Text

Initial Exam 2013-301 Final SRO Written Exam
	ML13275A076
Person / Time
Site:	Catawba
Issue date:	10/01/2013
From:	; NRC/RGN-II
To:	; Duke Energy Corp
References
	50-413/13-301, 50-414/13-301
	Download: ML13275A076 (110)
	v • d • e

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question I Given the following Unit 1 initial conditions:

The Unit is at 58% power.

Turbine bearing #8 vibration began to rise rapidly.

With bearing #8 vibration at 16 mils and continuing to rise, the operator attempted to manually trip the turbine by depressing the Turbine Trip pushbutton.

Current Conditions:

All turbine stop and control valves are OPEN.

lAD-i, B17 (Manual Turb Trip CIR) is DARK.

The crew is performing the Immediate Actions of AP/1/A/5500!002, (Turbine Generator Trip).

In accordance with AP/02, the operator will attempt to CLOSE the turbine control valves at a rate of 100% over a period of (1)

If that action is NOT successful, the NEXT required action is to (2)

A. (1) 3 minutes (2) trip the reactor B. (1) 3 minutes (2) close all MSIVs and bypass valves C. (1) 45 seconds (2) trip the reactor D. (1) 45 seconds (2) close all MSIVs and bypass valves Page 1 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 2 Given the following Unit 1 conditions:

Initial

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

SI has been terminated.

The crew is maintaining the piant in a stable condition per EPI1IAI5000IES-1.1 (SI Termination).

PZR pressure is 2185 psig and stable.

PZR level is 50% and stable.

Current

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

PRT pressure is 20 psig.

PZR level is 17%.

NC subcooling is negative 5°F.

Based on the event in progress:

(1) Safety Injection re-initiation be required.

(2) PZR Safety valve tailpipe temperature will be indicating A. (1) willNOT (2) 315°F B. (1) will (2) 315°F C. (1) willNOT (2) 260°F D. (1) will (2) 260°F Page2of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 3 Given the following:

A small-break LOCA has occurred.

EP/1/N5000/E-1 (Loss of Reactor or Secondary Coolant) has been entered.

Neither train of ICCM is available.

Total CA Flow is 600 gpm and stable.

Core Exit T/Cs on OAC indicate 545°F.

All Hot Leg temperatures are 530°F.

All Cold Leg temperatures are 51 5°F.

NC B LoopW/R pressure is stable at 1000 psig.

Pressurizer level is 33% and stable.

(1) In accordance with E-1,the value of subcooling is (1)

(2) S/I termination criteria (2) met.

Which ONE of the following completes the above statements?

Reference Provided A. (1) 0°F (2) ARE B. (1) 0°F (2) are NOT C. (1) +15°F (2) ARE D. (1) -15°F (2) are NOT Page3of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 4 During a Large Break LOCA, the operator notes the following trend (from Time 1 to Time 6) indication on Train A and Train B of ICCM subcooling margin monitor:

Time 1: 15°F Time 2: 0°F Time 3: minus 5°F Time 4: minus 35°F Time 5: minus 35°F Time 6: minus 35°F (1) Subcooling margin indications are based on the average of loop wide range hot leg temperatures and the average of the (2) What is the significance of the subcooling margin monitor indications for Times 4, 5, and 6?

A. (1) 5 highest CETs

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

B. (1) ShighestCETs (2) Unit conditions have stabilized.

C. (1) 40 ACC qualified CETs (2) Subcooling margin monitor indication is at the bottom of its scale.

D. (1) 40 ACC qualified CETs (2) Unit conditions have stabilized.

Page4of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 5 During a small break LOCA the following NCP vibration data are received for I D NCP:

Which ONE of the following is the earliest time at which the NCP trip criteria was MET, in accordance with annunciator response procedures?

A. 2100 B. 2105 C. 2110 D. 2115 Page 5of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 6 Given the following Unit 1 conditions:

The Unit is at 100% power.

Pressurizer level is currently 50% and slowly decreasing.

INV-294 (NV Pumps Disch Flow Controller) valve demand signal indicates 100%.

1 NV-309 (NCP Seal Injection Control Valve) is in auto.

(1) Assuming NO operator action, which ONE of the following describes the cause of this transient?

(2) Seal Injection providing cooling to the NCP seals.

A. (1) Tave input to the Pressurizer Level -Control System has failed LOW.

(2) Is NOT B. (1) Total Sealwater Flow Transmitter output has gradually failed LOW.

(2) Is C. (1) Tave input to the Pressurizer Level Control System has failed LOW.

(2) Is D. (1) Total Sealwater Flow Transmitter output has gradually failed LOW.

(2) Is NOT Page6of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 7 Given the following Unit 1 conditions:

The Unit has entered a refueling outage and is in Mode 5.

IA Train ND is OPERABLE and secured.

18 Train ND is in service.

NC temperature is 110°F.

All SIG NR levels are 10%.

NC system drain procedure is in progress.

NC Wide Range level is 22%.

Subsequently:

ND Pump lB TRIPS.

In accordance with Technical Specifications, the Required Action is to immediately 2

Which ONE of the following completes the above statement?

A. Suspend operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet SDM.

B. Initiate action to restore required S/G secondary side water levels to within limits.

C. Close all containment penetrations providing direct access from containment atmosphere to outside atmosphere.

D. Initiate action to establish > 23 ft. of water above the top of reactor vessel flange.

Page 7 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 8 Given the following Unit 1 conditions:

A LOCA inside containment is occurring.

Containment pressure peaked at 3.2 psig.

FWST level decreased to 30%.

(1) The non-essential KC headers are automatically isolated by the (1) signal.

(2) This isolation prevents KC pump runout due to the (2) valves receiving an OPEN signal.

Which ONE of the following completes the above statements?

A. (I) Safety Injection (2) NDHX Inlet (IKC-56A/81B)

B. (1) Phase B (2) NDHX Inlet (1 KC-56A/81 B)

C. (1) Safety Injection (2) NDI-IX Outlet (1 KC-57N82B)

D. (1) Phase B (2) NDHX Outlet (1 KC-57N828)

Page Bof 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 9 Given the following Unit 1 conditions:

Initial:

The Unit was at 100% power.

A turbine trip occurred.

The reactor did NOT trip and could NOT be tripped from the Control Room.

Current:

Pressurizer pressure is 2350 psig.

The crew has transitioned to EP/1/N5000/FR-S.1 (Response to Nuclear Power Generation/ATWS).

The crew is initiating emergency boration in accordance with Step 4 of FR-S.1.

(1) A minimum emergency boration flowrate of gpm is required to avoid swapping NV pump suction to the FWST.

(2) Pzr PORV operation be required to enhance emergency boration flow.

Which ONE of the following completes the above statements, in accordance with FR-S.1?

A. (1) 30 (2) Will NOT B. (1) 60 (2) Will NOT C. (1) 30 (2) Will D. (1) 60 (2) Will Page9of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 10 A Unit shutdown is in progress for a refueling outage with the following conditions:

Pressurizer pressure is 1800 psig.

Steam line pressure is 750 psig.

Subsequently:

A large steam break occurs upstream of B MSIV and outside containment.

B steam generator completely depressurizes.

(Assume NO manual action is taken after the steam break occurs.)

Based on the above information:

(1) Safety Injection automatically occur.

(2) Main Steam Isolation automatically occurred due to ONLY.

A. (1) did NOT (2) HIGH negative rate of B steam line pressure B. (1) did NOT (2) LOW B steam line pressure C. (1) did (2) HIGH negative rate of B steam line pressure D. (1) did (2) LOW B steam line pressure Page 10 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 11 Given the following Unit I conditions:

The Unit was at 6% power during a post refueling startup with IA CFPT in service.

Subsequently:

The following events occur at the listed times:

1000 An NC system leak develops.

PZR pressure is 2220 psig and decreasing at 2 psig/min.

PZR level is 26% and decreasing at 0.3%/minute

1003 IA CFPT trips due to low oil pressure.

1005 1C NCP trips on underfrequency.

1008 Containment pressure reaches 1.2 psig.

Which ONE of the following is the EARLIEST time at which the reactor will be tripped based on a setpoint or manual action taken by procedures?

A. 1000 B. 1003 C. 1005 D. 1008 Page 11 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 12 Given the following Unit I conditions:

The Unit tripped due to a complete loss of offsite power.

The crew completed the Immediate Actions of EP/I/N5000IE-O (Reactor Trip or Safety Injection).

The crew transitioned to EP/1/A/5000/ES-O.1 (Reactor Trip Response), and is at Step 2 RNO of ES-O. 1, which requires the MSIVs to be closed due to the loss of 6.9KV power.

The backup diesel VI compressor has been placed in service.

(1) The purpose of closing the MSIVs is to (2) Following completion of this step, automatic S/G PORV operation be available.

Which ONE of the following completes the above statements?

A. (I) maintain S/G inventory (2) will NOT B. (I) minimize cooldown (2) will NOT C. (I) maintain S/G inventory (2) will D. (I) minimize cooldown (2) will Page 12 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 13 During the performance of AP!OIA/55001020, (Loss of Nuclear Service Water), Case I, toss of RN Train, Step 8, the operator is directed to verify that each operating RN pump has the required minimum flow.

If this required minimum flow is NOT met, then a certain amount of flow will be directed through the (1) , not to exceed (2) in order to avoid flow induced vibration problems.

Which ONE of the following completes the above statement?

A. (1) KCHx (2) 4650 gpm B. (1) NSHx (2) 4650 gpm C. (1) KCHx (2) 2550 gpm D. (1) NSHx (2) 2550 gpm Pagel3of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 14 Given the following plant conditions:

Both Units are at 100% power.

A seismic event has occurred.

The crew is performing actions of AP101A155001022 (Loss of Instrument Air).

All available Instrument Air Compressors are running and loaded.

lnstwment Air pressure continues to DECREASE.

In accordance with AP!22:

(1) What is the LOWEST Instrument Air pressure at which the CRS is required to direct a reactor trip?

(2) Loss of Normal Feedwater supply the reason for the manual reactor trip.

A. (1) 55psig (2) is B. (1) 6Opsig (2) is not C. (1) 55psig (2) is not D. (1) 60psig (2) is Page 14 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 15 Note the step below from AP/1/A/5500/037 (Generator Voltage and Electric Grid Disturbances):

Select MANUAL on turbine control panel.

(1) The above direction is given ONLY in (2) The basis for this step is to ensure reactor power is maintained less than a maximum of Which ONE of the following completes the above statement?

A. (I) Case I (Abnormal Generator or-Grid Voltage)

(2) 69%

B. (1) Case I (Abnormal Generator or Grid Voltage)

(2) 100%

C. (1) Case II (Abnormal Generator or Grid Frequency)

(2) 69%

D. (1) Case II (Abnormal Generator or Grid Frequency)

(2) 100%

Page 15 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 16 Given the following Unit 1 initial conditions:

The Unit was at 100% power.

Subsequently:

At 0200: The reactor tripped due to a LOCA outside containment.

At 0210: The crew entered EP/1/A/5000/ECA-1 .2, (LOCA Outside Containment).

At 0220: The crew entered EP/1/A/5000/ECA-1 .1, (Loss of Emergency Coolant Recirc).

At 0240: The crew is at the step in ECA-1 .1 for determining NC subcooling.

Current Conditions:

NCS pressure is 1100 psig.

lB NC pump is running.

IA, IC, and ID NC pumps have been secured.

Reactor Vessel D/P is 20%.

1A NI pump is running with flow indicated at 320 gpm.

IA NV pump is running with flow indicated at 415 gpm.

Both ND pumps are OFF.

No NS pumps are running.

Subcooling is 35°F.

(1) What is the minimum required injection flowrate?

(2) Which, if any, pump can be secured?

Reference Provided A. (1) 380 gpm (2) NEITHER pump B. (1) 380 gpm (2) IA NI pump ONLY C. (1) 408 gpm (2) IANlpumpONLY D. (I) 408 gpm (2) NEITHER pump Page 16 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 17 Given the following Unit 2 conditions:

Initial:

The Unit was at 100% power.

Subsequently:

A medium break LOCA occurred inside containment.

Containment pressure peaked at 2.7 psig and is slowly decreasing.

The crew has implemented EP/2/N5000/FR-H.1 (Response to Loss of Secondary Heat Sink).

All attempts to restore flow to the S/Gs from the CA system have NOT been successful.

In accordance with FR-H.1:

(1) The next prioritized source of feedwater for restoration of flow to the S/Gs is through the CM/CF system by operating a (1)

(2) The crew is FIRST required to establish bleed and feed when W/R level in at least 3 S/Gs decreases to less than (2)

A. (1) main feedwater pump (2) 24%

B. (1) mainfeedwaterpump (2) 36%

C. (1) hotwell and booster pump ONLY (2) 24%

D. (1) hotwell and booster pump ONLY (2) 36%

Page 17 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 18 Given the following Unit I conditions:

An NC system LOCA occurred on Unit 1.

INI-184B and INI-185A (Containment Sump Isolation Valves) are CLOSED and CANNOT be opened.

EP/IIAI5000IECA-1.1 (Loss of Emergency Coolant Recirculation) was entered.

All NC pumps are OFF.

Minimum ECCS flow to remove decay heat has been established.

In accordance with ECA-1 .1, the operator will increase NCS make-up flow if...

A. Hot leg Wide Range (WR) temperatures increase by 5°F.

B. Pressurizer level is 2% and decreasing.

C. RVLIS Lower Range (LR) is 64% and stable.

D. Core Exit Thermocouples are 650°F and increasing.

Page 18 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 19 Given the following Unit I conditions:

AP/1/A15500/015 (Rod Control Malfunction) is entered due to continuous rod movement.

Rods have been placed in manual.

Initial group demand was 85 steps withdrawn on Control Bank D.

Final group demand was 101 steps withdrawn on Control Bank D.

Subsequently:

Rod D-4 DRPI experiences a Data A Failure.

(All rods are at the same actual height and in Control Bank D.)

Rod D-4 indicates steps withdrawn on DRPI.

Wtiich ONE of the following completes the above statement?

A. 108 B. 102 C.96 D.90 Page 19 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 20 Given the following Unit 1 conditions:

For a planned refueling outage, the Unit entered Mode 3 at 2120 on 08/12/2013.

Current Conditions:

The Unit is in Mode 6.

NC boron concentration is 2580 ppm.

At 1915 on 08/15/2013, a fuel bundle has been placed in the upender for transport to Spent Fuel Pool storage.

Based on the above conditions:

(1) SIC 16.9-17 (Refueling Operations Decay Time)

- required to be entered.

(2) Tech Spec 3.9.1 (Boron Concentration) required to be entered.

A. <1) is (2) is B. (1) is (2) is not C. (1) is not (2) is D. (1) is not (2) is not Page 20 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 21 Given the following Unit 1 conditions:

Unit 1 is at 100% power.

IA S/G has developed a 200 GPD tube leak.

1 EMF-33 (CSAE Discharge) Trip 2 light is LIT.

The following annunciator is alarming:

IRAD-1, B/i, 1EMF-33 CSAE EXHAUST HI RAD UNIT VENT VA UNIT 1 CSAE EXH

i. _ AUTO For the above conditions, and PRIOR TO any operator action, which ONE of the following describes whether the as-found configuration of the control switch and indication in the photo above is CORRECT and why or why not?

A. INCORRECT configuration. The VA light should be LIT due to automatic swapover caused by 1 EMF-33 reaching its Trip 2 setpoint.

B. INCORRECT configuration. The switch should have already been in AUTO, to enable CSAE exhaust automatic swapover to Aux. Bldg. (VA) filtered exhaust immediately upon I EMF-33 reaching its Trip 2 setpoint.

C. CORRECT configuration. Swapover of the CSAE exhaust to Aux. Bldg. (VA) filtered exhaust will ONLY occur when the operator OPENS 1ABF-D-1 1 and 1ABF-D-4.

D. CORRECT configuration. Swapover of the CSAE exhaust to Aux. Bldg. (VA) filtered exhaust will ONLY occur when the operator takes the switch to the AUTO position.

Page 21 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 22 In order to prevent condenser overpressurizaton upon a loss of vacuum, steam dump operation will be prevented by the C-9 permissive based on lowering vacuum sensed by at least (1) condenser pressure sensor(s) OR loss of cooling water supply based on (2)

Which ONE of the following completes the above statement?

A.(1)2 (2) RC Pump breaker position B. (1) 1 (2) RC Pump breaker position C. (1) 2 (2) RC system flowrate D. (1) 1 (2) RC system flowrate Page 22 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 23 Given the following LWR (Liquid Waste Release) Permit Report excerpt for a planned release of Recycle Monitor Tank A:

See Attached Liquid Waste Release Permit Report excerpt (1 page)

(1) In accordance with SLC 16.11-2, (Radioactive Liquid Effluent Monitoring Instrumentation),

which item on the provided LWR excerpt will require that additional sampling be performed prior to the release?

(2) If the concentration of radioactive material released to unrestricted areas exceeds the limits specified on the Liquid Waste Discharge Permit Report and in SLC 16.1 1-1 (Liquid Effluents), the concentration must be restored to within limits discovery.

Which ONE of the following completes the above statements?

A. (1) Setpoint Data (2) within one hour of B. (1) Setpoint Data (2) immediately upon C. (1) RL Pump Data (2) immediately upon D. (1) RL Pump Data (2) within one hour of Page 23 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

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CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 24 Which ONE of the following describes an action, including the reason for the action, in accordance with EP/1/A/5000/FR-Z.1 (Response to High Containment Pressure)?

A. Initiate ONE train of ND Auxiliary Spray, if containment pressure exceeds 5 psig 50 minutes following Rx Trip, in order to reduce the challenge to containment integrity due to high pressure.

B. Isolate faulted steam generators in order to reduce the challenge to containment integrity due to high pressure.

C. Secure ND Auxiliary Spray when containment pressure decreases below 3 psig in order to reduce the challenge to containment integrity due to low pressure.

D. Initiate BOTH trains of ND Auxiliary Spray, if containment pressure exceeds 15 psig 60 minutes following Rx Trip, in order to reduce the challenge to containment integrity due to high pressure.

Page 25 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 25 Given the following Unit I initial conditions:

The Unit is at 100% power.

Subsequently:

A small break LOCA occurs.

The crew is performing EP/IIA5000IES-l.2 (Post LOCACooldown and Depressurization).

Al NC pumps are secured.

(1) What is the maximum NC system cooldown rate specified in this procedure?

(2) Which method is the first choice for the NC system depressurization for the given conditions?

A. (1) 100°F/hr (2) NV auxiliary spray B. (1) Maximum achievable rate (2) NV auxiliary spray C. (I) 100°F/hr (2) NCPORV D. (1) Maximum achievable rate (2) NCPORV Page 26 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 26 Given the following:

Unit I has experienced a small break LOCA.

The crew has completed applicable steps of EP/1/A15000/E-0 (Reactor Trip or Safety Injection) and entered EPI1IA/50001E-l (Loss of Reactor or Secondary Coolant).

1 B NCP has been secured due to #1 seal failure.

Subsequently:

1A, 1C, & 1D NCPs are in service.

Core Exit Thermocouples: 706°F and slowly increasing.

RVLIS Level: 60% and slowly decreasing.

1 C NCP Motor Stator Temp: 315°F and slowly increasing.

Subcooling: -5°F.

The crew has transitioned to FR-C.2, (Response to Degraded Core Cooling).

How will the crew address immediate operation of the NCPs (trip vs. leave running), in accordance with FR-C.2?

IANCP ICNCP IDNCP A. leave running trip leave running B. leave running trip trip C. trip trip trip D. leave running leave running leave running Page 27 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 27 During a large break LOCA, the following conditions are given:

The ECCS suctions have been swapped to the Cold Leg Recirculation alignment.

NS suction has been swapped to the containment sump.

1A NS is in service.

FWST level 4%.

Containment Sump level is off scale high.

Containment pressure = 7 psig and slowly decreasing.

CETs56O°F.

RVLIS Level is 57% and slowly decreasing.

PZRIevelisO%.

NC Subcooling is -5°F.

Which ONE of the following describes:

(1) The implications of the above conditions.

(2) Which procedure entry conditions are met?

A. (1) Containment sump level is higher than would be expected for a Large Breal LOCA.

(2) EPI1IAI5000/FR-C.2 (Response to Degraded Core Cooling)

B. (1) The level of water in the ccwe region has been reduced such that the core has become uncovered.

(2) EP/1/N5000/FR-C.2 (Response to Degraded Cere-Cooling)

C. (1) Containment sump level is higher than would be expected for a Large Break LOCA.

(2) EPIIIN5000/FR-Z.2 (Response to Containment Flooding)

D. (1) The level of water in the core region has been reduced such that the core has become uncovered.

(2) EPI1IN5000IFR-Z.2 (Response to Containment Flooding)

Page 28 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 28 Given the following:

TIME NC Tcold Temperatures S!G Water Temperatures 0600 202°F 273°F 0700 205°F 264°F 0800 209°F 255°F 0900 212°F 246°F What is the EARLIEST time at which an NCP may be started, in accordance with Tech. Spec.

3.4.6, (RCS Loops Mode 4)?

A. 0600 B. 0700 C. 0800 D. 0900 Page 29 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 29 Given the following Unit I conditions:

The Unit is at 100% power.

NV makeup controls were last adjusted three (3) days ago.

The CRS directs setpoints to be updated per 0P111A16150/009, Enclosure 4.1 (Automatic Makeup).

Given the current sample results:

NC Boron = 600 ppm

RMWST Boron =35 ppm

FWST Boron = 2900 ppm

BAT Boron = 7500 ppm (1) Enclosure 4.1 will require changing I NV-238A (B/A Xfer Pmp to Blender Ctrl) setpoint to (2) Upon decreasing VCT level, an automatic makeup will begin at A. (1) 7.2 (2) 32.7 B. (1) 7.2 (2) 35 C. (1) 8.0 (2) 32.7 D. (1) 8.0 (2) 35 Page 30 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 30 Given the following:

Unit 1 is in Mode 5.

The reactor coolant system is water solid.

IA ND is in service. lB ND is secured.

lB NV pump is in service.

1 NV-294 (NV Pumps Disch Flow Controller) is being controlled manually.

INV-309 is in automatic.

All plant parameters are stable.

Subsequently:

1 KC-56A (KC to ND Hx 1A Sup Isol) closes due to controller malfunction.

Operators are taking action to stabilize NC system pressure while lB ND is placed in service.

Letdown flow is maintained constant in order to maximize system cleanup.

In response to this event(and prior to placing lB ND in service):

(1) lB NV pump motor amps will be (2) 1 NV-309 (NCP Seal Injection Control Valve) will throttle A. (1) lower (2) open B. (1) lower (2) closed C. (1) higher (2) open D. (1) higher (2) closed Page 31 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 31 Given the following Unit I conditions:

The Unit is in Mode 5 following core reload.

IA ND Pump is operating.

ND system flow is 3100 gpm.

NC system level is at 6.7%.

Subsequently:

NC system level remains stable at 6.7%.

Core Exit T/Cs are stable at I t5°F.

IA ND pump flow and discharge pressure begin to oscillate.

In accordance with AP/lIAt5500I0l9 (Loss of Residual Heat Removal System), Case IV, loss of ND in Mid Loop, the operator is first required to initiate containment evacuation, containment closure, and then to A. manually trip IA ND pump.

B. place 18 ND train in service.

C. attempt to mitigate IA ND pump conditions by raising NC level to greater than 25%.

D. attempt to mitigate 1A ND pump conditions by reducing ND flow to less than 1000 gpm.

Page 32 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 32 Given the following plant conditions:

Initial:

Unit 1 is at 100% power.

Unit2isinMode6.

lB NV pump is running.

1A NV pump is OFF.

Subsequently:

KC cooling flow to the Unit I NV pumps is lost.

The crew enters AP/l/A/5500/021, (Loss of Component Cooling) and has dispatched an operator to align backup cooling to an NV pump.

The crew is performing Enclosure 5, Maximize NV Pump Run Time.

(1) The crew dispatched the operator to align alternate cooling to (1) NV pump(s).

(2) While the alternate cooling alignment is being performed, the operating pump will be (2)

A. (1) ONLY1A (2) Secured immediately.

B. (1) ONLY IA (2) Operated for a maximum of 10 minutes.

C. (1) lAandlB (2) Secured immediately.

D. (1) lAandlB (2) Operated for a maximum of 10 minutes.

Page 33 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 33 I NC-54A (Nitrogen to PRT Containment Isolation) (I) receive an automatic isolation signal if containment pressure exceeds 1.2 psig.

1 NC-I 07 (PRT to NCDT Pumps Suction) (2) receive an automatic isolation signal if PRT pressure exceeds 8.0 psig.

A. (I) does (2) does B. (1) does (2) does not C. (1) does not (2) does D. (1) does not (2) does not Page 34 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 34 Given the following Unit 2 initial conditions:

The Unit was at 100% power when the reactor was manually tripped due to a partially stuck open PZR Safety Valve.

Subsequently:

At 1005: Containment pressure is NEGATIVE 0.2 psig.

At 1010: PRT pressure rises to approximately 50 psig and then rapidly decreases.

(1) At time 1005, Tech Spec. 3.6.4.(Containment Pressure) met.

(2) At time 1010, the PRT rupture disc(s) op&ated A. (1) is NOT (2) as designed B. (1) is NOT (2) earlier than designed C. (1) is (2) as designed D. (I) is (2) earlier than designed Page 35 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 35 Which ONE of the following describes the NORMAL and BACKUP makeup supplies to the KG Surge Tank?

NORMAL BACKUP A. YF RN B. YM YD C. YM RN D. YE YD Page 36 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 36 Given the following Unit 1 conditions:

The Unit was at 60% power prior to a steam leak in the turbine building.

The crew has isolated the leak per AP/1/A15500/028 (Secondary Steam Leak).

The crew is responding to low Pressurizer pressure per AP/1!N5500/01 I (Pressurizer Pressure Abnormalities).

Subsequently:

1A and 1 D Pressurizer Heaters automatically ENERGIZED at appropriate setpoint.

Pressurizer pressure is at 2140 psig and slowly increasing.

I B Pressurizer Heater is DE-ENERGIZED due to breaker failure.

Based on the above listed conditions:

(1) Automatic PZR PORV operation blocked.

(2) Tech Spec 3.4.9 (Pressurizer) met.

A. (1) is NOT (2) is B. (1) is NOT (2) is NOT C. (1) is (2) is D. (1) is (2) is NOT Page 37 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 37 Given the following Unit 2 conditions:

The Unit is at 100% power.

2B Pressurizer heaters are manually energized to promote mixing following unit start-up.

All plant parameters are at equilibrium.

A fault causes breaker 2LXH-6C (2B NC PZR Heater Power Panel PHP2B Feeder) to OPEN.

(I) How will the output of the pressurizer master control change?

(2) What is the systems response to the loss of heat input?

A. (1) Increase (2) Pressurizer Spray Valves will close prior to A & D Pressurizer Heaters energizing.

B. (1) Decrease (2) Pressurizer Spray Valves will close prior to A & D Pressurizer Heaters energizing.

C. (1) Increase (2) A and D Pressurizer Heaters will energize prior to Pressurizer Spray Valves closing.

D. (1) Decrease (2) A and D Pressurizer Heaters will energize prior to Pressurizer Spray Valves closing.

Page 38 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 38 In accordance with Technical Specifications, which ONE of the following reactoc trips is required to be OPERABLE to provide protection against Departure from Nucleate Boiling (DNB) from Mode 2 to 100% power?

A. Pressurizer low pressure B. OPDT C. Low NC loop flow D. OTDT Page 39 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 39 Given the following Unit I conditions:

The Unit is at 100%.

Testing has revealed that ONE channel of Auxiliary Feedwater Auto-Start logic on Trip of ALL Main Feedwater Pumps will NOT actuate within the acceptance criteria.

The channel is declared INOPERABLE at time 0415.

In accordance with T.S. 3.3.2, (ESFAS Instrumentation), the required action is to place the channel in A. trip no later than 0515.

B. bypass no later than 0515.

C. trip no later than 0445.

D. bypass no later than 0445.

Page 40 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 40 Given the following Unit I conditions:

Initial:

The Unit is at 80% power.

Lower Containment Ventilation Units (LCVUs) 1A, I B, IC are in operation.

Upper Containment Ventilation Unit {UCVU) I B is in operation.

Subsequently:

Containment temperature, pressure, and humidity are slowly increasing.

Containment radiation levels are normal.

In accordance with AP/I/A15500/028, (Secondary Steam Leak), ALL LCVUs will be operated in (1) speed, and {2) cooling.

A. (1) HIGH (2) NORM B. (I) HIGH (2) MAX C. (I) LOW (2) NORM D. (I) LOW (2) MAX Page 41 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 41 Given the following Unit I conditions:

The Unit is in Mode 4.

IAD-13 /A7 (ICE COND LOWER INLET DOORS OPEN) alarm is LIT.

The lower inlet door position display panel indicates that a door is open.

The door is confirmed to be cracked opened, and cannot be closed.

No other alarms related to the ice condenser, NF system or AHUs are lit.

Which, if any, of the following is REQUIRED to be entered based on the current plant conditions?

I. Tech Spec 3.6.13 (Ice Condenser Doors)

2. Tech Spec 3.6.12 (Ice Bed)

A. I ONLY B. 2 ONLY C. land2 D. No Tech. Spec. entry required.

Page 42 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 42 In order to align 1A train ND to supply containment spray, 1 NS-43A (ND Pump A to NS Spray Header Containment Isolation Valve) must be opened.

(I) In order to open this valve, must be open.

(2) Once aligned, spray be directed through the NS spray rings.

A. (1) 1NS-18A (NS Pump A Suct from Cont Sump)

(2) will B. (1) INS-i 8A (NS Pump A Suct from Cont Sump)

2) will NOT C. (1) 1NI-185A (ND Pump lACont Sump Suct)

(2) will D. (1) iNl-i85A (ND Pump IA Cont Sump Suct)

(2) will NOT Page 43 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 43 Which Motor Control Center provides power to 1NS-20A (NS Pump 1A Suct from FWST)?

A. 1EMXA B. IEMXD C. 1MXC D. 1MXD Page 44 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 44 In order to protect the Main Turbine from overspeed following a loss of generator load, the (1) will close at a maximum of (2) of rated speed.

A. (1) Intercept Valve (2) 103%

B. (1) Intercept Valve (2) 105%

C. (I) Reheat Stop Valve (2) 103%

D. (1) Reheat Stop Valve (2) 105%

Page 45 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 45 Given the following Unit I conditions:

Reactor power is 8%.

Steam Dumps are in MANUAL.

Preparations are being made to place the Main Turbine online.

Subsequently:

ISV-21 (IA S/G Safety No. 2) fails OPEN and cannot be isolated.

Complete the following statement:

(1) Assuming no operator action, reactor power will STABILIZE at approximately A. 8%

B. 10.5%

C. 13%

D. 15.5%

Page 46 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 46 Given the following Unit 2 conditions:

Unit 2 is currently at normal operating pressure and temperature making preparations for unit startup following refueling shutdown.

2A and 2B CA pumps are maintaining S/G levels.

2A CFPT has been reset and pump startup preparations are in progress.

Subsequently:

The RO allows all S/G levels to increase to 80%

(1) 2A CFPT is currently (2) A purpose of the P-14 signal to avoid challenging main steam piping and supports due to excess weight.

A. (1) reset (2) is B. (1) reset (2) is not C. (1) tripped (2) is not D. (1) tripped (2) is Page 47 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 47 Given the following Unit I initial conditions:

The Unit was at 100% power.

The 1C SIG secondary manway failed resulting in a reactor trip and safety injection.

10 minutes later:

Containment pressure is 3.2 psig and slowly decreasing.

SIG parameters are as follows:

NRLeveI 14% 8% 5% 16%

CA Flow 110 gpm

] 130 gpm 120 gpm j 100 gpm

All NC Tcolds are 445°F and decreasing.

All NC Thots are 475 °F and decreasing.

All MSIVs are OPEN and will NOT close.

The crew has entered EP/1 /A15000/ECA-2. I (Uncontrolled Depressurization of All Steam Generators).

(1) How will the crew respond to step 6 to Control feed flow... inEP/1/AI5000IECA-2.1?

(2) Which temperature indication is used to initiate dumping steam and evaluating changes to CA flow for stabilizing NC temperature in this procedure?

A. (1) Reduce flow to 0 gpm each in IA and ID S/Gs and maintain at least 75 gpm in I B and IC S/Gs.

(2) NC Thots B. (I) Reduce flow to 75 gpm each in all four S/Gs.

(2) NC Thots C. (1) Reduce flow to 0 gpm each in IA and ID SIGs and maintain at least 75 gpm in I B and IC S/Gs.

(2) NC Tcolds D. (1) Reduce flow to 75 gpm each in all four SIGs.

(2) NC Tcolds Page 48 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 48 Which ONE of the following breaker operations can be performed from the control room given the accompanying condition?

A. CLOSE 1 ETA-2 (Alternate Feeder to 1 FTA) with 1 ETA-i (Alternate Incoming Breaker from I ETA) OPEN.

B. CLOSE PCB-i 5 (Unit Tie PCB) with PCB 14 (Unit Tie PCB) CLOSED.

C. CLOSE GEN PCB I B while MOD lever is in the SAFE position.

D. CLOSE 1 HTA-5 (1 HTA and 2HTA Tie breaker) with I HTA-1 (Incoming Eeeder from XFMR lATE) and 2HTA-4 (Incoming Feeder from XFMR 2ATE) CLOSED.

Page 49 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 49 (1) Auxiliary Control Power Batteries 1CBA and ICBB are capable of powering their associated loads for at least 1) without any manual load shedding of DC loads.

(2) Manual DC load shedding is performed so that battery capacity is maintained at a value of no less than (2) , as indicated on 1CDA and 1CDB voltage indication on IMC 8.

In accordance with EPI1IAI5000/ECA-0.0 (Loss of All AC Power), Enclosure 23, DC Loads to be Shed During Loss of All AC Power, which ONE of the following completes the above statements?

A. (1) 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (2) 100 volts B. (1) 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (2) 105 volts C. (1) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (2) 100 volts D. (1) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (2) 105 volts Page 50 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 50 In order to prevent blowing inverter input fuses, the Static Inverter must be (1) prior to closing the (2)

A. (1) Synchronized (2) DC Input Breaker.

B. (1) Synchronized (2) AC Output Breaker.

C. (1) Pre-charged (2) DC Input Breaker.

D. (1) Pie-charged (2) AC Output Breaker.

Page 51 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 51 Given the following conditions:

Unit I is at 100% power when the following alarm is received:

lAD-il, B17, DIG A PANEL TROUBLE

An NLO is dispatched and confirms that the power supply to the 1A DIG Battery Charger is de-energized.

A loss of which ONE of the following power supplies is the cause for these conditions?

A. 1EDE B. 1EMXE C. 1EADA D. 1VADA Page 52 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 52 Given the following Unit 1 conditions:

Initial:

A containment air release (VQ) is in progress.

I EMF-39 (Containment Gas) Trip 2 setpoint is set to 1300 counts per minute (cpm) per the gas waste release permit.

1 EMF-36 (Unit Vent Gas) is operable.

Subsequently:

A small reactor coolant leak develops around an instrument line.

The crew has determined that Safety Injection initiation is not warranted.

1EMF-39 countrate is 1000 cpm and increasing.

Current:

1EMF-38/39 sample pump has tripped off due to breaker failure.

1 PAD-1 D/4, 1 EMF-38/39 Containment Loss of Flow alarm is LIT.

1EMF-36 Trip 2 has actuated.

Which ONE of the following describes the effect of the above conditions?

A. The VQ release will continue until manual operator action is taken to secure it.

B. 1 EMF-36 detects the activity released and stops the VQ release.

No Containment Ventilation Isolation (Sh) signal is initiated.

C. I EMF-39 loss of flow alarm actuates an Sh signal. The Sh signal stops the VQ release.

D. IEMF-36 detects the activity released and actuates an Sh signal.

The Sh signal stops the VQ release.

Page 53 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 53 Given the following Unit 2 conditions:

The Unit is at 100%.

B Train KC is in service.

2A RN train is in operation for testing.

The RN trains are split with 2RN-48B (RN Supply X-Over lsol) closed.

2B RN pump flow is indicating 2700 gpm.

Subsequently:

2RN-351 (2B KC HX Outlet Throttle) fails closed due to valve stem separation.

Assuming flow cannot be restored, which ONE of the following parameters will exceed an operational setpoint AND require a unit trip?

A. Containment temperature B. NCP stator temperatures C. NCP motor bearing temperatures D. Letdown Heat Exchanger temperature Page 54 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 54 Given the following Unit I conditions:

The VI system on Unit 1 has become heavily contaminated with oil and debris.

The VI Air Dryer begins to rapidly clog.

(1) VI header pressure will decrease until 1VI-670 (VI Auto Dryer Bypass) automatically opens at (1)

(2) If IVI-670 FAILS and does NOT automatically open, AP/OIA/5500!022, (Loss of Instrument Air), directs the operators to (2) the air dryers locally.

A. (1) 8Opsig (2) bypass B. (1) 85psig (2) bypass C. (1) 80 psig (2) swap D. (1) 85psig (2) swap Page 55 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 55 Given the following Unit I conditions:

Unit I was at 100% power.

At 1000, a secondary steam leak occurred in Unit 1 containment.

The crew has started a controlled shutdown per AP111A155001009 (Rapid Downpower).

Containment pressure and temperature trends indicate:

Time Temperature Pressure 1000 113°F 0.15 psig 1005 117°F 0.28 psig 1010 119°F 0.42 psig 1015 122°F 0.48 psig 1020 126°F 0.65 psig 1025 129°F 0.91 psig Assuming NO manual operator actions have occurred, which ONE of the following is the EARLIEST time period at which the Lower Containment Ventilation Units (LCVUs) cooling water bypass valves (full flow valves) automatically OPEN?

A. BetweenlOO5andlOlO B. Between 1010 and 1015 C. Between 1015 and 1020 D. Between 1020 and 1025 Page 56 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 56 Given the following Unit 1 conditions:

The Unit was at 8% power.

Turbine warming was in progress.

Subsequently:

IA and IC NCPs tripped due to A train power supply fault.

A fast transfer on the associated 6900V busses did NOT occur.

(1) An automatic reactor trip occur.

(2) Following a reactor trip, the setpoint for a main feedwater isolation to automatically occur is less than or equal to Which ONE of the following completes the above statements?

A. (1) Will (2) 553°F B. (I) Will (2) 564°F C. (1) Will NOT (2) 553°F D. (1) Will NOT

<2) 564°F Page 57 of 101 Catawba 2013 NRC Initial License Exam -Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 57 Given the following:

Steam Dump Valve 1 SB-3 (Main Steam Bypass to Condenser Control Valve #3) fails open during a plant startup. No operator action has been taken. Pressurizer pressure and reactor power trends (Power Range) indicate:

Time PZR Pressure N-41 N-42 N-43 N-44 (psig) % % % %

0835 1950 8 10 8 9 0836 1910 9 10 9 9

0837 1870 9 10 10 9 0838 1830 10 11 10 9 What is the EARLIEST time at which an automatic Reactor Trip signal will be generated?

A. 0835 B. 0836 C. 0837 D. 0838 Page 58 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 58 As Unit 1 power increases above 20%, (1) input(s) into the anticipatory circuit of narrow range S/G level response. This is due to a(n) (2) transfer within the S/G water level control system.

A. (1) Steam Flow and Feed Flow (2) Manual B. (1) Steam Flow and Feed Flow (2) Automatic C. (1) Wide Range S/G.Level (2) Manual D. (1) WideRangeS/G Level (2) Automatic Page 59 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 59 Unit I was initially at 100% power when the following sequence of events occurred:

1000

A Loss of Offsite Power occurred.

The reactor tripped.

When IA DIG attempted to load I ETA, 86N (Normal Incoming Undervoltage) relay actuated.

1005

A large break LOCA inside containment developed.

Containment pressure quickly increased to 3.0 psig and continues to slowly increase.

At 1010, which ONE of the following describes the status of the VE (Annulus Ventilation) fans?

A. ONLY 1 B VE fan is running.

B. 1A AND 1 B VE fans are running.

C. ONLY I B VE fan will start in 4 minutes.

D. IA AND 1 B VE fans will start in 4 minutes.

Page GOof 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 60 Given the following:

Unit 1 is in Mode 6 with core unload in progress.

IA KF pump is running.

An RP Technician in the Spent Fuel Pool (SFP) building reports that level in the SFP is DECREASING.

The fuel assembly most recently removed from the core is currently in the reactor building manipulator crane.

In accordance with AP/1/A15500/026 (Loss of Refueling Canal Level):

(1) If the level in the Spent Fuel Pool decreases to 38.0 feet, the 1A KF pump required to be secured.

(2) The fuel assembly in the reactor building manipulator crane is REQUIRED to be placed A. (1) is (2) Into the upender and lowered to the fully down position.

B. (1) is (2) Fully down in the core or the deep end of the canal.

C. 1) isNOT (2) Into the upender and lowered to the fully down position.

D. (1) is NOT (2) Fully down in the core or the deep end of the canal.

Page 61 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 61 Which ONE of the following describes the effect of 1 EMF-1 5, Spent Fuel Building Refueling Bridge Monitor losing power?

A. Fuel movement in the Spent Fuel Pool must be stopped immediately.

B. SFP Ventilation System automatically swaps to filter mode.

C. New fuel elevator cannot be operated in the UP direction.

D. The Auxiliary Hoist cannot be raised.

Page 62 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 62 Given the following conditions:

Unit 1 and 2 are at 100% power.

VQ release is in progress on both units.

Subsequently:

A leaking isolation valve has initiated an unplanned release from C Waste Gas Decay Tank.

A packing leak has developed at 1WG-160 (WGDT Outlet to Unit Vent Isol).

OEMF-41 (Aux Bldg Ventilation) is in Trip 2.

I EMF-36 (Unit Vent Gas Monitor) is in Trip 2.

No operator action has been taken.

Currently:

(1) 2AVA alignedtofiltermode.

(2) Unit 2 VQ release been secured.

A. (1) is (2) has B. (1) is (2) has NOT C. (1) is NOT (2) has NOT D. (1) is NOT (2) has Page 63 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 63 Given the following Unit 1 initial conditions:

The Unit is at 100% power.

1A1 Cont Floor & Equip Sump Pump has automatically started due to normal operational leakage.

Subsequently:

I EMF-53A, (Containment Hi Range) loses power.

(Note the following component designators):

IWL-825A, (Cont Smp Pumps Disch Cont Isol)

IWL-827B, (Cont Smp Pumps Disch Cont Isol)

Which ONE of the following describes the status of the components listed below?

IWL-825A IWL-827B Pump IAI A. OPEN OPEN ON B. CLOSED CLOSED OFF C. CLOSED OPEN OFF D. CLOSED OPEN ON Page 64 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 64 Which ONE of the following statements describes an interlock provided for the cross-connect of the instrument Air (Vi) and Station Air (VS) systems?

As (VI) system pressure decreases,__________________________________

A. IVI-500 (Vito VS Supply Isolation) CLOSES at 85 psig.

B. lVi-500 (Vito VS Supply isolation) CLOSES at 76 psig.

C. IVS-78 (VS Auto Backup to Vi) OPENS at 80 psig.

D. 1VS-78 (VS Auto Backup to Vi) OPENS at 76 psig.

Page 65 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 65 If normal cooling has been lost to the E and F VI compressors, the (1) System can be aligned to supply cooling water to the E and F VI compressors with the discharge aligned to the (2) System.

A. (1) RE (2) RN B. (1) RE (2) RL C. (1) RL (2) RN D. (1) RN

(2) RL Page 66 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 66 Which ONE of the following describes an appropriate example of information to be communicated to the shifts by use of an OPS Guide, in accordance with the requirements of SOMP 01-13 (Operations Work List, Routine Task List, and OPS Guides)?

A. Notification that engineering has determined a Tech Spec inoperability may exist under certain conditions due to new analyzed failure scenarios.

B. OSM direction to verify IA DIG Lube Oil Temp two times per shift due to an annunciator failure.

C. Temporary procedure instructions for a system which is currently being modified, while a procedure change is being completed.

D. Direction, from the unit lead, concerning work (or evolutions) that need(s) to be completed on a particular shift.

Page 67 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 67 In accordance with SOMP 02-01, (Safety Tagging and Configuration Control):

(1) Using a Configuration Control Card (CCC) to position components within the boundaries of an R&R to allow additional venting/draining capacity allowed.

(2) When more than Tag Sticker(s) is/are required for a control panel switch, a controlling sticker shall be placed on the switch and the Tag Sticker(s) will be placed in the Control Room Sticker Logbook.

Which ONE of the following completes the above statements?

A. (1) IS (2) One B. (1) IS (2) Two C. (1) IS NOT (2) One D. (1) IS NOT (2) Two Page 68 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 68 Given the following Unit I conditions:

The Unit is in Mode 6.

(1) In accordance with Tech. Spec. 3.9.6 (Refueling Cavity Water Level), if water level is LESS than 23 above the reactor vessel flange, then control rod drive shaft unlatching (2) In accordance with PTI1IAI4600/002 F, (Mode 6 Periodic Surveillance Items), if 1 KFP5I2O (Spent Fuel Pool Level) fails low during fuel unloading operations, a check of NC system WR level (2) adequate to satisfy the requirements of this PT.

A. (1) must bestopped (2) is B. (1) must be stopped (2) is NOT C. (I) may continue (2) is D. (1) may continue (2) is NOT Page 69 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 69 With Unit 1 in Mode 3, which ONE of the following describes the MAXIMUM NC system pressure, in accordance with Tech Spec 2.1.2 (RCS Pressure SL), and the MAXIMUM time allowed to restore compliance, per Tech Spec 2.2.2 (SL Violations)?

A. 2735 psig 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. 2735 psig 5 minutes C. 2750 psig 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months D. 2750 psig 5 minutes Page 70 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 70 With both Units at 100% power the following alarm will not function.

lAD-i 3, N5, Main Fire Pump A Ctrl Pwr Trouble To identify the status of this annunciator, a will be placed on or near the annunciator window in the Control Room.

A. distinctive GREEN flag B. distinctive RED flag C. WHITE deficiency sticker D. YELLOW Restricted sticker Page 71 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 71 Consider the following conditions relating to planned radiation releases:

1. EMF-50 (WG Disch Monitor Waste Gas) Trip 2 has actuated.

2. Turbine Building Sump release exceeds EMF-31 (Turbine Building Sump) pre-set level.

In accordance with the applicable procedures, which ONE of the following completes the below statements (consider each separately):

(1) Re-initiation of the Waste Gas release at least once without resampling (1) allowed.

(2) Re-initiation of the Turbine Building Sump release at least once without resampling (2) allowed when the release exceeds EMF-31 pre-set level.

A. (1) is (2) is NOT B. (1) is (2) is C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Page 72 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 72 Given the following Unit I conditions:

The Unit has just entered Mode 5 in preparation for refueling.

The missile shield has not been removed.

A lower containment entry is planned for the next shift.

The on-duty crew will perform purge of containment in preparation for the containment entry.

Currently, the VP system is secured with all fans off and containment purge and exhaust valves closed.

For this planned containment purge:

(1) The NORMAL-REFUEL SELECTOR switch is placed in the (1) position.

(2) This alignment is used in order to (2)

Which ONE of the following completes the above statements, in accordance with OP111N6450/015 (Containment Purge System)?

A. (1) NORM (2) Prevent overpressurization of upper containment and an unmonitored release path.

B. (1) NORM (2) Prevent opening the ice condenser doors and to ensure air flow is routed through clean up filters.

C. (1) REFUEL (2) Prevent overpressurization of upper containment and an unmonitored release path.

D. (1) REFUEL (2) Prevent opening the ice condenser doors and to ensure air flow is routed through clean up filters.

Page 73 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 73 Given the following Unit I conditions:

The crew is performing a SIG depressurization in accordance with EP/I/A/5000FFR-C.2 (Response to Degraded Core Cooling) due to an ORANGE Path on SPDS.

While in FR-C.2 the crew receives a RED Path for NC Integrity.

The crew (1) transition to EPIIIAI5000!FR-P.1 (Response To Imminent Pressurized Thermal Shock Condition) because (2)

A. (1) will (2) Pressurized Thermal Shock is a higher priority concern because of the potential challenge to reactor vessel integrity.

B. (1) will (2) during the performance of an ORANGE path procedure, if any RED condition arises, then the RED condition is addressed first.

C. (I) willNOT (2) Core Cooling is a higher priority concern and should be completed prior to performing a lower priority procedure.

D. (1) wilINOT (2) transition to this procedure could cause further degradation of core cooling.

Page 74 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 74 (1) OEMF-41 (Aux. Bldg. Radiation Monitor) indicating 5x10 5 cpm (1) require initiation of a Site Assembly.

(2) The minimum level of emergency classification which ALWAYS requires an evacuation of non-essential personnel is A. (1) will (2) Site Area Emergency B. (1) will (2) General Emergency C. (1) will NOT (2) Site Area Emergency D. (1) willNOT (2) General Emergency Page 75 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 75 Which ONE of the following is a Post Accident Monitoring Instrument, AND is controlled by Tech. Spec. 3.3.3, [Post-Accident Monitoring (PAM) Instrumentation]?

A. Containment Humidity B. SG Water Level Wide Range C. I EMF-36L, Unit Vent Gas Monitor D. I EMF-38L, Containment Monitor Particulate Page 76 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 76 Following a refueling outage, given the following Unit I conditions:

NC temperature is 225°F.

NC pressure is 900 psig.

Subsequently:

I NC-34A (PZR PORV) fails open.

Attempts to close I NC-33A (PZR PORV isol) are unsuccessful.

The criteria for initiation of Safety Injection (1) located in AP/1/A/5500/027 (Shutdown LOCA), and is based on (2)

A. (I) is (2) 1 NC-33A /1 NC-34A position B. (1) is not (2) 1 NC-33A /1 NC-34A position C. (1) is (2) containment pressure D. (1) is not (2) containment pressure Page 77 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 77 Given the following Unit 1 conditions:

The Unit was initially at 100%.

A large break LOCA occurred 45 minutes ago.

Currently:

Containment pressure indicates 9 psig.

Containment hydrogen concentration is 1%.

CETs indicate 1100°F.

RVLIS lower range level indicates 48%.

1 EMF- 53A indicates 165 R/hr.

Subcooling margin indicates -35°F.

All SIG NR levels are off scale LOW.

NO CA flow indicated.

I KC-425A (NC Pumps Ret Hdr Cont Isol) is open and will not close.

All other containment isolation valves are in the proper position for conditions listed.

Which ONE of the following is the classification and associated EAL Number for this event?

Reference Provided A. Site Area Emergency based on EAL # 4.1 .S.2 B. General Emergency based on EAL # 4.1.G.2 C. Site Area Emergency based on EAL # 4.1.8.1 D. General Emergency based on EAL # 4.1 .G.1 Page 78 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 78 Given the following Unit I conditions:

Unit I evacuated the Control Room due to a Fire Event.

The decision is made to initiate a cooldown to Mode 5.

Attempts to place the ND system in service have failed due to loss of power to I ND-I B (ND Pump 1A Suction from Loop B).

(I) The CRS will use (I) for the detailed steps needed for aligning alternate power to I ND-I B.

(2) Following the alternate power alignment, the Reactor Operator will be dispatched to the (2) in order to open the valve.

A. (I) APIOIN5500!045, (Plant Fire)

(2) Breaker Faceplate B. (I) AP/O/A/5500/045, (Plant Fire)

(2) Annulus TBOX C. (1) OP/i 1N6200/004, (Residual Heat Removal System)

(2) Breaker Faceplate D. (1) OP/IIA/62001004, .(Residual Heat Removal System)

(2) Annulus TBOX Page 79 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 79 Given the following Unit 1 conditions:

The Unit tripped due to a loss of offsite power.

The CRS is currently reading step 9 of EPIIIAI5000/ES-O.2 (Natural Circulation Cooldown) for verification of natural circulation capability.

For these conditions:

(1) One requirement of this step is that N/R levels in all S!Gs be at least GREATER THAN (2) The Background Document for ES-O.2 states that the basis for Step 9 is to prevent A. (1) 11%

(2) uneven cooling which could impact cooldown B. (1) 15%

(2) uneven cooling which could impact cooldown C. (1) 11%

(2) void formation which could impact depressurization D. (1) 15%

(2) void formation which could impact depressurization Page 80 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 80 Given the following Unit I conditions:

The Unit was initially at 100% power.

Subsequently:

The Unit tripped due to a loss of offsite power.

VI pressure is currently 68 psig and decreasing.

Attempts to start the diesel back-up VI compressor have been unsuccessful.

Note:

APIO/A15500/022 (Loss of Instrument Air)

EP/1 /AI5000IES-O. I (Reactor Trip Response)

(1) Is N2 alignment to the PORVs required at this time?

(2) If the N2 alignment is required, how are the procedures implemented?

A. (1) NO.

(2) N2 alignment to the PORVs is not required at this time.

B. (1) YES.

(2) ES-O.1 directs the required actions. No AP procedure guidance is required.

C. (1) YES.

(2) ES-0.1 does NOT direct the N2 alignment. AP-22 implementation is required for the alignment.

D. (1) YES.

(2) ES-O.1 DOES contain the required actions for the alignment, but the CRS will direct the actions from AP-22.

Page 81 of 101 Catawba 2013 NRC Initial License Exam -Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 81 Given the following Unit 1 conditions:

The Unit has experienced a loss of all offsite power, concurrent with a valid Safety Injection.

Control Room indications are:

Containment pressure 0.13 psig

Containment sump level 0.5 feet

PZR level 7% and decreasing

PZR pressure 1820 psig and decreasing

EMF-1 (522 FF-57 AUX BLDG 522) Trip 2

ND A Train discharge flow to the cold legs is 60 gpm and slowly decreasing.

ND A Train discharge pressure is 530 psig.

ND B Train discharge flow to the cold legs is 0 gpm.

ND B Train discharge pressure is 530 psig.

Once EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) has been implemented, which ONE of the following describes the required sequence of procedures and the action(s) for isolating ND?

A. 1. Isolate both trains of ND per OMP 1-7

2. EP/1 /A/5000IES-1 .1 (SI Termination)

B. 1. Isolate both trains of ND per OMP 1-7

2. EP/1/AI5000IECA-1.2 (LOCA Outside Containment)

3. EP/1 /A15000/ES-1 .1 (SI Termination)

C. 1. EP/1/N5000/E-1 (Loss of Reactor or Secondary Coolant)

2. Isolate A or B Train of ND

3. EP/1 /A/5000/ES-1 .1 (SI Termination)

D. 1. EPII/N5000IECA-1.2 (LOCA Outside Containment)

2. IsolateAorBTrainofND

3. EP/1/A/5000/E-1 (Loss of Reactor or SecondaryCoolant)

Page 82 of 101

-Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 82 Unit 1 is at 3% during a post refueling startup.

In accordance with Tech Spec 3.3.1, (Reactor Trip System Instrumentation), the High Pressurizer Water Level Trip Cl) required because (2)

A. (1) IS (2) of potential overfill of the Pressurizer.

B. (1) is NOT (2) it is a backup to the Pressurizer High Pressure Trip.

C. (1) IS (2) it is a backup to the Pressurizer High Pressure Trip.

D. (1) Is NOT (2) sufficient time is available to evaluate conditions and take corrective action.

Page 83 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 83 For high activity in the reactor coolant, to ensure that the requirements of Tech. Spec. 3.4.16, (RCS Specific Activity) are met, the SRO is ALSO required to apply the requirements of API1IN5500/018, (High Activity in Reactor Coolant) for NC System Dose Equivalent (1)

These ROS Specific Activity limits are based on the (2) Design Basis Accident.

A. (1) 1131 (2) LOCA outside containment B. (1) 1-131

(2) Steam Generator Tube Rupture C. (1) Xe-i 33 (2) tOCA outside containment D. (1) Xe-i33 (2) Steam Generator Tube Rupture Page 84 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 84 Which ONE of the following describes conditions for which selection of EPI1IAI5000/ES-1 .2 (Post LOCA Cooldown and Depressurization) will be effective in mitigating the effects of a LOCA?

A. From EP/1/A15000!E-O (Reactor Trip or Safety Injection) if pressurizer level can be maintained stable or increasing when normal charging conditions are achieved.

B. From EPI1/N5000IE-1 (Loss of Reactor or Secondary Coolant), if NC pressure is greater than the shutoff head of the ND pumps.

C. From EP/1/N5000/ES-1.1 (Safety Injection Termination), if NC pressure increases with only one NV pump in service.

D. From EP/IIN5000IES-1 .1 (Safety Injection Termination), if NC pressure is greater than the shutoff head of the NI pumps.

Page 85 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 85 Given the following Unit I conditions:

A loss of off-site power resulted in a Unit trip.

A PZR PORV failed OPEN and has now been isolated.

A bubble formed in the reactor vessel head while the failed PZR PORV was being isolated.

The crew is presently cooling down in accordance with EP/1/A15000/ES-0.3 (Natural Circulation Cooldown with Steam Void in Vessel).

(1) In accordance with ES-0.3, during NC System cooldown and depressurization, the MAXIMUM allowed cooldown rate is less than (1) per hour.

(2) In accordance with EBG/1/5000/ES-0.3, (Background Document for ES-0.3), the above cooldown rate requirement is based on the concern for (2)

Which ONE of the following completes the above statements?

A. (1) 50°F (2) high temperature differential between the reactor vessel head and body B. (1) 100°F

(2) high temperature differential between the reactor vessel head and body C. (1) 50°F (2) pressurized thermal shock D. (1) 100°F (2) pressurized thermal shock Page 86 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 86 Given the following Unit 1 conditions:

The Unit is at 100% power.

An electrical short has caused I ND-32A (ND Train IA Hot Leg In] IsoI) to inadvertently close.

Attempts to re-open the valve have been unsuccessful.

Due to this equipment failure, Tech Spec 3.0.3 entry (1) required because (2)

A. (1) is NOT (2) 1 B ND is available with full flow capability for decay heat removal B. (1) is NOT (2) only one train of ND is required to satisfy hot leg recirc requirements C. (1) is (2) a shared piping arrangement prevents a single ND pump from supplying two (2) intact cold legs assumed in the safety analysis D. (1) is (2) a shared piping arrangement prevents a single ND pump from supplying three (3) intact cold legs assumed in the safety analysis Page 87 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 87 Given the following Unit I conditions:

The Unit is at 80% power.

A malfunction has caused I KC-1 32 (Letdown Temperature Control Valve) to CLOSE.

Control Room has received IAD-7 Ff3 (LETDN HX OUTLET HI TEMP).

Letdown temperature is 145°F and increasing.

(1) This malfunction will initially cause NC system Tave to (1)

(2) Steps for BOTH of the following:

V restoration of KC flow through the Letdown Heat Exchanger AND V restoration of letdown flow through the mixed bed demineralizers will be directed using (2)

A. (1) Increase (2) 1AD-7 F/3 Annunciator Response procedure.

B. (1) Increase (2) AP/1/A/5500/021 (Loss of Component Cooling Water).

C. (1) Decrease (2) AP/1/A/5500/021 (Loss of Component Cooling Water).

D. (1) Decrease (2) 1AD-7 Ff3 Annunciator Response Procedure.

Page 88 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 88 Given the following:

0800 IA NS Pump is started (in recirc alignment to FWST) in preparation of IWP.

0815 Unit I Safety Injection occurs due to a LOCA.

0820 1 EMF-53A and I EMF-53B indicate 112 Rem.

0822 1A NS pump has been restored to standby alignment.

0825 The OSM declares a Site Area Emergency.

0835 Emergency Notification Form is transmitted to States and Counties.

0845 ECCS systems are transferred to Cold Leg Recirc Alignment. IA NS pump is STARTED.

0850 It is discovered that the IA NS Pump manual recirc alignment was NOT isolated when system was restored to standby and it CANNOT be isolated.

The next notification will be required at (1) and will be marked (2)

Reference Provided A. (1) 1235 (2) Follow-up B. (1) 0935 (2) follow-up C. (1) 0920 (2) Follow-up D. (1) 0920 (2) Initial Page 89 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 89 (I) The 6.9KV Automatic Fast Transfer switch for 1TA is located on (1)

(2) What procedure and related unit condition directs this switch to be placed to DEFEAT?

A. (1) IMC-11 in the Control Room (2) OP/1/B/6300!OO1, Enclosure 4.4 (Turbine Generator Shutdown)

B. (1) 1MC-11 in the Control Room (2) OP/1/N6350/OO1 Enclosure 4.14 (Train B Main Power Isolation and Return to Service).

C. (1) the local panel 1SCPA (2) 0P111A16350/OO1 Enclosure 4.14 (Train B Main Power Isolation and Return to Service).

D. (1) the local panel ISCPA (2) 0P111B16300/OO1, Enclosure 4.4 (Turbine Generator Shutdown)

Page 90 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 90 Given the following Unit I conditions:

The Unit is at 100% power.

Battery 1DGBA has been aligned for an equalizing charge.

The equalizing charge has been in progress for several hours.

The following alarm is received:

DIG 1A, E16, (Battery Enclosure Loss of Air Flow)

A check of the interior Battery Enclosure vents indicates NO air flow.

(1) The impact of the loss of ventilation is that (1)

(2) Procedure guidance for an action to establish partial air circulation and cooling to the Battery Enclosure is located in (2)

A. (1) unacceptable specific gravity gradients will occur in battery cells.

(2) 0P111A161001009 A (Annunciator Response for IA DIG Panel).

B. (1) unacceptable specific gravity gradients will occur in batterycells.

(2) 0P111A163501006 (125 VDC Diesel Auxiliary Power).

C. (1) an explosive mixture of hydrogen and oxygen may build up in the Battery Enclosure.

(2) 0P111N61001009 A (Annunciator Response for 1A D/G Panel).

D. (1) an explosive mixture of hydrogen and oxygen may build up in the Battery Enclosure.

(2) 0P111A163501006 (125 VDC Diesel Auxiliary Power).

Page 91 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 91 Given the following:

Unit 1 has experienced a Loss of Load runback from 100%.

During the runback, control rods are manually inserted due to failure to automatically insert.

The following alarm is received:

1AD-2, B19, Control Rod Bank LO-LO Limit Subsequently:

The CRS is reading step 15 of AP/1/A/5500/003 (Load Rejection).

1& Verify the foflowing PCBs CLOSED:

The Steam Dump valves indicate closed on the Main Control Board.

Tavg-Tref difference indicates 3°F.

The OATC requests a focus brief for direction concerning control rod insertion.

In response to this request, the CRS will use the guidance found in:

A. Step 2 of AP/03 to insert control rods until Tavg-Tref difference is no more than 1.50 F.

B. AP/1/A15500/015, (Rod Control Malfunction) to stop inserting control rods once steam dumps are closed.

C. Step 13 of AP/03, Verify reactor power less than 30% RNO to insert control rods until Tavg-Tref difference is no more than 1°F.

D. OMP 1-7 (Emergency/Abnormal Procedure Implementation Guidelines) regarding limiting further rod insertion to address insertion limits and account for the effects of Xenon.

Page 92 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 92 Given the following conditions:

Unit 1 is in Mode 6.

Both trains of SSPS are in test.

1A VP is in service in refueling mode.

Venting from a contaminated system has caused 1EMF-39 (ContainmentGas Monitor) to reach Trip 2 setpoint.

(1) In order to restart the VP system, an Sh signal required to be reset.

(2) In accordarce with SLC 16.7-10 (Radiation Monitoring for Plant Operations), 1EMF-36 (Unit Vent Gas Monitor) be used as the required monitor for initiating containment purge.

A. (1) is NOT (2) may NOT B. (1) is NOT (2) may C. (1) is (2) may NOT D. (1) is (2) may Page 93 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 93 Given the following Unit 1 conditions:

A LOCA has occurred on the Unit.

Containment pressure is 2.8 psig.

Containment Hydrogen Concentration is 1.0% and stable.

The CRS desires to place the A Train Hydrogen Recombiner in service.

For the above conditions:

(1) The instruction steps for placing the Hydrogen Recombiner in service (1) located in FR-Z.4 (Response to High Containment Hydrogen Concentration).

(2) If the A Hydrogen Recombiner is placed in service with a power setting of 52 kw, this setting is (2)

Reference Provided A. (1) are not (2) correct B. (1) are not (2) NOT correct C. (1) are (2) correct D. (1) are (2) NOT correct Page 94 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 94 Assume Unit I is at 100% power.

In accordance with Technical Specification 5.0, Administrative Controls, if the Control Room Supervisor needs to leave the control room, an STA with an active license may assume the duties of the Control Room Supervisor provided that:

(1) the CRS or a relief SRO is available to return to the control room within 1)

AND (2) the time during which the STA assumes the SRO duties does not exceed a total time of (2) for the shift duration.

Which ONE of the following completes the above statements?

A. (1) 10 minutes (2) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. (1) 15 minutes (2) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months C. (1) 10 minutes (2) 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months D. (1) 15 minutes (2) 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Page 95 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 95 Given the following plant conditions:

Unit 1 has entered Mode 5 and fuel shuffles are in progress in the Unit 1 Spent Fuel Building.

Unit 2 is in Mode 6 with core alterations in progress.

(1) A Fuel Handling Supervisor (SRO) currently required to be designated for UNIT 1.

(2) A Fuel Handling Supervisor must be active or certified for Fuel Handling in accordance with the certification requirements contained in A. (1) is (2) NSD 512 (Maintenance of RO/SRO NRC Licenses)

B. (1) is not (2) NSD 512 (Maintenance of ROISRO NRC Licenses)

C. (1) is (2) SOMP 01-04 (Conduct of Operations)

D. (1) is not (2) SOMP 01-04 (Conduct of Operations)

Page 96 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 96 Given the following Unit I conditions:

The Unit is at 100% power.

IRL-152 (Main Turbine Lube Oil Coolers Temperature Control) has failed CLOSED.

An NEO has been dispatched to throttle I RL-1 54 (Unit I LT Coolers Control Bypass) to stabilize turbine lube oil temperature.

Once lube oil temperature is stabilized, the NEO is directed to isolate 1RL-i 52 with I RL 141 (IA Main Turbine Lube Oil Cooler Inlet).

In accordance with SOMP 02-01, (Safety Tagging and Configuration Control):

(1) The SRO will document the operation of IRL-154 with (2) If a component cannot be returned to the as-found position, the normal process will be to issue prior to shift turnover.

A. (1) an entry into the Control Room log (2) a Configuration Control Card B. (I) a Configuration Control Card (2) anR&R C. (1) an entry into the Control Room log (2) an R&R D. (1) anR&R (2) a Configuration Control Card Page 97 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 97 Given the following Unit I conditions:

An NCS heatup is in progress in preparation for a Mode change following refueling.

Tavg is 195°F.

Outside air temperature is 29°F.

Only one train of FWST heaters is in service.

FWST water temperature is 64° F.

Which ONE of the following identifies the status of the FWST and the actions relative to the upcoming Mode Change?

Reference Provided Status of FWST Actions Relative to Mode Change A. Below minimum temperature. Heatup to Mode 4 is allowed if LCO 3.O.4.b requirements are met.

B. Below minimum temperature. Heatup must be stopped, and may continue only after FWST temperature is above limits.

C. Above minimum temperature. Heatup to Mode 4 is allowed if LCO 3.O.4.b requirements are met.

D. Above minimum temperature. Heatup must be stopped, and may continue only after the other train of FWST heaters is operable.

Page 98 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 98 SLC 16.11.19 (Gas Storage Tanks) limits the quantity of radioactivity in each Waste Gas Decay Tank (WGDT) to (1) . This limit is based on exposure received by a (2) during an accidental release.

Which ONE of the following completes the statement above?

A. (1) 97,000 Curies (2) Member of the Public B. (1) 97,000 Curies (2) Plant Worker C. (1) lOCurjes (2) Member of the Public D. (1) lOCuries (2) Plant Worker Page 99 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 99 A fire event has occurred inside the Protected Area. The TSCIOSC have been activated.

(1) In accordance with RPIOIB/5000/029, (Fire Brigade Response), the Fire Emergency Report is filled out by the (1)

(2) If required, (2) will direct partial transfer to the SSF.

A. (1) Fire Brigade Leader (2) RP/O/B/5000/029, (Fire Brigade Response)

B. (1) Fire Brigade Leader

2) AP!01A15500/045, (Plant Fire)

C. (1) Operations Shift Manager (2) RP/O!B15000/029, (Fire Brigade Response)

D. (1) Operations Shift Manager (2) AP/OIA/55001045, (Plant Fire)

Page 100 of 101 Catawba 2013 NRC Initial License Exam Senior Reactof Operator

CNS 2013 NRC Exam 100 Questions SENIOR REACTOR OPERATOR Question 100 In accordance with RPIOIN5000/007, (Natural Disaster and Earthquake), Enclosure 4.2, Tornado Warning Issued For York Country OR Tornado On-Site:

(1) The VF system (Fuel Pool Ventilation) (2) required to be shutdown.

(2) If the tornado touches down on-site (outside the protected area), and an emergency classification is NOT required, a courtesy notification to the states and counties (2) required.

A. (1) is (2) is B. <1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Page 101 of 101 Catawba 2013 NRC Initial License Exam Senior Reactor Operator

SENIOR REACTOR OPERATOR Catawba Nuclear Station ILT 2013 NRC Written Exam (Sept. 2013)

REFERENCE PACKAGE CONTENTS EXAM ID: ILT2O13NRC Exam SRO Exam I Databook Figure 57, Reactor Coolant Saturation Curve, Wide Range 2 Databook Figure 58, Reactor Coolant Saturation Curve, Narrow Range 3 ECA-1 .1 (Loss of Emergency Coolant Recirculation), Step 18 4 ECA-1 .1, Enclosure 4 (Minimum S/I flowrate Versus Time After Trip) 5 RPIOIN5000/OO1, (Classification of Emergency), End. 4.1 6 Unit I Data Book, Figure 1, Unit I Hydrogen Recombiners Post-LOCA Power Consumption 7 LCO 3.5.4 (Refueling Water Storage Tank), page 3.5.4-1

Unit I Data Book Source: OAC Reactor Coolant Saturation Calculations 2500 2400 2300 2200 2100 2000 1900 1800 1700

.2 1600 C,

S 1500 1400 1300 Q 1200 1100 1000 C., 900 800 700 600 500 400 300 200 100 0

200 250 300 350 400 450 500 550 600 650 700 NC System Temperature (Deg F)

Rev. 2, 4/5/2002 Figure 57 Reactor Coolant Saturation Curve, Wide Range Page 1

Unit I Data Book Source: OAC Reactor Coolant Saturation Calculations 850 800 750 700 650 600 550 500 450 400 350 300 250 200 150 100 50 0

100 150 200 250 300 350 400 450 500 550 NC Temperature (Deg F)

Norrnal Conditions Adverse Conditions Rev. 2, 4/5/2002 Figure 58 - Reactor Coolant Saturation Curve, Narrow Range Page 1

CNS LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE NO.

EPIIIAI5000IECA-l .1 20 of 82 Revision 40 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

17. (Continued)

d. Attempt to start I B NC pump to provide d. if I B NC pump cannot be started, normal pressurizer spray. REFER IQ THEN start NC pump(s) as necessary Enclosure 3 (NC Pump Start). to provide normal pressurizer spray.

REFER ] Enclosure 3 (NC Pump Start).

18. Verify Sf1 termination criteria as follows:

a. Verify RVLIS indication is adequate as a. Q IQ. Step 25.

follows:

. IF all NC pumps are off, THEN verify REACTOR VESSEL LR LEVEL -

GREATER THAN 61%.

OR

. if any NC pump is on, THEN verify REACTOR VESSEL DIP -

GREATER THAN REQUIRED DIP FROM TABLE BELOW:

Required REACTOR VESSEL DIP TRNA TRNB Number of With NC Pump 1A With NC Pump IC NC Pumps On On Off On Off 4 80% N/A 80% N/A 3 60% 32% 60% 32%

2 45% 20% 45% 20%

1 35% 14% 35% 14%

CNS LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE NO.

EP/11A15000/ECA-l.l 21 of 82 Revision 40 ACTION/EXPECTED

RESPONSE

I RESPONSE NOT OBTAINED

18. (Continued)

b. NC subcooling based on core exit TICs b. Perform the following:

- GREATER THAN 50°F.

1) Determine minimum S/I flow required. REFER TO Enclosure 4 (Minimum S/I Flowrate Versus Time After Trip).

2) Stop S/I pumps as required to obtain the following:

. Minimize S/I flow

. Maintain S/I flow greater than or equal to flow required by Enclosure 4 (Minimum S/I Flowrate Versus Time After Trip).

3) Q IP. Step 25.

19. Ensure the following containment isolation signals RESET:

. PhaseA Phase B.

I CNS I LOSS OF EMERGENCY COOLANT RECIRCULATION II PAGE NO. II EPIIIN5000IECA-1 .1 76 of 82 Enclosure 4 - Page 1 of I Revision 40 Minimum S!I Flowrate Versus Time After Trip S/I FLOW REQUlRED TO MATCH DECAY HEAT FLOW RATE (GPM) 600 F 4

\

V 500 400 300 4

200 100 IE = = = = = I 0 2 3 456789 2 3 458789 2 3 456789 10 100 1000 10000 TIME (MINUTES)

Unit I Data Book Source: TPIIIA120011 I 68 66 64 62 60 I

o 58 0

56 54 52 50 2 3 4 5 6 7 8 9 10 Post- LOCA Containment Pressure (psig)

ATrain B Train Rev. 0, 6/30/98 Figure 1 - Unit I Hydrogen Recombiners Post-LOCA Power Consumption Page 1

RWST 3.5.4 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.4 Refueling Water Storage Tank (RWST)

LCO 3.5.4 The RWST shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RWST boron A. I Restore RWST to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months concentration not within OPERABLE status.

limits.

OR RWST borated water temperature not within limits.

B. RWST inoperable for B.1 Restore RWST to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reasons other than OPERABLE status.

Condition A.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Catawba Units I and 2 3.5.4-1 Amendment Nos. 173/165

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