Text

2011-03-Final Written Exam
	ML110970446
Person / Time
Site:	Waterford
Issue date:	03/21/2011
From:	Chris Steely; Operations Branch IV
To:	; Entergy Operations
	Laura Hurley
References
	Download: ML110970446 (178)
	v • d • e

2011 NRC Written Examination Waterford 3 Reactor Operator and Senior Reactor Operator

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2011 NRC Written Examination Waterford 3 Reactor Operator and Senior Reactor Operator

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2011 Written Exam Student References Question Reference Number RO 10 OP-902-009, Att. 2A RO 19 COLR Fig 3 RO 21 OP-901-110, Attachment 1 PDB Figure 1 RCS Temperature Bands vs Power RO 24 Tech Spec 3.6.1.3 RO 33 OP-902-009 Attachment 2-E and 2-F RO 53 Tech Spec 3.7.4 SRO 5 TRM 3.8.3.1, Amendment 111 SRO 6 Waterford Generator Capability Curve SRO 10 Tech Spec 3.3.3.1 SRO 14 OP-100-014 Att 6.6 page 15 Tech Spec 3.6.3 Tech Spec 3.7.1.6 SRO 19 OP-010-004, Att 9.6, Fuel Preconditioning Guidelines SRO 24 EP-001-001 SRO 25 EP-002-052

2011 Waterford 3 RO Written Exam Question 1 Given:

Feedwater Control System (FWCS) 1 was in AUTO with a setpoint of 68% when FWCS 1 Master Controller output failed to 0%

The operator depresses the MANUAL pushbutton on the FWCS 1 Master Controller and manually raises the output of FWCS 1 Master Controller Prior to matching steam flow and feed flow, the reactor trips on S/G 1 Low Level Final FWCS 1 Master Controller flow demand is 50% in MANUAL Reactor Trip Override (RTO) actions are verified S/G 1 level is currently rising When S/G 1 level exceeds the automatic setpoint of 68% NR, RTO will

_____(1)_______ in FWCS 1 and S/G 1 level will ______(2)_______.

(1) __ (2) __

A. reset stabilize at setpoint B. remain active stabilize at setpoint C. reset continue to rise D. remain active continue to rise 1

2011 Waterford 3 RO Written Exam Question 2 Given:

The plant is at 10% power following refueling A Pressurizer Relief Valve spuriously opens Reactor Coolant System pressure drops from 2250 PSIA to 1900 PSIA and then slowly recovers Quench Tank temperature rises to 135°F and stabilizes The Pressurizer Relief Valve is currently ____(1)____. During this event, Pressurizer Level will ________(2)________.

(1) (2)

A. closed lower due to mass loss B. closed rise to 100% due to head bubble formation C. open lower due to mass loss D. open rise to 100% due to head bubble formation 2

2011 Waterford 3 RO Written Exam Question 3 Given:

A Small Break Loss of Coolant Accident with a concurrent Loss of Offsite Power has occurred OP-902-002, Loss of Coolant Accident Recovery, is being implemented Containment pressure is 17.3 PSIA Reactor Coolant System pressure is 1380 PSIA Reactor Coolant System Tcold temperatures are 550°F in loops 1 and 2 A cooldown to Shutdown Cooling entry conditions is commencing The ATC should reset ________(1)________ bistable setpoints during the cooldown to ensure continued _________(2)_________ availability.

(1) (2)

A. Pressurizer Pressure Low Pressurizer Heater and and Steam Generator Emergency Feedwater Pressure Lo B. Steam Generator Pressure Pressurizer Heater and Low only Emergency Feedwater C. Pressurizer Pressure Low Emergency Feedwater and Steam Generator Pressure Low D. Steam Generator Pressure Emergency Feedwater Low only 3

2011 Waterford 3 RO Written Exam Question 4 OP-902-002, Loss of Coolant Accident Recovery procedure requires sampling both Steam Generators for activity. The Shift Chemist should be notified that

____________(1)____________ has occurred to ensure actions are taken to

____________(2)____________.

(1) (2)

A. Safety Injection Actuation minimize the potential for radioactive Signal/Containment Isolation release Actuation Signal B. Containment Spray Actuation establish alternate sample cooling Signal C. Safety Injection Actuation establish alternate sample cooling Signal/Containment Isolation Actuation Signal D. Containment Spray Actuation minimize the potential for radioactive Signal release 4

2011 Waterford 3 RO Written Exam Question 5 Given:

The reactor was operating at 100%

Reactor Coolant Pump 2B experienced a Locked Rotor event All other Reactor Coolant Pumps remain in service Post trip, Steam Generator ___(1)____ level will be lower than the other Steam Generator due to a __(2)___ rate of heat transfer to that Steam Generator.

(1) (2)

A. 1 lower B. 2 lower C. 1 higher D. 2 higher 5

2011 Waterford 3 RO Written Exam Question 6 Given:

The reactor was operating at 100% steady state Pressurizer level starts to lower Regen HX Tube Outlet temperature rises from 220°F to 300°F Regen HX Shell Outlet temperature rises from 430°F to 460°F Letdown Flow is 38 GPM Charging Header flow is 44 GPM with one charging pump running Determine the location of the leak.

A. Charging header upstream of the Regenerative HX B. Charging header downstream of CVC-218A, Charging Line 1A Shutoff Valve C. Letdown header upstream of the Regenerative HX D. Letdown header downstream of CVC-140, Ion Exchanger Bypass Valve 6

2011 Waterford 3 RO Written Exam Question 7 Given:

The reactor is at 100% power A leak occurs in Component Cooling Water (CCW) that closes the A and B train CCW supply and return valves for the AB Loop If neither train of Component Cooling Water (CCW) can be restored to the AB Loop within __(1)__ minutes, trip the reactor, secure all Reactor Coolant Pumps (RCPs).

Isolation of the Component Cooling Water AB loop also causes loss of cooling to the

_______(2)______.

(1) (2)

A. 3 Containment Fan Coolers B. 3 Letdown Heat Exchanger C. 10 Containment Fan Coolers D. 10 Letdown Heat Exchanger 7

2011 Waterford 3 RO Written Exam Question 8 Given:

The plant was operating at 2250 PSIA when the selected Pressurizer Pressure Control Channel, RC-IPT-0100X failed high.

Operator action was taken to stabilize RCS pressure The lowest pressure seen was 2235 PSIA Backup Heater Bank 3 is in ON Backup Heaters Banks 1,2, 4-6 are in AUTO Pressurizer backup heater capability will be restored when the Pressurizer Pressure Channel selector switch___(1)___ the Lo Level Heater Cutout selector switch is(are) transferred to the non-faulted channel and _____(2)_______ will energize.

1 2 A. or Backup Heater Bank 3 B. and Backup Heater Bank 3 C. or all Backup Heater Banks D. and all Backup Heater Banks 8

2011 Waterford 3 RO Written Exam Question 9 Which of the following describes how the Diverse Reactor Trip System (DRTS) interrupts power to the Control Element Drive Mechanism (CEDM) Coils during an Anticipated Transient Without Scram (ATWS) condition?

A. The shunt trip coils of the Reactor Trip Breakers are energized.

B. The undervoltage (UV) coils of the Reactor Trip Breakers are de-energized.

C. The CEDM Motor-Generator Set feeder breakers on busses 32A and 32B open.

D. The CEDM Motor-Generator Set output load contactors open.

9

2011 Waterford 3 RO Written Exam Question 10 Given:

OP-902-007, Steam Generator Tube Rupture is being implemented and Steam Generator (S/G) 1 is diagnosed as the affected Steam Generator Reactor Coolant System (RCS) pressure is stable at 1300 PSIA A cooldown is performed and the RCS depressurizes to 900 PSIA Tcold is 525°F

____(1)______ Reactor Coolant Pumps should be secured at this time. Reactor Coolant Pumps in Loop 1 should be disabled by opening the DC Control Power knife switches to _______(2)_________.

(1) (2)

A. Two prevent a dilution event B. All prevent a dilution event C. Two allow pressure equalization of RCS with S/G 1 D. All allow pressure equalization of RCS with S/G 1 10

2011 Waterford 3 RO Written Exam Question 11 OP-902-004, Excess Steam Demand Recovery Procedure, requires verifying no more than two Reactor Coolant Pumps running if Tcold is less than ___(1)___ °F to

__________(2)___________.

(1) (2)

A. 382[384] prevent generating excessive core uplift forces B. 382[384] aid in stabilizing Reactor Coolant System temperature after Steam Generator dryout C. 500[502] prevent generating excessive core uplift forces D. 500[502] aid in stabilizing Reactor Coolant System temperature after Steam Generator dryout 11

2011 Waterford 3 RO Written Exam Question 12

1) What is the operational concern with feeding a dry Steam Generator?

AND

2) Describe the appropriate method for restoring feedwater if both Steam Generators are dry.

A. 1) Steam Generator internal component damage

2) Slowly restore feed to only ONE Steam Generator.

B. 1) Steam Generator internal component damage

2) Slowly restore feed to BOTH Steam Generators.

C. 1) Rapid cooldown of the RCS

2) Slowly restore feed to only ONE Steam Generator.

D. 1) Rapid cooldown of the RCS

2) Slowly restore feed to BOTH Steam Generators.

12

2011 Waterford 3 RO Written Exam Question 13 Given:

A Station Blackout occurred Offsite power is now available A Probable Maximum Precipitation (PMP) event just commenced Power must be restored to the non-safety section of Motor Control Center

_____(1)_____ and at least one Dry Cooling Tower Motor Driven Sump Pump aligned for operation within ___(2)___ of the PMP event.

(1) (2)

A. 312A or B 30 minutes B. 314A or B 30 minutes C. 312A or B 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months D. 314A or B 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 13

2011 Waterford 3 RO Written Exam Question 14 The Undervoltage Override feature of the Load Sequencer provides protection against degraded voltage resulting from ________(1)__________.

The Undervoltage Override feature is active between the ________(2)________ second load blocks.

(1) (2)

A. the start of large transformer 0.5 to 17 (inductive) loads B. failure of the Emergency Diesel 0.5 to 17 Generator excitation system C. the start of large transformer 17 to 200 (inductive) loads D. failure of the Emergency Diesel 17 to 200 Generator excitation system 14

2011 Waterford 3 RO Written Exam Question 15 Given:

Reactor Coolant System Cooldown is in progress using the Atmospheric Dump Valves (ADVs)

The Main Condenser is unavailable Static Uninterruptible Power Supply (SUPS) SMC inverter fails Due to the failure of SUPS SMC, Atmospheric Dump Valve 1 must be operated manually using the ______(1)______, because Atmospheric Dump Valve 1 failed ___(2)___.

(1) (2)

A. handwheel only closed B. handwheel only open C. local air station or handwheel closed D. local air station or handwheel open 15

2011 Waterford 3 RO Written Exam Question 16 Comparing a loss of the Train B DC Safety Busses to a loss of the Train AB DC Safety Busses, select the problem that occurs ONLY for a loss of Train B.

A. Emergency power to a Static Uninterruptible Power Supply is lost.

B. A reactor trip occurs due to loss of power to Reactor Trip Breaker UV coils.

C. Overcurrent protection is lost for associated 4.16 KV bus loads.

D. Control Power is lost to the associated 480V switchgear loads.

16

2011 Waterford 3 RO Written Exam Question 17 In accordance with OP-002-001, Auxiliary Component Cooling Water (ACCW) A header flow should be at least ____(1)______ GPM flow to minimize _______(2)________.

(1) (2)

A. 100 ACC-126A, ACC Header A CCW HX Outlet Temp Control Valve seat and disc erosion B. 100 ACC Pump A vibration C. 1000 ACC-126A, ACC Header A CCW HX Outlet Temp Control Valve seat and disc erosion D. 1000 ACC Pump A vibration 17

2011 Waterford 3 RO Written Exam Question 18 Given:

The plant is at 100% Power Instrument Air pressure is 63 PSIG and lowering rapidly The crew should:

A. Direct the turbine building watch to suspend all operations involving the condensate polisher operations.

B. Commence a rapid down power IAW OP-901-212, Rapid Plant Power Reduction.

C. Commence a normal plant shutdown when MSR temperature control valves fail closed to maintain Rx Power less than 100% Power.

D. Trip the reactor and enter OP-902-000, Standard Post Trip Actions.

18

2011 Waterford 3 RO Written Exam Question 19 Given:

The reactor was operating at 80%

Control Element Assembly (CEA) 20 drops to 0.0 Within 15 minutes, turbine load will be reduced at a rate of approximately

______(1)______ MW/MINUTE. 45 minutes from the time the CEA dropped, reactor power must be reduced to _____(2)_____ %.

(1) (2)

A. 30 60 B. 30 70 C. 60 60 D. 60 70 19

2011 Waterford 3 RO Written Exam Question 20 Given:

The plant is at 55% performing a power ascension Group P is at 140 INCHES for ASI control At 0335 Group P Control Element Assembly (CEA) 35 slips to 125 Power is stabilized at 55%

The crew implements OP-901-102, CEA or CEDMCS Malfunction Attempts to move the CEA are unsuccessful, CEA 35 is declared INOPERABLE At 0420 o Malfunctioning Automatic Control Timing Module (ACTM) card is replaced and o CEA 35 was realigned to 140 and CEA 35 is declared OPERABLE The earliest that the crew can re-commence the power ascension is _______(1)_______

to _________(2)________.

(1) (2)

A. 0535 minimize the effects of Xenon redistribution B. 0535 allow for clad relaxation C. 0620 minimize the effects of Xenon redistribution D. 0620 allow for clad relaxation 20

2011 Waterford 3 RO Written Exam Question 21 Given:

The plant is at 50% power Tave and Tref are matched and stable The Standby Charging Pump Selector Switch is in AB-A Due to a PAC card failure the output of the Pressurizer Level Controller auto output failed to the high limit.

The crew entered OP-901-110, took manual control of the Pressurizer Level Controller and stabilized level at 41% (lowest level attained)

Charging Pumps B and AB are running Charging pump A _____(1)_______be running. The lowest pressurizer level the crew should maintain while operating is ______(2)______%.

(1) (2)

A. should 25 B. should NOT 25 C. should 30 D. should NOT 30 21

2011 Waterford 3 RO Written Exam Question 22 Given:

A reactor startup is in progress Startup Channel 2 high voltage is automatically removed when power exceeds approximately _____(1)_____% on ENI Logarithmic Channel A, if the HV Control Switch in Startup Channel 2 is selected to _____(2)_____.

(1) (2)

A. 1.0 X 10-4 Primary B. 1.0 X 10-4 Alternate C. 5.3 X 10-6 Primary D. 5.3 X 10-6 Alternate 22

2011 Waterford 3 RO Written Exam Question 23 Given:

Primary-to-Secondary leakage in Steam Generator 1 has changed over the last hour with a rate and value that requires the plant to be at 50% in one hour and MODE 3 in a total of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Waterford 3 is designed for a ramp load change of ___(1)___ %/MINUTE between 100%

and 15%; however, the target shutdown rate will be approximately ____(2)___

MW/MINUTE provided pressurizer level can be maintained.

(1) (2)

A. 10 60 B. 5 60 C. 10 30 D. 5 30 23

2011 Waterford 3 RO Written Exam Question 24 Concerning Tech Spec Containment Integrity in Mode 1, which of the following conditions would require action within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ?

A. The Personnel Air Lock outer door is found closed and unlocked.

B. The Escape Air Lock outer door seal is failed with the operable inner door verified locked closed.

C. The Personnel Air Lock door interlocks are inoperable, allowing both doors to be open at the same time.

D. The Escape Air Lock door position indications are inoperable on CP-8 and on the Plant Monitoring Computer.

24

2011 Waterford 3 RO Written Exam Question 25 Given:

The plant was in MODE 3 at Normal Operating Temperature and Pressure A steam line break occurs on Main Steam Line 1 outside Containment upstream of the Main Steam Isolation Valve After 5 minutes Steam Generator 1 completely blows down Representative Core Exit Thermocouple (CET) lower to 460°F Tcold lowers to 430°F With Reactor Coolant Pumps in operation ____(1)_____ should be used to monitor RCS cooldown limits. The Reactor Coolant System cooldown limits ______(2)______ been exceeded.

(1) (2)

A. Tcold have B. Tcold have NOT C. Representative CET have D. Representative CET have NOT 25

2011 Waterford 3 RO Written Exam Question 26 Given:

RCS Tavg is 574°F and stable Letdown flow is 28 GPM All Charging Pumps are OPERABLE Annunciator Panel H Window B1, Pressurizer Level HI/LO is actuated Pressurizer level is 49% and slowly lowering Based on these conditions, pressurizer level will _______(1)_______ and the crew should _______(2)________.

(1) (2)

A. continue to lower perform a rapid shutdown B. continue to lower trip the reactor C. recover perform a rapid shutdown D. recover trip the reactor 26

2011 Waterford 3 RO Written Exam Question 27 Given:

The reactor tripped due to a loss of offsite power On the trip, a Main Steam Safety Valve on Main Steam Line 1 opened and will not reseat Steam Generator 1 pressure is 500 PSIA and lowering Main Steam Line 1 and Blowdown Radiation Monitors are in Hi-Hi alarm RCS pressure is 1300 PSIA and lowering Pressurizer level is 0%

All engineering safeguards equipment is operable OP-902-000, Standard Post Trip Actions is being implemented After Standard Post Trip Actions are complete, the crew will implement:

A. OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery B. OP-902-004, Loss of Excess Steam Demand Recovery C. OP-902-007, Steam Generator Tube Rupture Recovery D. OP-902-008, Functional Recovery Procedure 27

2011 Waterford 3 RO Written Exam Question 28 Given:

The reactor was at 100% power RCP 1A trips on overcurrent

__(1)__ RCP 1A Lift Oil Pump(s) started when RCP 1A __(2)__.

(1) (2)

A. One load breaker opened B. Both load breaker opened C. One speed lowered to 600 RPM D. Both speed lowered to 600 RPM 28

2011 Waterford 3 RO Written Exam Question 29 Given:

The reactor is operating at 100% power At 0100 RCP 1A Lower Seal fails and Controlled Bleedoff flow rises to 2.5 GPM OP-901-130, Reactor Coolant Pump Malfunction is implemented and the plant remains at 100% power At 0530 RCP 1A Middle Seal fails RCP 1A Controlled Bleedoff flow went out of range high and then went to 0 GPM RCP 1A Controlled Bleedoff flow went low due to closure of ________(1)_________.

The crew should ________(2)_________ and secure RCP 1A.

(1) (2)

A. a RCP Controlled Bleedoff perform a shutdown to MODE 3 per Containment Isolation Valve OP-010-005, Plant Shutdown B. a RCP Controlled Bleedoff manually trip the reactor and Containment Isolation Valve perform Standard Post Trip Actions C. the check valve on RCP 1A perform a shutdown to MODE 3 per Controlled Bleedoff line OP-010-005, Plant Shutdown D. the check valve on RCP 1A manually trip the reactor and Controlled Bleedoff line perform Standard Post Trip Actions 29

2011 Waterford 3 RO Written Exam Question 30 Given The plant is at 100% power VCT Level Instrument, CVC-ILT-0227 fails low CVC-183, VCT Outlet Valve closes CVC-507, RWSP to Charging Pump Suction Isolation opens The crew should enter __(1)__ and __(2)__ to match Tavg and Tref.

(1) (2)

A. OP-901-113, Volume Control lower turbine load Tank Makeup Control Malfunction B. OP-901-113, Volume Control raise turbine Load Tank Makeup Control Malfunction C. OP-901-112, Charging or Letdown lower turbine load Malfunction D. OP-901-112, Charging or Letdown raise turbine Load Malfunction 30

2011 Waterford 3 RO Written Exam Question 31 Given:

The plant has tripped from 100% power Reactor Coolant System pressure lowered and stabilized at 1500 psia Containment Pressure is 17.3 PSIA and rising Which of the following describes the condition of the Chemical Volume Control system?

A. CVC-101, Letdown Stop Valve is open.

B. CVC-103 & CVC-109, Letdown Isolation Valves are open.

C. CC-636, Component Cooling Water to Letdown Heat Exchanger is closed.

D. Charging Pumps A, B, and AB are running.

31

2011 Waterford 3 RO Written Exam Question 32 Given:

The plant is in Mode 4 Shutdown Cooling Train B is being placed in service What would be an acceptable manipulation to compensate for the increased heat load on the Component Cooling Water system prior to starting LPSI Pump B?

A. CC-963B, Shutdown HX B CCW Flow Control is placed to OPEN.

B. CC-963B, Shutdown HX B CCW Flow Control is placed to SETPNT.

C. Dry Cooling Tower fans are manually started in slow speed.

D. Dry Cooling Tower fans are manually started in fast speed.

32

2011 Waterford 3 RO Written Exam Question 33 Given:

A Loss Of Cooling Accident is in progress Reactor Coolant System (RCS) pressure is 200 PSIA High Pressure Safety Injection Pump B trips shortly after starting All other equipment functions as designed The minimum required Safety Injection flow for High Pressure Safety Injection is

___(1)____ and __(2)__ is required for Low Pressure Safety Injection.

(1) (2)

A. >185 GPM total flow to no flow the cold legs B. >185 GPM total flow to >185 GPM flow to the cold legs loop 2 cold legs C. >185 GPM to each cold no flow leg D. >185 GPM to each cold >185 GPM flow to leg loop 2 cold legs 33

2011 Waterford 3 RO Written Exam Question 34 Given Reactor Coolant System Code safety valve has been weeping for the past week Quench tank level is 81%

Quench tank temperature is 147 F Control Room Supervisor orders the ATC operator to fill and drain the Quench Tank to reduce Quench Tank temperature.

The Quench Tank will be drained to the ___(1)___ and it will be filled from the ___(2)___

system.

(1) (2)

A. Containment Sump Condensate Make Up B. Reactor Drain Tank Primary Make Up C. Containment Sump Primary Make Up D. Reactor Drain Tank Condensate Make Up 34

2011 Waterford 3 RO Written Exam Question 35 Given:

The plant is at 100% power Emergency Diesel Generator A is running paralleled to the 3A bus in TEST Mode The Unit Auxiliary Transformer A 4.16 KV feeder breaker to the 2A bus trips on overcurrent Component Cooling Water Pump A will start on the __(1)___ Second load block of the Sequencer and will be powered from __(2) .

(1) (2)

A. 7 Emergency Diesel Generator A B. 168 Emergency Diesel Generator A C. 7 Startup Transformer A D. 168 Startup Transformer A 35

2011 Waterford 3 RO Written Exam Question 36 Given The plant is at 100% steady state Pressurizer Pressure Controller, RC-IPIC-0100, output fails to 100%

If no operator actions are taken which of the following describes the plant response:

A. Pressurizer pressure would rise and be controlled by the spray valves at 2275 PSIA.

B. Pressurizer pressure will rise until all back up and proportional heaters secure at 2270 PSIA.

C. Pressurizer pressure would lower until the reactor trips on low Reactor Coolant System pressure.

D. Pressurizer pressure would lower until all Pressurizer heaters are energized which will maintain RCS pressure at 2225 PSIA.

36

2011 Waterford 3 RO Written Exam Question 37 Given The Reactor Coolant System (RCS) pressure is 350 PSIA The plant is raising pressure to 2250 PSIA As RCS pressure rises above 500 PSIA the Pressurizer Pressure Operating Bypass

__(1)___ from service. The set point tracks __(2)__ below actual Reactor coolant System pressure during the pressure rise.

(1) (2)

A. must be manually removed 400 PSIA B. is automatically removed 400 PSIA C. must be manually removed 184 PSIA D. is automatically removed 184 PSIA 37

2011 Waterford 3 RO Written Exam Question 38 Given A Safety Injection Actuation Signal (SIAS) was inadvertently actuated The CRS directs the BOP operator to reset the SIAS The SIAS initiation relays are reset at ___(1)___ and the actuation relays are reset at

___(2)___.

(1) (2)

A. CP-10 CP-33 B. CP-10 CP-10 C. CP-33 CP-33 D. CP-33 CP-10 38

2011 Waterford 3 RO Written Exam Question 39 Given:

The plant is at 100% Power Emergency Diesel Generator A is Out of Service for Maintenance A Loss Of Off Site Power Occurs Which of the following is available to Emergency Borate the RCS?

A. Charging Pump B and Boric Acid Makeup pump B B. Charging Pump A and Boric Acid Make up pump A C. Charging Pump B and Gravity Feed Valve BAM-113A D. Charging Pump A and Gravity Feed Valve BAM-113B 39

2011 Waterford 3 RO Written Exam Question 40 Plant Conditions are as follows:

Power is 100%, 300 EFPD Reactor Power Cutback is in service with subgroups 5 and 11 selected A Shutdown Bank CEA drops into the core The crew entered OP-901-102, CEA or CEDMCS Malfunction Subsequently conditions are as follows:

Power is 80%

Main Feedwater pump A trips on overspeed Based on this event, the crew should A. Remain in OP-901-102 and perform OP-901-101, Reactor Power Cutback concurrently.

B. Trip the reactor, exit OP-901-102, and enter OP-902-000, Standard Post Trip Actions.

C. Remain in OP-901-102 and adjust turbine load to maintain Tavg -Tref matched.

D. Exit OP-901-102 and enter OP-901-101, Reactor Power Cutback.

40

2011 Waterford 3 RO Written Exam Question 41 Given:

Reactor Coolant System pressure is 1600 PSIA Containment pressure is 17.5 PSIA and rising The crew has diagnosed into OP-902-002, Loss of Coolant Accident Recovery Component Cooling Water (CCW) Pumps A and B are running The BOP operator reports that Containment Fan Cooler A has tripped. Which action is required?

A. Place CCW AB Assignment Switch in the A position and manually start CCW Pump AB.

B. Override and close the Containment Fan Cooler A Component Cooling Water isolation valves.

C. Verify Containment Cooling Safety Damper, CCS-102A, closed when CFC A tripped.

D. Verify Containment Spray flow is greater than 1750 GPM for both trains of Containment Spray.

41

2011 Waterford 3 RO Written Exam Question 42 Given the following:

A Loss of Coolant Accident has occurred Reactor Coolant System pressure is 700 PSIA Containment pressure is 18 PSIA Refueling Water Storage Pool level is 9% and lowering No operator actions have been taken Low Pressure Safety Injection pumps A and B are running High Pressure Safety Injection pumps A and B are running Based on the given conditions the Balance of Plant operator should:

A. Close SI-602A and B, ESF Pump Suction Valves from the SI Sump.

B. Open SI-120A and B, SI Pumps Recirculation Isolation Valves.

C. Secure High Pressure Safety Injection Pumps A and B.

D. Secure Low Pressure Safety Injection Pumps A and B.

42

2011 Waterford 3 RO Written Exam Question 43 Given:

Reactor Coolant System Tcold is 500 F and lowering 15 minutes ago the Reactor Coolant System Tc was 515 F when a controlled cool down was established The cool down is being controlled using MS-319A, Main Steam Bypass 1A, at 15% open IF MS-319A failed open, the maximum allowed cool down rate of ___(1)____ which protects the ___(2)__________, would be exceeded.

(1) (2)

A. 60 F/Hr The most limiting component in Reactor Coolant System under all conditions B. 60 F/Hr SG tube sheet from cyclic stress which is the most limiting component under all conditions C. 100 F/Hr SG tube sheet from cyclic stress which is the most limiting component under all conditions D. 100 F/Hr The most limiting component in Reactor Coolant System under all conditions 43

2011 Waterford 3 RO Written Exam Question 44 Given The plant is performing an up power Dilution to the Volume Control Tank is in progress for power ascension Reactor Power is 70%

Turbine is in GO with a rate of 2MW/MIN Tave is 565 F Tref is 561 F To match Tave and Tref, The BOP operator should ____(1)_____ the rate the Main Turbine governor valves open. To accomplish this task, the BOP operator is required to

___(2)________.

(1) (2)

A. raise depress LOAD RATE pushbutton, entering new value, and press ENTER B. raise place the Main Turbine in HOLD, depress LOAD RATE pushbutton, enter new value, and push GO C. lower depress LOAD RATE pushbutton, entering new value, and press ENTER D. lower place the Main Turbine in HOLD, depress LOAD RATE pushbutton, enter new value, and push GO 44

2011 Waterford 3 RO Written Exam Question 45 Plant Conditions are as Follows:

Power is 100%

SG-ILR-1111, Steam Generator 1 Narrow Range level indicator is reading 0% on the CP-1 recorder SG-ILR-1105, Steam Generator 1 Narrow Range level indicator is reading 68%

on the CP-1 recorder All Narrow Range Steam Generator levels on CP-7 are indicating 68%

A reactor trip occurs All systems performed as designed before and after the trip The expected post trip responses to these conditions are that FW IHIC 1107 Main Feedwater Pump A speed controller ___(1)___ and FW IHIC1111, Main Feedwater Regulating Valve A and FW IHIC1105 Startup Feedwater Regulating Valve A Controller

__(2)___.

(1) (2)

A. lowers to 3900 RPM remain at their pre trip positions B. lowers to 3900 RPM reposition to their Reactor Trip Positions C. remains at 4500 RPM remain at their pre trip positions D. remains at 4500 RPM reposition to their Reactor Trip Positions 45

2011 Waterford 3 RO Written Exam Question 46 The EFW system is designed to prevent ________(1)_______ by providing lines with an orifice from the Main Feedwater discharge headers to the EFW ____(2)____ piping.

(1) (2)

A. feed ring thermal stress suction B. feed ring thermal stress discharge C. EFW piping damage suction D. EFW piping damage discharge 46

2011 Waterford 3 RO Written Exam Question 47 Static Uninterruptable Power Supply SMA requires maintenance to the inverter section requiring the Inverter to be secured.

Other SUPS SMA components are not affected by maintenance.

Will the AC loads remain powered up with the Inverter de energized?

A. Yes, loads will be powered from the Normal AC supply through the rectifier.

B. Yes, loads will be powered from the DC supply through the rectifier.

C. Yes, loads will be powered from the Bypass AC supply.

D. No, PDP SMA must be de energized to support this maintenance.

47

2011 Waterford 3 RO Written Exam Question 48 Given:

The plant is at 100% power The RAB watch reports that the AB battery bus indicates a positive 125 volt DC ground.

An additional ___(1)___ ground of the same magnitude on the AB battery bus, would require implementing OP-901-313, Loss of a 125 Volt DC Bus. This will ____(2)___.

(1) (2)

A. negative make Emergency Feedwater Pump AB unavailable and TS 3.7.1.2 must be addressed B. negative require the crew to manually trip the reactor if bus AB-DC can not be restored C. positive make Emergency Feedwater Pump AB unavailable and TS 3.7.1.2 must be addressed D. positive require the crew to manually trip the reactor if bus AB-DC can not be restored 48

2011 Waterford 3 RO Written Exam Question 49 Given:

Reactor Coolant System Pressure is 1600 PSIA and lowering slowly Containment pressure is 19 PSIA and rising A Loss Of Offsite Power has occurred Five minutes into this event Emergency Diesel Generator A tripped on Overspeed What of the following describes the MINIMUM actions required to maintain containment integrity?

A. CS-125A, Containment Spray Header Isolation, must be closed by taking the CP-8 control switch to CLOSE only.

B. CS-125A, Containment Spray Header Isolation, must be closed by taking the CP-8 control switch to OPEN and then to CLOSE only.

C. CS-125A, Containment Spray Header Isolation, must be closed by taking the override switch in the +35 Relay Room to OVERRIDE only.

D. CS-125A, Containment Spray Header Isolation, must be closed by taking the override switch in the +35 relay room to OVERRIDE, followed by taking the CP-8 control switch to OPEN and then to CLOSE.

49

2011 Waterford 3 RO Written Exam Question 50 Given:

An earthquake has occurred at Waterford 3 A loss of offsite power has occurred .

Emergency Diesel Generator A and B have started to supply in house loads A support beam in the A Emergency Diesel Generator room has fallen on and damaged both Air compressors A1 and A2 Both air receiver pressures are 0 PSIG.

Emergency Diesel Generator A develops an oil leak requiring it to be shutdown.

What action is required to shutdown Emergency Diesel Generator A?

A. Depress the Emergency Shutdown push buttons on CP-1.

B. Select STOP on the local Emergency Diesel Generator control panel.

C. Pull the Overspeed Trip Plunger located on the Overspeed Governor.

D. Pull and hold the manual Fuel Rack Override lever to the no fuel position.

50

2011 Waterford 3 RO Written Exam Question 51 Given:

A Main Steam Line break has occurred inside containment Safety Injection Actuation Signal, Containment Isolation Actuation Signal, Main Steam Isolation Signal and, Containment Spray Actuation are all actuated The crew has entered OP-902-004, Excess Steam Demand Recovery Containment Temperature is 204 F ARM-IRE 5400A and ARM-IRE-5400B, Containment High Range Radiation Monitors alarmed 15 minutes into the event and radiations levels are trending down No other Containment Radiation monitors are in alarm For the given conditions the crew should:

A. Remain in OP-902-004 and monitor the Containment radiation monitors for thermally induced current effects.

B. Enter OP-901-403, High Airborne Activity inside Containment, and perform concurrently with OP-902-004.

C. Take no action since these area monitors are isolated on a CIAS and are unreliable.

D. Enter OP-902-008, Functional Recovery, due to high activity in Containment.

51

2011 Waterford 3 RO Written Exam Question 52 Given A Loss Of Coolant Accident is in Progress Loss Of Off Site Power has occurred Emergency Diesel Generator A has tripped on overspeed Component Cooling Water temperature is 98 °F and rising B Train Dry Cooling Tower Fans 1-4 are operating in Fast Speed B Train Dry Cooling Tower Fans 5-15 are operating in Slow Speed As Component Cooling Water System temperature continues to rise, Dry Cooling Tower B fans 5-15 will start simultaneously in FAST speed when temperature rises above (1) . The fans will start cycling to SLOW when system temperature drops below (2) .

(1) (2)

A. 100 °F 92 °F B. 115 °F 92 °F C. 100 °F 88 °F D. 115 °F 88 °F 52

2011 Waterford 3 RO Written Exam Question 53 Given Dry Cooling Tower fans 7B and 2B are out of service.

Outside air temperature is 92 °F.

Wet Bulb temperature is 73 °F.

What is the most limiting time to restore Dry Cooling Tower fans to comply with Tech Spec 3.7.4?

A. 1 Hour B. 2 Hour C. 72 Hour D. 7 Days 53

2011 Waterford 3 RO Written Exam Question 54 Given the following conditions:

Instrument Air Header pressure has lowered to 100 psig due to a leak SA-125, Station Air Backup is at its normal setpoint SA-125 is _________ and SA-123, Air Dryer Bypass is _________.

A. OPEN, OPEN B. CLOSED, OPEN C. OPEN, CLOSED D. CLOSED, CLOSED 54

2011 Waterford 3 RO Written Exam Question 55 Given:

The plant is in Mode 6 Core alterations are in progress The Reactor Auxiliary Building watch reports that train A Main Steam Line Bellows has been removed from the containment penetration for replacement Control room staff verified that the Bellows work is not being tracked by a containment impairment Containment integrity is _ (1) _. The crew should __(2)__.

(1) (2)

A.

met immediately suspend core alterations B. met isolate the affected penetration within 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months or suspend core alterations C. not met isolate the affected penetration within 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months or suspend core alterations D. not met immediately suspend core alterations 55

2011 Waterford 3 RO Written Exam Question 56 To cool the magnetic jack coils of the CEDM System, Control Element Drive Cooling System air flows (1) rejecting the CEDM Cooling System heat to the (2) System.

(1) (2)

A. across the CEDM coils and then Component Cooling Water through the CEDM coolers, B. through the CEDM coolers then Component Cooling Water across the CEDM coils, C. across the CEDM coils and then Reactor Cavity Cooling through the CEDM coolers, D. through the CEDM coolers then Reactor Cavity Cooling across the CEDM coils, 56

2011 Waterford 3 RO Written Exam Question 57 Given A small break loss of coolant accident is in progress A Safety Injection Actuation Signal (SIAS) has occurred Voids in the Reactor Coolant System (RCS) are indicated The CRS directs the NPO to vent non-condensable gases from the Reactor Vessel Head The Reactor Vessel Head Vent valves ________(1)________. The Reactor Vessel Head is vented to the ____(2)____.

(1) (2)

A. can not be opened until SIAS is reset Quench Tank B. must be energized from CP-8 and the Quench Tank valves can then be opened C. can not be opened until SIAS is reset Reactor Drain Tank D. must be energized from CP-8 and the Reactor Drain Tank valves can then be opened 57

2011 Waterford 3 RO Written Exam Question 58 Given Plant is at 100% power steady state conditions Static Uninterruptable Power Supply SMA fails Core Protection Calculator A and ____(1)____ deenergize. TCB 1, 2, 5, and 6 Open and the reactor ___(2)___.

(1) (2)

A. Linear Channel A trips B. Control Channel #1 does not trip C. Linear Channel A does not trip D. Control Channel #1 trips 58

2011 Waterford 3 RO Written Exam Question 59 Given the following conditions A Loss Of Coolant Accident has occurred Which of the following describes the temperature when Zr-Water reaction becomes self sustaining?

A. 1800 F B. 2200 F C. 3350 F D. 5080 F 59

2011 Waterford 3 RO Written Exam Question 60 The containment atmosphere Hydrogen Analyzer takes a suction from ___(1)____ and provides indication of Hydrogen concentration on CP-____(2)______

(1) (2)

A. Below the Missile Shield 33 B. Lower Reactor Cavity 8 C. Below the Missile Shield 8 D. Lower Reactor Cavity 33 60

2011 Waterford 3 RO Written Exam Question 61 Given CCW Surge Tank Level Switch CC-ILS-7013A failed low.

CC-200A/727, CCW Hdr A TO AB Supply and Return Isolations, failed closed.

CC-134 A, CCW A Dry Cooling Tower Bypass failed open.

CC-135 A, CCW A Dry Cooling Tower Isolation, failed closed.

Both Train A and Train B CC-620, Fuel Pool Heat Exchanger Temperature Control Valve, control switches are in the CONTROL position at CP-18.

Based on this level switch failure, A. Spent Fuel Pool temperature will rise since CC-620 failed closed.

B. Spent Fuel Pool temperature will lower since CC-134 A, CCW A Dry Cooling Tower Bypass failed open.

C. Spent Fuel Pool temperature will rise since CC-135 A, CCW A Dry Cooling Tower Isolation, failed closed.

D. Spent Fuel Pool temperature is controlled in automatic since the Train B CC-620 control switch is in CONTROL.

61

2011 Waterford 3 RO Written Exam Question 62 Given The Reactor tripped from 100% power OP-902-000, Standard Post Trip Actions, has been entered and is being performed Reactor Coolant System (RCS) pressure is 2115 PSIA and rising One Control Element Assembly is stuck out Reactor power is 10-4% and lowering Steam Generator 1 level is 25% NR and lowering Steam Generator 2 level is 29% NR and lowering Pressurizer level is 28% and rising 3 Charging pumps are operating Steam Generator 1 and 2 pressures are 950 PSIA All ESFAS systems are in standby Based on the given conditions the Reactor Operator should _____________________.

A. commence emergency boration B. secure Charging pump AB C. take manual control of RCS pressure and control between 2125 to 2275 PSIA D. manually initiate Emergency Feedwater Actuation Signal for Steam Generator 1 62

2011 Waterford 3 RO Written Exam Question 63 The following plant conditions exist:

300 EFPD The plant is at 15% power following a mid cycle outage startup The Main Turbine in on line with the Speed Loop in service Spurious operation of the Steam Bypass Control System resulted in MS-319 A, Main Steam Bypass 1A and MS-320 A, Main Steam Bypass 2A opening Which of the following parameters will be lower after the event than before the event?

A. Steam Generator pressure B. Reactor power C. RCS THOT temperature.

D. Main Steam flow 63

2011 Waterford 3 RO Written Exam Question 64 Given Plant is 100% Power A Waste Condensate Tank is being discharged A power supply on PRM-IRE-0647 Liquid Waste Management Radiation Monitor fails As a result of this failure ___(1)___ and ___(2)___.

(1) (2)

A. LWM-441, Liquid Waste to LWM-442, Liquid Waste to Circulating Water Shutoff Circulating Water Control Valve, Valve, closes remains open B. LWM-441, Liquid Waste to LWM-442, Liquid Waste to Circulating Water Shutoff Circulating Water Control Valve, Valve, closes closes C. LWM-441, Liquid Waste to LWM-442, Liquid Waste to Circulating Water Shutoff Circulating Water Control Valve, Valve, remains open remains open D. LWM-441, Liquid Waste to LWM-442, Liquid Waste to Circulating Water Shutoff Circulating Water Control Valve, Valve, remains open closes 64

2011 Waterford 3 RO Written Exam Question 65 Given Fire alarms are received for the +35 Cable Vault area.

The Fire Brigade leader has reported that the automatic deluge actuation has failed and the fire is not under control.

The Control Room Supervisor has entered OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown.

The Control Room Supervisor has directed the immediate actions be completed and the Control Room evacuated.

Based on the given conditions the AT-THE-CONTROLS Operator will (1) and (2) .

(1) (2)

A. trip 2 Reactor Coolant Pumps secure Charging and Letdown B. trip 2 Reactor Coolant Pumps start all available Charging Pumps C. trip all 4 Reactor Coolant Pumps secure Charging and Letdown D. trip all 4 Reactor Coolant Pumps start all available Charging Pumps 65

2011 Waterford 3 RO Written Exam Question 66 Per OI-024-000, Maintaining Active SRO/RO Status, to maintain your Reactor Operator license in an ACTIVE status, you must stand a minimum of ______(1)_______ 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts in a calendar quarter. To upgrade from INACTIVE status to ACTIVE status, a license holder must stand _______(2)________ hours of under instruction watches.

(1) (2)

A. five 40 B.

seven 40 C.

five 60 D.

seven 60 66

2011 Waterford 3 RO Written Exam Question 67 In accordance with EN-OP-102, Protection and Caution Tagging, __________________

should have double valve isolation and tagging applied during removal and replacement of the component.

A. Instrument Air Compressor A Unloader Valve B. Turbine Cooling Water pump A C. Containment Fan Cooler C Cooling Coils D. Hydrogen Excess Flow Control Valve 67

2011 Waterford 3 RO Written Exam Question 68 Given:

The plant is in MODE 6 The Upper Guide Structure is removed Core offload is suspended Reactor Cavity Level is 44 ft MSL The plant has been shutdown for 200 Hours

______(1)______ train(s) of Shutdown Cooling must be OPERABLE and Shutdown Cooling flow must be at least _____(2)______ GPM.

(1) (2)

A. One 2000 B. Two 2000 C. One 3000 D. Two 3000 68

2011 Waterford 3 RO Written Exam Question 69 Given The plant is at 100% Power At 0100, the BOP operator bypasses the Channel C High LPD and Low DNBR trip bistables for a scheduled 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months I&C surveillance on Channel C Core Protection Calculator.

The I&C technician informs the CRS that the CPC has failed the surveillance and will require a card replacement.

Operability will be tracked by ___(1)___ when the work begins. The Shift Manager will authorize operability following retest on ___(2)___.

(1) (2)

A. the work package OP-100-010, Att. 7.1, TS/TRM Entry Guidelines B. OP-100-010, Att. 7.1, OP-100-010, Att. 7.2, EOS TS/TRM Entry Guidelines, Checklist C. the work package OP-100-010, Att. 7.2, EOS Checklist D. OP-100-010, Att. 7.1, OP-100-010, Att. 7.1, TS/TRM TS/TRM Entry Guidelines, Entry Guidelines 69

2011 Waterford 3 RO Written Exam Question 70 The Peak Centerline Temperature safety limit for new fuel with no burnable poison is

____(1)______°F. Per TS 2.2.1, Reactor Trip Setpoints, a steady state peak linear heat rate of ___(2)___ has been selected as the Limited Safety System Setting to prevent fuel centerline melt.

(1) (2)

A. 5080 12.9 KW/Ft B. 5080 21.0 KW/Ft C. 5022 12.9 KW/Ft D. 5022 21.0 KW/Ft 70

2011 Waterford 3 RO Written Exam Question 71 Given the following:

The plant is at 10% Power A containment entry is desired Which of the following areas inside containment are forbidden from being entered?

A. Pressurizer Cubicle below +21 elevation B. +46 elevation at the Quench Tank C. Main Steam Line Crossovers on the +46 elevation D. 1A Cold Leg penetration through the D Ring Wall 71

2011 Waterford 3 RO Written Exam Question 72 A high activity detected by the Industrial Waste Sump Radiation Monitor results in the discharge path of Industrial Waste Sump 2 pumps swapping from _______(1)________

to ______(2)_______.

A. (1) Industrial Waste Sump 1 (2) Waste Tanks B. (1) Industrial Waste Sump 1 (2) RAB Oil Sump 3 C. (1) Oil Separator Sump (2) Waste Tanks D. (1) Oil Separator Sump (2) RAB Oil Sump 3 72

2011 Waterford 3 RO Written Exam Question 73 To verify Core Heat Removal during Standard Post Trip Actions, the ATC should check RCS Loop Delta T for _______(1)________ and check Th Subcooling only when on

______(2)_____ circulation.

(1) (2)

A. loops with an forced operating RCP B. all loops forced C. loops with an natural operating RCP D. all loops natural 73

2011 Waterford 3 RO Written Exam Question 74 When an Emergency Plan classification is upgraded from an Unusual Event to an Alert and no site evacuation is required, ________(1)________ must be notified within

_____(2)_____ minutes of the upgrade.

(1) (2)

A. US Coast Guard 15 B. Waterford 1 & 2 15 C. US Coast Guard 60 D. Waterford 1 & 2 60 74

2011 Waterford 3 RO Written Exam Question 75 Given:

A Control Room Evacuation is in progress due to a fire in CP-2.

Immediate Actions of OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown, have been completed The BOP is currently performing Attachment 4, BOP Time Critical Actions After completion of the attachment, only the ____(1)____ 4.16 KV Safety bus will be energized and the bus will be loaded through the _____(2)_____ sequencer.

(1) (2)

A. A3 mini B. A3 normal C. B3 mini D. B3 normal END OF EXAM 75

2011 Waterford 3 SRO Written Exam Question 1 Given:

Feedwater Control System (FWCS) 1 was in AUTO with a setpoint of 68% when FWCS 1 Master Controller output failed to 0%

The operator depresses the MANUAL pushbutton on the FWCS 1 Master Controller and manually raises the output of FWCS 1 Master Controller Prior to matching steam flow and feed flow, the reactor trips on S/G 1 Low Level Final FWCS 1 Master Controller flow demand is 50% in MANUAL Reactor Trip Override (RTO) actions are verified S/G 1 level is currently rising When S/G 1 level exceeds the automatic setpoint of 68% NR, RTO will

_____(1)_______ in FWCS 1 and S/G 1 level will ______(2)_______.

(1) __ (2) __

A. reset stabilize at setpoint B. remain active stabilize at setpoint C. reset continue to rise D. remain active continue to rise 1

2011 Waterford 3 SRO Written Exam Question 2 Given:

The plant is at 10% power following refueling A Pressurizer Relief Valve spuriously opens Reactor Coolant System pressure drops from 2250 PSIA to 1900 PSIA and then slowly recovers Quench Tank temperature rises to 135°F and stabilizes The Pressurizer Relief Valve is currently ____(1)____. During this event, Pressurizer Level will ________(2)________.

(1) (2)

A. closed lower due to mass loss B. closed rise to 100% due to head bubble formation C. open lower due to mass loss D. open rise to 100% due to head bubble formation 2

2011 Waterford 3 SRO Written Exam Question 3 Given:

A Small Break Loss of Coolant Accident with a concurrent Loss of Offsite Power has occurred OP-902-002, Loss of Coolant Accident Recovery, is being implemented Containment pressure is 17.3 PSIA Reactor Coolant System pressure is 1380 PSIA Reactor Coolant System Tcold temperatures are 550°F in loops 1 and 2 A cooldown to Shutdown Cooling entry conditions is commencing The ATC should reset ________(1)________ bistable setpoints during the cooldown to ensure continued _________(2)_________ availability.

(1) (2)

A. Pressurizer Pressure Low Pressurizer Heater and and Steam Generator Emergency Feedwater Pressure Lo B. Steam Generator Pressure Pressurizer Heater and Low only Emergency Feedwater C. Pressurizer Pressure Low Emergency Feedwater and Steam Generator Pressure Low D. Steam Generator Pressure Emergency Feedwater Low only 3

2011 Waterford 3 SRO Written Exam Question 4 OP-902-002, Loss of Coolant Accident Recovery procedure requires sampling both Steam Generators for activity. The Shift Chemist should be notified that

____________(1)____________ has occurred to ensure actions are taken to

____________(2)____________.

(1) (2)

A. Safety Injection Actuation minimize the potential for radioactive Signal/Containment Isolation release Actuation Signal B. Containment Spray Actuation establish alternate sample cooling Signal C. Safety Injection Actuation establish alternate sample cooling Signal/Containment Isolation Actuation Signal D. Containment Spray Actuation minimize the potential for radioactive Signal release 4

2011 Waterford 3 SRO Written Exam Question 5 Given:

The reactor was operating at 100%

Reactor Coolant Pump 2B experienced a Locked Rotor event All other Reactor Coolant Pumps remain in service Post trip, Steam Generator ___(1)____ level will be lower than the other Steam Generator due to a __(2)___ rate of heat transfer to that Steam Generator.

(1) (2)

A. 1 lower B. 2 lower C. 1 higher D. 2 higher 5

2011 Waterford 3 SRO Written Exam Question 6 Given:

The reactor was operating at 100% steady state Pressurizer level starts to lower Regen HX Tube Outlet temperature rises from 220°F to 300°F Regen HX Shell Outlet temperature rises from 430°F to 460°F Letdown Flow is 38 GPM Charging Header flow is 44 GPM with one charging pump running Determine the location of the leak.

A. Charging header upstream of the Regenerative HX B. Charging header downstream of CVC-218A, Charging Line 1A Shutoff Valve C. Letdown header upstream of the Regenerative HX D. Letdown header downstream of CVC-140, Ion Exchanger Bypass Valve 6

2011 Waterford 3 SRO Written Exam Question 7 Given:

The reactor is at 100% power A leak occurs in Component Cooling Water (CCW) that closes the A and B train CCW supply and return valves for the AB Loop If neither train of Component Cooling Water (CCW) can be restored to the AB Loop within __(1)__ minutes, trip the reactor, secure all Reactor Coolant Pumps (RCPs).

Isolation of the Component Cooling Water AB loop also causes loss of cooling to the

_______(2)______.

(1) (2)

A. 3 Containment Fan Coolers B. 3 Letdown Heat Exchanger C. 10 Containment Fan Coolers D. 10 Letdown Heat Exchanger 7

2011 Waterford 3 SRO Written Exam Question 8 Given:

The plant was operating at 2250 PSIA when the selected Pressurizer Pressure Control Channel, RC-IPT-0100X failed high.

Operator action was taken to stabilize RCS pressure The lowest pressure seen was 2235 PSIA Backup Heater Bank 3 is in ON Backup Heaters Banks 1,2, 4-6 are in AUTO Pressurizer backup heater capability will be restored when the Pressurizer Pressure Channel selector switch___(1)___ the Lo Level Heater Cutout selector switch is(are) transferred to the non-faulted channel and _____(2)_______ will energize.

1 2 A. or Backup Heater Bank 3 B. and Backup Heater Bank 3 C. or all Backup Heater Banks D. and all Backup Heater Banks 8

2011 Waterford 3 SRO Written Exam Question 9 Which of the following describes how the Diverse Reactor Trip System (DRTS) interrupts power to the Control Element Drive Mechanism (CEDM) Coils during an Anticipated Transient Without Scram (ATWS) condition?

A. The shunt trip coils of the Reactor Trip Breakers are energized.

B. The undervoltage (UV) coils of the Reactor Trip Breakers are de-energized.

C. The CEDM Motor-Generator Set feeder breakers on busses 32A and 32B open.

D. The CEDM Motor-Generator Set output load contactors open.

9

2011 Waterford 3 SRO Written Exam Question 10 Given:

OP-902-007, Steam Generator Tube Rupture is being implemented and Steam Generator (S/G) 1 is diagnosed as the affected Steam Generator Reactor Coolant System (RCS) pressure is stable at 1300 PSIA A cooldown is performed and the RCS depressurizes to 900 PSIA Tcold is 525°F

____(1)______ Reactor Coolant Pumps should be secured at this time. Reactor Coolant Pumps in Loop 1 should be disabled by opening the DC Control Power knife switches to _______(2)_________.

(1) (2)

A. Two prevent a dilution event B. All prevent a dilution event C. Two allow pressure equalization of RCS with S/G 1 D. All allow pressure equalization of RCS with S/G 1 10

2011 Waterford 3 SRO Written Exam Question 11 OP-902-004, Excess Steam Demand Recovery Procedure, requires verifying no more than two Reactor Coolant Pumps running if Tcold is less than ___(1)___ °F to

__________(2)___________.

(1) (2)

A. 382[384] prevent generating excessive core uplift forces B. 382[384] aid in stabilizing Reactor Coolant System temperature after Steam Generator dryout C. 500[502] prevent generating excessive core uplift forces D. 500[502] aid in stabilizing Reactor Coolant System temperature after Steam Generator dryout 11

2011 Waterford 3 SRO Written Exam Question 12

1) What is the operational concern with feeding a dry Steam Generator?

AND

2) Describe the appropriate method for restoring feedwater if both Steam Generators are dry.

A. 1) Steam Generator internal component damage

2) Slowly restore feed to only ONE Steam Generator.

B. 1) Steam Generator internal component damage

2) Slowly restore feed to BOTH Steam Generators.

C. 1) Rapid cooldown of the RCS

2) Slowly restore feed to only ONE Steam Generator.

D. 1) Rapid cooldown of the RCS

2) Slowly restore feed to BOTH Steam Generators.

12

2011 Waterford 3 SRO Written Exam Question 13 Given:

A Station Blackout occurred Offsite power is now available A Probable Maximum Precipitation (PMP) event just commenced Power must be restored to the non-safety section of Motor Control Center

_____(1)_____ and at least one Dry Cooling Tower Motor Driven Sump Pump aligned for operation within ___(2)___ of the PMP event.

(1) (2)

A. 312A or B 30 minutes B. 314A or B 30 minutes C. 312A or B 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months D. 314A or B 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 13

2011 Waterford 3 SRO Written Exam Question 14 The Undervoltage Override feature of the Load Sequencer provides protection against degraded voltage resulting from ________(1)__________.

The Undervoltage Override feature is active between the ________(2)________ second load blocks.

(1) (2)

A. the start of large transformer 0.5 to 17 (inductive) loads B. failure of the Emergency Diesel 0.5 to 17 Generator excitation system C. the start of large transformer 17 to 200 (inductive) loads D. failure of the Emergency Diesel 17 to 200 Generator excitation system 14

2011 Waterford 3 SRO Written Exam Question 15 Given:

Reactor Coolant System Cooldown is in progress using the Atmospheric Dump Valves (ADVs)

The Main Condenser is unavailable Static Uninterruptible Power Supply (SUPS) SMC inverter fails Due to the failure of SUPS SMC, Atmospheric Dump Valve 1 must be operated manually using the ______(1)______, because Atmospheric Dump Valve 1 failed ___(2)___.

(1) (2)

A. handwheel only closed B. handwheel only open C. local air station or handwheel closed D. local air station or handwheel open 15

2011 Waterford 3 SRO Written Exam Question 16 Comparing a loss of the Train B DC Safety Busses to a loss of the Train AB DC Safety Busses, select the problem that occurs ONLY for a loss of Train B.

A. Emergency power to a Static Uninterruptible Power Supply is lost.

B. A reactor trip occurs due to loss of power to Reactor Trip Breaker UV coils.

C. Overcurrent protection is lost for associated 4.16 KV bus loads.

D. Control Power is lost to the associated 480V switchgear loads.

16

2011 Waterford 3 SRO Written Exam Question 17 In accordance with OP-002-001, Auxiliary Component Cooling Water (ACCW) A header flow should be at least ____(1)______ GPM flow to minimize _______(2)________.

(1) (2)

A. 100 ACC-126A, ACC Header A CCW HX Outlet Temp Control Valve seat and disc erosion B. 100 ACC Pump A vibration C. 1000 ACC-126A, ACC Header A CCW HX Outlet Temp Control Valve seat and disc erosion D. 1000 ACC Pump A vibration 17

2011 Waterford 3 SRO Written Exam Question 18 Given:

The plant is at 100% Power Instrument Air pressure is 63 PSIG and lowering rapidly The crew should:

A. Direct the turbine building watch to suspend all operations involving the condensate polisher operations.

B. Commence a rapid down power IAW OP-901-212, Rapid Plant Power Reduction.

C. Commence a normal plant shutdown when MSR temperature control valves fail closed to maintain Rx Power less than 100% Power.

D. Trip the reactor and enter OP-902-000, Standard Post Trip Actions.

18

2011 Waterford 3 SRO Written Exam Question 19 Given:

The reactor was operating at 80%

Control Element Assembly (CEA) 20 drops to 0.0 Within 15 minutes, turbine load will be reduced at a rate of approximately

______(1)______ MW/MINUTE. 45 minutes from the time the CEA dropped, reactor power must be reduced to _____(2)_____ %.

(1) (2)

A. 30 60 B. 30 70 C. 60 60 D. 60 70 19

2011 Waterford 3 SRO Written Exam Question 20 Given:

The plant is at 55% performing a power ascension Group P is at 140 INCHES for ASI control At 0335 Group P Control Element Assembly (CEA) 35 slips to 125 Power is stabilized at 55%

The crew implements OP-901-102, CEA or CEDMCS Malfunction Attempts to move the CEA are unsuccessful, CEA 35 is declared INOPERABLE At 0420 o Malfunctioning Automatic Control Timing Module (ACTM) card is replaced and o CEA 35 was realigned to 140 and CEA 35 is declared OPERABLE The earliest that the crew can re-commence the power ascension is _______(1)_______

to _________(2)________.

(1) (2)

A. 0535 minimize the effects of Xenon redistribution B. 0535 allow for clad relaxation C. 0620 minimize the effects of Xenon redistribution D. 0620 allow for clad relaxation 20

2011 Waterford 3 SRO Written Exam Question 21 Given:

The plant is at 50% power Tave and Tref are matched and stable The Standby Charging Pump Selector Switch is in AB-A Due to a PAC card failure the output of the Pressurizer Level Controller auto output failed to the high limit.

The crew entered OP-901-110, took manual control of the Pressurizer Level Controller and stabilized level at 41% (lowest level attained)

Charging Pumps B and AB are running Charging pump A _____(1)_______be running. The lowest pressurizer level the crew should maintain while operating is ______(2)______%.

(1) (2)

A. should 25 B. should NOT 25 C. should 30 D. should NOT 30 21

2011 Waterford 3 SRO Written Exam Question 22 Given:

A reactor startup is in progress Startup Channel 2 high voltage is automatically removed when power exceeds approximately _____(1)_____% on ENI Logarithmic Channel A, if the HV Control Switch in Startup Channel 2 is selected to _____(2)_____.

(1) (2)

A. 1.0 X 10-4 Primary B. 1.0 X 10-4 Alternate C. 5.3 X 10-6 Primary D. 5.3 X 10-6 Alternate 22

2011 Waterford 3 SRO Written Exam Question 23 Given:

Primary-to-Secondary leakage in Steam Generator 1 has changed over the last hour with a rate and value that requires the plant to be at 50% in one hour and MODE 3 in a total of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Waterford 3 is designed for a ramp load change of ___(1)___ %/MINUTE between 100%

and 15%; however, the target shutdown rate will be approximately ____(2)___

MW/MINUTE provided pressurizer level can be maintained.

(1) (2)

A. 10 60 B. 5 60 C. 10 30 D. 5 30 23

2011 Waterford 3 SRO Written Exam Question 24 Concerning Tech Spec Containment Integrity in Mode 1, which of the following conditions would require action within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ?

A. The Personnel Air Lock outer door is found closed and unlocked.

B. The Escape Air Lock outer door seal is failed with the operable inner door verified locked closed.

C. The Personnel Air Lock door interlocks are inoperable, allowing both doors to be open at the same time.

D. The Escape Air Lock door position indications are inoperable on CP-8 and on the Plant Monitoring Computer.

24

2011 Waterford 3 SRO Written Exam Question 25 Given:

The plant was in MODE 3 at Normal Operating Temperature and Pressure A steam line break occurs on Main Steam Line 1 outside Containment upstream of the Main Steam Isolation Valve After 5 minutes Steam Generator 1 completely blows down Representative Core Exit Thermocouple (CET) lower to 460°F Tcold lowers to 430°F With Reactor Coolant Pumps in operation ____(1)_____ should be used to monitor RCS cooldown limits. The Reactor Coolant System cooldown limits ______(2)______ been exceeded.

(1) (2)

A. Tcold have B. Tcold have NOT C. Representative CET have D. Representative CET have NOT 25

2011 Waterford 3 SRO Written Exam Question 26 Given:

RCS Tavg is 574°F and stable Letdown flow is 28 GPM All Charging Pumps are OPERABLE Annunciator Panel H Window B1, Pressurizer Level HI/LO is actuated Pressurizer level is 49% and slowly lowering Based on these conditions, pressurizer level will _______(1)_______ and the crew should _______(2)________.

(1) (2)

A. continue to lower perform a rapid shutdown B. continue to lower trip the reactor C. recover perform a rapid shutdown D. recover trip the reactor 26

2011 Waterford 3 SRO Written Exam Question 27 Given:

The reactor tripped due to a loss of offsite power On the trip, a Main Steam Safety Valve on Main Steam Line 1 opened and will not reseat Steam Generator 1 pressure is 500 PSIA and lowering Main Steam Line 1 and Blowdown Radiation Monitors are in Hi-Hi alarm RCS pressure is 1300 PSIA and lowering Pressurizer level is 0%

All engineering safeguards equipment is operable OP-902-000, Standard Post Trip Actions is being implemented After Standard Post Trip Actions are complete, the crew will implement:

A. OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery B. OP-902-004, Loss of Excess Steam Demand Recovery C. OP-902-007, Steam Generator Tube Rupture Recovery D. OP-902-008, Functional Recovery Procedure 27

2011 Waterford 3 SRO Written Exam Question 28 Given:

The reactor was at 100% power RCP 1A trips on overcurrent

__(1)__ RCP 1A Lift Oil Pump(s) started when RCP 1A __(2)__.

(1) (2)

A. One load breaker opened B. Both load breaker opened C. One speed lowered to 600 RPM D. Both speed lowered to 600 RPM 28

2011 Waterford 3 SRO Written Exam Question 29 Given:

The reactor is operating at 100% power At 0100 RCP 1A Lower Seal fails and Controlled Bleedoff flow rises to 2.5 GPM OP-901-130, Reactor Coolant Pump Malfunction is implemented and the plant remains at 100% power At 0530 RCP 1A Middle Seal fails RCP 1A Controlled Bleedoff flow went out of range high and then went to 0 GPM RCP 1A Controlled Bleedoff flow went low due to closure of ________(1)_________.

The crew should ________(2)_________ and secure RCP 1A.

(1) (2)

A. a RCP Controlled Bleedoff perform a shutdown to MODE 3 per Containment Isolation Valve OP-010-005, Plant Shutdown B. a RCP Controlled Bleedoff manually trip the reactor and Containment Isolation Valve perform Standard Post Trip Actions C. the check valve on RCP 1A perform a shutdown to MODE 3 per Controlled Bleedoff line OP-010-005, Plant Shutdown D. the check valve on RCP 1A manually trip the reactor and Controlled Bleedoff line perform Standard Post Trip Actions 29

2011 Waterford 3 SRO Written Exam Question 30 Given The plant is at 100% power VCT Level Instrument, CVC-ILT-0227 fails low CVC-183, VCT Outlet Valve closes CVC-507, RWSP to Charging Pump Suction Isolation opens The crew should enter __(1)__ and __(2)__ to match Tavg and Tref.

(1) (2)

A. OP-901-113, Volume Control lower turbine load Tank Makeup Control Malfunction B. OP-901-113, Volume Control raise turbine Load Tank Makeup Control Malfunction C. OP-901-112, Charging or Letdown lower turbine load Malfunction D. OP-901-112, Charging or Letdown raise turbine Load Malfunction 30

2011 Waterford 3 SRO Written Exam Question 31 Given:

The plant has tripped from 100% power Reactor Coolant System pressure lowered and stabilized at 1500 psia Containment Pressure is 17.3 PSIA and rising Which of the following describes the condition of the Chemical Volume Control system?

A. CVC-101, Letdown Stop Valve is open.

B. CVC-103 & CVC-109, Letdown Isolation Valves are open.

C. CC-636, Component Cooling Water to Letdown Heat Exchanger is closed.

D. Charging Pumps A, B, and AB are running.

31

2011 Waterford 3 SRO Written Exam Question 32 Given:

The plant is in Mode 4 Shutdown Cooling Train B is being placed in service What would be an acceptable manipulation to compensate for the increased heat load on the Component Cooling Water system prior to starting LPSI Pump B?

A. CC-963B, Shutdown HX B CCW Flow Control is placed to OPEN.

B. CC-963B, Shutdown HX B CCW Flow Control is placed to SETPNT.

C. Dry Cooling Tower fans are manually started in slow speed.

D. Dry Cooling Tower fans are manually started in fast speed.

32

2011 Waterford 3 SRO Written Exam Question 33 Given:

A Loss Of Cooling Accident is in progress Reactor Coolant System (RCS) pressure is 200 PSIA High Pressure Safety Injection Pump B trips shortly after starting All other equipment functions as designed The minimum required Safety Injection flow for High Pressure Safety Injection is

___(1)____ and __(2)__ is required for Low Pressure Safety Injection.

(1) (2)

A. >185 GPM total flow to no flow the cold legs B. >185 GPM total flow to >185 GPM flow to the cold legs loop 2 cold legs C. >185 GPM to each cold no flow leg D. >185 GPM to each cold >185 GPM flow to leg loop 2 cold legs 33

2011 Waterford 3 SRO Written Exam Question 34 Given Reactor Coolant System Code safety valve has been weeping for the past week Quench tank level is 81%

Quench tank temperature is 147 F Control Room Supervisor orders the ATC operator to fill and drain the Quench Tank to reduce Quench Tank temperature.

The Quench Tank will be drained to the ___(1)___ and it will be filled from the ___(2)___

system.

(1) (2)

A. Containment Sump Condensate Make Up B. Reactor Drain Tank Primary Make Up C. Containment Sump Primary Make Up D. Reactor Drain Tank Condensate Make Up 34

2011 Waterford 3 SRO Written Exam Question 35 Given:

The plant is at 100% power Emergency Diesel Generator A is running paralleled to the 3A bus in TEST Mode The Unit Auxiliary Transformer A 4.16 KV feeder breaker to the 2A bus trips on overcurrent Component Cooling Water Pump A will start on the __(1)___ Second load block of the Sequencer and will be powered from __(2) .

(1) (2)

A. 7 Emergency Diesel Generator A B. 168 Emergency Diesel Generator A C. 7 Startup Transformer A D. 168 Startup Transformer A 35

2011 Waterford 3 SRO Written Exam Question 36 Given The plant is at 100% steady state Pressurizer Pressure Controller, RC-IPIC-0100, output fails to 100%

If no operator actions are taken which of the following describes the plant response:

A. Pressurizer pressure would rise and be controlled by the spray valves at 2275 PSIA.

B. Pressurizer pressure will rise until all back up and proportional heaters secure at 2270 PSIA.

C. Pressurizer pressure would lower until the reactor trips on low Reactor Coolant System pressure.

D. Pressurizer pressure would lower until all Pressurizer heaters are energized which will maintain RCS pressure at 2225 PSIA.

36

2011 Waterford 3 SRO Written Exam Question 37 Given The Reactor Coolant System (RCS) pressure is 350 PSIA The plant is raising pressure to 2250 PSIA As RCS pressure rises above 500 PSIA the Pressurizer Pressure Operating Bypass

__(1)___ from service. The set point tracks __(2)__ below actual Reactor coolant System pressure during the pressure rise.

(1) (2)

A. must be manually removed 400 PSIA B. is automatically removed 400 PSIA C. must be manually removed 184 PSIA D. is automatically removed 184 PSIA 37

2011 Waterford 3 SRO Written Exam Question 38 Given A Safety Injection Actuation Signal (SIAS) was inadvertently actuated The CRS directs the BOP operator to reset the SIAS The SIAS initiation relays are reset at ___(1)___ and the actuation relays are reset at

___(2)___.

(1) (2)

A. CP-10 CP-33 B. CP-10 CP-10 C. CP-33 CP-33 D. CP-33 CP-10 38

2011 Waterford 3 SRO Written Exam Question 39 Given:

The plant is at 100% Power Emergency Diesel Generator A is Out of Service for Maintenance A Loss Of Off Site Power Occurs Which of the following is available to Emergency Borate the RCS?

A. Charging Pump B and Boric Acid Makeup pump B B. Charging Pump A and Boric Acid Make up pump A C. Charging Pump B and Gravity Feed Valve BAM-113A D. Charging Pump A and Gravity Feed Valve BAM-113B 39

2011 Waterford 3 SRO Written Exam Question 40 Plant Conditions are as follows:

Power is 100%, 300 EFPD Reactor Power Cutback is in service with subgroups 5 and 11 selected A Shutdown Bank CEA drops into the core The crew entered OP-901-102, CEA or CEDMCS Malfunction Subsequently conditions are as follows:

Power is 80%

Main Feedwater pump A trips on overspeed Based on this event, the crew should A. Remain in OP-901-102 and perform OP-901-101, Reactor Power Cutback concurrently.

B. Trip the reactor, exit OP-901-102, and enter OP-902-000, Standard Post Trip Actions.

C. Remain in OP-901-102 and adjust turbine load to maintain Tavg -Tref matched.

D. Exit OP-901-102 and enter OP-901-101, Reactor Power Cutback.

40

2011 Waterford 3 SRO Written Exam Question 41 Given:

Reactor Coolant System pressure is 1600 PSIA Containment pressure is 17.5 PSIA and rising The crew has diagnosed into OP-902-002, Loss of Coolant Accident Recovery Component Cooling Water (CCW) Pumps A and B are running The BOP operator reports that Containment Fan Cooler A has tripped. Which action is required?

A. Place CCW AB Assignment Switch in the A position and manually start CCW Pump AB.

B. Override and close the Containment Fan Cooler A Component Cooling Water isolation valves.

C. Verify Containment Cooling Safety Damper, CCS-102A, closed when CFC A tripped.

D. Verify Containment Spray flow is greater than 1750 GPM for both trains of Containment Spray.

41

2011 Waterford 3 SRO Written Exam Question 42 Given the following:

A Loss of Coolant Accident has occurred Reactor Coolant System pressure is 700 PSIA Containment pressure is 18 PSIA Refueling Water Storage Pool level is 9% and lowering No operator actions have been taken Low Pressure Safety Injection pumps A and B are running High Pressure Safety Injection pumps A and B are running Based on the given conditions the Balance of Plant operator should:

A. Close SI-602A and B, ESF Pump Suction Valves from the SI Sump.

B. Open SI-120A and B, SI Pumps Recirculation Isolation Valves.

C. Secure High Pressure Safety Injection Pumps A and B.

D. Secure Low Pressure Safety Injection Pumps A and B.

42

2011 Waterford 3 SRO Written Exam Question 43 Given:

Reactor Coolant System Tcold is 500 F and lowering 15 minutes ago the Reactor Coolant System Tc was 515 F when a controlled cool down was established The cool down is being controlled using MS-319A, Main Steam Bypass 1A, at 15% open IF MS-319A failed open, the maximum allowed cool down rate of ___(1)____ which protects the ___(2)__________, would be exceeded.

(1) (2)

A. 60 F/Hr The most limiting component in Reactor Coolant System under all conditions B. 60 F/Hr SG tube sheet from cyclic stress which is the most limiting component under all conditions C. 100 F/Hr SG tube sheet from cyclic stress which is the most limiting component under all conditions D. 100 F/Hr The most limiting component in Reactor Coolant System under all conditions 43

2011 Waterford 3 SRO Written Exam Question 44 Given The plant is performing an up power Dilution to the Volume Control Tank is in progress for power ascension Reactor Power is 70%

Turbine is in GO with a rate of 2MW/MIN Tave is 565 F Tref is 561 F To match Tave and Tref, The BOP operator should ____(1)_____ the rate the Main Turbine governor valves open. To accomplish this task, the BOP operator is required to

___(2)________.

(1) (2)

A. raise depress LOAD RATE pushbutton, entering new value, and press ENTER B. raise place the Main Turbine in HOLD, depress LOAD RATE pushbutton, enter new value, and push GO C. lower depress LOAD RATE pushbutton, entering new value, and press ENTER D. lower place the Main Turbine in HOLD, depress LOAD RATE pushbutton, enter new value, and push GO 44

2011 Waterford 3 SRO Written Exam Question 45 Plant Conditions are as Follows:

Power is 100%

SG-ILR-1111, Steam Generator 1 Narrow Range level indicator is reading 0% on the CP-1 recorder SG-ILR-1105, Steam Generator 1 Narrow Range level indicator is reading 68%

on the CP-1 recorder All Narrow Range Steam Generator levels on CP-7 are indicating 68%

A reactor trip occurs All systems performed as designed before and after the trip The expected post trip responses to these conditions are that FW IHIC 1107 Main Feedwater Pump A speed controller ___(1)___ and FW IHIC1111, Main Feedwater Regulating Valve A and FW IHIC1105 Startup Feedwater Regulating Valve A Controller

__(2)___.

(1) (2)

A. lowers to 3900 RPM remain at their pre trip positions B. lowers to 3900 RPM reposition to their Reactor Trip Positions C. remains at 4500 RPM remain at their pre trip positions D. remains at 4500 RPM reposition to their Reactor Trip Positions 45

2011 Waterford 3 SRO Written Exam Question 46 The EFW system is designed to prevent ________(1)_______ by providing lines with an orifice from the Main Feedwater discharge headers to the EFW ____(2)____ piping.

(1) (2)

A. feed ring thermal stress suction B. feed ring thermal stress discharge C. EFW piping damage suction D. EFW piping damage discharge 46

2011 Waterford 3 SRO Written Exam Question 47 Static Uninterruptable Power Supply SMA requires maintenance to the inverter section requiring the Inverter to be secured.

Other SUPS SMA components are not affected by maintenance.

Will the AC loads remain powered up with the Inverter de energized?

A. Yes, loads will be powered from the Normal AC supply through the rectifier.

B. Yes, loads will be powered from the DC supply through the rectifier.

C. Yes, loads will be powered from the Bypass AC supply.

D. No, PDP SMA must be de energized to support this maintenance.

47

2011 Waterford 3 SRO Written Exam Question 48 Given:

The plant is at 100% power The RAB watch reports that the AB battery bus indicates a positive 125 volt DC ground.

An additional ___(1)___ ground of the same magnitude on the AB battery bus, would require implementing OP-901-313, Loss of a 125 Volt DC Bus. This will ____(2)___.

(1) (2)

A. negative make Emergency Feedwater Pump AB unavailable and TS 3.7.1.2 must be addressed B. negative require the crew to manually trip the reactor if bus AB-DC can not be restored C. positive make Emergency Feedwater Pump AB unavailable and TS 3.7.1.2 must be addressed D. positive require the crew to manually trip the reactor if bus AB-DC can not be restored 48

2011 Waterford 3 SRO Written Exam Question 49 Given:

Reactor Coolant System Pressure is 1600 PSIA and lowering slowly Containment pressure is 19 PSIA and rising A Loss Of Offsite Power has occurred Five minutes into this event Emergency Diesel Generator A tripped on Overspeed What of the following describes the MINIMUM actions required to maintain containment integrity?

A. CS-125A, Containment Spray Header Isolation, must be closed by taking the CP-8 control switch to CLOSE only.

B. CS-125A, Containment Spray Header Isolation, must be closed by taking the CP-8 control switch to OPEN and then to CLOSE only.

C. CS-125A, Containment Spray Header Isolation, must be closed by taking the override switch in the +35 Relay Room to OVERRIDE only.

D. CS-125A, Containment Spray Header Isolation, must be closed by taking the override switch in the +35 relay room to OVERRIDE, followed by taking the CP-8 control switch to OPEN and then to CLOSE.

49

2011 Waterford 3 SRO Written Exam Question 50 Given:

An earthquake has occurred at Waterford 3 A loss of offsite power has occurred .

Emergency Diesel Generator A and B have started to supply in house loads A support beam in the A Emergency Diesel Generator room has fallen on and damaged both Air compressors A1 and A2 Both air receiver pressures are 0 PSIG.

Emergency Diesel Generator A develops an oil leak requiring it to be shutdown.

What action is required to shutdown Emergency Diesel Generator A?

A. Depress the Emergency Shutdown push buttons on CP-1.

B. Select STOP on the local Emergency Diesel Generator control panel.

C. Pull the Overspeed Trip Plunger located on the Overspeed Governor.

D. Pull and hold the manual Fuel Rack Override lever to the no fuel position.

50

2011 Waterford 3 SRO Written Exam Question 51 Given:

A Main Steam Line break has occurred inside containment Safety Injection Actuation Signal, Containment Isolation Actuation Signal, Main Steam Isolation Signal and, Containment Spray Actuation are all actuated The crew has entered OP-902-004, Excess Steam Demand Recovery Containment Temperature is 204 F ARM-IRE 5400A and ARM-IRE-5400B, Containment High Range Radiation Monitors alarmed 15 minutes into the event and radiations levels are trending down No other Containment Radiation monitors are in alarm For the given conditions the crew should:

A. Remain in OP-902-004 and monitor the Containment radiation monitors for thermally induced current effects.

B. Enter OP-901-403, High Airborne Activity inside Containment, and perform concurrently with OP-902-004.

C. Take no action since these area monitors are isolated on a CIAS and are unreliable.

D. Enter OP-902-008, Functional Recovery, due to high activity in Containment.

51

2011 Waterford 3 SRO Written Exam Question 52 Given A Loss Of Coolant Accident is in Progress Loss Of Off Site Power has occurred Emergency Diesel Generator A has tripped on overspeed Component Cooling Water temperature is 98 °F and rising B Train Dry Cooling Tower Fans 1-4 are operating in Fast Speed B Train Dry Cooling Tower Fans 5-15 are operating in Slow Speed As Component Cooling Water System temperature continues to rise, Dry Cooling Tower B fans 5-15 will start simultaneously in FAST speed when temperature rises above (1) . The fans will start cycling to SLOW when system temperature drops below (2) .

(1) (2)

A. 100 °F 92 °F B. 115 °F 92 °F C. 100 °F 88 °F D. 115 °F 88 °F 52

2011 Waterford 3 SRO Written Exam Question 53 Given Dry Cooling Tower fans 7B and 2B are out of service.

Outside air temperature is 92 °F.

Wet Bulb temperature is 73 °F.

What is the most limiting time to restore Dry Cooling Tower fans to comply with Tech Spec 3.7.4?

A. 1 Hour B. 2 Hour C. 72 Hour D. 7 Days 53

2011 Waterford 3 SRO Written Exam Question 54 Given the following conditions:

Instrument Air Header pressure has lowered to 100 psig due to a leak SA-125, Station Air Backup is at its normal setpoint SA-125 is _________ and SA-123, Air Dryer Bypass is _________.

A. OPEN, OPEN B. CLOSED, OPEN C. OPEN, CLOSED D. CLOSED, CLOSED 54

2011 Waterford 3 SRO Written Exam Question 55 Given:

The plant is in Mode 6 Core alterations are in progress The Reactor Auxiliary Building watch reports that train A Main Steam Line Bellows has been removed from the containment penetration for replacement Control room staff verified that the Bellows work is not being tracked by a containment impairment Containment integrity is _ (1) _. The crew should __(2)__.

(1) (2)

A.

met immediately suspend core alterations B. met isolate the affected penetration within 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months or suspend core alterations C. not met isolate the affected penetration within 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months or suspend core alterations D. not met immediately suspend core alterations 55

2011 Waterford 3 SRO Written Exam Question 56 To cool the magnetic jack coils of the CEDM System, Control Element Drive Cooling System air flows (1) rejecting the CEDM Cooling System heat to the (2) System.

(1) (2)

A. across the CEDM coils and then Component Cooling Water through the CEDM coolers, B. through the CEDM coolers then Component Cooling Water across the CEDM coils, C. across the CEDM coils and then Reactor Cavity Cooling through the CEDM coolers, D. through the CEDM coolers then Reactor Cavity Cooling across the CEDM coils, 56

2011 Waterford 3 SRO Written Exam Question 57 Given A small break loss of coolant accident is in progress A Safety Injection Actuation Signal (SIAS) has occurred Voids in the Reactor Coolant System (RCS) are indicated The CRS directs the NPO to vent non-condensable gases from the Reactor Vessel Head The Reactor Vessel Head Vent valves ________(1)________. The Reactor Vessel Head is vented to the ____(2)____.

(1) (2)

A. can not be opened until SIAS is reset Quench Tank B. must be energized from CP-8 and the Quench Tank valves can then be opened C. can not be opened until SIAS is reset Reactor Drain Tank D. must be energized from CP-8 and the Reactor Drain Tank valves can then be opened 57

2011 Waterford 3 SRO Written Exam Question 58 Given Plant is at 100% power steady state conditions Static Uninterruptable Power Supply SMA fails Core Protection Calculator A and ____(1)____ deenergize. TCB 1, 2, 5, and 6 Open and the reactor ___(2)___.

(1) (2)

A. Linear Channel A trips B. Control Channel #1 does not trip C. Linear Channel A does not trip D. Control Channel #1 trips 58

2011 Waterford 3 SRO Written Exam Question 59 Given the following conditions A Loss Of Coolant Accident has occurred Which of the following describes the temperature when Zr-Water reaction becomes self sustaining?

A. 1800 F B. 2200 F C. 3350 F D. 5080 F 59

2011 Waterford 3 SRO Written Exam Question 60 The containment atmosphere Hydrogen Analyzer takes a suction from ___(1)____ and provides indication of Hydrogen concentration on CP-____(2)______

(1) (2)

A. Below the Missile Shield 33 B. Lower Reactor Cavity 8 C. Below the Missile Shield 8 D. Lower Reactor Cavity 33 60

2011 Waterford 3 SRO Written Exam Question 61 Given CCW Surge Tank Level Switch CC-ILS-7013A failed low.

CC-200A/727, CCW Hdr A TO AB Supply and Return Isolations, failed closed.

CC-134 A, CCW A Dry Cooling Tower Bypass failed open.

CC-135 A, CCW A Dry Cooling Tower Isolation, failed closed.

Both Train A and Train B CC-620, Fuel Pool Heat Exchanger Temperature Control Valve, control switches are in the CONTROL position at CP-18.

Based on this level switch failure, A. Spent Fuel Pool temperature will rise since CC-620 failed closed.

B. Spent Fuel Pool temperature will lower since CC-134 A, CCW A Dry Cooling Tower Bypass failed open.

C. Spent Fuel Pool temperature will rise since CC-135 A, CCW A Dry Cooling Tower Isolation, failed closed.

D. Spent Fuel Pool temperature is controlled in automatic since the Train B CC-620 control switch is in CONTROL.

61

2011 Waterford 3 SRO Written Exam Question 62 Given The Reactor tripped from 100% power OP-902-000, Standard Post Trip Actions, has been entered and is being performed Reactor Coolant System (RCS) pressure is 2115 PSIA and rising One Control Element Assembly is stuck out Reactor power is 10-4% and lowering Steam Generator 1 level is 25% NR and lowering Steam Generator 2 level is 29% NR and lowering Pressurizer level is 28% and rising 3 Charging pumps are operating Steam Generator 1 and 2 pressures are 950 PSIA All ESFAS systems are in standby Based on the given conditions the Reactor Operator should _____________________.

A. commence emergency boration B. secure Charging pump AB C. take manual control of RCS pressure and control between 2125 to 2275 PSIA D. manually initiate Emergency Feedwater Actuation Signal for Steam Generator 1 62

2011 Waterford 3 SRO Written Exam Question 63 The following plant conditions exist:

300 EFPD The plant is at 15% power following a mid cycle outage startup The Main Turbine in on line with the Speed Loop in service Spurious operation of the Steam Bypass Control System resulted in MS-319 A, Main Steam Bypass 1A and MS-320 A, Main Steam Bypass 2A opening Which of the following parameters will be lower after the event than before the event?

A. Steam Generator pressure B. Reactor power C. RCS THOT temperature.

D. Main Steam flow 63

2011 Waterford 3 SRO Written Exam Question 64 Given Plant is 100% Power A Waste Condensate Tank is being discharged A power supply on PRM-IRE-0647 Liquid Waste Management Radiation Monitor fails As a result of this failure ___(1)___ and ___(2)___.

(1) (2)

A. LWM-441, Liquid Waste to LWM-442, Liquid Waste to Circulating Water Shutoff Circulating Water Control Valve, Valve, closes remains open B. LWM-441, Liquid Waste to LWM-442, Liquid Waste to Circulating Water Shutoff Circulating Water Control Valve, Valve, closes closes C. LWM-441, Liquid Waste to LWM-442, Liquid Waste to Circulating Water Shutoff Circulating Water Control Valve, Valve, remains open remains open D. LWM-441, Liquid Waste to LWM-442, Liquid Waste to Circulating Water Shutoff Circulating Water Control Valve, Valve, remains open closes 64

2011 Waterford 3 SRO Written Exam Question 65 Given Fire alarms are received for the +35 Cable Vault area.

The Fire Brigade leader has reported that the automatic deluge actuation has failed and the fire is not under control.

The Control Room Supervisor has entered OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown.

The Control Room Supervisor has directed the immediate actions be completed and the Control Room evacuated.

Based on the given conditions the AT-THE-CONTROLS Operator will (1) and (2) .

(1) (2)

A. trip 2 Reactor Coolant Pumps secure Charging and Letdown B. trip 2 Reactor Coolant Pumps start all available Charging Pumps C. trip all 4 Reactor Coolant Pumps secure Charging and Letdown D. trip all 4 Reactor Coolant Pumps start all available Charging Pumps 65

2011 Waterford 3 SRO Written Exam Question 66 Per OI-024-000, Maintaining Active SRO/RO Status, to maintain your Reactor Operator license in an ACTIVE status, you must stand a minimum of ______(1)_______ 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts in a calendar quarter. To upgrade from INACTIVE status to ACTIVE status, a license holder must stand _______(2)________ hours of under instruction watches.

(1) (2)

A. five 40 B.

seven 40 C.

five 60 D.

seven 60 66

2011 Waterford 3 SRO Written Exam Question 67 In accordance with EN-OP-102, Protection and Caution Tagging, __________________

should have double valve isolation and tagging applied during removal and replacement of the component.

A. Instrument Air Compressor A Unloader Valve B. Turbine Cooling Water pump A C. Containment Fan Cooler C Cooling Coils D. Hydrogen Excess Flow Control Valve 67

2011 Waterford 3 SRO Written Exam Question 68 Given:

The plant is in MODE 6 The Upper Guide Structure is removed Core offload is suspended Reactor Cavity Level is 44 ft MSL The plant has been shutdown for 200 Hours

______(1)______ train(s) of Shutdown Cooling must be OPERABLE and Shutdown Cooling flow must be at least _____(2)______ GPM.

(1) (2)

A. One 2000 B. Two 2000 C. One 3000 D. Two 3000 68

2011 Waterford 3 SRO Written Exam Question 69 Given The plant is at 100% Power At 0100, the BOP operator bypasses the Channel C High LPD and Low DNBR trip bistables for a scheduled 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months I&C surveillance on Channel C Core Protection Calculator.

The I&C technician informs the CRS that the CPC has failed the surveillance and will require a card replacement.

Operability will be tracked by ___(1)___ when the work begins. The Shift Manager will authorize operability following retest on ___(2)___.

(1) (2)

A. the work package OP-100-010, Att. 7.1, TS/TRM Entry Guidelines B. OP-100-010, Att. 7.1, OP-100-010, Att. 7.2, EOS TS/TRM Entry Guidelines, Checklist C. the work package OP-100-010, Att. 7.2, EOS Checklist D. OP-100-010, Att. 7.1, OP-100-010, Att. 7.1, TS/TRM TS/TRM Entry Guidelines, Entry Guidelines 69

2011 Waterford 3 SRO Written Exam Question 70 The Peak Centerline Temperature safety limit for new fuel with no burnable poison is

____(1)______°F. Per TS 2.2.1, Reactor Trip Setpoints, a steady state peak linear heat rate of ___(2)___ has been selected as the Limited Safety System Setting to prevent fuel centerline melt.

(1) (2)

A. 5080 12.9 KW/Ft B. 5080 21.0 KW/Ft C. 5022 12.9 KW/Ft D. 5022 21.0 KW/Ft 70

2011 Waterford 3 SRO Written Exam Question 71 Given the following:

The plant is at 10% Power A containment entry is desired Which of the following areas inside containment are forbidden from being entered?

A. Pressurizer Cubicle below +21 elevation B. +46 elevation at the Quench Tank C. Main Steam Line Crossovers on the +46 elevation D. 1A Cold Leg penetration through the D Ring Wall 71

2011 Waterford 3 SRO Written Exam Question 72 A high activity detected by the Industrial Waste Sump Radiation Monitor results in the discharge path of Industrial Waste Sump 2 pumps swapping from _______(1)________

to ______(2)_______.

A. (1) Industrial Waste Sump 1 (2) Waste Tanks B. (1) Industrial Waste Sump 1 (2) RAB Oil Sump 3 C. (1) Oil Separator Sump (2) Waste Tanks D. (1) Oil Separator Sump (2) RAB Oil Sump 3 72

2011 Waterford 3 SRO Written Exam Question 73 To verify Core Heat Removal during Standard Post Trip Actions, the ATC should check RCS Loop Delta T for _______(1)________ and check Th Subcooling only when on

______(2)_____ circulation.

(1) (2)

A. loops with an forced operating RCP B. all loops forced C. loops with an natural operating RCP D. all loops natural 73

2011 Waterford 3 SRO Written Exam Question 74 When an Emergency Plan classification is upgraded from an Unusual Event to an Alert and no site evacuation is required, ________(1)________ must be notified within

_____(2)_____ minutes of the upgrade.

(1) (2)

A. US Coast Guard 15 B. Waterford 1 & 2 15 C. US Coast Guard 60 D. Waterford 1 & 2 60 74

2011 Waterford 3 SRO Written Exam Question 75 Given:

A Control Room Evacuation is in progress due to a fire in CP-2.

Immediate Actions of OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown, have been completed The BOP is currently performing Attachment 4, BOP Time Critical Actions After completion of the attachment, only the ____(1)____ 4.16 KV Safety bus will be energized and the bus will be loaded through the _____(2)_____ sequencer.

(1) (2)

A. A3 mini B. A3 normal C. B3 mini D. B3 normal END OF RO SECTION CONTINUE TO SRO SECTION 75

2011 Waterford 3 SRO Written Exam SRO Question 1 Given:

A planned Reactor Coolant System (RCS) cooldown is in progress RCS pressure is 350 psia Shutdown Cooling (SDC) Trains A and B are in service Component Cooling Water (CCW) Surge Tank A and B levels are rising CCW Radiation Monitors AB and B are in Alert Alarm and rising CCW Radiation Monitor A is in High Alarm Pressurizer level is being maintained at setpoint by Charging and Letdown Which of the following describes:

1) The potential source of the leak?

2) The action required per OP-901-411, High Activity in Component Cooling Water System?

(1) (2)

A. Low Pressure Safety Injection GO TO OP-901-111, Reactor Coolant Pump A seal cooler System Leak B. Low Pressure Safety Injection GO TO OP-901-111, Reactor Coolant Pump B seal cooler System Leak C. Low Pressure Safety Injection Refer to Attachment 1, Auxiliary Pump A seal cooler Equipment Supplied by CCW, secure affected Low Pressure Safety Injection Pump, and isolate CCW to seal cooler D. Low Pressure Safety Injection Refer to Attachment 1, Auxiliary Pump B seal cooler Equipment Supplied by CCW, secure affected Low Pressure Safety Injection Pump, and isolate CCW to seal cooler 76

2011 Waterford 3 SRO Written Exam SRO Question 2 Given:

The Plant was operating at 100% with all safety related equipment OPERABLE when a reactor trip is initiated due to a Steam Generator Tube Rupture in Steam Generator 1 OP-902-007, Steam Generator Tube Rupture Recovery was entered When the Control Room Supervisor reaches the step to implement the Placekeeper a Loss of Offsite Power occurs Emergency Diesel Generator B trips on Overspeed The rapid cooldown to Thot of 520°F will be performed in accordance with

_________(1)___________, using the Atmospheric Dump Valve(s) on ____(2)____

Steam Generator(s).

(1) (2)

A. OP-902-007, Steam Generator the unaffected Tube Rupture Recovery B. OP-902-007, Steam Generator both Tube Rupture Recovery C. OP-902-008, Functional Recovery the unaffected D. OP-902-008, Functional Recovery both 77

2011 Waterford 3 SRO Written Exam SRO Question 3 The following plant conditions exist:

The plant was operating in Mode 3 A Main Steam line break occurs S/G 1 pressure is 650 PSIA and very slowly lowering S/G 2 pressure is 300 PSIA and lowering The crew is performing OP-902-004, Excess Steam Demand Recovery Based on these conditions, the CRS should stabilize RCS Temperature by directing the BOP operator to fully open (1) when (2) starts to rise.

(1) (2)

A. ADV 1 and feed S/G 1 with EFW in CET temperatures and manual Pressurizer pressure B. ADV 1 and feed S/G 1 with EFW in S/G 2 level reaches 10%

manual WR and S/G 1 pressure C. ADV 2 and feed S/G 2 with EFW in CET temperatures and manual Pressurizer pressure D. ADV 2 and feed S/G 2 with EFW in S/G 2 level reaches 10%

manual WR and S/G 1 pressure 78

2011 Waterford 3 SRO Written Exam SRO Question 4 Given:

The plant is at the Point of Adding Heat, preparing to start the first Feedwater Pump Feedwater Pump A is being warmed up in accordance with, OP-003-033, Main Feedwater; the Feedwater Pump Casing to Feedwater T is 100°F The Auxiliary Feedwater Pump trips on overcurrent and can not be restarted The crew manually trips the reactor and Emergency Feedwater Actuation Signal 1 and 2 occur Emergency Feedwater Pump AB trips on overspeed and can not be restored The crew should GO TO ____________(1)___________. To conserve Steam Generator inventory ___(2)___ Reactor Coolant Pumps should be secured.

(1) (2)

A. OP-902-000, Standard Post Trip Actions Two and then transition to OP-902-006, Loss of Main Feedwater Recovery B. OP-902-000, Standard Post Trip Actions All and then transition to OP-902-006, Loss of Main Feedwater Recovery C. OP-902-006, Loss of Main Feedwater Two Recovery directly D. OP-902-006, Loss of Main Feedwater All Recovery directly 79

2011 Waterford 3 SRO Written Exam SRO Question 5 Given:

The plant is in MODE 1 All SUPS are in a normal alignment Battery Charger A1 is Out of Service due to a previous High Voltage Shutdown The normal AC input to SUPS MA trips open These conditions require that _________(1)__________ be restored within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to prevent _______(2)________.

(1) (2)

A. BOTH the SUPS A Rectifier and battery discharge Battery Charger A1 B. BOTH the SUPS A Rectifier and damage to the rectifier Battery Charger A1 assembly C. EITHER the SUPS A Rectifier OR battery discharge Battery Charger A1 D. EITHER the SUPS A Rectifier OR damage to the rectifier Battery Charger A1 assembly 80

2011 Waterford 3 SRO Written Exam SRO Question 6 Given:

Generator load is currently 1230 MWe and 100 MVARs Out Waterford 3 offsite grid parameters are within the prescribed operating ranges To maintain the grid stable, the Systems Operation Center (Pine Bluff) issues a formal request to the Shift Manager to adjust Reactive Load within the allowable limits to lower grid voltage as soon as possible, not to exceed 30 minutes The CRS should implement OP-901-314, Degraded Grid Conditions, Section

_________(1)__________. The administrative limit for Reactive Load that applies when lowering Main Generator voltage is ______(2)______.

(1) (2)

A. E1, Response to Degraded Grid 400 MVARs Out B. E2, Response to Transmission 400 MVARs Out Loading Relief Request C. E1, Response to Degraded Grid 75 MVARs In D. E2, Response to Transmission 75 MVARs In Loading Relief Request 81

2011 Waterford 3 SRO Written Exam SRO Question 7 Given The plant is in MODE 3 Reactor Power is 5 X 10-7% power The following operating bypasses are enabled on all channels:

o CPC Trip Bypass o Reactor Coolant Flow Low Trip Bypass o High SG Level Trip Bypass The middle detector for Excore Instrument Channel A has failed low In addition to bypassing the trip bistables for Hi Log Power, Hi Local Power, and Low DNBR on Channel A, the trip bistable(s) for ________________ must also be bypassed due to the loss of the __(2)__% bistable.

(1) (2)

A. SG Lo Flow 10-4 B. Hi SG-1 and 2 Level 10-4 C. SG Lo Flow 65 D. Hi SG-1 and 2 Level 65 82

2011 Waterford 3 SRO Written Exam SRO Question 8 Initial conditions:

Fuel movement was in progress Containment Purge was aligned for service under the Continuous Release Permit Current conditions:

An irradiated fuel assembly is significantly bent due to a Containment Upender malfunction Large bubbles are noted coming to the surface of the Reactor Cavity The Refueling Machine Radiation Monitor, ARM-IRE-5013 is in Hi-Hi Alarm All other radiation monitors servicing the Containment have risen but have not reached an alarm condition No RAB radiation monitors are in an alarm condition Containment Purge _______(1)__________. After entering the appropriate offnormal procedure the CRS will initiate action to __________(2)___________.

(1) (2)

A. remains in service isolate the Control Room Envelope B. isolated isolate the Control Room Envelope C. remains in service complete OP-901-131, Shutdown Cooling Malfunction, Attachment 1, Containment Closure Checklist D. isolated complete OP-901-131, Shutdown Cooling Malfunction, Attachment 1, Containment Closure Checklist 83

2011 Waterford 3 SRO Written Exam SRO Question 9 Given:

The plant is at 90% and performing a power reduction from 100% due to lowering condenser vacuum Per OP-901-220, Loss of Condenser Vacuum, the reactor will be tripped if condenser vacuum is approaching ___(1)____ Inches Hg. The crew will _________(2)_________.

(1) (2)

A. 14 perform OP-902-000, Standard Post Trip Actions, concurrently with OP-901-220 B. 20 perform OP-902-000, Standard Post Trip Actions, concurrently with OP-901-220 C. 14 go to OP-902-000, Standard Post Trip Actions, exit OP-901-220 D. 20 go to OP-902-000, Standard Post Trip Actions, exit OP-901-220 84

2011 Waterford 3 SRO Written Exam SRO Question 10 Given:

The plant is in MODE 4 A large leak on Train A Component Cooling Water (CCW) Supply Header resulted total isolation of the AB CCW Header Prior to isolation, all Component Cooling Water components and support systems were OPERABLE The ATC Operator notes that CCW AB Radiation Monitor is flashing light blue on CP-6 Radiation Monitoring CRT after the isolation CCW AB radiation monitor should be considered _____(1)______. The radiation monitor is ______(2)______ for the given MODE.

(1) (2)

A. INOPERABLE not required to be OPERABLE B. INOPERABLE required to be OPERABLE C. OPERABLE not required to be OPERABLE D. OPERABLE required to be OPERABLE 85

2011 Waterford 3 SRO Written Exam SRO Question 11 Given:

Mode 1 100% Power RCP 1B THRUST BRNG TEMPERATURE HI annunciator is in alarm RCP 1B Motor Lube Oil Reservoir Cooler CCW return temperature is rising.

RCP 1B Motor Oil Cooler Differential Temperature is 27 F and rising PMC and CP-2 indication for RCP 1B UPR THRST BRG TEMP indicates 228 F and rising CCW temperature has been lowered from 90 F to 76 F over the past 90 minutes The CRS should:

A. Trip the reactor, secure RCP 1B, and enter OP-902-000, Standard Post Trip Actions.

B. Make the required notifications only (Duty Plant Manager and Systems Engineering).

C. Start an ACCW pump only, while continuing to cool down CCW to 70 F in the next 30 minutes.

D. Start RCP 1B Oil Lift Pump A or B only, while monitoring thrust bearing temperature.

86

2011 Waterford 3 SRO Written Exam SRO Question 12 Given:

Plant is at 100% Power Component Cooling Water Pump B trips Attempts to start AB Component cooling water pump were unsuccessful Which of the following will be performed:

A. Split out Component Cooling Water Headers and isolate the AB header from Train A to protect Train A cooled components.

B. Split out Component Cooling Water Headers, isolate the AB header from Train B, verify selected Train B components secured.

C. Trip the reactor, secure Reactor Coolant Pumps, and enter OP-902-000, Standard Post Trip Actions.

D. Verify Containment Fan Coolers B and D are operating and Containment Average Temperature is maintained within limits.

87

2011 Waterford 3 SRO Written Exam SRO Question 13 Given:

The plant is at 100% power RC-IPR-0100, Pressurizer Pressure Channels X and Y, indicate 2225 PSIA and lowering on CP-2 RC-IPIC-0100, Pressurizer Pressure Controller output is 0%

Both RC-301A(B), Pressurizer Spray Valves are open The CRS should order the ATC to take manual control of RC-IHIC-0100, Pressurizer Spray Valve Controller, adjust output to __(1)__%, and enter OP-901-120, Pressurizer Pressure Control Malfunction, Section __(2)__.

(1) (2)

A. 0 E-3, Pressurizer Spray Valve Malfunction B. 0 E-1, Pressurizer Pressure Control Channel Instrument Failure C. 100 E-3, Pressurizer Spray Valve Malfunction D. 100 E-1, Pressurizer Pressure Control Channel Instrument Failure 88

2011 Waterford 3 SRO Written Exam SRO Question 14 Given:

The plant is at normal steady state 100% power Annunciator N-2, Cabinet M, SG 1 FW ISOL VLV ACCU PRES LO is received on CP-8 The white light on the test switch is illuminated An NAO is dispatched to the +46 wing area and reports the following:

MFIV 1 Accumulator A pressure reads 4700 PSIG MFIV 1 Accumulator B pressure reads 4970 PSIG What actions are required as a result of these accumulator pressures?

A. The MFIV is inoperable due to the low accumulator pressure, enter TS 3.7.1.6.

B. Re-pressurize Accumulator A above the alarm set point within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and enter TS 3.6.3.

C. The MFIV is operable. Re-pressurize Accumulator A if desired.

D. Enter a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months administrative time limit to restore Accumulator A pressure to an acceptable pressure.

89

2011 Waterford 3 SRO Written Exam SRO Question 15 Given Reactor tripped CEA 1 stuck out Start up rate is negative Pressurizer level 28% and rising 1A and 1B Buses are de-energized 2A and 2B Buses are de-energized A Emergency Diesel Generator tripped on over speed B Emergency Diesel Generator is supplying the 3B Bus A and B 125 VDC buses are energized Which of the following procedures should be implemented?

A. OP-902-003, Loss Of Off Site Power/Loss Of Forced Circulation Recovery B. OP-902-006, Loss of Main Feedwater Recovery C. OP-902-005, Station Blackout Recovery D. OP-902-008, Functional Recovery 90

2011 Waterford 3 SRO Written Exam SRO Question 16 Given The reactor is operating at 50% and power ascension is in progress Pressurizer Level Channels X and Y are at setpoint at 41%

Charging Pump A is running with Charging Pumps B and AB in standby Letdown flow is 40 GPM with Normal Letdown Flow Control Valve and Backpressure Regulating Valve in service Charging flow is 44 GPM The Main Turbine load is rising at 10 MW/MINUTE The Charging Pump Header Flow Lo and Charging pump A Trip Trouble alarms were just received, Charging flow indicates 0 GPM.

RCS Pressure is 2245 PSIA and lowering slowly Pressurizer Level Channels X and Y are at 39% and lowering slowly Letdown flow control valve controller output is at 35%

Normal letdown flow indicates 0 GPM Regenerative Heat Exchanger outlet temperature is 475 F The CRS should direct entry into __(1)__ and __(2)__

(1) (2)

A. OP-901-112, Charging or verify first backup charging pump Letdown Malfunction starts at a level deviation of 3.9%

B. OP-901-112, Charging or stop all Turbine load changes Letdown Malfunction C. OP-901-110, Pressurizer verify first backup charging pump Level Control Malfunction starts at a level deviation of 3.9%

D. OP-901-110, Pressurizer stop all Turbine load changes Level Control Malfunction 91

2011 Waterford 3 SRO Written Exam SRO Question 17 Which of the following equipment has a technical specification related surveillance that is required to be performed as part of the Pre-core Alteration Checklist?

A. New Fuel Elevator B. Fuel Transfer Machine C. Fuel Handling Building Crane D. Spent Fuel Handling Machine 92

2011 Waterford 3 SRO Written Exam SRO Question 18 Given The plant was at 100% power Reactor Power Cutback was in service The Main Turbine tripped on over speed The CRS should implement __(1)__. CEA Transient Insertion Limits may be exceeded for __(2)__ hours before entry into Technical Specification 3.1.3.6 is required.

(1) (2)

A OP-901-001, Reactor Power Cutback only 2 B OP-901-001, Reactor Power Cutback and OP-901-210, 2 Turbine Trip concurrently C OP-901-001, Reactor Power Cutback only 4 D OP-901-001, Reactor Power Cutback and OP-901-210, 4 Turbine Trip concurrently 93

2011 Waterford 3 SRO Written Exam SRO Question 19 Given:

The plant was performing initial power ascension following a refueling outage 12 hrs ago the plant commenced raising power from 50% at a steady rate of 2%/hour At 72% power, two Control Element Assemblies in Regulating Group 6 drop and the crew performs a manual reactor trip If the plant performed a startup and power ascension and reached 70% power five days later, the power ascension limit in effect should be ___(1)___ to prevent fuel damage due to _________(2)_________.

(1) (2)

A. 3%/hour pellet clad interaction B. 3%/hour radial power peaking C. 30%/hour pellet clad interaction D. 30%/hour radial power peaking 94

2011 Waterford 3 SRO Written Exam SRO Question 20 Given:

A full core offload is in progress.

The Normal Spent Fuel Pool Heat Exchanger is in service.

The Backup Spent Fuel Pool Heat Exchanger is secured and available.

The RAB Watch has reported a leak on the Normal Spent Fuel Pool Heat Exchanger that requires isolating CCW to the Heat Exchanger.

Based on this report, A. The full core off load may continue after placing the Backup SFPHX provided Spent Fuel Pool temperature is maintained < 140 °F.

B. The full core off load may continue after placing the Backup SFPHX provided Spent Fuel Pool temperature is maintained < 155 °F.

C. The full core off load must be secured. Both the Normal and Backup Heat Exchangers are required to be available to perform a full core off load.

D. The full core off load must be secured until a heat load calculation is performed to ensure the heat load does not exceed 15.3 x 106 BTU/HR.

95

2011 Waterford 3 SRO Written Exam SRO Question 21 Given:

The plant is in MODE 1 On 3/11 at 0500 the Control Room Supervisor determines that the 7 day surveillance for sampling Boric Acid Makeup Tank A was last completed on 3/1 at 0500 Boric Acid Makeup Pump A is currently Out of Service, but is expected to return to service in 5 days Per Technical Specification 4.0.3, provided that ________(1)________ is approved and risk impact is managed, the surveillance must be completed by 0500 on ___(2)___ or Boric Acid Makeup Tank A must be declared inoperable.

(1) (2)

A. NRC enforcement discretion 3/12 B. a satisfactory risk evaluation 3/12 C. NRC enforcement discretion 3/18 D. a satisfactory risk evaluation 3/18 96

2011 Waterford 3 SRO Written Exam SRO Question 22 The following plant conditions exist:

RAD MONITOR SYS ACTIVITY HI-HI annunciator is in alarm Plant Stack PIG A and B show rising activity HVAC Duct PIG D shows rising activity HVAC Duct PIG A is in alarm Chemistry Tech reports HIGH airborne activity in the lab following sampling.

The CRS should carry out the actions in:

A. OP-901-401, High Airborne Activity in Control Room B. OP-901-402, High Airborne Activity in Reactor Auxiliary Building C. OP-901-403, High Airborne Activity in Containment D. OP-901-404, High Airborne Activity in Fuel Handling Building 97

2011 Waterford 3 SRO Written Exam SRO Question 23 Given:

The plant is shutdown and in MODE 5 for a forced outage Waste Condensate Tank A is on recirculation in preparation for discharge The Liquid Waste Management discharge flow rate instrumentation is out of service Circulating Water Waterboxes A1, B1, and C1 are out of service Minimum dilution flow required is 250,000 gpm and discharge flow rate limit is 50 gpm Circulating Water Pumps A and B are running Which of the following must be done to discharge Waste Condensate Tank A?

A. Start either Circulating Water Pump C or D.

B. Complete independent valve lineups by two qualified persons.

C. Restore either Circulating Water Waterbox A1 or B1 to service.

D. Ensure flow rate is estimated every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during the release.

98

2011 Waterford 3 SRO Written Exam SRO Question 24 Given:

Emergency Diesel Generator B is OOS for preventive maintenance and is expected to be restored in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months The reactor was at 100%

20 minutes ago the Main Generator tripped and Offsite power was lost Emergency Diesel Generator A started and then tripped immediately on Generator Differential The reactor failed to trip automatically All CEAs inserted when the RPS manual trip pushbuttons were depressed As Emergency Coordinator you should implement _________________________.

A. EP-001-010, Unusual Event B. EP-001-020, Alert C. EP-001-030, Site Area Emergency D. EP-001-040, General Emergency 99

2011 Waterford 3 SRO Written Exam SRO Question 25 Given:

A General Emergency was declared A release of unknown duration is in progress The initial Protective Action Guideline issued for a wind direction of 0° were as follows:

o Evacuate A1, B1, C1, D1, D2 A wind shift has occurred to 180° Dose downwind of 0° is now projected to be < 1000 mrem TEDE and < 5000 mrem CDE THYROID at 2 miles and 5 miles Projected Dose in mrem for the new wind direction is:

EAB EAB 2 2 MILE 5 5 MILE TEDE CDE MILE CDE MILE CDE THYROID TEDE THYROID TEDE THYROID 3000 7500 2000 3000 1200 1500 The Protective Action Recommendation update will be to Evacuate Protective Response Areas A1, B1, C1, D1 and:

A. A2, C2 B. A2, C2, D2 C. A2, C2, A3, A4 D. A2, C2, D2, A3, A4 END OF SRO SECTION END OF EXAM 100

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