ML18136A771

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301 Exam Report Items SRO as Given - Delay Release 2 Yrs
ML18136A771
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 05/16/2018
From:
Duke Energy Carolinas
To:
NRC/RGN-II
References
Download: ML18136A771 (27)
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Text

Question:

(1 point) 76 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following on Unit 2:

  • The 2A DG is started at 0800 for monthly surveillance (Fast Start)
  • 15 minutes after the 2A DG is started, the 2B NV pump trips on overcurrent
  • While the 2A DG is being unloaded, the diesel trips on Low Lube Oil pressure at 0900 due to a failure of the Engine Driven Lube Oil pump In accordance with Tech Spec 3.8.1, AC SOURCES - OPERATING,
1) the LATEST time that 2A NV pump shall be declared INOPERABLE is by
2) Surveillance SR 3.8.1.1 for offsite circuits shall be performed by.

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

A.

1. 1300
2. 0900 B.
1. 1300
2. 1000 C.
1. 1215
2. 0900 D.
1. 1215
2. 1000 Page 76 of 100

Question:

(1 point) 77 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following Unit 2 conditions:

  • The Unit is at 100% RTP
  • A loss of 2EKVD has occurred
  • The crew has entered AP/2/A/5500/015 (Loss of Vital or Aux Control Power)
  • NO Tech Spec actions have been addressed In accordance with Tech Spec 3.3.2 (ESFAS Instrumentation) LCO Actions, when the failed channel is removed from service, I&E will place the Containment Pressure Hi-Hi Bistable in (1).

In accordance with Tech Spec 3.3.2 (ESFAS Instrumentation) Bases, the Containment Pressure trip of Phase B Containment Isolation is energized to trip in order to minimize the potential of spurious trips that (2).

Which ONE of the following completes the statements above?

A. 1.

2.

Trip will cause Containment flooding concerns B. 1.

2.

Bypass may damage the RCPs C. 1.

2.

Trip may damage the RCPs D. 1.

2.

Bypass will cause Containment flooding concerns Page 77 of 100

Question:

(1 point) 78 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following sequence of events:

1400 - Crew implements E-0 (REACTOR TRIP OR SAFETY INJECTION) due to a main steam line break 1405 - The following indications are observed:

  • Feed flow to each S/G = 125 GPM
  • All S/G NR Levels = 0%
  • NC T-Colds = 535°F and lowering 1430 - Crew transitions to E-2 (FAULTED S/G ISOLATION) 1435 - Crew transitions to ECA-2.1 (UNCONTROLLED DEPRESSURIZATION OF ALL S/Gs) because all MSIVs are failed OPEN 1505 - The following indications are observed:
  • Feed flow to each S/G = 125 GPM
  • All S/G NR Levels = 0%
  • All S/G WR Levels = 20%
  • NC T-Colds = 410°F and lowering Based on the conditions above, and in accordance with ECA-2.1, the crew will throttle feed flow to a MAXIMUM flowrate of (1) GPM to each S/G.

A thermal shock concern due to restoring feed flow to the S/Gs following dry out (2) a reason for the action taken by the crew.

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

A.

1. 25
2. is B.
1. 25
2. is NOT C.
1. 100
2. is D.
1. 100
2. is NOT Page 78 of 100

Question:

(1 point) 79 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following conditions on Unit 1:

  • Unit is at 100% RTP
  • A Manual Fast Start of 1A D/G has been performed from the 1A D/G local control panel in accordance with PT/1/A/4350/002 A (DIESEL GENERATOR 1A OPERABILITY TEST)
  • Upon starting, the D/G reached 4160VAC at 10.5 seconds
  • The D/G was subsequently loaded as follows:

TIME ACTION 1408 Synchronized to 1ETA 1425 Load = 3600 KW 1456 Load = 3800 KW 1515 Load = 3600 KW 1520 Load = 1900 KW 1535 Separated from 1ETA Based on the indications above, the acceptance criteria of PT/1/A/4350/002 A for:

1) fast start time to reach required voltage met.
2) KW loading met.

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

A.

1) is
2) is B.
1) is
2) is NOT C.
1) is NOT
2) is D.
1) is NOT
2) is NOT Page 79 of 100

Question:

(1 point) 80 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

  • A continuous release of the Ventilation Unit Condensate Drain Tank (VUCDT) is in progress
  • After the release is initiated 1EMF 44 (Ventilation Unit Condensate Drain Tank) count rate indication fails to a reading of less than background Given the conditions above, the contents of the VUCDT (1) be released via a batch release in accordance with OP/1/A/6500/001 A (VUCDT OPERATION),.1 (PUMPING VUCDT TO RC DISCHARGE USING THE BATCH METHOD)

When 1EMF-44 is returned to FUNCTIONAL, the continuous discharge of the VUCDT in accordance with OP/1/A/6500/001 A, Enclosure 4.3 (PUMPING VUCDT TO RC DISCHARGE USING CONTINUOUS RELEASE METHOD) (2) require an updated Release Permit (LWR paperwork).

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

A.

1. may
2. will B.
1. may
2. will NOT C.
1. may NOT
2. will D.
1. may NOT
2. will NOT Page 80 of 100

Question:

(1 point) 81 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

  • A unit startup is in progress
  • Reactor power is 4%
  • The crew determines that Control Rod M-4 is misaligned by 14 steps In accordance with AP-14 (ROD CONTROL MALFUNCTION) Enclosure 1 (RESPONSE TO DROPPED OR MISALIGNED ROD),
1) when checking reactor power at step 12 of Enclosure 1, the crew will use.
2) based on current plant conditions, the crew will.

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

PROCEDURE LEGEND:

OP/1/A/6100/003 (CONTROLLING PROCEDURE FOR UNIT OPERATION)

A.

1. Thermal Power Best Estimate
2. remain in AP-14 and hold at current power level B.
1. Excore Nuclear Instruments
2. remain in AP-14 and hold at current power level C.
1. Thermal Power Best Estimate
2. transition to OP/1/A/6100/003 and shutdown to MODE 3 D.
1. Excore Nuclear Instruments
2. transition to OP/1/A/6100/003 and shutdown to MODE 3 Page 81 of 100

Question:

(1 point) 82 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following on Unit 2:

  • Fuel movement is in progress when 2EMF-3 (CONTAINMENT REFUELING BRIDGE) fails due to a loss of power to the EMF module
  • A fuel assembly is currently being moved using the Reactor Building Manipulator Crane Based on the conditions above, the Containment Evacuation alarm (1).

sound.

In accordance with SLC 16.7.6 (RADIATION MONITORING FOR PLANT OPERATIONS) Basis, fuel movement (2) continue long enough to place a suspended fuel assembly in a storage location.

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

A.

1. will
2. may NOT B.
1. will
2. may C.
1. will NOT
2. may NOT D.
1. will NOT
2. may Page 82 of 100

Question:

(1 point) 83 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following indications on Unit 2:

  • Unit is operating at 100% power

Instrumentation) for the Containment Area Radiation (High Range) Function (1) met.

Tech Spec 3.3.3 bases states that diversity and backup information for this function is provided by (2) or by sampling and analysis.

EMF Legend:

  • 2EMF-39 (Containment Gas  Low Range)

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

A.

1. are NOT
2. portable instrumentation B.
1. are
2. portable instrumentation C.
1. are NOT
2. 2EMF-38 and 2EMF-39 D.
1. are
2. 2EMF-38 and 2EMF-39 Page 83 of 100

Question:

(1 point) 84 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

  • Unit is at 30% RTP
  • NC pump 1C trips due to mis-operation during I&E testing
  • Five minutes after the 1C NCP trip, a lockout occurs on 1A Busline due to a fault
1) Which ONE (1) of the following describes the plant response?
2) For the conditions described above, which ONE (1) of the following is a subsequent action required and the basis for this action?

PROCEDURE LEGEND:

TECHNICAL SPECIFICATION 3.4.4 (RCS LOOPS MODES 1 & 2)

A.

1. An ATWS is in progress.
2. Manually trip the turbine to conserve SG inventory.

B.

1. An ATWS is in progress.
2. Manually trip the turbine to generate a redundant reactor trip signal.

C.

1. 1TA and 1TC auto-swap.
2. Restart 1C NC pump within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to comply with TS 3.4.4.

D.

1. 1TA and 1TC auto-swap.
2. Place the unit in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to comply with TS 3.4.4.

Page 84 of 100

Question:

(1 point) 85 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following on Unit 2:

  • The crew is performing ES-1.1 (SAFETY INJECTION TERMINATION) and has reached Step 31 to "determine required plant recovery procedure"
  • Seal cooling to the NC pumps has been maintained throughout the event
  • NC CET Subcooling = 40°F
  • RVLIS Upper Range level = 80%
  • PZR level = 30%

At Step 31 the crew will transition from ES-1.1 (1).

Based on the conditions above, after the crew implements ES-0.3, if offsite power is restored, the MINIMUM required PZR level to start an NCP (2) met.

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

PROCEDURE LEGEND:

ES-0.2 (NATURAL CIRCULATION COOLDOWN)

ES-0.3 (NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN THE VESSEL)

A.

1. to ES-0.2 and then to ES-0.3
2. is B.
1. directly to ES-0.3
2. is C.
1. to ES-0.2 and then to ES-0.3
2. is NOT D.
1. directly to ES-0.3
2. is NOT Page 85 of 100

Question:

(1 point) 86 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

  • Containment pressure peaked at 3.8 PSIG
  • The crew has implemented ES-1.3 (TRANSFER TO COLD LEG RECIRC) and are aligning NS for recirc
  • The following conditions exist:

o Containment pressure is currently 2.8 PSIG and stable o 1NI-185A (1A ND PUMP SUCTION FROM CONT SUMP ISOL) is OPEN o 1NS-20A (1A NS PUMP SUCTION FROM FWST ISOL) FAILED to CLOSE from the control room o SPDS indicates an Orange path on NC Integrity Based on the conditions above,

1) 1NS-18A (1A NS Pump Suction From Cont Sump Isol) be OPENED.
2) FR-P.1 (RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION) required to be implemented.

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

A.

1. can
2. is B.
1. can
2. is NOT C.
1. can NOT
2. is D.
1. can NOT
2. is NOT Page 86 of 100

Question:

(1 point) 87 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following sequence of events on Unit 2:

Initial conditions:

Time = 0800:

  • Unit 2 is at 100% RTP
  • "2A" Train KC pumps are running
  • "2B" Train KC pumps are secured
  • "2A" KC Surge Tank level is 3.5 feet and decreasing slowly
  • 2B KC Surge Tank level is 6.1 feet Time = 0810:
  • 2A KC Surge Tank level is 2.8 feet and decreasing slowly
  • 2B KC Surge Tank level is 6.1 feet
  • Crew implements AP-21 (LOSS OF KC OR KC SYSTEM LEAKAGE)
  • An AO is dispatched to initiate makeup to the Unit 2 KC Surge tank Based on the conditions above, at time 0810, annunciator 2AD10 / C-1 (KC SURGE TANK ABNORMAL LEVEL) (1) be LIT.

In accordance with AP-21, considering that the AO initiates KC Surge Tank makeup within the time critical time, the criteria to perform Enclosure 2 (ISOLATION OF KC NON-ESSENTIAL HEADERS) (2) be met prior to makeup initiation.

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

A.

1. will NOT
2. will B.
1. will NOT
2. will NOT C.
1. will
2. will D.
1. will
2. will NOT Page 87 of 100

Question:

(1 point) 88 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

  • The unit is at 100% RTP
  • Pressurizer Pressure Channel 2 has been removed from service for I&E repairs
  • All associated bistables have been tripped Subsequently,
  • A momentary spike causes the 1EKVA Supply breaker to trip Based on the conditions above, a (1) has/have occurred.

After the immediate actions of E-0 (REACTOR TRIP OR SAFETY INJECTION) are complete, concurrent implementation of AP-015 (LOSS OF VITAL OR AUX CONTROL POWER) (2) allowed in accordance with OMP 4-3 (Use Of Emergency And Abnormal Procedures And FLEX Support Guidelines).

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

A.

1. Reactor Trip ONLY
2. is B.
1. Reactor Trip ONLY
2. is NOT C.
1. Reactor Trip AND Safety Injection
2. is D.
1. Reactor Trip AND Safety Injection
2. is NOT Page 88 of 100

Question:

(1 point) 89 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following on Unit 2:

  • The reactor vessel head has just been removed in preparation for refueling
  • Both trains of ND are in service
  • The CV Equipment Hatch is closed
  • Both airlocks are OPEN to allow personnel and equipment access
  • NC system temperature is 120°F Subsequently, the following sequence of events occur:
  • 0900 -

o A complete loss of Nuclear Service Water (RN) occurs o Component Cooling Water (KC) temperature is increasing o Containment Closure is initiated

  • 0916  NC System Temperature is 200°F
  • 0917 - Upper Containment Airlock is closed
  • 0920 - Lower Containment Airlock is closed Based on the conditions above, in accordance with the Emergency Action Levels (EALs), the EARLIEST time that an Emergency Action Level threshold will be met is (1).

In accordance with the Emergency Action Levels (EALs) and excluding Emergency Coordinator Judgement, the classification for this is an (2).

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

REFERENCE PROVIDED A.

1. 0916
2. ALERT B.
1. 0916
2. UNUSUAL EVENT C.
1. 0922
2. ALERT D.
1. 0922
2. UNUSUAL EVENT Page 89 of 100

Question:

(1 point) 90 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following on Unit 2:

  • The unit is operating at 100% RTP
  • Rod control is in AUTOMATIC
  • DRPI indicates that rod M14 (adjacent to Power Range N-44) has dropped Based on the conditions above, over the next several hours QPTR will (1).

To comply with the requirements of Tech Spec 3.1.4 (ROD GROUP ALIGNMENT LIMITS), power must be reduced to less than a MAXIMUM of (2) within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

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

A.

1. increase
2. 75%

B.

1. increase
2. 50%

C.

1. decrease
2. 75%

D.

1. decrease
2. 50%

Page 90 of 100

Question:

(1 point) 91 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

  • The unit is in a refueling outage
  • Core unload is in progress
  • The Spent Fuel Pool Level Low computer alarm has actuated
  • Actual pool level is minus 2 feet and slowly DECREASING
  • 1EMF-17 (SPENT FUEL BLDG. REFUELING BRIDGE) and 1EMF-42 (FUEL BUILDING RADIATION MONITOR) are in the trip 1 condition
  • 1AD-13 / B-6 (INCORE INST ROOM SUMP HI LEVEL) is LIT Based on the conditions above,
1) operator actions to combat this event are located in.
2) the action the crew is required to take is to initiate makeup using.

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

PROCEDURE LEGEND:

AP-40 (LOSS OF REFUELING CAVITY LEVEL)

AP-41 (LOSS OF SPENT FUEL COOLING OR LEVEL) CASE II (LOSS OF SPENT FUEL LEVEL)

A.

1. AP-41, CASE II
2. the FW pump from the FWST B.
1. AP-41, CASE II
2. Demineralized Water C.
1. AP-40
2. the FW pump from the FWST D.
1. AP-40
2. Demineralized Water Page 91 of 100

Question:

(1 point) 92 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

  • The unit is at 100% RTP
  • 1EMF-24 has a Trip I alarm with the following indication:
  • The crew implements AP-10 (NC SYSTEM LEAKAGE WITHIN THE CAPACITY OF BOTH NV PUMPS) Case 1 (STEAM GENERATOR TUBE LEAKAGE)

In accordance with AP-10, Case 1,

1) the CRS will determine if the indication is valid by directing RP to frisk all Unit 1 and compare them to determine if any activity level is significantly higher.
2) if the indication is valid and the leak rate is subsequently determined to be 0.08 GPM, a power reduction to less than 50% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> required.

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

A.

1. Main Steam Lines
2. is B.
1. Main Steam Lines
2. is NOT C.
1. SG Cation Columns
2. is D.
1. SG Cation Columns
2. is NOT Page 92 of 100

Question:

(1 point) 93 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following on Unit 2:

  • The unit is at 100% RTP
  • At 1000, the U2 TB Rounds AO reports that there is a fire on the 2A DG Battery Charger Panel, the panel is charred, and all breakers on the battery charger have tripped
  • The Fire Brigade is dispatched and at 1020, the Fire Brigade Team Leader reports that the fire is out Per RP/0/A/5700/000 (CLASSIFICATION OF EMERGENCY), based on the conditions above, the Shift Manager must classify the event no later than (1).

In accordance with the Emergency Action Levels (EALs) and excluding Emergency Coordinator Judgement, the classification for this event is a/an (2).

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

REFERENCE PROVIDED A.

1. 1015
2. ALERT B.
1. 1030
2. ALERT C.
1. 1015
2. UNUSUAL EVENT D.
1. 1030
2. UNUSUAL EVENT Page 93 of 100

Question:

(1 point) 94 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following on Unit 2:

  • The unit is cooling down in MODE 4 in preparation for a Forced Outage
  • Engineering has requested access to the Containment Annulus area for an inspection MSD-585 (REACTOR BUILDING PERSONNEL ACCESS AND MATERIAL CONTROL), (1) state to "obtain WCC SRO permission prior to entry into the annulus".

MSD-585 (2). state "the buddy system is required for entry into the Annulus".

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

A.

1. does
2. does B.
1. does
2. does NOT C.
1. does NOT
2. does D.
1. does NOT
2. does NOT Page 94 of 100

Question:

(1 point) 95 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following on Unit 2:

  • The crew observes that 2EMF-38L (Containment Particulate Monitor) is in Trip 1 In accordance with Tech Spec 3.4.15 (RCS LEAKAGE DETECTION INSTRUMENTATION) Bases, which ONE (1) of the following is required by the LCO to be capable of identifying a 1 GPM Reactor Coolant system leak in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or less after leakage has reached the sumps?

A.

Volume Control Tank level B.

Incore Instrument sump level C.

2EMF-39 (Unit 2 Containment Gas Monitor)

D.

Containment Floor and Equipment (CFAE) sump level Page 95 of 100

Question:

(1 point) 96 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

  • Unit is at 100% RTP Subsequently:
  • Battery Charger EVCA DC output breaker has OPENED
  • In accordance with AP/1/A/5500/015 (Loss of Vital or Aux Control Power), the CRS is directing alignment of Battery Charger EVCS to EVDA in accordance with OP/0/A/6350/001 A (125 VDC/120 VAC VITAL INSTRUMENT AND CONTROL POWER SYSTEM)

OP/0/A/6350/001 A (1) require aligning the Unit 1 power supply to charger EVCS prior to aligning it to EVDA.

Once EVCS is aligned to EVDA, LCO 3.8.4 (DC sources  Operating) (2) met.

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

A.

1. does NOT
2. is B.
1. does
2. is C.
1. does NOT
2. is NOT D.
1. does
2. is NOT Page 96 of 100

Question:

(1 point) 97 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

  • Unit is at 100% RTP
  • 1EMF-33 (CONDENSER AIR EJECTOR EXHAUST) is in Trip 2 alarm
  • 1EMF-71 (S/G A LEAKAGE) is in Trip 2 alarm
  • Pressurizer level has been stabilized using AP-10 (NC LEAKAGE WITHIN THE CAPACITY OF BOTH NV PUMPS)
  • Letdown flow is 45 GPM
  • Charging flow is 78 GPM The MAXIMUM time that AP-10 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. 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />
2. NON-FUNCTIONAL B.
1. 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />
2. FUNCTIONAL C.
1. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
2. NON-FUNCTIONAL D.
1. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
2. FUNCTIONAL Page 97 of 100

Question:

(1 point) 98 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following plant conditions:

  • Unit 1 is in the process of making a radioactive gaseous waste release from the Waste Gas Decay Tank in accordance with OP/0/A/6200/519 (WASTE GAS DECAY TANK RELEASE)
  • Allowable Release Rate = 40 CFM
  • Recommended Release Rate = 31 CFM
  • 0EMF-50 (WASTE GAS DISCH) Trip 1 setpoint = 2.0E5 CPM
  • 1EMF-36 (UNIT VENT GAS) is INOPERABLE Time 0215 0245 Release Rate (CFM) 25 41 0EMF-50 (CPM) 2.2E5 3.2E5 Based on the conditions above and in accordance with OP/0/A/6200/519, RP Management approval (1) required to initiate the release.

The EARLIEST time that the operators are required to terminate the GWR paperwork (Release Permit) is (2).

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

A.

1. was
2. 0215 B.
1. was NOT
2. 0215 C.
1. was
2. 0245 D.
1. was NOT
2. 0245 Page 98 of 100

Question:

(1 point) 99 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

  • The unit was initially at 25% RTP with a power increase in progress
  • The unit experienced a complete loss of all onsite and offsite power
  • ECA-0.0 (LOSS OF ALL AC POWER) has been implemented
  • Operators have been dispatched to the SSF to place the Standby Makeup Pump in service
  • The crew has determined that a cooldown and depressurization of the NC system is required using the S/G PORVs
  • No power has been restored from onsite or offsite sources yet In accordance with the ECA-0.0 Background Document,
1) the basis for not allowing the S/Gs to depressurize to less than 190 PSIG is to prevent.
2) the MAXIMUM time the crew has to start the Standby Makeup Pump to prevent a postulated NC Pump Seal LOCA is.

A.

1. inadvertent criticality due to cooldown
2. 5 minutes B.
1. nitrogen injection from the CLAs
2. 5 minutes C.
1. inadvertent criticality due to cooldown
2. 10 minutes D.
1. nitrogen injection from the CLAs
2. 10 minutes Page 99 of 100

Question:

(1 point) 100 MNS ILT 18-1 SRO NRC Examination McGuire Nuclear Station In accordance with RP-012 (Activation of the Technical Support Center) and RP-029 (Notifications to Offsite Agencies from the Control Room):

1) if the TSC is officially activated and the control room becomes aware that conditions for an upgrade to a General Emergency are now met, the Shift Manager (1) declare the General Emergency.
2) if evacuation of areas outside the site boundary are required, the MINIMUM geographic RADIUS around the site that requires evacuation is (2).

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

A.

1. can
2. 5 miles B.
1. can
2. 2 miles C.
1. can NOT
2. 5 miles D.
1. can NOT
2. 2 miles Page 100 of 100

Examination KEY for:

MNS ILT 18-1 SRO NRC Examination Question Number Answer 76 B

77 B

78 A

79 B

80 A

81 C

82 B

83 B

84 A

85 C

86 D

87 D

88 C

89 A

90 A

91 C

92 D

93 A

94 A

95 D

96 B

97 A

98 D

99 D

100 D

Printed 4/30/2018 1:49:21 PM Page 4 of 4

Reference List for: MNS ILT 18-1 SRO NRC Examination EAL Wall Charts MCFD-2580-01.00, Steam Generator Blowdown Recycle System Steam Tables Tech Spec 3.3.3 (PAM Intrumentation)

Printed 4/2/2018 11:17:34 AM Page 1 of 1

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