ML110410302

Initial Exam 2010-301 Final RO Written Exam

ML110410302
Person / Time
Site:	Catawba
Issue date:	02/02/2011
From:	NRC/RGN-II
To:	Duke Energy Corp
References
50-413/10-301, 50-414/10-301
Download: ML110410302 (77)

Text

2010 Catawba Nuclear Station NRC Initial License Exam ination 1.

With Unit 2 operating at 100% power, the following sequence of events occurs:

• 1000: A Train SSPS is placed in TEST.

• 1005: BYA is LOCALLY closed in preparation for testing RTA.

• 1010: A Train SSPS is placed in NORMAL.

• 1015: RTA is opened LOCALLY.

• 1020: B Train SSPS is placed in TEST.

• 1025: BYB is closed LOCALLY.

Which ONE of the following describes the time at which a react or trip will FIRST occur?

A. 1005 B. 1015 C. 1020 D. 1025 Page lof 100

2010 Catawba Nuclear Station NRC Initial License Examination 2.

Given the following Unit I conditions:

Initial

• The crew is recovering from a faulted Steam Generator outside contain ment, upstream of the MSIVs.

• SI has been terminated.

• The crew is maintaining the plant in a stable condition per ES-li (SI Termination).

• PZR pressure is 2285 psig and stable.

• PZR level is 60% and stable.

Current

• NC pressure starts to decrease rapidly due to a significant leak on one of the PZR safety valves.

• PRT pressure is 15 psig.

Based on the event in progress, which parameter will require the manua l reinitiation of Safety Injection, and what will the PZR Safety valve tailpipe temperature be indicat ing?

A. Low PZR level; 300°F tailpipe temperature.

B. Low NC subcooling; 300°F tailpipe temperature.

C. Low PZR level; 250°F tailpipe temperature.

D. Low NC subcooling; 250°F tailpipe temperature.

Page Zof 100

2010 Catawba Nuclear Station NRC Initial License Examination 3.

Given the following Unit 1 conditions;

• The unit has experienced a Reactor Trip and Safety Injecti on due to a Small-Break LOCA.

• The crew has just completed the actions of E-0 (Reactor Trip or Safety Injection).

• NV pump flow to the NC system Cold Legs is 390 gpm.

• NC system pressure is 1300 psig and stable.

• SG pressures are 1092 psig and stable.

• NC system subcooling on the ICCM is 22°F and stable.

Which ONE of the following describes plant condition s upon transition to E-1 (Loss of Reactor or Secondary Coolant)?

NC Pumps Running? SGs Needed for Heat Removal?

A. YES YES B. YES NO C. NO YES D. NO NO Page 3 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 4.

Given the following Unit 1 conditions:

• The Unit was initially at 100% power.

• A double-ended break of Loop IA Cold Leg occurred.

• I ETB has de-energized due to an overcurrent actua tion.

• E-1 (Loss of Reactor or Secondary Coolant) was impl emented.

• The crew has performed the appropriate steps of ES-i

.4 (Transfer to Hot Leg Recirculation).

For the above conditions, and per ES-I .4; which IMC-i I control panel indication is used to deter mine if hot leg recirculation has been established; AND is hot leg recirculation flow sufficient?

Control Panel Indication Hot Leg Recirc Flow Sufficient?

A. ND flow to Hot Legs B and C YES B. ND flow to Hot Legs B and C NO C. NI Pump discharge flow YES D. NI Pump discharge flow NO Page 4 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 5.

With Unit I reactor at 11% power, the following NC Pump IA temperatures are noted:

Time: 1102 1105 1108 Stator Winding 305°F 307°F 312°F Motor Bearing 178°F 182°F 186°F Pump Bearing 2 16°F 227°F 230°F Which ONE of the following describes the time that an NC Pump IA parameter FIRST exceeds a value which requires manual action; AND what is/are the manual action(s) required?

A. 1105 Trip the reactor and then trip NCP 1A.

B. 1105-Trip NCP IA ONLY.

C. 1108 Trip the reactor and then trip NCP 1A.

D. 1108- Trip NCP IA ONLY.

Page 5 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 6.

Given the following Unit I conditions:

• At 0320, a Loss of All AC Power occurred.

• At 0350, ONE operator was dispatched to the Standby Shutdo wn Facility and placed the Standby Makeup Pump in service.

• The Standby Makeup Pump has now been operating for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Which ONE of the following is correct regarding the above condit ions?

A. There should have been TWO operators dispatched, due to Independent Verification requirements.

B. The Spent Fuel Pool level has decreased by approximately 5 inches.

C. Damage to the NC Pump seals is expected to have occurred, due to previous loss of seal injection.

D. Damage to the Standby Makeup Pump has occurred due to excessive operation.

Page 6 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 7.

Given the following Unit I conditions:

Initial

• The Unit is in Mode 4.

• NC temperature is 220°F and slowly decreasing.

• 1A ND Pump is running in RHR mode.

• lB NC Pump is in service.

Subsequently

• 1RAD-3, A/I, IEMFI HI RAD 522 FF-57, AUX BLDG 522 Trip 2 alarm is received.

• I RAD-l, B/3, I EMF4I, AUX BLDG VENT HI RAD Trip 2 alarm is receive d.

Which ONE of the following describes; (1) the required immediate action(s),

AND (2) why is/are the action(s) taken for this event?

A. (I) Secure IA ND Pump ONLY.

(2) Reduce the rate of leakage.

B. (1) Secure lAND Pump AND lB NC Pump.

(2) Reduce the rate of leakage.

C. (1) Secure 1A ND Pump ONLY.

(2) Minimize heat input to the system.

D. (1) Secure IA ND Pump AND lB NC Pump.

(2) Minimize heat input to the system.

Page 7of 100

2010 Catawba Nuclear Station NRC Initial License Examination 8.

Given the following Unit I conditions:

• The Unit is at 100% power.

• BOTH CF pumps tripped.

• SSPS failed to process a reactor trip.

Which ONE of the following describes the status of the listed indications? (Assum e no operator action.)

lAD-I. B/I. AMSAC Turbine Trip annunciator Turbine Control Panel Turbine Trip Light A. Alarming LIT B. Alarming OFF C. NOT alarming LIT D. NOT alarming OFF Page 8 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 9.

Given the following Unit 1 conditions:

• The Unit was at 100% power when a tube rupture on I B SIG occurred.

• The crew is implementing E-3, (Steam Generator Tube Rupture).

• Both motor driven CA Pumps are running.

• CA system valve control has NOT been reset.

• The UST (Upper Surge Tank) level begins decreasin g rapidly.

• The following alarms annunciate:

1 AD-5, Eli, CA PUMPS TRAIN A LOSS OF NORM SUC T

I AD-5, E12, CA PUMPS TRAIN B LOSS OF NORM SUC T

Which ONE of the following completes the statement belo w?

The MINIMUM level to be maintained in the INTACT S/Gs is and 5 seconds after the above annunciators are received, the moto drive r n CA pumps will A. 11%; start taking suction from RN B. 29%; start taking suction from RN C. 11%; trip on low suction pressure D. 29%; trip on low suction pressure Page 9 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 10.

Given the following Unit I conditions:

• The Unit was initially at 100% power.

• A Steam Line break occurs on the Main Steam line from 1C S/G, outside of containment.

• Pressurizer pressure is stabilizing at approximately 1400 psig.

Which ONE of the following identifies expected valve positions which are ALL correct?

A. 1 NV-I 5B, (Letdown Containment Isolation) OPEN IVI-77B (VI to Containment Isolation) OPEN B. I NV-I 5B, (Letdown Containment Isolation) CLOSED 1VI-77B (Vito Containment Isolation) CLOSED C. 1 NV-i 5B, (Letdown Containment Isolation) OPEN iVl-77B (Vito Containment Isolation) CLOSED D. 1NV-15B, (Letdown Containment Isolation) CLOSED 1VI-77B (Vito Containment Isolation) OPEN Page 10 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 11.

Given the following Unit 1 conditions:

• Following a reactor trip the plant experienced a total loss of feedwater.

• The condition caused the crew to initiate NC bleed and feed.

• Subsequently CAPT #1 (Turbine Driven AFW) was resto red to service and the crew is ready to establish feedwater flow to the selected steam gene rator.

• Other plant conditions include:

• Selected S/G Wide Range level is 4%.

• NC loop hot leg temperature at 558°F.

• Core exit thermocouple temperatures are STABLE.

Which ONE of the following completes the statement belo w?

Per FR-H.1, (Loss of Secondary Heat Sink), feedwater flow will be re-established to the selected S/G at _(1). to prevent excessive thermal stresses on the _(2)_.

A. (1) less than 100 gpm until WR level is >12%

(2) reactor vessel nozzles B. (1) less than 100 gpm until WR level is >12%

(2) SG tubes C. (1) a rate which results in CETs decreasing (2) reactor vessel nozzles D. (1) a rate which results in CETs decreasing (2) SG tubes Page 11 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 12.

Given the following conditions:

• VI compressor E is tagged out.

• A Loss of Offsite Power occurs.

• The operating crew is performing actions in AP/OIA/55001022, (Loss of Instrument Air).

• VI pressure is 60 psig and decreasing.

Which ONE of the following describes:

(1) what is the primary motive force for the S/G PORVs, considering the current conditions; AND (2) if the operators will have ensured that the Unit air-operated valves are in their failure mode positions?

A. (1) N2 (2) YES B. (1) N2 (2) NO C. (1)Vl (2) NO D. (1)Vl (2) YES Page 12 of 100

2010 Catawba Nuclear Station NRC Initial License Exami nation 13.

Considering the guidance provided in APIOIA/5500/020, (Loss of Nuclear Service Water System):

Which ONE of the following describes:

(1) the RN flow requirement for continuous operation, AND (2) what is a correct sequence of actions for restoring the require d flow?

A. (1) Total RN system flow less than 25,800 gpm.

(2) Secure unneeded RN pump(s).

Initiate manual RN strainer backwash on unaffected RN pump(

s).

B. (1) Each RN pump flow greater than 8600 gpm.

(2) Establish flow through NS Heat Exchangers.

Secure unneeded RN pump(s).

C. (1) Total RN system flow less than 25,800 gpm.

(2) Initiate manual RN strainer backwash on unaffected RN pump(s).

Secure unneeded RN pump(s).

D. (1) Each RN pump flow greater than 8600 gpm.

(2) Secure unneeded RN pump(s).

Establish flow through NS Heat Exchangers.

Page 13 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 14.

Unit 1 is operating at 100% power when an air leak develops in the Turbine Building. The Turbine Building NEC reports that the leak is immediately upstream of the air operator for ICF-6, (CF Pump 1A Recirc. Control).

If the NEC isolates air to stop the leak, 1 CF-6 will (1) causing main feedwater pump fj.i speed to be (2)

(Assume no actions taken by the Main Control Room Operator during the event.)

(1) (2)

A. OPEN HIGHER B. OPEN LOWER C. CLOSE HIGHER D. CLOSE LOWER Page 14 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 15.

Given the following Unit I conditions:

• The Unit is operating at 100% power.

• Main Generator hydrogen pressure is at 60 psig.

• A grid disturbance then occurs.

• The operator observes the following indications in the Control Room:

• Turbine Load: 1225 MWs

• MegaVARS: - 500 MVARs (a negative value)

• Generator Voltage: 20.8 Kilovolts

• lAD-i, C14 GEN EXCITATION LIMITER ACTIVE is in alarm.

• lAD-i, D/5 GEN VOLT REG COMMON TROUBLE is in alarm.

• GEN VOLT REG EMERGENCY MANUAL MODE indicating light is LIT.

Which ONE of the following describes how the operator will operate the Turbine Generator controls, per AP/l/A/5500/037, (Generator Voltage and Electric Grid Disturbances) to address these conditions?

Reference Provided A. Maintain turbine load at 1225 MWs.

Manually lower excitation current to change MVARs by a value of 250 MVARs.

B. Maintain turbine load at 1225 MWs.

Manually raise excitation current to change MVARs by a value of 250 MVARs.

C. Decrease turbine load to 1180 MWs.

Operate the VOLTAGE ADJUST AUTO setpoint to a higher value.

D. Decrease turbine load to 1180 MWs.

Operate the VOLTAGE ADJUST AUTO setpoint to a lower value.

Page 15 of 100

2010 Catawba Nuclear Station NRC Initial License Exami nation 16.

Given the following Unit 2 conditions:

• The crew has entered ECA-1 .2, (LOCA Outside Containment) from E-0, (Reactor Trip or Safety Injection) based upon high radiation levels in the Auxili ary Building.

• After closing 2N1-173A (ND Hdr 2A to Cold Legs C&D), the follow ing conditions exist:

NC pressure is approximately 1500 psig and slowly increas ing.

FWST level is decreasing at a slightly higher rate.

Which ONE of the following completes the statements below?

The LOCA is .(1 )_. The actions for mitigating any adverse parameter trend are _(2).

A. (I) isolated:

(2) stop the 2A ND Pump and close 2FW-27A (ND Pump 2A Suct from FWST).

B. (1) isolated:

(2) Leave the 2A ND Pump running and aligned through 2ND-3 2A (Train 2A Hot Leg Inj Isol) and 2ND-65B (Train 2B Hot Leg lnj Isol).

C. (1) NOT isolated; (2) Re-open 2N1-173A, and close 2N1-178B (ND Hdr 2B to Cold Legs A&B).

D. (1) NOT isolated; (2) Leave 2N1-173A closed and close 2N1-178B.

Page 16 of 100

2010 Catawba Nuclear Station NRC Initial License Exami nation 17.

Given the following Unit 1 conditions:

• The Unit was initially at 100% power.

• An accident has occurred.

• NC System pressure is 2335 psig.

• Only ONE Charging (NV) pump is available.

• NO Safety Injection (NI) pumps are available.

• The criteria for initiating NC bleed and feed have just been met, per FR-H.1, (Response to Loss of Secondary Heat Sink).

• It has been two hours since the reactor tripped.

Which ONE of the following describes:

(1) if NC heat removal will be adequate; AND (2) what motive force will be used for PORV operation?

A. (1) Adequate, since at least one NV OR NI pump will provide adequa te heat removal.

(2) Nitrogen is aligned ONLY to I NC-32B and I NC-34A.

B. (1) NOT adequate, since at least one NV AND one NI pump is require d for adequate heat removal.

(2) Instrument Air is used to operate All PZR PORVs.

C. (1) Adequate, since at least one NVOR NI pump provide adequate heat removal.

(2) Instrument Air is used to operate All PZR PORVs.

D. (1) NOT adequate, since at least one NV AND one NI pump is require d for adequate heat removal.

(2) Nitrogen is aligned ONLY to 1NC-32B and 1NC-34A.

Page 17 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 18.

Which ONE of the following is a complete description of the reasons for the reactor operator performing a controlled depressurization of the Steam Generators (SGs) during the perform ance of ECA-1 .1, (Loss of Emergency Coolant Recirculation)?

List of Reasons

1. Minimize NC dilution potential in case of a subsequent tube rupture.

2. To establish conditions for injection of the Cold Leg accumulators.

3. Minimize reactor coolant flow from the LOCA.

4. To establish conditions for ND system operation.

A. I and 2 ONLY.

B. 3 and 4 ONLY.

C. 1,2, and 3 ONLY D. 2,3, and 4 ONLY Page 18 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 19.

Given the following Unit 1 conditions:

• The Unit is at 80% power with all systems aligned normal.

• Control rod Bank D is at 180 steps.

• Rod control is in AUTOMATIC.

• Turbine Impulse pressure values are:

Channel I: 693 psig Channel II: 693 psig Channel Ill: 0 psig Which ONE of the following completes the statement below?

For the above conditions, control bank D rods will be continuously _(1)_.

If the rods continue to move after controls are shifted to MANUAL the operator will initiate a reactor trip, and then confirm that the reactor is tripped by observing the _(2)_.

(1) (2)

A. Inserting Reactor Trip Breakers GREEN lights LIT, and the Bypass Breaker indicating lights DARK.

B. Inserting GREEN lights LIT on both the Reactor Trip Breakers and Bypass Breakers.

C. Withdrawing Reactor Trip Breakers GREEN lights LIT, and the Bypass Breaker indicating lights DARK.

D. Withdrawing GREEN lights LIT on both the Reactor Trip Breakers and Bypass Breakers.

Page 19 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 20.

Given the following Unit 1 conditions:

• The Unit is at 100% power.

• Channel I Pressurizer Level has been removed from service for calibra tion.

• Channel II Pressurizer Level begins to malfunction and is drifting LOW.

Which ONE of the following describes expected alarms and how the operators will respond to these conditions?

A. IAD-2, Ff9 DCS ALTERNATE ACTION, AND 1AD-6, C/9 PZR HI LEVEL DEV CONTROL Take manual control of 1 NV-294 and reduce charging flow.

B. IAD-2, F19 DCS ALTERNATE ACTION, AND IAD-6, C!9 PZR HI LEVEL DEV CONTROL Verify Pressurizer level is automatically controlling at 60%.

C. 1AD-2, F/9 DCS ALTERNATE ACTION ONLY Take manual control of 1NV-294 and reduce charging flow.

D. IAD-2, F19 DCS ALTERNATE ACTION ONLY Verify Pressurizer level is automatically controlling at 60%.

Page 20 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 21.

Given the following conditions:

• The refueling crew is lowering an irradiated fuel assembly next to a new fuel assembly in the core for Unit 1.

• The assembly inadvertently drops completely into the core and a notabl e amount of bubbles are observed.

• The RO notes that source range count rates increased by 0.4 decades and are stabilizing.

Which ONE of the following describes:

(1) the expected alarm; AND (2) how this alarm will impact evacuation of containment?

A. (1) 1AD-2, D13 & D14 SIR HI FLUX LEVEL AT SHUTDOWN (2) Causes an automatic actuation of the Containment Evacuation alarm.

B. (1) IAD-2, D!3 & D14 SIR HI FLUX LEVEL AT SHUTDOWN (2) Requires Control Room crew to manually actuate the Containment Evacua tion alarm.

C. (1) IRAD-3, D/2 1EMF-17 REACTOR BLDG REFUEL BRIDGE (2) Causes an automatic actuation of the Containment Evacuation alarm.

D. (1) IRAD-3, D/2 1EMF-17 REACTOR BLDG REFUEL BRIDGE (2) Requires Control Room crew to manually actuate the Containment Evacua tion alarm.

U Page 21 of 100

2010 Catawba Nuclear Station NRC Initi

- al License Examination 22.

During a fuel handling accident with VP in oper ation, which ONE of the following describ required operation of VP and containment closu es re, and what is the reason per APII/A155001 (Damaged Spent Fuel)? 025 A. Establish containment closure FIRST to prev ent an unmonitored release to the environm ent.

B. Establish containment closure FIRST to prev ent an unfiltered release to the environment.

C. Shutdown VP FIRST to prevent drawing a vacuum in containment.

D. Shutdown VP FIRST, and then establish cont ainment closure to terminate any release soon as possible. as Page 22 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 23.

Given the following Unit 1 conditions:

• The Unit is at 100% power.

• A fire is occurring on one of the turbine bearings Considering the classification of this fire, which ONE of the following is the correct sequence how the deluge system is actuated, AND when of the alarms are received in the control room?

Events (listed in random order):

1. lAD-i, TURBINE OIL FIRE TURB TRIP, alarm s.

2. OAC alarm is received for high temperature at fire detector.

3. The deluge valve automatically opens.

4. Operator activates the breakglass station at I MC9 to open the deluge valve.

A. 1,2,3 B. 2,3,1 C. 2,4,1 D. 1,2,4 Page 23 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 24.

Given the following conditions:

• The Control Room has been evacuated, due to toxic gases, per AP111A155001017.

• Control has been transferred to the Auxiliary Shut down Panel (ASP).

• A cooldown to COLD SHUTDOWN is in progress.

• Pressurizer level is at 15% and slowly decreasin g.

• SG WR levels are approximately 50% and decr easing.

• VCT level is 20% and slowly decreasing.

Which ONE of the following describes a local actio n which will be performed by the NEC for mitigating the above conditions?

A. De-energize Pressurizer heaters.

B. Align NV pump suction from VCT to FWST.

C. Initiate emergency boration.

D. Throttle CA flow to the SGs.

Page 24 of 100

2010 Catawba Nuclear Station NRC Initial Lice nse Examination 25.

During implementation of APII/A/5500/018, (Hig h Activity in Reactor Coolant), where does IEMF 48, (NC Sample Line Reactor Coolant) draw its samp le from, and which event(s) can it be used to diagnose?

Sample Drawn From Diagnose Which Event A. Cold Leg failed fuel OR crud burst B. Cold Leg failed fuel ONLY C. Hot Leg failed fuel ONLY D. Hot Leg failed fuel OR crud burst Page 25 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 26.

Given the following Unit I conditions:

• A Main Steam Line Break has occurred inside containment.

• Containment pressure is 2.9 psig.

• The crew has entered FR-P.I, (Response to Imminent Pressurized Therm al Shock Condition).

• NO NCPs are operating.

• An NC System pressure reduction is in progress using a PZR PORV

• NC System subcooling is at 3OF.

• RVLIS LR level indicates 70%.

Which ONE of the following describes the required action, per FR-P.I?

A. Continue with the depressurization of the NC System.

B. Dump steam from an intact S/G to increase subcooling.

C. Start NCP B to promote thermal mixing of NC System and ECCS fluids.

D. Close the PORV to stop NC System depressurization.

Page 26 of 100

2010 Catawba Nuclear Station NRC Initi

- al License Examination 27.

Given the following Unit 1 conditions:

• A reactor trip occurred.

• The crew was performing ES-0. 1, (Reactor Trip Response) when a loss of off-site power occurred.

• The crew then transitions to ES-0.2, (Nat ural Circulation Cooldown) to cool down the plant.

Which ONE of the following identifies (1) potential subsequent conditions which invo lve entry into ES-0.3, (Natural Circulation Cooldown with Steam Void In Vessel).

AND (2) why the Reactor Vessel UR level is main tained at greater than 73% during the perfo of ES-0.3? rmance A. (1) If NCS subcooling drops to less than 20°F (2) To prevent loss of natural circulation due to steam voiding in the S/G tubes.

B. (1) If NCS subcooling drops to less than 20°F (2) To ensure pressurizer level is adequate to accommodate void collapse.

C. (1) If plant conditions require a cooldown rate faster than allowed by ES-O.2.

(2) To prevent loss of natural circulation due to steam voiding in the S/G tubes.

D. (1) If plant conditions require a cooldown rate faster than allowed by ES-0.2.

(2) To ensure pressurizer level is adequate to accommodate void collapse.

0 Page 27 of 100

2010 Catawba Nuclear Station NRC - Initial License Examination 28.

Given the following Unit 1 conditions:

• The Unit is in Mode 3 with 1A, lB and 1C NC Pumps in service.

• One oil lift pump for ID NCP is in service.

• The operator presses the ON pushbu tton for ID NCP.

• 1 D NCP did NOT start.

Which ONE of the following describes a condition(s), which prevented ID NC P from starting?

A. Annunciator 1AD-6 C/4 (NCP D MTR Upper BRG KC Outlet HI/LO Flow) LIT.

B. Annunciator IAD-6 F14 (NCP D Upp er/Lower Oil Reservoir La Level) LIT.

C. Bearing oil lift pressure at 400 psig D. Bearing oil lift pressure at 550 psig AND Annunciator 1AD-6 F14 (NCP D Upper/L Reservoir La Level) LIT. ower Oil Page 28 of 100

2010 Catawba Nuclear Station NRC Initi

- al License Examination 29.

Given the following Unit I conditions:

• The Unit is operating at 40% power.

• NCP 1 C trips on overcurrent.

Assuming no operator action, which ONE of the following describes the effect on the Depa from Nucleate Boiling Ratio (DNBR) AND react rture or thermal power?

A. DNBR will INCREASE.

Reactor power decreases and stabilizes at a new lower thermal power.

B. DNBR will DECREASE.

Reactor power decreases and stabilizes at a new lower thermal power.

C. DNBR will INCREASE.

Reactor power initially decreases and then retur ns to 40% thermal power.

D. DNBR will DECREASE.

Reactor power initially decreases and then returns to 40% thermal power.

C)

Page 29 of 100

2010 Catawba Nuclear Station NRC Initial Lice nse Examination 30.

Given the following Unit I conditions:

• The Unit is at 45% power during a power escalation.

• The control power for INV-309, (Seal Water Injection Flow) control valve is lost.

Which ONE of the following describes the effect on NC Pump seal injection flow, and whether LCO 3.5.5, (Seal Injection Flow) entry is required?

Seal Injection Flow LCO 3.&5 Entry Conditions A. Decreases NO B. Decreases YES C. Increases NO D. Increases YES Page 30 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 31.

Which ONE of the following describes:

(I) one of the criteria given in ES-I .3, (Transfer to Cold Leg Recirculation) for initiation of ND auxiliary containment spray; AND (2) why that criterion is important?

A. (1) Greater than 50 minutes after the reactor trip.

(2) To meet decay heat removal requirements.

B. (1) NO greater than 50 minutes after the reactor trip.

(2) To ensure containment pressure will remain below desig n pressure.

C. (1) Both ND pumps must be operating.

(2) To ensure containment pressure will remain below design pressure.

D. (I) Both ND pumps must be operating.

(2) To meet decay heat removal requirements.

Page 31 of 100

2010 Catawba Nuclear Station - NRC Initial License Examination 32.

(J Given the following Unit 1 conditions

• The Unit is in Mode 6.

• Refueling cavity is filled to 23 feet

• Core reload is in progress.

• NC temperature is 145°F.

• 1A residual heat removal (ND) train is in operation.

A leak has been reported on the IA ND pump motor cooler. To repair motor cooler must be isolated. Ma the leak, cooling flow to the intenance estimates it will take 70 minutes to complete repairs.

What is the reason for having one ND loop in operation in this conditi the ability to continue core reload? on and how does this affect A. Provides an indication of reactor coolant temperature.

Core reload must be stopped.

B. Ensures that a core Keff of less than or equal to 0.95 is maintained dur operations. ing fuel handling Core reload must be stopped.

C. Provide an indication of reactor coo lant temperature.

Core reload may continue provided no operations are permitted that wou refueling cavity boron concentration ld dilute the D. Ensures that a core Keff of less than or equal to 0.95 is maintained dur operations. ing fuel handling Core reload may continue provided no operations are permitted that wou refueling cavity boron concentration ld dilute the

)

Page 32 of 100

2010 Catawba Nuclear Station NRC Initial License Exami nation 33.

Given the following Unit I conditions:

• The Unit was initially at 100% power when a small break LOCA occurred.

• A loss of all offsite power has occurred.

• I B DG panel trouble is in alarm due to lube oil pressure at 20 psig.

• The crew transitions to ES-I .2, (Post LOCA Cooldown and Depres surization).

• An operator has been dispatched to perform ES-I .2, Enclosure 4, (Power Alignment for CLA Valves).

Based on the above conditions:

(1) which accumulator isolation valves can be energized; AND (2) what action should be taken once the valves are energized?

A. ALL.

Close ALL and leave them energized.

B. ALL.

Close ALL and then de-energize them.

C. ONLY TWO.

Close these TWO and vent ALL accumulators.

D. ONLY TWO.

Close these TWO and vent the OTHER two accumulators.

Page 33 of 100

2010 Catawba Nuclear Station - NRC Initial License Examination 34.

Given the following Unit I conditions:

• The Unit has completed NC fill and vent activities following a forced outage.

• A nitrogen blanket was placed on the pressurizer during the outage.

• NC level is 85% in preparation for drawing a bubble in the pressurizer.

Which ONE of the following describes; (1) What is the limit on pressurizer heat up rate per Selected Licensee Commitment 16.5-4 (Pressurizer)?

AND (2) What indication verifies nitrogen venting is complete while drawing a bubble in the pressurizer, per OPI1IA/6100/OOl, (Unit Startup)?

A. 1. 100°Fperhour

2. PRT temperature equalizes with PZR steam space temperature.

B. 1. 100°F per hour

2. PRT level increases without a corresponding PRT pressure increase.

C. 1. 200°F per hour

2. PRT temperature equalizes with PZR steam space temperature.

D. 1. 200°F per hour

2. PRT level increases without a corresponding PRT pressure increase.

Page 34 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 35.

With Unit I at 100% power, the values of the four (4) channels of Pressu rizer pressure control are as follows:

Channel I 2229 psig Channel Il 2237 psig Channel III 2227 psig Channel IV 2232 psig Channel II then experiences a loss of power.

Which ONE of the following completes the following statement?

PRIOR to the Channel II failure, SELECTED Pressurizer pressure value was (1)

AFTER the Channel II failure, SELECTED Pressurizer pressure value is (2)

A. (1) 2232 psig (2) 2229 psig B. (1) 2232 psig (2) 2232 psig C. (1) 2229 psig (2) 2229 psig

0. (1) 2237 psig (2) 2232 psig Page 35 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 36.

Per Technical Specifications, which ONE of the follo wing reactor trips is required to be operable to provide protection against DNB when the plant is in Mod e 2?

A. Pressurizer low pressure B. OPDT C. Low NC loop flow D. OTDT Page 36 of 100

2010 Catawba Nuclear Station NRC - Initial License Examination 37.

Given the following Unit 2 conditions:

• The Unit is conducting a startup at 6%

power.

• Intermediate range channel N-35 begins to operate erratically.

• Rod motion was stopped.

• The N-35 channel LEVEL TRIP swi tch is in BYPASS.

Which ONE of the following describes whi ch N-35 fuses, if any, can be removed in a reactor trip? without resulting A. Control power fuses ONLY.

B. Instrument power fuses ONLY.

C. None of the fuses can be removed.

D. Either the instrument power control power fuses, but not both at the same time.

Page 37 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 38.

Which ONE of the following describes how a loss of Vital I & C power panelboards I ERPA and 1 ERPD affects SSPS Train A and Train B?

Train A Logic Bay Train B Logic Bay A. Energized Energized B. Energized De-energized C. De-energized De-energized D. De-energized Energized Page 38 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 39.

Given the following conditions:

• The Unit is operating at 100% power.

• Pressurizer Pressure Channel Ill has been placed in the required configuration for testing.

Which ONE of the following lists the resulting logic for a Safety Injection initiation on Pressurizer pressure based on the conditions above?

A. 1/3 B. 2/3 C. 1/2 D. 2/2 Page 39 of 100

2010 Catawba Nuclear Station NRC Initi

- al License Examination 40.

Given the following Unit I conditions:

• The Unit is at 100% power.

• The following Lower Containment Ventilation Units (LCVU) are operating in low speed:

• LCVU1A

• LCVU1B

• LCVU1D

• Upper Containment Ventilation Units (UCVU)

IC is the only operating UCVU.

• Containment pressure is at 0.2 psig.

• LCVU ID then on overcurrent.

Which ONE of the following describes:

(1) the next required action for providing additiona l containment cooling, per OP/1/A/6450/001, (Containment Ventilation Systems), in address ing the above conditions; AND (2) if this action is NOT successful, AND no furth er operator actions are taken, which LCO or alarm condition, will FIRST be reached for entry, containment pressure?

A. (1) Start LCVU IC in low speed, AND start ALL UCVUs.

(2) LCO 3.6.4, Containment Pressure B. (I) Start LCVU IC in low speed, AND start ALL UCVUs.

(2) Annunciator LIT which instructs operators to initiate high speed for LCVUs.

C. (1) Start LCVU IC in low speed ONLY.

(2) LCO 3.6.4, Containment Pressure D. (1) Start LCVU IC in low speed ONLY.

(2) Annunciator LIT which instructs operators to initiate high speed for LCVUs.

C)

Page 40 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 41.

With Unit I in MODE 4, which ONE of the following desc ribes a condition associated with the Ice Condenser system which requires an LCO entry with a Required Action Completion Time of within ONE hour?

A. I AD-13, B18, ICE BED HI TEMP SWITCHES alarm s, due to one ice bed at 30°F and slowly increasing.

B. I AD-13, C18, GLYCOL EXPANSION TANK HI/LO LVL alarms, due to a low level at 30%.

C. Accumulation of ice in ice bed flow channels resulting in 20% blockage.

D. An ice condenser intermediate deck door temporari ly blocked from opening.

C )

Page 41 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 42.

Which ONE of the following conditions, or annunciator alarms, relating to operation of the Ice Condenser system will automatically close I NF-228A (NE Supply Containment Isolation Valve)?

A. lAD-i 3, E/7, FLOOR COOLING SYS GLYCOL LO FLOW B. All Unit I Glycol Chiller Compressors trip.

C. lAD-I 3, D18, GLYCOL EXPANSION TNK LO-LO LVL D. All Unit I NF Glycol pumps trip.

Page 42 of 100

2010 Catawba Nuclear Station NRC Initial License Exami nation 43.

Given the following Unit 1 conditions:

• Following an accident, containment pressure is 8 psig, and slowly decreasing.

• IA and lB containment spray (NS) pumps are running.

• The crew has begun the actions of ECA-1 .1, (Loss of Emergency Coolant Recirculation).

• Refueling Water Storage Tank (FWST) level is 10%, and slowly decreasing.

• Efforts to OPEN 1NI-185A (ND Pump IA Cont Sump Suct) and 1NI-184B (ND Pump lB Cont Sump Suct) have NOT been successful.

Based on the above conditions, which ONE of the following describ es:

(1) How are the NS pumps operated at this point per ECA-1

.1; AND (2) What is the purpose for operating the NS pumps in this manne r?

A. (1) Shutdown both NS pumps.

(2) To prevent pump cavitation.

B. (1) Secure one NS pump. Continue operating one NS pump aligned (2) to the FWST.

To conserve FWST inventory.

C. (1) Shutdown both NS pumps.

(2) To conserve FWST inventory.

D. (1) Secure one NS pump. Continue operating one NS pump aligned to the FWST.

(2) To prevent pump cavitation.

Page 43 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 44.

Given the following Unit 1 conditions:

• With the Unit initially at 100% power, a steam line rupture occurs inside containment.

• The operating crew notes the following trend for containment pressure:

paiac Pressure *Dta Pressure Pointy Point 1 , 0 5 psig 6 0 8 psig I 5psig O4psig 3J 3 5 psig ,, 0 3 psig 4 3 4 psig 0 5 psig 5j 3opsig 12 O8psig 2.1 psig :is,;: 1.1 psig 7 1 4 psig 1 3 psig

• The operators have NOT taken any actions regarding ESF signals.

(Note: The term Data Point denotes a time interval.)

Which ONE of the following describes the status of the Containment Spray (NS) Pumps and Spray Valves, based on automatic operation for the three Data Points listed below?

Data Point #2 Data Point #8 Data Point #13 A. Pumps ON ON ON Valves OPEN OPEN OPEN B. Pumps ON OFF OFF Valves OPEN CLOSED CLOSED C. Pumps OFF ON ON Valves CLOSED OPEN OPEN D. Pumps OFF OFF OFF Valves CLOSED CLOSED CLOSED Page 44 of 100

2010 Catawba Nuclear Station - NRC Initial License Examination 45.

Given the following Unit 1 conditions:

• Unit 1 is at 100% power.

• 1A SIG has developed a 200 GPO tube leak.

• 1 EMF-33 (CSAE Discharge) Trip 2 ligh t is LIT.

• The following annunciator is alarming:

IRAD-1, B/I, 1EMF-33 CSAE EXHA

• UST HI RAD The reactor operator consults the Ann unciator Response Procedure (ARP)

Panel 1MC13. and proceeds to

• At Panel 1 MCi 3, the operator observes the as-found pictured control as seen below: in the photo UNIT f IP UNIT 1 CSAE EXH For the above conditions, and prior to any operator action, which ONE of the foll whether the as-found configuration owing describes of the control switch and indication CORRECT and why or why not? in the photo above is A. CORRECT configuration. Swapover of the CSAE exhaust to Aux. Bldg. (VA will ONLY occur when the operator ) filtered exhaust takes the switch to the AUTO positio n.

B: INCORRECT configuration. The VA light by 1 EMF-33 reaching its Trip 2 setpoin should be LIT due to automatic swapover caused t.

C. CORRECT configuration. Swapover of the CSAE exhaust to Aux. Bldg.

will ONLY occur when the operator (VA) filtered exhaust OPENS 1ABF-D-1 1 or 1ABF-D-4.

D. INCORRECT configuration. The swi tch should have already been in AU exhaust automatic swapover to Aux TO, to enable CSAE

. Bldg. (VA) filtered exhaust immedia reaching its Trip 2 setpoint. tely upon I EMF-33 Page 45 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 46.

Given the following Unit I conditions:

• The Unit is at 100% power.

• 1 EMF-71 (SIG A Leakage) is INOPERABLE.

• 1 EMF-74 (SIG D Leakage) Trip 2 is LIT.

• I EMF-33 (CSAE Offgas) Trip 2 is LIT.

• The crew is currently taking actions in AP/1/A/5500/

010, (Reactor Coolant Leak).

• For the noted times, the following parameters are also observed:

0330 0332 0334 0336 IA SIG Level (NR) % 65 67 68 66 IBS/GLeveI(NR)% 65 65 65 65 1CS!GLeveI(NR)% 64 64 64 64 1DS/GLevel(NR)% 65 65 65 65 LID Flow gpm 75 45 0 0 Charging Flow gpm 128 129 130 131 PZR Level % 55 51 47 43 Which ONE of the following describes:

(1) the cause of the above conditions; AND (2) what actions are taken to mitigate the even t?

A. (1) 1A SIG tube leakage (2) Perform a rapid shutdown using AP111N55001009

, (Rapid Downpower) per AP/lO (Reactor Coolant Leak).

B. (1) IA SIG tube leakage (2) Manually trip the reactor and initiate Safety Injec tion per AP/11N5500/010, (Reactor Coolant Leak) and go to E-0, (Reactor Trip and Safety Injection).

C. (I) ID S/G tube leakage (2) Perform a rapid shutdown using AP/I/A15500/009, (Rapid Downpower) per AP/lO (Reactor Coolant Leak).

D. (I) ID S/G tube leakage (2) Manually trip the reactor and initiate Safety Injec tion per AP/I 0, (Reactor Coolant Leak) and go to E-0, (Reactor Trip and Safety Injection)

Page 46 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 47 Given the following Unit I conditions:

• The crew is shutting down the Unit for a refueling outage, per OPIIIAI6100/002, (Controlling Procedure for Unit Shutdown).

• The Unit is at 11% power.

• CF flow is 14% for all SIGs.

• CA nozzle swap permissive lights are LIT for all SIGs.

• The operator depresses CA NOZZLE pushbutto n.

Which ONE of the following completes the state ment below?

When the first CF containment isolation valve has CLOSED, the speed of the operating CF will by 150 rpm. pump A. be manually DECREASED B. automatically DECREASE C. be manually INCREASED D. automatically INCREASE Page 47 of 100

2010 Catawba Nuclear Station NR - C Initial License Examination 48.

Given the following Unit I conditions

• The operators are conducting a cooldo wn in Mode 3.

• Tave is 51 0°F.

• NC system pressure is 1900 psig.

• 1A CF Pump is maintaining S/G leve ls.

• I B CF Pump is shutdown, per the OP.

• ECCS Train A/B PZR PRESS has bee n blocked.

• ECCS Train A/B STM PRESS has bee n blocked.

• Both CA train AUTO-START-DEFE AT buttons have been depressed whi performs a special test. le engineering Which ONE of the following describes events, which will, in conjunction with conditions, cause the motor driven CA the above plant pumps to start automatically?

A. 1A CF Pump trips, and causes all S/G levels to decrease below the Lo-Lo level trip setpoint.

B. NC loop B spray valve, INC-29, fails open, and results in NC pressure dec psig. reasing to 1500 C. A steamline rupture in the doghouse cau ses 1C S/G pressure to decrease rate of 200 psig/sec. to 700 psig at a D. A feedline rupture results in 1D S/G level decreasing to less than the Lo-L containment pressure increasing to o level setpoint and 2 psig.

Page 48 of 100

2010 Catawba Nuclear Statio n NRC Initial License Exam ination 49.

Given the following Unit 1 condit ions:

• IA RN Pump is in service.

• All other essential equipment is in operation on Unit 1, pow

• OPII/A/63501002, (Diesel Gener ered from B Train.

ator) is in progress with the IA to the grid when the following seq Diesel running in parallel uence of events occurs:

• Load is reduced on the diesel to 200KW in anticipation of ope Breaker. ning the Emergency

• Prior to opening the Emergenc y Breaker, the Normal Feeder spuriously OPENS. Breaker from IATC Which ONE of the following com pletes the statement below?

The Blackout Sequencer Actua ted Train A status light on SI-14 and the A. illuminates; 1A DG load increa ses B. remains dark; 1A DG load inc reases C. illuminates; 1A DG Emergenc y Breaker trips open, then re-closes 8.5 seconds later

) D remains dark 1A DG Emergenc y Breaker trips open then re-closes 8 5 seconds later Page 49 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 50.

() Given the following Unit 2 conditions:

• The Unit is in Mode 4 during a normal cooldown for refueling.

• Train 2A of ND is in service.

• ND flow is stable at 3400 gpm.

• NC return temperature is 154°F and decreasing.

Which ONE of the following describes:

(I) the effect on NC cooldown rate of losing power to Vital DC Bus 2EPA; AND (2) what action the operator will take to restore the desired cooldown rate, per AP/2/A155001029, (Loss of Vital or Aux Control Power)?

A. (1) Rate INCREASES.

(2) Manually adjust setpoint of ND HX 2A OUTLET CTRL (for 2ND-26).

B. (1) Rate DECREASES.

(2) Place PWR DISCON FOR 2N1-173A switch to THROT and manually control 2N1-173A.

C. (1) Rate INCREASES.

(2) Place PWR DISCON FOR 2N1-173A switch to THROT and manually control 2N1-173A.

D. (1) Rate DECREASES.

(2) Manually adjust setpoint of ND HX 2A OUTLET CTRL (for 2ND-26).

Page 50 of 100

2010 Catawba Nuclear Station NRC Initial Lice nse Examination 51.

Given the following condition:

Inverter 1 KXIA experienced a total loss of output voltage.

Which ONE of the following describes:

(1) an indication used to aid in determining that the backup power supply has aligned to 1KX PA; AND (2) Once I KXIA has returned to normal operating parameters, how will 1 KXPA supply be swapped back to 1 KXIA?

A. (1) IKMAA In Sync light is LIT.

(2) Automatically after 60 seconds.

B. (1) IKMAA In Sync light is LIT.

(2) Manually.

C. (1) IKXAA Alternate Source Supplying Load light is LIT.

(2) Automatically after 60 seconds.

D. (1) IK)(AA Alternate Source Supplying Load light is LIT.

(2) Manually.

Page 51 of 100

2010 Catawba Nuclear Station NRC Initial Lice nse Examination 52.

Given the following conditions:

• DIG IA has been started and fully loaded for a Perio dic Test.

• The control room operators note the following alarm annunciates:

• IAD-12, D/1, DIESEL GEN HXAOUTLETFLO W-LO

• Lube oil temperature has risen rapidly and is now 207°F.

• Jacket water outlet temperature is 185°F and risin g.

• DIG 1A continues to run and is fully loaded.

Per the Annunciator Response Procedure, whic h ONE of the following actions will be taken FIRST to address the above conditions?

A. Start an additional RN pump to increase D/G heat exchanger cooling water flow.

B. Dispatch an operator to ensure that IRN-232A (D/G 1A Hx Inlet Isol) is FULLY open.

C. Reduce loading on D/G IA.

D. Manually trip the D/G IA.

Page 52 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 53.

Consider the following Mode 1 plant conditions involving the following radiation monitors:

• 1 EMF-38, Containment Radiation Monitor.

• I EMF-46A, KC (Component Cooling) System Train A Radiation Monitor.

• I EMF-71, Main Steam Line Radiation Monitor.

Which ONE of the following identifies conditions where both Condition 1 and 2 will result in an entry into a Technical Specification LCO or a Selected Licensee Commitment (SLC)?

Condition I Condition 2 (IEMF-46A is NOT functional, and KC Train is in service.)

A. B Plant at 50% power and I EMF-71 is NOT functional.

B. A Plant at 50% power and 1EMF-71 is NOT functional.

C. B 1 EMF-38 sample lined up to INCORE ROOM and LOWER ONLY.

D. A 1 EMF-38 sample lined up to INCORE ROOM and LOWER ONLY.

Page 53 of 100

2010 Catawba Nuclear Station - NRC Initial License Examination 54.

Given the following Unit I conditions:

• The Unit is at 100% power normal operations.

• ONE train of KC is in service.

• KC HX lB OTLT MODE control switch is configured as indicated in the photo below.

Which ONE of the following describes:

(1) the expected position of the KG HX IA OTLT MODE control switch; AND (2) if 1 2OVAC Auxiliary Power Panelboard 1 KPA beco mes de-energized, KC HX 1A Outlet controlling mode will be KC HX lB -I OTLT MODE 1 RN-351 KC HX lB OuT T/V S5 RESET

[RESEF.

KC HX IA OTLT MODE KC HX IA Outlet control mode Switch position after loss of I KPA A. XC TEMP MINI FLOW B. FLOW Mh -LOVV U. KL.

U. MN LL.A

2010 Catawba Nuclear Station NRC Initial License Examination 55.

Given the following Unit 1 conditions:

• The Unit was initially at 100% power.

• A LOCA has occurred.

• Containment pressure is 8 psig and decreasing.

• Safety Injection signal has NOT been reset.

• Phase A and Phase B have NOT been reset.

Which ONE of the following describes the response if the operator pushes the Phase A and the Phase B RESET buttons on control panel I MC-1 I for the above conditions?

A. 1) Phase A will reset.

2) Phase B will NOT reset.

B. 1) Phase A will reset.

2) Phase B will reset.

C. 1) Phase A will NOT reset.

2) Phase B will NOT reset.

D. 1) Phase A will NOT reset.

2) Phase B will reset.

Pane

2010 Catawba Nuclear Station NRC Initial License Examination 56.

Given the following Unit 1 conditions:

• Plant conditions have been stable for the past 15 minutes.

• Loop IA Tave is 572.0 °F.

• Loop I B Tave is 570.0 °F.

• Loop IC Tave is 570.0 °F.

• Loop ID Tave is 568.0 °F.

• Tref is 568.0°F.

• The CRD Bank Select Switch is in MANUAL.

If the CRD Bank Select Switch is placed in AUTO, the control rods will initially A. NOT step.

B. Step IN at 8 steps/minute.

C. Step IN at 40 steps/minute.

D. Step IN at 54 steps/minute.

P

2010 Catawba Nuclear Station NRC Initial License Examination 57 Given the following Unit I conditions:

• The Unit is at 100% power.

• Channel Ill Pressurizer Level has been removed from service for calibration.

• Channel I Pressurizer Level begins to malfunction and is drifting HIGH.

• IAD-2, F19 DCS ALTERNATE ACTION has alarmed.

• Indicated Pressurizer Level Control Channel values are as follows:

• Channel I 60%

• Channel II 55%

• Channel III 0%

• A leak on the NC system develops.

• The crew has determined the leakrate to be approximately 130 gpm.

Which ONE of the following describes the effect of these conditions as Pressurizer level continues to lower?

A. Pressurizer heaters automatically trip.

Letdown automatically isolates.

B. Pressurizer heaters automatically trip.

Operators will have to manually isolate letdown.

C. Operators will have to manually trip all Pressurizer heaters.

Operators will have to manually isolate letdown.

D. Operators will have to manually trip all Pressurizer heaters.

Letdown automatically isolates.

Pane 57 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 58.

Which ONE of the following completes the statement below to describe how a severe axial flux imbalance that is outside of the normal limits, as defined in the ROD Book section 3.9 (OAC Manual Input Data), affects automatic and/or manual rod withdrawal at 100% power?

Axial Flux Distribution (AFD) inputs to OPDT and OTDT cause both setpoints to which could actuate a C3 or C4 rod stop which will prevent A. decrease; automatic AND manual rod withdrawal B. increase; automatic AND manual rod withdrawal C. decrease; automatic rod withdrawal ONLY D. increase; automatic rod withdrawal ONLY Page 58 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 59.

A Reactor Trip and Safety Injection have occurred on Unit 1 due to a Loss of Coolant Accident (LOCA).

The following conditions exist:

• Containment pressure is 10 psig and slowly decreasing.

• All NC pumps have been secured.

• NC system subcooling is -50°F.

• CETs indicate 750°F and increasing.

• Reactor Vessel Lower Range Level (RVLIS) is currently 34% and slowly decreasing.

Which ONE of the following completes the statement below?

The status of Core Cooling is currently A. ORANGE, and will remain ORANGE even if RVLIS increased by 10%.

B. ORANGE, but will be YELLOW 11 CETs decreased by 100°F.

C. RED, and will remain RED even if CETs decreased by 100°F.

D. RED, but will be ORANGE if RVLIS stabilized at 10% higher.

Pan

2010 Catawba Nuclear Station NRC Initial License Examination 60.

Unit 1 was operating at 100% power when the following sequence of events occurred:

• A Loss of Offsite Power occurred.

• The reactor tripped.

• When 1A DIG attempted to load 1 ETA, 87G (Generator Differential) relay actuated due to a fault on the bus.

• Just after the reactor trip, a LOCA inside containment developed.

• Containment pressure has risen to 3.1 psig and is slowly increasing.

Which ONE of the following describes the status of the VE (Annulus Ventilation) fans?

A. ONLY 1 B VE fan is running.

B. IA AND I B VE fans are running.

C. ONLY 1 B VE fan will start after a 9 minute time delay.

D. 1A AND 1 B VE fans will start after a 9 minute time delay.

P

2010 Catawba Nuclear Station NRC Initial License Examination 61.

Given the following Unit I conditions:

• The Unit is in Mode 5.

• Containment Purge is in service.

Which ONE of the following identifies alarm conditions that will automatically isolate Containment Purge?

A. I EMF-1 1, Reactor Bldg. Incore Inst Rm Monitor.

1 EMF-36, Unit Vent Gas Hi Rad Monitor.

B. I EMF-36, Unit Vent Gas Hi Rad Monitor.

1 EMF-38, Containment Particulate Radiation Monitor.

C. 1 EMF-38, Containment Particulate Radiation Monitor.

1 EMF-39, Containment Gas Hi Rad Monitor.

D. 1 EMF-1 1, Reactor Bldg. Incore Inst Rm Monitor.

1EMF-39, Containment Gas Hi Rad Monitor.

Pane 61 of

2010 Catawba Nuclear Station NRC Initial License Examination 62.

Given the following Unit I conditions:

• The reactor is stable at approximately 10-8 amps.

• A Steam Generator safety valve fails open.

• NO Reactor Trip or Safety Injection actuation occurs.

Which ONE of the following describes the difference in the plant response if this event were to occur at the beginning-of-life (BOL) as compared to the end-of-life (EOL)?

The NC system will stabilize at a lower temperature at A. BOL than at EOL.

Reactor power will stabilize at a higher value at BOL than at EOL.

B. BOL than at EOL.

Reactor power will stabilize at approximately the same value at BOL and EOL.

C. EOL than at BOL.

Reactor power will stabilize at a higher value at BOL than at EOL.

D. EOL than at BOL.

Reactor power will stabilize at approximately the same value at BOL and EOL.

Page 62 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 63.

Given the following Unit 1 conditions:

• The Unit is at 100% power.

• Generator Breaker IA then spuriously opens.

• The ONLY annunciator associated with the Turbine or Generator that alarms is:

lAD-Il, F/I, GEN BKR B OVERCURRENT Which ONE of the following describes:

(1) another annunciator which SHOULD have alarmed; AND (2) a manual action required for mitigating these conditions?

A. (1) lAD-i, F14, TURB RUNBACK INITIATED (2) Manually initiate a turbine runback to 48%.

B. (1) lAD-i, F/4, TURB RUNBACK INITIATED (2) If condition has not cleared within three minutes, manually trip Generator Breake r 1 B.

C. (1) lAD-li, F17, GEN BKR B TROUBLE (2) Manually initiate a turbine runback to 48%.

D. (1) lAD-Il, F17, GEN BKR B TROUBLE (2) If condition has not cleared within three minutes, manually trip Generator Breake r I B.

Page 63 of 100

2010 Catawba Nuclear Station - NRC Initial License Examination 64.

Given the following conditions:

• All liquid waste system controls are in normal configuration.

• A large amount of highly radioactive water begins entering the CA pump room sump.

• The room sump pump automatically starts and the sump level begins to decrease slowly.

• The following annunciator is then received:

• 1 RAD-2, B/3, I EMF 52 CLEAN AREA FLOOR DRN HI RAD.

Due to the above conditions, the level in the Turbine Building Sump will A. NOT increase, because the CA Pump Room Sump Pumps will trip on high radiation.

B. INCREASE to the sump pumps automatic start setpoint, the sump pumps start, and then they all trip on high radiation.

C. NOT increase, because the CA Pump Room Sump Pumps discharge is automatically rerouted to the ND/NS sump due to the high radiation.

D. INCREASE, but the sump pumps will start ONLY if the Emergency High level is reached.

Page 64 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 65.

An air leak has developed on the VI System.

As VI pressure decreases, the setpoint at which 1 Vl-500, VI Supply to VS closes is _(1

)_,

and the setpoint at which the VS BASE air compressor starts is _(2).

A. (1) 85psig.

(2) 90 psig.

B. (1) 8opsig (2) 76 psig C. (1) 85psig (2) 8Opsig.

D. (1) 8opsig.

(2) 90 psig.

Page 65 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 66.

Which ONE of the following describes a required duty of the Reactor Operator stationed in the Control Room during fuel handling operations, per NSD 414, (Fuel Handling)?

A. Monitor Source Range instrumentation while a fuel assembly is being placed in the core.

B. During actual core alterations, conduct PT!1A/4550/OO1 C (Refueling Communications Test) once each hour.

C. Monitor the refueling communications circuit to track correct placement of fuel assemblies.

D. Ensure the correct fuel assembly is being moved to the reactor building by monitoring SEP upender camera.

Pane 66 of

2010 Catawba Nuclear Station - NRC Initial License Examination 67.

Given the following conditions:

• Unit 1 is at 50% power.

• Unit 2 is in a refueling outage, with fuel moves in progress from the Reactor cavity to the Spent Fuel Pool.

For the above conditions, and per Selected Licensee Commitment 16.13-4, (Minimum Station Staffing Requirements), which ONE of the following describes the MINIMUM required numbe r of RO5 to be present at all times in the area marked NORMAL (total for both units);

AND the total MINIMUM required number of ROs on shift?

Reference Provided Total Minimum ROs in Area Marked NORMAL Total Minimum Required ROs on shift A. 2 3 B. 2 4 C. 3 3 D. 3 4 Pan

2010 Catawba Nuclear Station NRC Initial License Examination 68.

The DC Power On light for CAPT Elect Ops Status, 1SA-145 on 1MC-1O is OUT.

Which ONE of the following describes the process for troubleshooting this condition?

A. Follow the guidance in lAD-I I, L12 (BIO ALTERNATE CONT PWR LOSS) to dispatch an NEO to 1TBOXO398 (SB594, U-31) to troubleshoot the condition.

B. Replace the light bulb, If it is still not lit, this means FU1 or FU2 is blown. Write a Work Request to have the fuse replaced.

C. Follow the guidance in OMP 2-39, (Changing Control Indicating Lights). It provides specific a

troubleshooting sequence for this particular component.

D. Use OP/O/A163501014, (Operations Troubleshooting Guidelines), to determine the cause of this condition. Then write the appropriate Work Request for repair.

Page 68 of 100

4 2010 Catawba Nuclear Station NRC Initial License Examination 69.

During a pre-job brief it is identified that several steps in an operating procedure need to be performed in a different sequence from what is written in the procedure.

Which individual must approve this change, per NSD-704, (Technical Procedure Use and Adherence)?

A. Operations Shift Manager (OSM)

B. Shift Operations Manager (SCM)

C. Work Control Center (WCC) Supervisor D. Unit Supervisor (US)

Page 69 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 70.

Given the following conditions:

A planned Liquid Waste Release of Waste Monitor Tank (WMT) A was initiated at 1110.

The following timeline of events then occurs:

1120- 1 RAD-1, C15, EMF-49 LIQUID WASTE DISCH HI RAD alarms.

1130 The release is manually re-initiated without re-sampling.

1145- 1 RAD-1, C15, EMF-49 LIQUID WASTE DISCH HI RAD alarms.

1155 The release is manually re-initiated without re-sampling.

1215- 1RAD-1, C15, EMF-49 LIQUID WASTE DISCH HI RAD alarms.

Based on the above conditions:

(1) can the release be manually re-initiated, without re-sampling, per OP/0/B/6500/113, (Operations Liquid Waste Release);

AND (2) which valve has been automatically closed to terminate the release?

A. (1) NO (2) 1WL-X28 B. (1) NO (2) 1WL-124 C. (1) YES (2) IWL-X28 D. (1) YES (2) 1WL-124 Page 70 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 71.

Prior to a refueling outage an operator has received 1500 mR so far for that year. During the refueling outage, the operators first assigned task results in receiving a dose of 230 mR.

The NEXT time the operator logs on to the EDC computer, what type of notification flag will the operator see next to their name; AND per NSD 507,( Radiation Protection), what will be required prior to RCA entry?

Type of Notification Flag Required Prior to RCA Entry A. Alert Notify their supervisor.

B. Alert Obtain a dose extension approval.

C. Exclude Notify their supervisor.

D. Exclude Obtain a dose extension approval.

Page 71 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 72.

Given the following conditions:

• An operator has logged on to RWP #23, Entry for Routine Plant and Systems Operation (Operations), Task #4, Entry for Troubleshooting/Special Inspections.

• The operator needs to reach across a Contaminated Area boundary to access a component located in Unit I ND Pump Room.

• RP has determined that donning a single rubber glove will be adequate to prevent a personnel contamination.

The operator then proceeds as follows:

1. Contacts RP and obtains verbal authorization to reach across the Contaminated Area boundary.

2. Dons the rubber glove and accesses the component across the Contaminated Area boundary.

3. Removes rubber glove and places it in the contaminated clothing container.

4. Exits the ND Pump Room and immediately proceeds to SPA (Single Point of Access).

5. Notifies RP of the results of completion of the task.

6. Exits the RCA and reports to the Control Room.

Which ONE of the following is the correct evaluation of the above conditions, per NSD 507, (Radiation Protection)?

A. All RWP requirements were met.

B. RP was required to issue a revised RWP before authorizing this operation.

C. RP was required to take additional smear samples of the component before the operation.

D. The operator was required to frisk hands and feet upon exiting the ND Pump Room.

Page 72 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 73.

Of the four (4) nuclear instruments listed in F-O, (Critical Safety Function Status Trees), for assessing the Subcriticality safety function, which ONE is a Post-Accident Monitoring (PAM) instrument required by LCO 3.3.3, PAM (Post-Accident Monitoring) Instrumentation?

A. Source Range B. Intermediate Range C. Power Range D. Wide Range Page 73 of 1

2010 Catawba Nuclear Station NRC Initial License Examination 74.

Given the following Unit 1 conditions:

• The Unit is at 50% power.

Which ONE of the foIlowng indications will result in entry into an emergency procedure?

(Consider each separately.)

A. EHC pressure indicates 1000 psig.

B. INCFT5O1O (NC Flow Loop A Ch. 2) indicates 85%.

C. Stator inlet pressure indicates 45 psig.

D. Two (2) SG IC NR levels indicate 84%.

Page 74 of 100

2010 Catawba Nuclear Station NRC Initial License Examination 75.

Given the following Unit 1 conditions:

• The Unit is tripped from 100% power due to a loss of Component Cooling Water (KC).

• The crew transitions to ES-0.1, (Reactor Trip Response), while continuing to perform the actions of AP/1/A15500/021, (Loss of Component Cooling).

Fifteen minutes after the trip, the following conditions exist:

• SG pressures are all approximately 1005 psig and stable.

• NC System pressure is 2235 psig and stable.

• Thot is approximately 570°F in all loops and slowly decreasing.

• Core Exit Thermocouples (CETs) indicate approximately 575°F and stable.

• Tcold is approximately 547°F in all loops and stable.

Reference Provided Which ONE of the following describes the status of NC System heat removal for the current plant conditions?

A. Natural circulation is NOT established. NC System subcooling is inadequate.

B. Natural circulation is NOT established. CETs are not decreasing.

C. Natural circulation is established. Heat removal is via the steam dumps.

D. Natural circulation is established. Heat removal is via the SG PORVs.

Page 75 of 100

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December 2010 CNS NRC Initial License Examination Written Exam KEY

1. C 50.C 99.D

2. D 51. C 100.D

3. A 52.D

4. C 53.B

5. A 54.D

6. C 55.B

7. B 56.B

8. A 57.C

9. A 58.A 10.D 59.D 11.B 60.A 12.B 61.C 13.D 62.B 14.A 63.A 15.B 64.C 16.A 65.D 17.A 66.A 18.D 67.A 19.C 68.C 20.C 69.A 21.C 70.B 22.A 71.A 23.C 72.D 24.B 73.D 25.D 74.D 26.A 75.C 27.C 76.BLD4 28.C 77.A 29.D 78.B 30.A 79.A 31.A 80.D 32.A 81.D 33.D 82.C

34. B 83. BEJ3

35. A 84. C 36.D 85.C

37. B 38.A 87.B 39.A 88.A 40.C 89.B

90. A 42.C 91.B 43.C 92.C 44.C 93.D 45.A 94.A 46.B 95.D 47.D 96.B 48.D 97.A 49.B 98.A Page lof 1