ML17354B289

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05000280/2017301, 05000281/2017301 Final RO Written Exam - Delay Release 2 Yrs
ML17354B289
Person / Time
Site: Surry  Dominion icon.png
Issue date: 12/20/2017
From:
NRC/RGN-II
To:
References
50-280/17-301, 50-281/17-301
Download: ML17354B289 (83)
v • d • e


See also: IR 05000280/2017301

Text

SURRY 2017 NRC EXAM - RO

Question: 1

Given the following:

  • Control Bank D Rod H14 IRPI indicates 218 steps.
  • TAVG is 547 °F and stable.

Which ONE of the following completes the statements below?

1) One minute after the trip, shutdown margin is rising due to the decay of (1)_.

2) In accordance with 1 -ES-0. 1, Reactor Trip Response, Emergency Boration _(2)_ required.

A. 1) Iodine 2) is NOT

B. 1) Iodine 2) is

C. 1)Xenon 2)is

D. 1) Xenon 2) Is NOT

Page lof 75

SURRY 2017 NRC EXAM - RO

Question: 2

Given the following:

  • The team is in 1-ES-i .2, Post-LOCA Cooldown and Depressurization.
  • An RCS cooldown has been initiated by dumping steam.
  • All RCPs are running.
  • Pressurizer level is 40% and rising slowly.
  • Subcooling is 50°F and rising.

The Operator has just been directed to stop RCPs not requited for normal Pressurizer spray.

In accordance with 1-ES-I .2 which ONE of the following describes:

1) The optimum RCP configuration required for normal Pressurizer spray.

2) The reason for securing RCPs.

A. 1) 1-RC-P-1C

2) Minimize inventory loss from the RCS.

B. 1) i-RC-P-lAor 1-RC-P-iB.

2) Minimize heat input to the RCS

C. 1) i-RC-P-1C.

2) Minimize heat input to the RCS

D. 1) 1-RC-P-lAorl-RC-P-1B.

2) Minimize inventory loss from the RCS.

Page 2 of 75

SURRY 2017 NRC EXAM - RO

Question: 3

During a Large Break LOCA, the operator notes the following trends (from time 1 to time 6) of ICCM

Train A Subcooling margin monitor, and Core Exit Thermocouple indication (Train B shows similar

values):

Time (after start of Subcooling CETC

LBLOCA)

Time 1 (30 sec) 0°F 546°F

Time 2 (1 mm) -3°F 538°F

Time 3(2 mm) -33°F 372°F

Time 4 (3 mm) -35°F 360°F

Time 5(4 mm) -35°F 332°F

Time 6 (5 mm) -35°F 284°F

Which ONE of the following completes the statements:

1) Subcooling margin indications are based on the average of the

2) What is the significance of the subcooling margin monitor indications for Times 4, 5, and 6?

A. 1) 5 highest CETs

2) Subcooling margin monitor is at the bottom of its scale.

B. 1) 5 highest CETs

2) Unit conditions have stabilized.

C. 1) 25 compensated CETs

2) Subcooling margin monitor is at the bottom of its scale.

D. 1) 25 compensated CETs

2) Unit conditions have stabilized.

Page 3 0175

SURRY 2017 NRC EXAM - RD

Question: 4

Given the following:

  • Unit 1 reactor is operating at 30% power.
  • 1-RC-P-JA, A RCP, trips on ground overcurrent.

Which ONE of the following statements describes how the plant will respond and the reason a reactor

trip is necessary?

A. The reactor will immediately trip to avoid challenging DNB limits.

B. The Reactor will NOT immediately trip. It should be tripped to avoid challenging DNB limits.

C. The reactor will immediately trip to avoid challenging kW!ft limits.

D. The reactor will NOT immediately trip. It should be tripped to avoid challenging kW!ft limits.

Page 4 of 75

SURRY 2017 NRC EXAM - RO

Question: 5

Initial Conditions:

  • The RCS is solid.
  • RCS pressure is 300 psig.
  • RCS temperature of 150°F.
  • Cooldown in progress.
  • A RHR pump and the A RHR heat exchanger are in service.
  • 2-RC-P-1C, C RCP, running.
  • 2-CH-PCV-2145 is controlling pressure with 2-CH-FCV-2122, Charging Flow CNTRL, in

Manual.

Current Conditions:

  • A RHR pump trips

Based on the above conditions, which ONE of the following describes:

1) Initial response of RCS pressure?

2) What adjustment to 2-CH-PCV-2145, LTDN LINE PRESS CNTRL, controller demand will

maintain RCS pressure at 300 psig?

A. 1) Lowers.

2) Raise.

B. 1) Rises.

2) Lower.

C. 1) Lowers.

2) Lower.

D. 1) Rises.

2) Raise.

Page 5 of 75

SURRY 2017 NRC EXAM - RO

Question: 6

Initial Conditions:

  • A normal plant cooldown is in progress on Unit 1. The Unit is not yet on RHR.
  • CC Surge tank level indication is 60% and stable.
  • SFP level is 23.5 and stable.

Current Conditions:

  • 1-SW-RI-i 07B, CC/SW HX B, indicates EEEEE.
  • Annunciator VSP-D4, SPENT FUEL PIT HI LEVEL has been received.
  • CC Surge tank level indication is 36% and lowering.
  • Makeup to the CC surge tank is in progress.

Which ONE of the following identifies:

1) The source of the leak?

2) The source of water for maintaining CC System inventory?

A. 1) Spent Fuel Pit Heat Exchanger. 2) PG water.

B. 1) Spent Fuel Pit Heat Exchanger. 2) Condensate System.

C. 1) lB CC Heat Exchanger 2) PG Water.

D. 1) lB CC Heat Exchanger 2) Condensate System.

Page 6 of 75

SURRY 2017 NRC EXAM - RO

Question: 7

Unit 1 is at 100% power.

  • A Failure occurs in the Pressurizer pressure control

system.

  • All Pressurizer pressure controllers are in AUTO. 2500
  • The RO observes the Pressurizer pressure control

channels responding as shown: 2300

o 1-RC-Pl-1444 is rising. 2200

PSIG

o 1-RC-Pl-1445 is lowering.

2000

If these trends continue, which one of the following describes

1 900

the response of the Przr Pressure Control System?

1800 1800

1700 1700

A. Both PRZR spray valves are currently open and 1-

RC-PCV-1456 will OPEN.

PRZR PRESS CNTRL

1-RC-PI-1444 1.RC.PI.1445

CfL1 C.2

B. Both PRZR spray valves are currently open and 1-

RC-PCV-1455C will OPEN.

C. Only the Proportional Heaters turn FULL ON, both

PRZR spray valves CLOSE.

D. ALL Heaters turn ON, both PRZR spray valves

CLOSE.

Page 7 0175

SURRY 2017 NRC EXAM - RO

Question: 8

The Crew is responding to a SGTR in accordance with 1 -E-3, Steam Generator Tube Rupture.

The Rapid RCS cooldown has been completed.

Which ONE of the following describes:

1) The subcooling value for RCS depressurization termination.

2) The purpose for the RCS depressurization.

A. 1) 50°F.

2) Minimize break flow and refill the pressurizer.

B. 1) 50°F.

2) Minimize Reactor Vessel stress for PTS concerns.

C. 1) 30°F.

2) Minimize break flow and refill the pressurizer.

D. 1) 30°F.

2) Minimize Reactor Vessel stress for PTS concerns.

Page 8 of 75

SURRY 2017 NRC EXAM - RO

Question: 9

The Crew is restoring offsite power to Unit 1 in accordance with 0-AP-10.08, Station Power Restoration.

Which ONE of the following completes the statements?

1) Breaker 1 5D1, Transfer Bus D Supply breaker control switch is located on the _(1)____

2) At a minimum, the control switch for 15F1 must held in close for _(2)__ seconds.

A. 1) Bench Board 1-2

2) 15

B. 1) Bench Board 1-2

2) 5

C. 1) Liquid Waste Panel

2) 15

D. 1) Liquid Waste Panel.

2) 5

Page 9of75

SURRY 2017 NRC EXAM - RO

Question: 10

Given the following:

  • Unit 2 initially operating at 100% when a loss of offsite power occurred.
  • The Crew is currently in 2-ES-0.2, Natural Circulation Cooldown.

Which ONE of the following completes the statements below:

1) _(1)_ CRDM fans should be running.

2) The maximum cooldown rate of the RCS is limited to _(2) in the reactor vessel head.

A. 1)2

2) allow for potential void formation

B. 1)3

2) preclude void formation

C. 1)2

2) preclude void formation

D. 1)3

2) allow for potential void formation

Page 10 of 75

SURRY 2017 NRC EXAM - RO

Question: 11

Given the following:

  • Unit 1 is operating at 100%.
  • Local report finds the following AMBER lights lit on UPS 1A1:
  • Inverter output voltage low.
  • Alternate source voltage low.
  • Inverter to static switch fuse F204.
  • Alternate source to Static Switch fuse F205.

Which ONE of the following describes the status of Vital Bus I and IA?

Vital Bus I Vital Bus IA

A. De-energized De-energized

B. De-energized Energized

C. Energized De-energized

D. Energized Energized

Page 11 of 75

SURRY 2017 NRC EXAM - RO

Question: 12

Given the following conditions on Unit 1:

  • Actions of 1-ECA-0.0, Loss of All AC Power, are being performed.
  • Battery 1A and 1 B voltages are 118 VDC and slowly lowering.

Which one of the following completes the statements below?

1) In accordance with 1-ECA-0.0, when station batteries reach a minimum voltage of_(1)_VDC,

the voltage will begin to lower exponentially.

2) 4 KV Switchgear breakers without DC control power _(2)_ trip automatically if a Fault

condition occurs.

A. 1)110 2)wilI

B. 1)110 2) will not

C. 1)105 2)will

D. 1)105 2)willnot

Page 12 of 75

SURRY 2017 NRC EXAM - RO

Question: 13

Initial Condition

  • Unit I is operating at 100% power.
  • Unit 2 is in RSD with core off-load to the SEP complete 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> ago.

Current Condition

  • A tagging error results in isolation of SW flow to all CC HXs.
  • CC surge tank level is 55% and rising.
  • CC HX Disch Temp is 76°F and rising.

Which ONE of the following describes:

1) CC Surge Tank High Level alarm setpoint is (1).

2) The CC Surge Tank Vent Valve (2) automatically close on high level.

A. 1) 93%

2) will not

B. 1) 93%

2) will

C. 1) 70%

2) will not

D. 1) 70%

2) will

Page 13 of 75

SURRY 2017 NRC EXAM - RO

Question: 14

Given the following:

  • A major grid disturbance results in the loss of off-site power and the trip of both Units.
  • Due to multiple failures, the Unit 1 Crew has entered 1-ECA-0.0, Loss of All AC Power.

Which ONE of the following completes the statement below:

The Temporary Diesel Driven Air Compressor (1) require local action to align its discharge

to the Instrument Air System, and local action (2) be required to align Station Instrument Air

to the Containment Instrument Air System.

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 14 of 75

SURRY 2017 NRC EXAM - RO

Question: 15

Initial Conditions:

  • Unit 1 and Unit 2 are operating at 100%.
  • The plant has been notified by SOC that there are significant grid instabilities due to numerous

base load plants being out of service.

  • The SOC has requested maximum power generation from both units.

Current Conditions:

  • The SOC reports that the 500 Ky system is most impacted and the Emergency Low Limit for

that network has been reached.

  • The BOP reports the following Unit 1 changes (Note: Unit 2 parameters are comparable):

GEN MWe GEN Grid Freg Gen Amps Gen Volts Gen H2

MVARS Press

Initial 907 + 10 60 Hz 23,500 22.3 KV 75 psig

Current 1020 - 210 58.0 Hz 27,500 21.6 KV 75 psig

Which ONE of the following completes the statements below?

1) Based on the information given the Reactor _(1 )_ required to be tripped.

2) Which Emergency buses are most affected by the current conditions stated above?

(REFERENCE PROVIDED)

A. 1) is

2) Buses 1J and 2H.

B. 1) is not

2) Buses 1J and 2H.

C. 1) is not

2) Buses lHand2J.

D. 1) is

2) Buses 1H and 2J.

Page 15 of 75

SURRY 2017 NRC EXAM - RO

Question: 16

Given the following:

  • Operators have just transitioned to 1-ECA-1 .2, LOCA OUTSIDE CONTAINMENT.

Which ONE of the following parameters is used to determine if the break has been isolated, in

accordance with 1-ECA-1.2?

A. RVLIS level.

B. RCS subcooling.

C. PRZR level.

D. RCS pressure.

Page 16 of 75

SURRY 2017 NRC EXAM - RO

Question: 17

Given the following:

0900 Earthquake felt at Surry Power Station.

0905 Auto Reactor trip (both units) and Loss of offsite power.

0910 Unit 1 Auto Safety Injection occurs and following conditions noted:

RCS pressure is 1505 psig and lowering.

Containment pressure is 13.2 psia and rising.

RO reports that the B LHSI pump, 1-SI-P-i B has tripped on overcutrent.

0920 The crew has entered 1-E-1, Loss of Reactor or Secondary Coolant.

0925 The A LHSI pump trips on overcurrent.

0945 Current time.

Per 1-ECA-1.1, Loss of Emergency Coolant Recirculation, which ONE of the following identifies the

minimum SI flow rate needed for decay heat removal?

(REFERENCE PROVIDED)

A. 280 gpm

B. 310 gpm

C. 330 gpm

D. 380 gpm

Page 17 of 75

SURRY 2017 NRC EXAM - RO

Question: 18

Initial Conditions:

  • Unit 1 reactor operating at 100% power.
  • The reactor is tripped and safety injection actuated.
  • A steam leak is reported in Unit 1 Safeguards.

Current Conditions:

  • The Crew has entered ECA-2.1, Uncontrolled Depressurization of All Steam Generators.
  • All SG NR levels are off-scale low.
  • RCS Cooldown rate is 155°F/hour.

Which ONE of the following states:

1) What is the MINIMUM AFW flow (gpm) to each SG?

2) Will a transition to 1-FR-H.1 be required after AFW has been throttled?

A. 1)60

2) No

B. 1)100

2) No

C. 1)60

2) Yes

D. 1)100

2) Yes

Page 18 of 75

SURRY 2017 NRC EXAM - RO

Question: 19

Initial Conditions:

  • Reactor Power is 85% with a ramp to 100% in progress.
  • Rod control is in Auto.

Current Conditions:

  • A 100 gallon Alt. Dilute is in progress.
  • Control Bank D rods begin withdrawing at 8 steps per minute.

Which ONE of the following states the action taken by the RO in accordance with the Abnormal

Procedures?

A. Trip the reactor.

B. Place rod control in manual.

C. Stop the dilution.

D. Stoptheramp.

Page 19 of 75

SURRY 2017 NRC EXAM - RO

Question: 20

Unit 1 is operating at 100%, AND 1-AP-1 6.00, Excessive RCS Leakage, is in progress:

o JA-A3,N-16HIGH.

o 1A-B3,N-16ALERT

  • Letdown has been isolated.
  • Charging flow is 45 gpm and stable.
  • Pressurizer level is 53% and stable.

Which of the following completes the statements below concerning the tube leak on A SG?

In accordance with 1-AP-1 6.00, Excessive RCS Leakage, a reactor trip _(1) required. The

Appropriate AOP entry is _(2)_.

A. 1) is 2) 1-AP-24.01, Large SG Tube Leak

B. 1) is not 2) 1-AP-24.00, Minor SG Tube Leak

C. 1) is 2) 1-AP-24.00, Minor SG Tube Leak

D. 1) is not 2) 1-AP-24.01, Large SG Tube Leak

Page 20 of 75

SURRY 2017 NRC EXAM - RO

Question: 21

Given the following:

  • Fuel movement is in progress in the Fuel Building.
  • Fuel Handlers report an assembly has been dropped and appears to be damaged.
  • 1-RM-Rl-153, FUEL PIT BRIDGE, HIGH Alarm is received.
  • The Crew has initiated 0-AP-22.00, Fuel Handling Abnormal Conditions.

Which ONE of the following identifies:

1) The MCR must be ISOLATED within (1) minutes.

2) The release is monitored using (2)

A. 1)2

2) 1-VG-Rl-104, Vent Vent 1 Gas

B. 1)2

2) 1-VG-Rl-131 NB/C, Vent #2 Gas/Particulate

C. 1)60

2) 1-VG-Rl-104, Vent Vent 1 Gas

D. 1)60

2) 1-VG-Rl-131 NB/C, Vent #2 Gas/Particulate

Page 21 of75

SURRY 2017 NRC EXAM RO

Question: 22

Given the following:

  • MCR Evacuation is in progress lAW O-FCA-1 .00, LIMITING MCR FIRE, due to a fire in the

MCR.

  • All Control room actions have been completed on both units.
  • Operators have been dispatched to perlorm 0FCA-1 1 .00, Remote Monitoring.

Which ONE of the following completes the statement below:

Charging Line flow is monitored at the (1), and Neutron flux is monitored at the _(2)_.

A. 1) Auxiliary Shutdown Panel 2) Auxiliary Shutdown Panel

B. 1) Remote Monitoring Panel 2) Remote Monitoring Panel

C. 1) Auxiliary Shutdown Panel 2) Remote Monitoring Panel

D. 1) Remote Monitoring Panel 2) Auxiliary Shutdown Panel

Page 22 of 75

SURRY 2017 NRC EXAM - RO

Question: 23

Unit conditions are as follows:

  • RCS pressure 650 psig.
  • Containment pressure is 38 psia and slowly lowering.
  • RCPs have been secured.
  • RVLIS Full Range level is 44% and lowering slowly.
  • CETC Temperature is 745°F and rising slowly.
  • The Crew has entered FR-C.1, Response to Inadequate Core Cooling.
  • The Crew has reached Step 14, DEPRESSURIZE ALL INTACT SGs TO 200 PSIG.

Which ONE of the following identifies:

1) The component(s) used to depressurize the Intact SGs.

2) The purpose for the depressurization.

A. 1) Steam Dumps.

2) Reduce secondary to primary DIP across the SG tubesheet.

B. 1) Steam Dumps.

2) Reduce RCS pressure to allow SI Accumulator and LSI pump injection.

C. 1) SGPORVs.

2) Reduce RCS pressure to allow SI Accumulator and LSI pump injection.

D. 1) SGPORVs.

2) Reduce secondary to primary D/P across the SG tubesheet.

Page 23 of 75

SURRY 2017 NRC EXAM - RO

Question: 24

Given the following:

  • Unit 1 is operating at 100% power.
  • The reactor is tripped and SI actuated.
  • Containment pressure is 25 psia and rising slowly.

Which ONE of the following completes the statement:

1-RM-TV-100C, CTMT ATMOS RM INLET I/S TV, closes on a (1) containment isolation

signal, and is checked in the required position using (2) of 1-E-0, Reactor Trip or Safety

Injection.

A. 1) Phase I

2) Attachment 1, System Alignment Verification

B. 1) Phase I

2) Attachment 4, CLS Component Verification

C. 1) Phase II

2) Attachment 4, CLS Component Verification

D. 1) Phase II

2) Attachment 1, System Alignment Verification

Page 24 of 75

SURRY 2017 NRC EXAM - RO

Question: 25

Initial Conditions:

  • Unit 2 has been tripped and safety injection actuated.
  • At Step 6 of 2-E-0, Reactor Trip or Safety Injection, RCS Subcooling is 20°F and lowering.
  • Containment pressure is 19 psia and is slowly rising.
  • PRZR level is offscale low.
  • The Crew has entered 2-ES-i .2, Post LOCA Cooldown and Depressurization.

Current Conditions:

  • The Crew has reached Step 14 DEPRESSURIZE RCS TO REFILL PRZR.

Which ONE of the following completes the statement below:

The RCS is depressurized using (1), until a MINIMUM (2) is reached.

A. 1) one PRZR PORV

2) Subcooling value

B. 1) normal PRZR Spray

2) Subcooling value

C. 1) One PRZRPORV

2) PRZR level

D. 1) normal PRZR Spray

2) PRZR level

Page 25 of 75

_____?

SURRY 2017 NRC EXAM - RO

Question: 26

Initial Conditions:

  • Unit 1 was at 100% power when Main Steamline breaks occurred on B and C SGs.
  • B and C SG wide-range levels are now 0%.
  • RCS Hot Leg temperatures are rising.

Current Conditions:

  • SI has been terminated per 1-FR-P.1, Response to Imminent Pressurized Thermal Shock

Condition.

  • 1-FR-P.1 directs controlling feed flow and dumping steam to stabilize RCS Hot Leg

temperatures.

Which ONE of the following completes the statement:

The basis for stabilizing RCS Hot Leg Temperature is to prevent

A. loss of RCS subcooling

B. RCS repressurization

C. tube failure in the Faulted SGs

D. voiding in the reactor vessel head

Page 26 of75

SURRY 2017 NRC EXAM - RO

Question: 27

Unit 1 is on Cold Leg Recirculation following a LOCA.

  • Containment pressure is 22 psia and slowly lowering.
  • Containment sump is 10 feet and slowly rising.
  • The crew is performing 1-FR-Z.2, Response to Containment Flooding, and Chemistry is

sampling the Containment sump.

In accordance with 1-FR-Z.2, Response to Containment Flooding which ONE of the following

describes:

1) Containment sump is sampled for _(1 )_ prior to release from containment.

2) What actions should be taken if this containment function is not restored upon completion of the

procedure?

A. 1) Activity

2) Exit 1-FR-Z.2, and return to procedure and step in effect.

B. 1) Activity

2) Re-perform actions of 1-FR-Z.2 until the containment function is satisfied.

C. 1) Total Dissolved Solids

2) Re-perform actions of 1-FR-Z.2 until the containment function is satisfied.

D. 1) Total Dissolved Solids

2) Exit 1-FR-Z.2, and return to procedure and step in effect.

Page 27 of 75

SURRY 2017 NRC EXAM - RO

Question: 28

Given the following:

  • Unit 1 is operating at 29% power.
  • 1-RC-P-1A breaker spuriously trips open on overcurrent.

With no operator actions which of the following describes:

1) How Loop A Tavg will change as compared to previous Tave Loop A.

2) The reason for the Loop A Tavg change?

A. 1) Lower 2) due to no forced flow in the loop A.

B. 1)Lower 2) due to reverse flow in the loop A.

C. 1) Higher 2) due to reverse flow in the loop A.

D. 1)Higher 2) due to no forced flow in the loop A.

Page 28 of 75

SURRY 2017 NRC EXAM - RO

Question: 29

Unit 1 is operating at 100%, Letdown flow orifice configuration is being changed, when the following

sequence of events occur:

  • 1-CH-HCV-1200C, LETDOWN ORIFICE ISOL valve is opened.
  • Annunciator 1 D-F4, LO PRESS LETDOWN LINE HI FLOW, alarms, and remains LIT when

acknowledged.

  • 1-CH-HCV-1200B, LETDOWN ORIFICE ISOL valve is closed.

Which ONE of the following states:

1) The Maximum Letdown flow limit been exceeded.

2) The limit is based on the Bed Ion Exchanger.

A. 1) has

2) Cation

B. 1) has

2) Mixed

C. 1) has not

2) Cation

D. 1)has not

2) Mixed

Page 29 of 75

SURRY 2017 NRC EXAM - RO

Question: 30

Given the following:

  • Unit 1 is operating at 100%.
  • A failure occurs causing Letdown temperature 1-CH-Tl-1143 to rise rapidly to 114 °F and rising.
  • 1-CH-TCV-1 143 is in AUTO.

With no operator action, which of the following completes the statement below?

1-CH-TCV-1143, Letdown Divert Control valve will divert to the _(1)_, as soon as Letdown

temperature exceeds _(2)_.

A. 1) Volume Control Tank 2)130°F

B. 1) Primary Drain Tank 2)130 °F

C. 1) Primary Drain Tank 2)145°F

D. 1) Volume Control Tank 2)145°F

Page 30 of 75

SURRY 2017 NRC EXAM - RO

Question: 31

Initial Conditions:

  • Unit us in CSD with the PRZR solid.
  • 1 -RC-P-1 C, C RCP running for crud burst cleanup.
  • RCS temperature is 158 °F and lowering.
  • RCS pressure is 305 psig.
  • Station Instrument Air is supplying containment, the CMT IA compressors are in OFF.

Current Conditions:

  • Unit 1 Instrument Air header ruptures.

Which ONE of the following completes the statements below:

1) RCS pressure will (1).

2) Procedure (2) is used to mitigate the effects of this transient.

A. 1)rise

2) 1-AP-27.00, Loss of Decay Heat Removal Capability

B. 1)lower

2) 1-AP-27.00, Loss of Decay Heat Removal Capability

C. 1)rise

2) 0-AP-40.00, Non-Recoverable Loss of Instrument Air

D. 1)lower

2) 0-AP-40.00, Non-Recoverable Loss of Instrument Air

Page 31 of 75

SURRY 2017 NRC EXAM - RO

Question: 32

Given the following:

  • Large Break LOCA has occurred on Unit 1 and the crew is presently performing 1-ES-i .3,

Transfer to Cold Leg Recirculation.

  • RWST level is 14% and lowering slowly.

Which of the following completes the following statements.

1) Automatic swapover to RMT will occur as soon as RWST level transmitters are less than

_(1 )_.

2) During phase 1 of RMT one of the automatic actions the RO should observe is the (2)

to

stroking from CLOSE OPEN.

A. i) 13.5%

2) LHSI suction from SUMP MOVs, i-Sl-MOV-1860A and B

B. 1) 13.0%

2) LHSI suction from SUMP MOV5, 1-Sl-MOV-1860A and B

C. 1) 13.5%

2) LHSI discharge to HHSI MOVs, 1-Sl-MOV-1863A and B

D. 1) 13.0%

2) LHSI discharge to HHSI MOVs, i-Sl-MOV-i863A and B

Page 32 of 75

SURRY 2017 NRC EXAM - RO

Question: 33

The Unit is operating at 100% power when a reactor trip and safety injection occur.

Which ONE of the following completes the statement below?

Following safety injection actuation, RCP seal return is directed to the (1), through a relief

valve set at (2) psig.

A. 1)PDT

2)75

B. 1)PDT

2)150

C. 1)PRT

2)75

D. 1)PRT

2)150

Page 33 of 75

SURRY 2017 NRC EXAM - RD

Question: 34

Which ONE of the following describes the operation of the Component Cooling Water Service Water

Supply MOVs, 1-SW-MOV-102 A and B?

1) Close on a Unit 1 HI-HI CLs in coincidence with a loss of RSST (1).

2) After a MINIMUM time delay of (2) minutes, the valves may be reopened from the

MCR.

A. 1) A&C

2) 5

B. 1) A&C

2) 2

C. 1) B&C

2) 5

D. 1) B&C

2) 2

Page 34 of 75

SURRY 2017 NRC EXAM RO

Question: 35

Initial Conditions:

  • Unit 1 is operating at 100% Power.
  • PRZR Heater Group C and D are in ON.
  • PRZR Heater Group A, B, and E are in AUTO.
  • Loss of off-site power occurs.

Current Conditions:

  • The Crew is performing actions in accordance with 1-ES-0.1, Reactor Trip Response, and 1-AP-

10.07, Loss of Unit 1 Power.

  • RCS Pressure is 2000 psig and lowering slowly.

Which ONE of the following describes the 1A Pressurizer Heater Group operation?

A. Will have power available, NO actions are required to energize them.

B. Will have power available AND manual actions are required to energize them.

C. Will NOT have power available. Manual actions are required to align power to them but NO

other actions are required to energize them.

D. Will NOT have power available. Manual actions are required to align power to them AND

manual actions are required to energize them.

Page 35 of75

SURRY 2017 NRC EXAM - RO

Question: 36

Given the following:

  • Reactorpoweris 100%.
  • Pressurizer Pressure control is in automatic.
  • An internal fault causes 1-RC-PC-1444J to fail as shown.

Which ONE of the following describes the immediate response of

the Pressure Control System.

A. Power operated relief valve 1-RC-PCV-1455C opens,

spray valves open, pressurizer heaters de-energize.

B. Power operated relief valve 1-RC-PCV-1456 opens, spray

valves open, pressurizer heaters de-energize.

C. Spray valves open, pressurizer heaters de-energize.

D. Spray valves close, pressurizer heaters energize.

PRZR PRESS

MASTER CNTRL

Page 36 of 75

SURRY 2017 NRC EXAM - RO

Question: 37

Initial Conditions:

5% Power, with reactor trip breaker status as shown:

..

CTOR T

RO R

ACTON TR

(R mu

CONTROL ROD SOUDSERTE

..

POWER SUPPLY ROD CONTROL

0*

RE BYPASS RE BYPASS

SER BYA BKR BYE

Current conditions:

  • The A DC bus loses power/de-energizes.

Based on the current conditions, which one of the following is the automatic response of the Reactor

Protection System?

A Reactor Trip Breaker B Reactor Trip Bypass Breaker

A. OPEN CLOSED

B. CLOSED OPEN

C. CLOSED CLOSED

D. OPEN OPEN

Page 37 of 75

SURRY 2017 NRC EXAM - RD

Question: 38

Given the following:

  • Unit 1 is operating at 100% power.
  • RWST Level Transmitter 1-CS-LT-100B

has failed as shown.

o lA-AZ, RWST LO LVL.

o 1A-B2, RMT CH2 TRIP/BYPASS.

o 1 B-F4, RWST LVL RS PP START

INTLK CH2.

The channel HAS NOT been placed in TRIP or RST LEVEL RWStLEVL RhStLE. 1TLE1EL

1-CS-U-IDEA 1-CS.U-lDEfl 1-CS.lJ1O 1-CSU-ID8D

BYPASS at this time.

If another RWST Level Transmitter channel fails LOW, before action has been taken for the first

RWST Level Transmitter failure, Recirc Spray pumps _(1)_ start, and Recirc Mode Transfer

(RMT) _(2)_ occur.

Recirc Spray RMT

A. will NOT will NOT

B. will NOT will

C. will will

D. will will NOT

Page 38 of 75

SURRY 2017 NRC EXAM - RO

Question: 39

Given the following:

  • Unit 1 operating at 100% power, Unit 2 is in HSD preparing for reactor startup.
  • Unit 1 Containment is on Chilled CC; 1-CD-REF-lA, York 400 ton Chiller, is in service.
  • Upon entering 1-ES-0.1, Reactor Trip Response, the RO notes that Load Shed has failed to

actuate.

  • The SOP initiates 0-AP-10.10, Loss of Auto Load Shed.

Which ONE of the following describes:

1) The location of 1-CD-REF-lA, York 400 Ton Chiller, breaker control switch.

2) The major components affected if 1-CD-REF-lA breaker is jammed closed and the Bus

must be de-energized to secure the Chiller?

A. 1) Control Panel on the Turbine Building Mezzanine.

2) B RCP and B MFP.

B. 1) Control Panel on the Turbine Building Mezzanine.

2) A RCP and A MFP.

C. 1) Breaker cubicle in the Normal Switchgear Room.

2) B RCP and B MFP.

D. 1) Breaker cubicle in the Normal Switchgear Room.

2) A RCP and A MFP.

Page 39 of 75

_____

SURRY 2017 NRC EXAM - RO

Question: 40

Initial Conditions:

  • Unit 1 was operating at 100%.

o 1K-A7, BATT SYSTEM 1ATROUBLE.

o 1 K-A8, UPS SYSTEM 1A TROUBLE.

o 1K-G7, 480 EMERG BUS MCC BKR TRIP.

o VSP-E8, CVCS HT TRACE TRBL.

  • Multiple loads are lost on Unit 1.

Current Conditions (1 mm later):

  • The RO reports the following Ventilation Fans have lost power:

o 1-VS-F-40A, Safeguard Exh Fan.

o 1-VS-F-60A, CRDM FAN.

o 1-VS-F-60F, CRDM FAN.

  • CRDM FAN 1-VS-F-60E is the only CRDM Fan running.

Which ONE of the following completes the statement below.

1) Which procedure should be entered to address aM the conditions listed above?

2) The standby CRDM Fans automatically start.

A. 1) 1-AP-10.07, Loss of Unit 1 Power.

2) will

B. 1) 1-AP-1 0.07, Loss of Unit 1 Power.

2) will NOT

C. 1) 1-AP-25.00, Loss of Containment Air Cooling.

2) will

D. 1) 1-AP-25.00, Loss of Containment Air Cooling.

2) will NOT

Page 40 of 75

SURRY 2017 NRC EXAM - RU

Question: 41

Initial Conditions:

  • Unit 1 operating at 65%, ramping up to full power.
  • A Large Break LOCA occurs.

Current Conditions: (3 minutes later)

  • Containment pressure peaks at 42 psia and is slowly lowering.

Which ONE of the following states the power source to the CS pumps?

1-CS-P-lA 1-CS-P-lB

A. Offsite power Offsite power

B. Offsite power #3 EDG

C. #1 EDG Offsite power

D. #1 EDG #3 EDG

Page 41 of 75

SURRY 2017 NRC EXAM - RO

Question: 42

Given the following:

. Unit 1 Turbine Control is in IMP IN.

. Control rods are in MANUAL.

. The following parameters are given:

Rx. Pwr Delta T Tave I ref. Gen MWe

89% 90% 569.7 569.7 784

. 1-MS-SOV-104, MSR Steam Supply fails CLOSED.

With no operator action which ONE of the following parameters would be higher when steady-state

conditions are reached?

A. Reactor Power.

B. Generator MWe.

C. Tref.

D. Tave.

Page 42 of 75

SURRY 2017 NRC EXAM - RO

Question: 43

Unit 1 reactor power is 100%, when a spurious reactor trip occurs.

Which ONE of the following completes the following statement.

The P-4 signal is generated by a direct input from the _(l)_ breakers being open, and the

MFRVs wW cose when (2).

A. 1) Generator output 2) 2/3 RCS Loop Tave <543°F

B. 1) Generator output 2) Median Tave < 554°F

C. 1) Reactor trip 2) Median Tave < 554°F

D. 1) Reactor trip 2) 2/3 RCS Loop Tave < 543° F

Page 43 of 75

SURRY 2017 NRC EXAM - RO

Question: 44

Initial Conditions at 0800:

  • Unit 1 at 50% power.
  • 1-FW-P-1B, Main Feedwater pump is running, 1-FW-P-1A is secured.
  • 1-FW-P-1B, Main Feedwater Pump discharge valve inadvertently closes.
  • 1-FW-P-1B, Main Feedwater Pump Recirc valve fails to open.

Current Conditions at 0805:

  • A S!G NR level = 23% and lowering.
  • B S/G NR level = 19% and lowering.
  • C SIG NR level = 15% and lowering.

Which ONE of the following completes the following statement:

Based on the above plant conditions, at 0801 _(1 )_ pump(s) will be running, and at 0805 _(2)_

pump(s) will be running.

A. 1) 1-FW-P-2, TDAFW

2) 1-FW-P-2, 1-FW-P-3A, AND 1-FW-P-3B

B. 1) 1-FW-P-3A, AND 1-FW-P-3B MDAFW

2) 1-FW-P-3A, AND 1-FW-P-3B MDAFW

C. 1) 1-FW-P-2, TDAFW

2) 1-FW-P-2, TDAFW

D. 1) 1-FW-P-3A, AND 1-FW-P-3B MDAFW

2) 1-FW-P-2, 1-FW-P-3A, AND 1-FW-P-3B

Page 44 of 75

SURRY 2017 NRC EXAM - RO

Question: 45

Initial Conditions:

  • Unit 1 tripped from 100% due to a Generator Trip.
  • Following the Trip the IJ bus locked out.
  • NLO dispatched AND completed AFW] Header isolation in accordance with ES-0.1.
  • AFW initially throttled to 200 gpm!S/G.

Current Conditions:

  • SIG A, B, and C all read 12% NR and slowly rising.

Which of the following completes the statements below.

1) Per ES-0.1, Reactor Trip response the AFW header isolation was done by closing _(1)_

header isolation valve(s).

2) With current conditions, as the AFW MOVs are throttled to control SIG level, AEW pump

discharge pressure will _(2)_.

A. 1)one 2) lower

B. 1)three 2) rise

C. 1)three 2) lower

D. 1) one 2) rise

Page 45 of 75

SURRY 2017 NRC EXAM - RO

Question: 46

In accordance with J-AP-21 .01, Response to AFW Check Valve Backleakage, which ONE of the

following completes the statements below?

An AFW pump is considered vapor bound if casing temperature exceeds 1). If J, AFW

Pumps are vapor bound, 2)_ AFW pump(s) should be cooled FIRST.

A. 1)200°F

2) Motor Driven

B. 1)200°F

2) Turbine Driven

C. 1) 165°F

2) Motor Driven

D. 1) 165°F

2) Turbine Driven

Page 46 of 75

SURRY 2017 NRC EXAM - RO

Question: 47

Given the following:

  • 1-RH-P-lA, RHR pump A is operating during a plant cooldown.
  • The DC control power breaker supplying RHR Pump A trips.

Which ONE of the following complete the statements below:

1) Main Control Board red/green running indication will be _(1 )_.

2) If 1-RH-P-lA were tripped locally, then the pump (2) be restarted locally by pulling the

breaker MANUAL CLOSE lever.

A. 1) lost 2) could

B. 1) available 2) could not

C. 1) available 2) could

D. 2) lost 2) could not

Page 47 of 75

SURRY 2017 NRC EXAM - RO

Question: 48

Unit 1 and 2 are operating at 100% power when a Loss of Off-Site Power (LOOP) occurs.

  • #3 EDG is tagged out for a major maintenance package.
  • #1 EDG developed an oil leak and was tripped.
  • The AAC Diesel has been aligned to one Emergency Bus.

Which ONE of the following identifies the Station Battery bus, or busses, with a continuously lowering

DC voltage?

UNIT I UNIT 2

Battery Battery

Bus Bus

A. A B

B. B B

C. B A

D. A A

Page 48 of 75

SURRY 2017 NRC EXAM - RO

Question: 49

Given the following:

  • Unit 2 is operating at 100% power.
  • 2B DC bus inadvertently de-energized.

Which ONE of the following completes the statement:

The turbine is tripped (1), and the generator output breakers (2) open automatically.

A. 1) manually 2) will

B. 1) manually 2) will not

C. 1) automatically 2) will

D. 1) automatically 2) will not

Page 49 0175

SURRY 2017 NRC EXAM - RO

Question: 50

Initial Conditions:

  • The crew is in 1-E-1, Loss of Reactor or Secondary Coolant, at Step 6.
  • RCS pressure is 115 psig and lowering.
  • Containment pressure is 30 psia and rising.
  • RWST level is 50% and lowering.

Current Conditions:

  • Breaker 1 5H8, Normal supply to 1 H 41 60v bus tripped (10 sec. ago) and breaker 1 5H3, #1 EDG

output breaker closed.

Which of the following describes:

1) The first load that will be sequenced onto #1 EDG.

2) The maximum continuous running electrical load allowed for #1 EDG.

A. 1) 1-VS-F-58A, Filtered Exhaust Fan

2) 2600 KW.

B. 1) 1-RS-P-2A, Outside Recirc Spray pump.

2) 2750 KW.

C. 1) 1-RS-P-2A, Outside Recirc Spray pump.

2) 2600 KW.

D. 1) 1-VS-F-58A, Filtered Exhaust Fan

2) 2750 KW.

Page 50 of 75

SURRY 2017 NRC EXAM - RO

Question: 51

Given the following:

  • Both Units are operating at 100%.
  • Normal Ventilation lineup.
  • Annunciator 0-RM-L4, VENT VENT 1 GAS ALERT/FAILURE has just alarmed.
  • Indications for 1-VG-Rl-104 are as shown below.

1.OOEJ

Which ONE of the following describes:

1) The effluent release path that is monitored by this radiation monitor _(1)_ be automatically

isolated.

2) What type of detector failure could cause the indications shown?

A. 1) will

2) No pulses provided by the detector for five minutes.

B. 1) will

2) Large rise in pulses causing detector saturation.

C. 1) willnot

2) Large rise in pulses causing detector saturation.

D. 1) willnot

2) No pulses provided by the detector for five minutes.

Page 51 of 75

SURRY 2017 NRC EXAM - RO

Question: 52

Initial Conditions:

  • A Stop Log is installed in the IA Screenwell.

Current Conditions:

  • The IC Screenwell is 90% fouled/blocked by Hydroids.

Based on current conditions, which ONE of the following will indicate a rise in temierature?

A. Main Control Room Chillers.

B. Charging Pump Lubricating Oil.

C. Bearing Cooling Water cooled components.

D. Component Cooling Water cooled components.

Page 52 of75

SURRY 2017 NRC EXAM - RO

Question: 53

Initial Conditions:

  • 1-SW-P-bA, CHG Pump SW Pump, is running in HAND
  • 1-SW-P-lOB, CHG Pump SW Pump is in AUTO and OFF.
  • 1 D-G5, SW or CC PPS DISCH TO CHG PPS LO PRESS has just alarmed.

Current Conditions (2 minutes later):

  • 1-SW-P-bA, CHG Pump SW Pump, continues running in HAND.
  • 1-SW-P-i GB, CHG Pump SW Pump is in AUTO and OFF.
  • The Service Building Inside Operator reports the following readings:

Parameter Previous Current Log spec

1-SW-DPI-i OOA, 1-VS-S-lA, SW Strainer D/P 0.8 psid 0.8 psid Max: 1.5 psid

1-SW-DPI-27, 1-SW-S-2A, SW Suct. Strainer D/P 0.2 psid 1.8 psid Max: 1.5 psid

i-SW-Pl-140A, 1-SW-P-i GA, Suction press 3.8 psig 0.8 psig Mm: -5 psig

i-SW-Pl-26, 1-SW-P-bA, discharge pressure 27.5 psig 6 psig Mm: 15 psig

Which of the following describes the actions the operator must take per 0-AP-12.00, Service Water

System Abnormal Conditions?

A. Start i-SW-P-i GB, place duplex strainer 1-SW-S-la in service, and open 1-SW-263 Suction

Cross-tie.

B. Place i-SW-S-2A, suction strainer standby basket in service, and vent 1-SW-P-i GA.

C. Start 1-SW-P-i GB, stop and vent 1-SW-P-bA, place 1-SW-S-2A, suction strainer standby

basket in service.

D. Place additional SW header in service, vent all three SW headers, vent 1-SW-P-i GA Chg SW

pump.

Page 53 of 75

SURRY 2017 NRC EXAM - RO

Question: 54

Which ONE of the following states the power source for Station Instrument Air Compressor, 2-IA-C-i?

A. 480V Bus 2C3.

B. 480VBus2A2.

C. 480V Bus 2H1-i.

D. 480V Bus 2J1-i.

Page 54 of 75

SURRY 2017 NRC EXAM - RO

Question: 55

Initial Conditions:

  • Unit 2 was operating at 100%.

Current Conditions (1 minute later)

  • RCS pressure is 10 psig and lowering.
  • Containment Pressure is 45.0 psia and slowly rising.
  • RWST level is 95% and lowering.

o 2K-F4, 4KV EMERG BUS NOR SUP AUTO TRIP.

o 2K-G4, 4KV EMERG BUS EMERG SUP BKR AUTO TRIP.

o 2K-Hi, BUS2H UNDERVOLT.

  • The RO reports that EDG #2 is running but has failed to close in to supply Bus 2H.

Which of the following describes:

1) How many Containment Air Recirculation Fans are operating at this time.

2) With the current complement of ESF equipment how long will it take to reduce containment

pressure to subatmospheric?

A. 1) One. 2)4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

B. 1) Two. 2) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

C. i) One. 2) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

D. i) Two. 2) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Page 55 of 75

SURRY 2017 NRC EXAM - RO

Question: 56

Given the following:

  • Unit 1 is operating at 100% power.
  • Rod Control is in AUTO.
  • NLO reports the Urgent Failure light is lit on Power Cabinet lAG.
  • NLO reports normal indications for all other Power and Logic Cabinets.

Which of the following describes the effect of this on movement of Bank D rods?

A. Bank D rods can be moved in ANY mode.

B. Bank D rods can be moved in MAN only.

C. Bank D rods can be moved in Bank Select only.

D. Bank D rods CANNOT be moved in any Mode.

Page 56 of 75

SURRY 2017 NRC EXAM - RO

Question: 57

Given the following:

  • Due to multiple failures, the PRZR spray and PORVs are unavailable to depressurize the

RCS.

  • PRZR level is offscale low.
  • The Crew is attempting to re-establish Letdown flow in accordance with ECA-3.3, SGTR

with loss of Pressure Control.

In accordance with 1-ECA-3.3, which ONE of the following identifies:

1) The fuses for LC-1-460C and LC-1-459C are removed.

2) 1-CH-LCV-1460A and B

A. 1) input

2) open automatically

B. 1) input

2) are opened manually

C. 1) output

2) open automatically

D. 1) output

2) are opened manually

Page 57 of 75

____

SURRY 2017 NRC EXAM - RO

Question: 58

Given the following:

  • Unit 2 is in a Refueling Outage.
  • The crew is currently filling the cavity and making preparations to offload the core.
  • Power Range NI channel 2 is removed from service for troubleshooting.
  • l&C requests permission to remove U2 Power Range NI channel 1 from service to perform a

calibration of the channel.

Which ONE of the following answers the questions below:

1) What impact (if any) will removing U2 Power Range Channel 1, from service have on NI system

operation?

2) For core offload Source range NI channel(s) is (are) required to be OPERABLE.

A. 1) No impact. Power range channels are not required to be Operable in

Refueling.

2) one

B. 1) No impact. Power range channels are not required to be Operable in

Refueling.

2) two

C. 1) Insert a P-JO signal which will de-energize both Source Range

channels.

2) one

D. 1) Insert a P-JO signal which will de-energize both Source Range

channels.

2) two

Page 58 of 75

SURRY 2017 NRC EXAM - RO

Question: 59

Initial Conditions

  • Unit 1 is operating at 100% power.
  • A Large Break LOCA occurs.
  • Unit 1 reactor is tripped and safety injection actuated.
  • Breaker 1 5H8, 1 H Emergency Bus normal supply breaker trips on overcurrent.
  • #1 EDG output breaker will NOT close.

Current Conditions

  • The Crew has entered 1 -E-1, Loss of Reactor or Secondary Coolant.
  • The Containment Hydrogen Analyzer has been placed in service.

Which ONE of the following completes the statement:

The number of Containment Hydrogen recombinets that can be placed in service is (1); at a

MINIMUM hydrogen concentration of(2)% inside Containment.

A. 1)1

2) 4.0

B. 1) 2

2) 4.0

C. 1) 2

2) 0.5

D. 1) 1

2) 0.5

Page 59 of 75

SURRY 2017 NRC EXAM - RO

Question: 60

Initial Conditions:

  • The reactor is operating at 100% power.
  • Rod Control is in Manual for l&C troubleshooting.
  • A turbine control malfunction causes Impulse pressure to drop suddenly to 83%.

Current Conditions:

  • RCS Tave is 575°F; Tref is 568.6°F.
  • No Operator Action is taken.

Which ONE of the following describes the response of the Steam Dumps to these conditions?

A. 1-MS-TCV-105 NB are partially open.

B. 1-MS-TCV-105 NB are full open, 1-MS-TCV-106 NB are partially open.

C. Steam Dumps are closed, Steam Dump Demand is 13%.

D. Steam Dumps are closed, Steam Dump Demand is 32%.

Page 60 of 75

SURRY 2017 NRC EXAM - RO

Question: 61

Given the following:

  • Unit 1 is at 90% power with steady-state conditions.
  • Control Bank D rods are at 227 steps.
  • The crew is preparing to ramp to 100%.

Which of the following completes the statement below?

As turbine load is raised to 100%, main steam header pressure (1)_, and MTC will become

_(2)_.

Main Steam Header Pressure MTC

A. 1) lowers 2) more negative

B. 1) rises 2) less negative

C. 1) lowers 2) less negative

D. 1)rises 2) more negative

Page 61 of 75

SURRY 2017 NRC EXAM - RO

Question: 62

Given the following:

  • Unit 1 is operating at 100%.
  • Condenser Vacuum is 27.6 inches Hg and is lowering 0.4 inches Hg/minute.
  • Turbine 1 and 2 operators dispatched to look for leaks.
  • Generator Megawatts are 890 Mwe and lowering rapidly.

Which of the following completes the following statements:

1) _(1)_ is required to be entered.

2) 1 -E-0 is required to be entered if Main Condenser Vacuum lowers to (2).

A. 1) 0-AP-12.01, Loss of Intake Canal Level

2) 25.0 in-Hg

B. 1) 0-AP-12.01, Loss of Intake Canal Level

2) 22.5 in-Hg

C. 1) 1-AP-14.00, Loss of Main Condenser Vacuum

2) 25.0 in-Hg

D 1) 1-AP-14.00, Loss of Main Condenser Vacuum

2) 22.5 in-Hg

Page 62 of 75

SURRY 2017 NRC EXAM - RO

Question: 63

Unit 1 is operating at 100% when the Reactor Operator notices that Main Feed Pump suction pressure

has lowered on both Main Feed pumps and is now reading 400 psi9 (20 psig lower than before).

Which one of the following identifies a possible cause for this lower reading.

A. 1-SD-LCV-106, HP Heater Drain Pump Level Control valve fails OPEN.

B. J-CN-FCV-107, Condensate Recirculation valve inadvertently opened.

C. 1-CP-MOV-100, Condensate Polisher Bypass valve fails OPEN.

D. 1-CN-126, Condensate bypass for LP FW Heaters 2, 3 and 4 inadvertently opened.

Page 63 of 75

SURRY 2017 NRC EXAM - RO

Question: 64

Initial Conditions:

  • Unit 1 is in CSD, PRZR level at 5%, with RCS draindown to 18 feet in progress.
  • CTMT is on purge using 1-VS-F-59, Aux Bldg (CAT 2) Filter Fan.

CURRENT CONDITIONS

  • The Unit 2 BOP notes the following indication:

ALAMMZ

I

UIGH WN FAiL RANO

Which ONE of the following completes the statement:

The Unit 1 CTMT purge MOVs are 1), and 1 -VS-F-59 is 2).

A. 1) closed

2) tripped

B. 1) closed

2) running

C. 1) open

2) tripped

D. 1) open

2) running

Page 64 of 75

SURRY 2017 NRC EXAM - RO

Question: 65

Initial Conditions:

  • Unit 1 Startup in progress, with power at 6%. Unit 2 is operating at 100% power.
  • The Turbine was just latched and the crew is preparing to bring the Main Generator on line.
  • A Lightning strike at the Low Level intake has resulted in loss of all Circ Water pumps.
  • Operators have been dispatched to attempt to start ESW pumps.

Current Conditions:

o 1 F-H7, INTK CANAL LO LVL CH-1.

o 1 F-H8, INTK CANAL LO LVL CH-2.

o 2F-H7, INTK CANAL LO LVL CH-3.

o 2F-H8, INTK CANAL LO LVL CH-4.

o 1 F-G1, INTK CANAL LO LVL TRIP.

o 2F-G1, INTK CANAL LO LVL TRIP

With no operator action, which of the following completes the statement below.

At this time the Unit 1 Reactor _(1 )_ tripped. All service water flow paths through the station are

isolated except _(2)_.

A. 1) is 2) Bearing cooling water

B. 1) is not 2) Charging pump service water

C. 1) is 2) Charging pump service water

D. 1) is not 2) Bearing cooling water

Page 650175

SURRY 2017 NRC EXAM - RO

Question: 66

Initial Conditions:

  • Unit 1 reactor is operating at 100% power.
  • At 1122 the Plant Computer fails.
  • The Crew initiates 1-AP-20.02, Loss of the Unit 1 Plant Computer.

Current Conditions: (18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> later)

  • The Plant Computer Vendor and l&C are working to restore the Plant Computer.
  • All programs and displays are out of service.

Per 1 -AP-20.02, Loss of the Unit 1 Plant Computer, which ONE of the following completes the

statements:

_1) is/are monitored each hour. The crew will monitor Reactor Power in accordance with

2).

A. 1) Charging Pump bearing temperatures

2) 1-OPT-RX-004, Rx Power Calorimetric Using Feed Flow with PCS Out of Service

B. 1) Delta Flux

2) 1-OPT-RX-007, Shift Average Power Calculation

C. 1) Delta Flux

2) 1-OPT-RX-004, Rx Power Calorimetric Using Feed Flow with PCS Out of Service

D. 1) Charging Pump bearing temperatures

2) 1-OPT-RX-007, Shift Average Power Calculation

Page 66 of 75

SURRY 2017 NRC EXAM - RO

Question: 67

Which ONE of the following completes the statement from 1-GOP-i .4, Unit Startup, HSD to 2%

Reactor Power, concerning the Reactivity Plan provided by Reactor Engineering?

The plan shall contain recommendations for control of Delta Flux, rod height and/or Boron

adjustments, and

A. expected Xenon transient

B. startup rate limitations

C. RCS temperature control

D. source range counts at doubling points

Page 67 of 75

SURRY 2017 NRC EXAM - RO

Question: 68

Given the following:

  • Unit 2 has tripped due to a FW Heater break.
  • Unit 2 Turbine Building basement has been evacuated and quarantined for personnel

safety.

  • Unit 1 has lost both Charging Pump SW pumps due to electrical failure, and restoration is

unlikely.

Which ONE of the following will answer the following questions:

1) Which valve must be operated to cross-tie Charging Pump SW from Unit 2 to Unit 1?

2) What is the location of the valve?

A. 1) 2-SW-443, 1(2)-SW-P-lOB pump discharge cross tie valve.

2) MER4.

B. 1) 1-SW-269, 1(2)-SW-P-bA pump discharge cross tie valve.

2) MER4.

C. 1) 1-SW-269, 1(2)-SW-P-bA pump discharge cross tie valve.

2) MER3.

D. 1) 2-SW-443, 1(2)-SW-P-lOB pump discharge cross tie valve.

2) MER 3.

Page 68 of 75

SURRY 2017 NRC EXAM - RO

Question: 69

According to surveillance procedure 1-OPT-RC-1O.00, Reactor Coolant Leakage-Computer Calculated,

which of the following parameters is an input into the calculation for IDENTIFIED RCS leakage?

A. Pressurizer Level.

B. VCT Level.

C. Pressurizer Relief Tank Level.

D. Containment Sump Level.

Page 69 of 75

SURRY 2017 NRC EXAM - RO

Question: 70

Unit 1 is operating at 100% power.

  • 1-RC-MOV-1 536, 1-RC-PCV-1455C PRZR PORV block valve, is being closed in accordance

with 1-IPT-FT-RC-P-403, Rx. Coolant System Pressure Loop Functional Test.

  • Shortly after the Operator attempts to close the MOV, 1 -RC-MOV-1 536 stops moving and is

stuck in an intermediate position.

Which ONE of the following completes the statement below:

1-RC-MOV-1 536 must be returned to OPERABLE within (1) minutes, or the (2) is

placed in MANUAL.

A. 1) 60 2) 1-RC-PCV-1455C control switch

B. 1) 60 2) Master Pressure Controller

C. 1) 15 2) 1-RC-PCV-1455C control switch

D. 1) 15 2) Master Pressure Controller

Page 70 of 75

SURRY 2017 NRC EXAM - RO

Question: 71

Given the following:

  • Unit 1 is at 100% power.
  • 1-CS-P-iA breaker is tacked in.
  • The next step in the tagging process is to close Containment Spray Suction Valve,1-CS-MOV-

100A.

Using the schematic drawing for l-CS-MOV-100A, select the ONE choice that completes the following

statements.

1) If the operator places the handswitch for 1-CS-MO V-i OOA to CLOSE momentarily, then

releases the handswitch, the MOV _(i) stroke fully CLOSED.

2) The breaker for 1-CS-P-iA must be racked in and_(2)_ in order for the MOVto stroke

CLOSED.

(REFERENCE PROVIDED)

A. 1) will 2) CLOSED

B. i) will not 2) CLOSED

C. i)will 2)OPEN

D. 1) will not 2) OPEN

Page 71 of 75

SURRY 2017 NRC EXAM - RO

Question: 72

Which ONE of the following identifies:

1) The Federal Annual Limit for Dose to the Skin (REM)?

2) The TEDE Emergency Exposure Limit to save valuable equipment in accordance with EPIP

4.04, Emergency Personnel Radiation Exposure (REM)?

A. 1) 5

2) 10

B. 1) 50

2) 10

C. 1) 5

2) 25

D. 1) 50

2) 25

Page 72 of 75

SURRY 2017 NRC EXAM - RO

Question: 73

Given the following:

  • You are assigned as a reflash watch for the next 30 minutes in the Emergency Switchgear

room.

  • An Event occurs that results in declaration of a Site Area Emergency.

With respect to establishing Accountability which ONE of the following describes:

1) Your response to the Site Evacuation alarm.

2) The time limit to complete Accountability.

A. 1) Remain on station, and phone in badge # to Security.

2) 60 minutes.

B. 1) Report to the Operations Support Center (OSC).

2) 60 minutes.

C. 1) Remain on station, and phone in badge # to Security.

2) 30 minutes.

D. 1) Report to the Operations Support Center (OSC).

2) 30 minutes.

Page 73 of 75

SURRY 2017 NRC EXAM - RO

Question: 74

In accordance with OP-AP-1 04, Emergency and Abnormal Operating Procedures:

1) The EOP network is entered by procedure E-0, Reactor Trip or Safety Injection or _(1).

2) Substeps of Emergency Operating Procedure that are designated by _(2)_ must be

performed in order.

A. 1) FR-S.1, Response to Nuclear Generation ATWS

2) letters or numbers

B. 1) ECA-0.0, Loss of All AC Power

2) bullets or asterisks

C. 1) FR-S.1, Response to Nuclear Generation ATWS

2) bullets or asterisks

D. 1) ECA-0.0, Loss of All AC Power

2) letters or numbers

Page 74 of 75

SURRY 2017 NRC EXAM - RO

Question: 75

Given the following:

0130 Unit 1 was at 100% power when a spurious Safety Injection occurred.

0131 The crew enters 1-E-0, Reactor Trip or Safety Injection.

0145 Thecrewtransitionsto 1-ES-li, SI Termination.

0155 The RCS is solid and PRZR PORV,i-RC-PCV-1456 begins to cycle.

0158 HHSI flow has been isolated and charging placed in service.

0212 While placing letdown in service 1-RC-PCV-1456 opens and will not close.

0217 The block valve for 1-RC-PCV-1456 will not close.

RCS pressure is 1000 psig and lowering rapidly.

All steam generators are at 900 psig and slowly lowering.

Which ONE of the following describes the correct actions and procedure implementation.

A. Initiate Safety Injection and go to 1-E-0, Reactor Trip or Safety Injection.

B. Transition to 1-E-1, Loss of Reactor or Secondary Coolant, and use 1-E-1 guidance to

reinitiate Safety Injection.

C. Manually start charging pumps and align HHSI flow path, and go to 1-ES-i .2 Post

LOCA Cooldown and Depressurization.

D. Manually start charging pumps and align HHSI flow path, and go to i-E-i, Loss of

Reactor or Secondary Coolant.

Page 75 of 75

RO EXAM

LIST OF ATTACHMENTS

Attachment # Attachment Description

1 11448-ESK-6BQ SH1, 1-CS-MOV-100A & B

11448-ESK-6AC, CONTAINMENT SPRAY PUMPS

1144$-ESK-3D, CONTROL SWITCH DIAGRAM

2 ECA-1.1, Attachment 1, Minimum SI flow rate

3 Capability Curves

Separate STEAM TABLES

1

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2017 NRC ANSWER KEY

Question # Answer Question Answer

RD

I A 41 C

2 C 42 D

3 A 43 C

4 B 44 B

5 B 45 B

6 B 46 B

7 B 47 A

8 C 48 A

9 A 49 D

10 C 50 B

11 A 51 D

12 D 52 C

13 A 53

14 A 54 D c04. %%1;..-f- ,z/i,//7

15 A 55 A

16 D 56 C

17 B 57 D

18 C 58 D

19 B 59 D

20 A 60 A

21 B 61 A

22 C 62 D

23 C 63 B

24 C 64 B

25 C 65 B

26 B 66 B

27 A 67 A

28 B 68 D

29 B 69 C

30 D 70 A

31 C 71 C

32 C 72 B

33 D 73 C

34 A 74 D

35 C 75 D

36 D

37 D

38 B

39 B

40 B

NRC Validation Page 1

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