page 72 of 75

McGu ire Nuclear Station Question: 73 2013A MNS RO 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 75

McGu ire Nuclear Station Question: 74 2013A MNSRONRCExamination (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
  • lA and 1B Jockey Pumps are OFF
  • A Main Fire Pump is running
  • B and C Main Fire Pumps are OFF (1) The automatic start setpoint for the A Main Fire Pump on decreasing fire header pressure is PS 1G.

(2) In accordance with OPII/A164001002A (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 75

McGu ire Nuclear Station Question:

  • 75 2013A MNSRONRCExamination (1 point)

Given the following conditions on Unit 1:

  • A BLACKOUT has occurred on 1 ETA
  • DIG IA failed to start due to an 86N relay actuation
  • Annunciator lAD-Il/ 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 2EMXA Page 75 of 75

Reference Listfor: 2013A MNS RO NRC Examination Steam Tables UI Data Book Enclosure 4.3, Fuel Maneuvering Limits Generic Enclosure 33 Generator Capability Curve Printed 12/3/2013 5:45:05 PM Page 1 of 1

Examination KEYfor: 2013A MNS RO 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 5:44:34 PM Page 1 of 3

Examination KEYfor: 2013A MNS RO 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 5:44:34 PM Page 2 of 3

Examination KEYfor: 2013A MNS RO 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 5:44:34 PM Page 3 of 3

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