ML16166A099

301 as Given RO Written Exam with References and Answer Key

ML16166A099
Person / Time
Site:	Catawba
Issue date:	06/13/2016
From:	NRC/RGN-II
To:
References
Download: ML16166A099 (79)

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Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: I (1 point)

Given the following conditions on Unit 2:

• The unit is operating at 50% RTP

• Pzr pressure is 2235 PSIG

• Pzr Relief Tank (PRT) pressure is 20 PSIG

• PRT temperature is 125°F

• A Pzr code safety valve is leaking by its seat Which ONE (1) of the following identifies the approximate temperature that is indicated on the leaking safety valve discharge RTD?

REFERENCE PROVIDED A. 123-127°F B. 161-165°F C. 227-231°F D. 258-262°F Page 1 of 75

Catawba Nuclear Station ILTJ6 CNS RO NRC Examination Question: 2 (1 point)

Given the following conditions on Unit 2:

• Mode 1 was entered 30 minutes ago

• Power currently stable at 8% RTP

• The crew has entered AP/2/A15500/010 (NC System Leak)

• Pressurizer pressure trend is as follows:

Time Pressurizer Pressure 0800 2200 PSIG 0802 2050 PSIG 0804 1900 PSIG 0806 1800 PSIG Assuming no operator action, the EARLIEST listed time that an automatic reactor trip signal will be present will be (1)

In accordance with the Emergency Core Cooling System (ECCS) acceptance criteria, established by 10 CFR 50.46, peak cladding temperatures are required to be maintained less than a MAXIMUM of (2) following a small break LOCA.

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

A. 1. 0804

2. 5080 °F B. 1. 0804

2. 2200 °F C. 1. 0806

2. 5080 °F D. 1. 0806

2. 2200°F Page 2 of 75

Catawba Nuclear Station ILT16 CNS RO NRC Examination Question: 3 (1 point)

The crew has entered EP/1/N5000/FR-P.1 (Response to Imminent Pressurized Thermal Shock) due to a RED path condition on the Reactor Coolant Integrity CSF Status Tree.

FR-P.1 utilizes the parameters of NC pressure and to check if a large break LOCA has occurred.

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

A. NC T-cold temperatures B. SIG pressure C. ND flow rate to cold legs D. RVLIS level Page 3 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 4 (1 point)

Given the following conditions on Unit 1:

• 1A NV pump tripped

• Control room crew entered AP111N55001012 (Loss of Charging or Letdown)

Subsequently:

• Charging and letdown flow have been restored

• Pressurizer level has been restored to programmed level

• The crew has just placed 1 NV-294 (NV Pmps A&B Disch Flow Ctrl) in AUTO Immediately following placing 1 NV-294 in Automatic, pressurizer level control is in (1)

In order for the charging low flow limit (LM) to be active, the Pressurizer Level Master controller (2) required to be in AUTO.

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

A. 1. AUTO

2. is NOT B. 1. MANUAL

2. is NOT C. 1. AUTO

2. is D. 1. MANUAL

2. is Page 4 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 5 (1 point)

Given the following conditions on Unit 1:

• Refueling was in progress when a loss of ND occurred

• CRS has implemented AP111N55001019 (Loss of Residual Heat Removal System) Case Ill (Loss of ND With Large Vent Path Established)

Subsequently:

• The reason for the loss of ND has been corrected

• Crew is performing Enclosure 8 (Restoring an ND Train To Operation) to place 1A ND train in service In accordance with Enclosure 8:

The MINIMUM KC flow established to the ND heat exchanger is (1) GPM.

Prior to starting the 1A ND pump, 1 ND-27 (ND Hx 1A Bypass Ctrl) is placed in the (2) position.

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

A. 1. 5000

2. CLOSED B. 1. 5000

2. OPEN C. 1. 3000

2. CLOSED D. 1. 3000

2. OPEN PageS of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Exarniitation Question: 6 (1 point)

Given the following conditions on Unit 1:

• Operating at 100% RTP at normal temperature and pressure Subsequently:

• The Pressurizer Pressure Master controller has suffered an internal failure resulting in a Pressurizer Pressure Error of +100 PSIG

• Actual Pressurizer Pressure is 2100 PSIG and decreasing Pressurizer Spray valves are currently (1)

At the time of the failure, (2) received a signal to open.

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

A. 1. OPEN

2. 1 NC-34A ONLY B. 1. OPEN

2. all Pressurizer PORVs C. 1. CLOSED

2. all Pressurizer PORVs D. 1. CLOSED

2. 1 NC-34A ONLY Page 6 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 7 (1 point)

Given the following initial conditions on Unit 1:

• Power stable at 100% RTP with surveillance testing in progress

• Reactor Trip Breaker A (RTA) and Bypass Breaker B (BYB) are racked-in and closed The following sequence of events occurs:

• A complete loss of feedwater occurred

• All efforts to trip the reactor from the control room were unsuccessful

• Annunciator lAD-i N5 (P-14, S/I OR RX TRIP CAUSES TURBINE TRIP) is LIT

• Operators entered EP/1/N5000/FR-S.1 (Response to Nuclear Power Generation/ATWS)

• An AO was dispatched to locally trip the Reactor Based on the given conditions, the Reactor Trip Breaker A (RTA) (1) failed to operate as designed.

If the AO is successful in opening all Reactor Trip and Bypass breakers, then per FR-SI, it (2) required to open the MG set breakers locally.

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

A. 1. shunttrip coil ONLY

2. is NOT B. 1. shunt trip AND undervoltage coils

2. is NOT C. 1. shunt trip coil ONLY

2. is D. 1. shunt trip AND undervoltage coils

2. is Page 7 of 75

Catawba Nuclear Station ILTJ6 CNS RO NRC Examination Question: 8 (1 point)

Given the following conditions on Unit 1:

• A Loss of Offsite Power occurred

• Following the reactor trip, the crew entered EP/1IN5000IE-3 (Steam Generator Tube Rupture) due to a rupture of 1 B S/G o Cooldown to target CET temperature is complete o NC system depressurization has not begun

• NC System Integrity CSF indication is ORANGE due to lB NC Loop Tcold tern peratu re In accordance with E-3:

Operators (1) required to disregard the NC System Integrity Status due to the 1 B NC Icold indication.

NC system depressurization will be performed using (2)

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

A. 1. are NOT

2. a pressurizer PORV B. 1. are

2. a pressurizer PORV C. 1. are NOT

2. normal pressurizer spray D. 1. are

2. normal pressurizer spray Page 8 of 75

Catawba Nuclear Station ILT16 CNS RO NRC Examination Question: 9 (1 point)

Which ONE (1) of the following is the primary reason for stopping all NC pumps in EP/1/N5000/FR-H.1 (Response to Loss of Secondary Heat Sink)

A. To preserve the NC pumps for long term core cooling after the mitigation strategies of FR-H.1 have been successful.

B. To reduce the heat added from the NC pumps, thereby delaying the need for feed and bleed and gaining time to establish a means of supplying feed flow to a SIG.

C. To prevent the heat added by the NC pumps from adversely affecting indications used to determine whether or not NC system feed and bleed will be required.

D. Anticipatory response to prevent cavitation damage to NC pumps due to a loss of NC system subcooling.

Page 9 of 75

Catawba Nuclear Station JL Ti 6 CNS RO NRC Exanti,,ation Question: 10 (1 point)

Given the following conditions on Unit 1

• The crew has just entered EP/11N5000/ECA-O.O (Loss of All AC Power)

• 1A DIG automatically started, but then immediately tripped

• 1 B DIG failed to automatically start

• Unit 2 was unaffected by the loss of offsite power on Unit 1 Which ONE (1) of the following states the FIRST action attempted per ECA-O.O to restore power to an essential bus?

A. Manually start both diesel generators from the control room B. Initiate Safety Injection on both trains C. Locally start the 1 B diesel generator D. Align offsite power from Unit 2 Page 10 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 11 (1 point)

Given the following conditions on Unit 1:

• Reactor power is 25%

• A Zone A and Zone B Lockout results in a Loss of Offsite Power (LOOP)

• 1 B DIG starts and is powering 1 ETB

• 1A D/G failed to start

• Safety Injection (S/I) is NOT actuated

• 1A CFPT remains in service Based on the given conditions, lB CA pump (1) receive an automatic start signal from AMSAC.

Assuming no operator action, 1A S/G N/R level will be (2)

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

A. 1. did NOT

2. increasing B. 1. did NOT

2. decreasing C. 1. did

2. increasing D. 1. did

2. decreasing Page II ot75

Catawba Nuclear Station IL T16 CNS RO NRC Examination Question: 12 (1 point)

Given the following conditions on Unit 2:

• Reactor power stable at 100%

• RN suction and discharge are aligned to Lake Wylie Subsequently:

• A loss of 2ERPA occurs Automatic makeup to 2A DIG fuel oil day tank (1) available.

With no operator action, RN pump suction and discharge (2) remain aligned to Lake Wylie.

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

A. 1. is NOT

2. will B. 1. is

2. will C. 1. is NOT

2. will NOT D. 1. is

2. will NOT Page 12 of 75

Catawba Nuclear Station ILTJ6 CNS RO NRC Examination Question: 13 (1 point)

Given the following conditions on Unit 1:

• Unit is stable at 100% RTP

• The following Annunciators actuate:

o lAD-i 1 N8 I25VDC Diesel Gen A Control Pwr Sys Trbl o lAD-i 1 B/7 DIG A Panel Trouble

• The dispatched operator reports that the 1A D/G Control Power supply breaker 1 DGCA-B304 has tripped open and appears to be damaged Upon a Loss of Offsite Power, the 1A D/G (1) automatically start.

The IA D/G (2) be started manually.

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

A. 1. will

2. can B. 1. will NOT

2. can C. 1. will

2. can NOT D. 1. will NOT

2. can NOT Page 13 of 75

Catawba Nuclear Station ILTJ6 CNS RO NRC Examination Question: 14 (1 point)

Given the following indications on Unit 1:

• Power is stable at 80% RTP

• Generator hydrogen pressure is 60 PSIG

• A failure on the Main Generator Voltage Regulator then occurs

• The operator observes the following indications in the control room:

o Turbine load is 1000 MWs o Generator is indicating f7O0 KVARs-4VA1)l (_) 7c0 f1)(/,4Rc 3//i Generator excitation voltage is currently too (1)

If allowed to operate in this region of the Generator Capability Curve, (2) overheating will occur.

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

REFERENCE PROVIDED A. 1. HIGH

2. field winding B. 1. LOW

2. field winding C. 1. HIGH

2. armature core end D. 1. LOW

2. armature core end Page 14 of 75

Catawba Nuclear Station ILTJ6 CNSRO NRC Examination Question: 15 (1 point)

Given the following conditions on Unit 2:

• EP/2/N5000/ECA-1 .2 (LOCA Outside Containment) has been entered Containment Phase A Isolation (1) automatically actuated.

In accordance with ECA-1 .2, the parameter(s) used to check if the LOCA has been isolated is/are (2)

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

A. 1. has

2. Pressurizer level or RVLIS level B. 1. has

2. NC pressure C. 1. has NOT

2. Pressurizer level or RVLIS level D. 1. has NOT

2. NC pressure Page 15 of 75

Catawba Nuclear Station ILT16 CNS RO NRC Exan;ination Question: 16 (1 point)

Given the following conditions on Unit 1:

• A Safety Injection has occurred due to High Containment Pressure

• Containment pressure peaked at 2.7 psig and is now slowly decreasing

• The crew is implementing EP/1/N5000/FR-H.1 (Response to Loss of Secondary Heat Sink)

• All attempts to restore CA flow have been unsuccessful In accordance with FR-Hi:

The NEXT source of feed water attempted for restoration of flow to the S/Gs is through the CM/CF system using (1)

The crew will be required to establish bleed and feed when W/R level in at least 3 S/Gs is less than a MAXIMUM level of (2)

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

A. 1. Hotwell and Booster pumps

2. 24%

B. 1. Hotwell and Booster pumps

2. 36%

C. 1. either Main Feed Water pump

2. 24%

0. 1. either Main Feed Water pump

2. 36%

Page 16 of 75

Catawba Nuclear Station ILTJ6 CNS RO NRC Examination Question: 17 (1 point)

Given the following conditions on Unit 1

• The crew has entered EPI1IN5000IECA-1 .1 (Loss of Emergency Coolant Recirculation) and is preparing to initiate an NC system cooldown

• Primary chemistry has been instructed to sample the NC system for boron concentration

• The SOP is performing Enclosure 2 (Aligning NS for Recirculation) o NS suction valves from the containment sump are opened o Containment CSF status turns ORANGE Per ECA-1 .1, The Containment CSF status (1) valid.

Boron sample results (2) required prior to beginning the cooldown.

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

A. 1. is NOT

2. are NOT B. 1. is

2. are NOT C. 1. is NOT

2. are D. 1. is

2. are Page 17 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 18 (1 point)

Given the following conditions on Unit 1:

• Reactor trip from 100% power has occurred

• Crew is implementing EP/1/N5000/ECA-2.1 (Uncontrolled Depressurization of All Steam Generators)

• All S/G N/R levels are 0%

• Cooldown rate based on NOT-colds in the last hour is 150°F

• CA flow to each S/G has been throttled to 75 GPM A RED path on the Heat Sink CSF (1) exist.

Based on the above conditions and in accordance with ECA-2. 1 CA flow to all but one S/G (2) required be isolated.

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

A. 1. does

2. is B. 1. does

2. is NOT C. 1. does NOT

2. is D. 1. does NOT

2. is NOT Page 18 of 75

Catawba Nuclear Station IL TI 6 (NS RO NRC Examination Question: 19 (1 point)

Given the following conditions on Unit 1:

• Initially at 100% power when Control Bank A rod H-6 dropped fully into the core

• AP/1/N5500/014 (Control Rod Misalignment) Case II (Dropped Control Rod) was entered

• Recovery of the dropped rod is in progress, in accordance with OPI1/N6150/008 (Rod Control) Enclosure 4.6 (Rod Retrieval)

• The operators have placed the lift coils in the required position for all rods in the affected bank in the CONTROL ROD DISCONNECT SWITCH BOX The lift coil for rod H-6 is in the (1) position.

When the OATC operates the ROD MOTION lever, a ROD CONTROL URGENT FAILURE alarm (2) be received.

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

A. 1. CONNECTED

2. will B. 1. DISCONNECTED

2. will C. 1. CONNECTED

2. will NOT D. 1. DISCONNECTED

2. will NOT Page 19 of 75

Catawba Nuclear Station ILT16 CNS RO NRC Examination Question: 20 (1 point)

Given the following conditions on Unit 1:

• A runback from 100% RTP has occurred

• During the runback, control rod H-8 became stuck

• Rod H-8 is determined to be 16 steps misaligned The action statement of Tech Spec 3.1.4 (Rod/Group Alignment Limits)

(1) required to be entered.

In accordance with Tech Spec 3.2.3 (Axial Flux Difference (AFD)), if AFD exceeds the COLR limits due to the stuck rod, reactor THERMAL POWER must be reduced to a value less than a MAXIMUM of (2)

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

A. 1. is NOT 2 50%

B. 1. is NOT 2 75%

C. 1. is 2 50%

D. 1. is 2 75%

Page 20 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 21 (1 point)

Given the following conditions on Unit 1:

• The crew has entered EPI1/N5000IFR-S.1 (Response To Nuclear Power Generation/ATWS) and is initiating emergency boration

• 1 NV-236B (Boric Acid to NV Pump Suct) is opened

• Boric Acid transfer pump switches are in ON

• INV-312A & 1NV-314B (Chrg Line Cont Isol) are OPEN

• Pressurizer pressure is 2340 PSIG Based on the given conditions, and in accordance with FR-Si, the crew is required to (1) to ensure a MINIMUM boration flow of (2)

Which ONE (1) of the following complete the statement above?

A. 1. manually initiate safety injection

2. 3ogpm B. 1. manually initiate safety injection

2. 6ogpm C. 1. depressurize the NC system

2. 3ogpm D. 1. depressurize the NC system

2. 60gpm Page 21 of75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 22 (1 point)

Given the following conditions on Unit 1:

• Unit is in Mode 3

• NC pressure is stable at 1900 psig

• All shutdown banks have been withdrawn

• N-31 indication becomes erratic and the crew enters API1/N55001016 (Malfunction of Nuclear Instrumentation System)

• The LEVEL TRIP switch for N-31 has been placed in BYPASS A loss of N-31 (1) will result in an automatic reactor trip, and operators are required to enter (2)

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

A. 1. instrument power

2. AP/11N5500/005 (Reactor Trip or Inadvertent S/I Below P-li)

B. 1. instrument power

2. EP/1IN5000IE-0 (Reactor Trip or Safety Injection)

C. 1. control power

2. API1/N5500/005 (Reactor Trip or Inadvertent S/I Below P-i 1)

D. 1. control power

2. EPIIIN5000/E-0 (Reactor Trip or Safety Injection)

Page 22 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 23 (1 point)

Given the following conditions on Unit 1:

• A reactor startup is in progress

• Eased on the following indications, the startup has been placed on hold:

o N-31 indicates 1.lxlO4cps o N-32 indicates 1.0x104 cps o N-35 indicates 1.9x105 % power o N-36 indicates 2.0x106 % power

• Rods are in manual with no rod motion

• CRS has entered AP/11A155001016 (Malfunction of Nuclear Instrumentation System) Case 3 (Intermediate Range Malfunction) due to one of the intermediate range channels being inoperable The affected intermediate range channel is (1)

The P-6 S/R BLOCK PERMISSIVE light on 1SI-18 (2) lit.

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

A. 1. N-35

2. is B. 1. N-35

2. is NOT C. 1. N-36

2. is D. 1. N-36

2. is NOT Page 23 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 24 (1 point)

Given the following conditions on Unit 1:

• The Unit is at the POAH following a refueling outage

• A Containment Air (VQ) release is in progress

• I EMF-39L (Containment Gas Low Range) is inoperable Subsequently:

• 1RAD-3, D12 IEMF-17 Reactor Bldg Refuel Bridge alarms Based on the given conditions, the containment evacuation alarm (1) automatically actuate.

Based on the given conditions, the 1 EMF-1 7 annunciator response procedure (2) require the operators to manually secure the VQ release.

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

A. 1. did NOT

2. does B. 1. did NOT

2. does NOT C. 1. did

2. does D. 1. did

2. does NOT Page 24 of 75

Catawba Nuclear Station ILT16 CNS RO NRC Examination Question: 25 (1 point)

In accordance with AP/O/N5500/45 (Plant Fire):

A 002 actuation in the (1) must be considered an ACTIVE fire because (2)

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

A. 1. CA pump pits

2. C02 actuation in this area is ONLY initiated manually B. 1. CA pump pits

2. there is no fire detection in this area C. 1. D/G rooms

2. 002 actuation in this area is ONLY initiated manually D. 1. D/G rooms

2. there is no fire detection in this area Page 25 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 26 (1 point)

Given the following conditions on Unit 1:

• Operating at 100% RTP

• An inadvertent Main Steam Isolation results in a Reactor Trip

• EP/1/N5000/FR-H.2 (Response to Steam Generator Overpressure) has been implemented due to a Yellow Path on Heat Sink

• The OATC notes that lB S/G pressure is 1230 PSIG and STABLE Based on given conditions, a MAXIMUM of (1) MSSVs (Main Steam Safety Valves) for 1 B S/G have failed to operate as designed.

In order to use S/G 1 B PORV in MANUAL to reduce S/G pressures, the Main Steam Isolation Signal (2) have to be RESET.

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

A. 1.3

2. does B. 1.4

2. does C. 1.3

2. does NOT D. 1.4

2. does NOT Page 26 of 75

Catawba Nuclear Station ILTJ6 CNS RO NRC Examination Question: 27 (1 point)

Given the following conditions on Unit 1:

• Unit is responding to a LOCA

• All sources of feedwater have been lost, S/G N/R levels are 17% and decreasing

• NC pumps are secured

• EP/1/N5000/FR-C.1 (Response to Inadequate Core Cooling) has been implemented

• kC, NI and NV pumps are unavailable

• Peak Containment pressure reached 2.5 PSIG Subsequently:

• S/G depressurization has failed to restore adequate core cooling

• Core Exit Thermocouples are currently indicating 1210°F Eased on the above conditions, which ONE (1) of the following states the next major action(s) required by FR-Cl?

A. Do NOT restart NC pumps, open all Pzr PORVs and head vents to depressurize the NC system.

B. Restart aN NC pumps and restore secondary heat sink per EP/1/N5000/FR-H.1 (Response to Loss of Secondary Heat Sink) prior to proceeding in FR-C. 1.

C. Restart NC pumps one at a time until CETs are less than 1200°F to force two phase flow through the core for core cooling.

D. Do NOT restart NC pumps, continue efforts to initiate feed and bleed of the NC system to restore core cooling.

Page 27 of 75

Catawba Nuclear Station ILT16 CNS RO NRC Examination Question: 28 (1 point)

Given the following conditions on Unit 1

• Unit is at 100% RTP Subsequently:

• 10 NC pump trips due to an operator error on the Main Control Board

• The crew verifies the reactor trips 10 S/G N/R level will initially (1) than the other S/Gs after the 10 NC pump trips.

NC loop 1C delta T would initially be (2) than the other NC loops delta Ts.

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

A. 1. shrink lower

2. lower B. 1. swell higher

2. lower C. 1. swell higher

2. higher D. 1. shrink lower

2. higher Page 28 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 29 (1 point)

Given the following initial conditions on Unit 1:

• NCSTavgis2l5°F

• NCS pressure is 250 PSIG

• VCT pressure is 28 PSIG

• The 1A NC pump is to be started for a unit heatup Subsequently:

• The 1A2 Oil Lift pump is started

• Oil Lift pressure is 480 PSIG In accordance with OP/i /N61 50/002A (Reactor Coolant Pump Operation) Enclosure 4.1 (Startup And Operation), the MINIMUM required #1 Seal differential pressure for starting the NC pump (1) met.

Based on the conditions above, if the 1A NC PUMP SAFETY BKR ON pushbutton is depressed, the pump (2) start.

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

A. 1. is

2. will NOT B. 1. is

2. will C. 1. is NOT

2. will NOT D. 1. is NOT

2. will Page 29 of 75

Catawba Nuclear Station ILTJ6 CNS RO NRC Examination Question: 30 (1 point)

Given the following conditions on Unit 1:

• Unit is in Mode 5

• The NC system is in a water solid condition

• lANDisinservice

• lB NV pump is in service

• 1 NV-i 35 (ND Flow To Letdn Hx) is THROTTLED to 50% to maintain letdown flow from ND

• 1 NV-294 (NV Pumps A & B Disch Flow Ctrl) is in MANUAL

• All plant parameters are stable If VI were lost to 1 NV-I 35, NC system pressure would (1)

If VI were lost to 1 NV-294, NC system pressure would (2)

Which ONE (1) of the following completes the statements above? (Consider each failure separately)

A. 1. increase

2. decrease B. 1. increase

2. increase C. 1. decrease

2. decrease D. 1. decrease

2. increase Page 30 of 75

Catawba Nuclear Station ILT16 CNS RO NRC Examination Question: 31 (1 point)

Given the following conditions on Unit 1:

• The unit is in MODE 5 with the A Train of ND in service

• The NC System is in a water solid condition

• LTOP key switches for PORVs are selected to NORM position Subsequently:

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

• Annunciator 1AD-9 N6 (ND SUCT OPEN AND NC HI PRESS) has just come in alarm

• NC WR pressure is indicating 460 PSIG Which ONE (1) of the following describes the redundant indication which would be used to verify that this annunciator is valid?

A. PORVs 1 NC-32B and 1 NC-34A would be cycling to lower NC pressure B. 1ND-1B (ND Pump 1A Suct Frm Loop B) would have auto closed C. CF&E sump level increasing ONLY D. PRT Level increasing ONLY Page 31 of75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 32 (1 point)

Given the following conditions on Unit 1:

• A Steamline break has occurred on the equalization header

• NC system pressure is 1200 PSIG and decreasing

• Main Steam equalization header pressure is 500 psig and decreasing slowly

• MSIVs on lB & 10 S/Gs did NOT close on the Main Steam Isolation signal

• 1A and 1 D SIG N/R levels are 30% and increasing Per EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) Enclosure 1 (Foldout Page):

1 NV-202B & 1 NV-203A (NV Pumps A&B Recirc Isol) were required to be closed by the operators when NC system pressure decreased to less than a MAXIMUM of (1) PSIG.

Auxiliary Feedwater flow (2) required to be isolated to the 1 B & 10 S/Gs.

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

A. 1. 1500

2. is B. 1. 1500

2. is NOT C. 1. 2000

2. is D. 1. 2000

2. is NOT Page 32 of 75

Catawba Nuclear Station IL T16 CNS RO NRC Examination Question: 33 (1 point)

Given the following conditions on Unit 1:

• NC fill and vent activities have been completed 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 The limit on pressurizer heat up rate per Selected Licensee Commitment 16.5-4 (Pressurizer) is (1)

In accordance with OP/1/N61001001 (Unit Startup), N2 venting is considered complete when PRT pressure (2) increase with a corresponding PRT level increase.

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

A. 1. 100°Fperhour

2. does B. 1. 200°Fperhour

2. does C. 1. 100°Fperhour

2. does NOT D. 1. 200°Fperhour

2. does NOT Page 33 of 75

Catawba Nuclear Station IL Ti 6 (J4J$ RO NRC Examination Question: 34 (1 point)

Given the following conditions on Unit 1:

• Unit is at 100% power

• A malfunction has caused 1 KC-1 32 (Letdn Hx OtIt Temp Ctrl) to fail closed

• Annunciator 1AD-7 F13 (Letdn Hx Outlet High Temp) has alarmed The Annunciator Response Procedure for 1AD-7 F13 refers the crew to (1) which will direct alignment of (2) to the VCT position.

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

A. 1. AP/1/N5500/012 (Loss of Charging or Letdown)

2. 1 NV-i 72A (3-Way Divert To VCT-RHT)

B. 1. AP/i/N5500/012 (Loss of Charging or Letdown)

2. 1 NV-i 53A (Letdn Hx OtIt 3-Way Valve)

C. 1. AP/1/N5500/021 (Loss of Component Cooling Water)

2. 1 NV-i 72A (3-Way Divert To VCT-RHT)

D. 1. AP/1/N5500/02i (Loss of Component Cooling Water)

2. 1 NV-i 53A (Letdn Hx OtIt 3-Way Valve)

Page 34 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 35 (1 point)

Given the following conditions on Unit 1:

• A Small Break LOCA occurred in Containment

• S/I has actuated on both trains

• 1 B NV pump tripped on overcurrent

• Containment pressure is 3.5 PSIG Based on the above conditions, ALL cooling will be lost to the NC pump Which ONE (1) of the following completes the statement above?

A. motor bearings AND pump lower bearings B. seals AND pump lower bearings C. motor bearings ONLY D. seals ONLY Page 35 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 36 (1 point)

Given the following conditions on Unit 1:

• Unit is operating at 80% RIP

• A Pressurizer PORV sticks open Departure From Nucleate Boiling Ratio (DNBR) (1)

Over Temperature Delta T (CT AT) setpoint (2)

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

A. 1. decreases

2. decreases B. 1. decreases

2. increases C. 1. increases

2. decreases D. 1. increases

2. increases Page 36 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 37 (1 point)

Given the following conditions and sequence of events on Unit 1:

• Unit is operating at 100% RTP

• The crew enters AP/1/N5500/016 (Malfunction of Nuclear Instrumentation) due to N-42 lower detector failing LOW

• IAE has placed the required bistables in the trip condition per AP/16

• A complete loss of 1 ERPA occurs Which ONE (1) of the following describes the NEXT action the crew will take?

A. Enter API1/A/55001029 (Loss of Vital or Aux Control Power)

B. Enter EP/1/N5000/E-0 (Reactor Trip or Safety Injection)

C. Enter AP/1/N5500/003 (Load Rejection)

D. Continue in AP/16 Page 37 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 38 (1 point)

Which ONE (1) of the following describes the impact on the Reactor Protection System for a loss of 125 VDC Panelboard 1 EPA or 1 EPD?

A. The associated Reactor Trip Breaker cannot be opened by the Shunt trip B. The associated Reactor Trip Breaker cannot be opened by the UV trip C. SSPS Output Bay has lost one of two power supplies D. SSPS Logic Bay has lost one of two power supplies Page 38 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 39 (1 point)

Given the following conditions on Unit 2:

• A unit shutdown and cooldown is in progress

• All actions associated with NC system pressure going below P-i 1 have been corn pleted

• B Train components are in service The following sequence of events occurs:

1. 1 2OVAC Vital panel board 2ERPD de-energizes due to an electrical fault

2. A Main Steam line ruptures

3. Pressurizer pressure is 1840 PSIG and decreasing

4. Containment pressure is 1 .2 PSIG and increasing Which ONE (1) of the following (if any) would automatically START? (Assume no operator actions have occurred.)

A. Only A Train ECCS equipment B. Only B Train ECCS equipment C. None of the ECCS equipment D. All ECCS equipment Page 39 of 75

Catawba Nuclear Station ILT16 CNS RO NRC Examination Question: 40 (1 point)

Given the following conditions on Unit 2:

• Unit is at 50% RTP

• 2A CFPT is in service

• 25 CFPT is RESET but has not been placed in service Subsequently:

• 2A CFPT trips A CA autostart signal will FIRST be generated Which ONE (1) of the following completes the statement above? (Assume no operator action)

A. immediately due to loss of both CFPTs B. immediately due to actuation of AMSAC circuitry C. upon Lo/Lo S/G level setpoint of 11%

D. upon Lo/Lo S/G level setpoint of 37%

Page 40 of 75

Catawba Nuclear Station ILTJ6 CNS RO NRC Examination Question: 41 (1 point)

Given the following conditions on Unit 2:

• 2A, 2B, & 2C Lower Containment Ventilation Units (LCVU5) are operating in low speed Subsequently:

• A safety injection occurs due to high containment pressure

• Containment pressure is 1.5 PSIG and stable One minute after the Safety Injection, with no operator actions:

The 2A, 2B, & 2C LCVUs will be operating in (1) speed.

2RN-473 (LWR CONT VENT UNIT 2A FULL FLOW) valve is (2)

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

A. 1. low

2. CLOSED B. 1. low

2. OPEN C. 1. high

2. CLOSED D. 1. high

2. OPEN Page 41 of7S

Catawba Nuclear Station ILTJ6 CNS RO NRC Examination Question: 42 (1 point)

Which ONE (1) of the following lists of conditions would ALL result in 1 NF-228A (NE Supply Containment Isolation Valve) closing? (Evaluate each condition separately)

1. Loss of instrument air (VI)

2. Trip of all running Ice Condenser Glycol Pumps

3. Glycol Expansion Tank Lo/Lo Level

4. Loss of DC power to 1 NE-228A A. 1,2,and3 B. 2,3,and4 C. 1,2,and4 D. 1,3,and4 Page 42 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 43 (1 point)

Given the following conditions on Unit 1:

• OTG is performing Aux Safeguards testing

• A spurious automatic signal caused 1 NF-233B (Containment Return Isolation) to inadvertently close during the testing 1NF-233B was closed by an inadvertent (1) signal.

The glycol expansion tank (2) overflow inside containment.

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

A. l.ST

2. will NOT B. l.Sp

2. will NOT C. iS1

2. will D. iSp

2. will 1iF-?3I3 C125Ec) (AJ/7/ ,V A t no,vAt &PERFTIc . ,4iitw , T?)E Ex ci j v (?)

G L COL OUEIcFLOIAJ /AJSll1E co,iJm/AJE/l/T //

Page 43 of 75

Catawba Nuclear Station ILTJ6 CNS RO NRC Examination Question: 44 (1 point)

Given the following conditions on Unit 1:

• A Large Break LOCA has occurred

• Crew is performing EP/1/N5000/ES-1.3 (Transfer to Cold Leg Recirculation)

• Containment pressure is 3.5 PSIG

• Containment sump level is 5 feet

• 1A NS pump is running

• The BOP has just completed Enclosure 2 (Aligning NS for Recirculation) 1A NS pump will automatically stop when the CPCS signal decreases to a MA)(IMUM of (1) PSIG.

After the 1A NS pump automatically stops, If containment pressure quickly increases to 2 PSIG due to a large hydrogen burn in containment, the 1A NS pump (2) automatically start.

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

A. 1. 0.35

2. will NOT B. 1. 0.90

2. will NOT C. 1. 0.35

2. will D. 1. 0.90

2. will Page 44 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 45 (1 point)

Given the following conditions on Unit 1:

• Unit initially operating at 100% RTP when a Loss of Offsite Power occurs

• Train A CA has been RESET

• Train B CA could NOT be RESET and a maintenance crew is investigating Subsequently:

• The CA common suction piping from condensate grade sources ruptures

• 1AD-5, Eli CA Pumps Train A Loss of Norm Suct is LIT

• 1AD-5, E12 CA Pumps Train B Loss of Norm Suct is LIT With no operator actions, after a 5 second time delay from the receipt of the above alarms,:

CAPT #1 will automatically (1) 1 B CA pump will automatically (2)

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

A. 1. align to take a suction from the RN system

2. trip B. 1. align to take a suction from the RN system

2. align to take a suction from the RN system C. 1. trip

2. trip D. 1. trip

2. align to take a suction from the RN system Page 45 of 75

Catawba Nuclear Station ILTJ6 CNS RO NRC Examination Question: 46 (1 point)

Given the following conditions on Unit 1:

• The Unit is at 50% RTP

• SIG 1A N/R level increases to 90%

• All other S/G N/R levels are 52% and stable The above condition will isolate CF Flow to (1)

In order to mitigate the above condition, operators are required to enter procedure (2)

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

A. 1) S/G1AONLY

2) EP/1/N5000/E-0 (Reactor Trip or Safety Injection)

B. 1) S/G1AONLY

2) APIJ /N5500f002 flu rbine Trip)

C. 1) ALL S/Gs

2) EP/1/N5000/E-0 (Reactor Trip or Safety Injection)

D. 1) ALL S/Gs

2) AP/1/N5500/002 (Turbine Trip)

Page 46 of 75

Catawba Nuclear Station ILT16 CNS RO NRC Examination Question: 47 (1 point)

Given the following conditions on Unit 2:

• A loss of offsite power occurs from 100% RIP

• Crew is implementing EPI2IN5000/ES-0.1 (Reactor Trip Response)

• 2A and 2B motor driven CA pumps failed to start automatically or manually

• BOP placed switch CA PMP #2 to ON to feed the S/Gs Subsequently:

• Alarm 2AD-5 F/3 (CAPT MECH OS TRIP) actuated

• CA System Valve control has been RESET on both A and B trains Valves 2SA-2 (S/G 2B SM To CAPT) & 2SA-5 (S/G 2C SM To CAPT) are (1)

CAPT #2 (2) be restarted from the control room WITHOUT local operator actions.

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

A. 1. open

2. can NOT B. 1. open

2. can C. 1. closed

2. can NOT D. 1. closed

2. can Page 47 of 75

Catawba Nuclear Station ILTJ6 CNS RO NRC Examination Question: 48 (1 point)

Given the following conditions on Unit 2:

• Stable at 25% RTP

• The power supply to 2TB from transformer 2T1 B spuriously opens Due to the above conditions:

NCPump2Bis (1)

Once available, the power supply to 2TB is restored to normal alignment by a(n)

(2) transfer.

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

A. 1) tripped

2) automatic B. 1) running

2) automatic C. 1) tripped

2) manual D. 1) running

2) manual Page 48 of 75

Catawba Nuclear Station ILT16 CNS RO NRC Examination Question: 49 (1 point)

Given the following conditions on Unit 1:

• Unit 1 is operating at 100% RTP

• lB NI pump is inoperable

• The 1A DIG has just been declared inoperable due to an oil leak on the Woodward governor Which ONE (1) of the following describes an action which must be performed WITHIN ONE HOUR of declaring 1A DIG inoperable to ensure compliance with TS 3.8.1 (AC SOURCES OPERATING)?

A. Perform PT/1IN4350f002 C (Available Power Source Operability Check)

B. Determine the OPERABLE 1 B D/G is not inoperable due to a common cause failure C. Perform PT111N43501002 B (Diesel Generator lB Operability Test)

D. Declare 1A NI pump inoperable, because it is a required redundant feature supported by the inoperable 1A D/G, and declare entry into LCD 3.0.3 Page 49 of 75

Catawba Nuclear Station ILTJ6 CNS RO NRC Examination Question: 50 (1 point)

Vital battery 1 EBA is supplying 1 ERPA through inverter 1 EIA without a battery charger on line.

As battery terminal voltage decreases from 125 VDC to 120 VDC, battery current flow (1) and battery discharge rate (2)

Which ONE (1) of the following correctly completes the statement above?

A. 1. increases

2. decreases B 1. decreases

2. decreases C. 1. decreases

2. increases D. 1. increases

2. increases Page 50 of 75

Catawba Nuclear Station ILTJ6 CNS RO NRC Examination Question: 51 (1 point)

Given the following conditions on Unit 1:

• The BOP is performing OP/i /A/6350/002 (Diesel Generator Operation)

Enclosure 4.12 (D/G Startup and Shutdown from the Control Room)

• The BOP is preparing to parallel iA D/G to the grid and notes the following control room indications:

o Line Volts 4160 volts o D/G 1A Volts 4150 volts o D/G iA synchroscope is moving rapidly in the counter-clockwise (SLOW) direction Per OP/i /N6350/002 Enclosure 4.12, prior to closing the 1A D/G breaker:

The D/G 1A voltage control (1) pushbutton must be operated.

The D/G iA governor control (2) pushbutton must be operated.

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

A. 1. RAISE

2. LOWER B. 1. RAISE

2. RAISE C. 1. LOWER

2. LOWER D. 1. LOWER

2. RAISE Page 51 of75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 52 (1 point)

Given the following conditions on Unit 1:

• Unit is operating at 100% RTP

• BOP is setting up 1 EMF-39L (Containment Gas Low Range) for a VQ release per OP/i /N6450/0l 7 (Containment Air Release and Addition System)

• Current 1 EMF-39L setpoints are as follows:

o Trip 1 7.OE+2 cpm o Trip 2 1 .0E+3 cpm If the BOP inputs a Trip 1 value of 1 .2E÷3, the EMF module (1) accept it.

When performing the source check on 1 EMF-39L, the Trip 1 and Trip 2 lights (2) illuminate.

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

A. 1. will

2. will B. 1. will

2. will NOT C. 1. will NOT

2. will D. 1. will NOT

2. will NOT Page 52 of 75

Catawba Nuclear Station ILT16 CNSRO NRC Examination Question: 53 (1 point)

Given the following power supplies for Unit 2:

1. 2TA

2. 2TB

3. 2TC

4. 2TD Which ONE (1) of the following is a COMPLETE list of the YV (Containment Chilled Water System) chiller power supplies on Unit 2?

A. 1,2,and3 B. 2,3,and4 C. 1,3,and4 D. 1,2,and4 Page 53 of 75

Catawba Nuclear Station ILTJ6 CNS RO NRC Examination Question: 54 (1 point)

Given the following conditions on Unit 2:

• Unit operating at 100% RTP

• 2V1-77B (VI Cont Isol) fails closed Lower containment temperature will (1)

The LCVU full flow bypass valves will fail (2)

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

A. 1. increase

2. CLOSED B. 1. decrease

2. CLOSED C. 1. increase

2. OPEN D. 1. decrease

2. OPEN Page 54 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 55 (1 point)

During a normal containment air release (VQ), valve (1) automatically closes to prevent containment pressure from decreasing below 0 PSIG.

The limit on negative (-) containment pressure per Tech Spec 3.6.4 (Containment Pressure) is (2) P51G.

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

A. 1. VQ-10 (VQ Fans Disch To Unit Vent)

2. -0.1 B. 1. VQ-3B (VQ Fan Suct From Cont Isol)

2. -0.1 C. 1. VQ-1 0 (VQ Fans Disch To Unit Vent)

2. -0.3 D. 1. VQ-3B (VQ Fan Suct From Cont Isol)

2. -0.3 Page 55 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examincttion Question: 56 (1 point)

Given the following conditions on Unit 1:

• Unit operating at 100% RTP Subsequently:

• C NC loop Tavg is HIGH

• C NC loop tiT is LOW The failure that caused the above indications was (1)

The C-3 OTDT Rod Stop & Turbine Runback status light on 1SI-18 is (2)

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

A. 1. C loop Thot failed high

2. DARK B. 1. C loop I-hot failed high

2. LIT C. 1. C loop T-cold failed high

2. DARK D. 1. C loop T-cold failed high

2. LIT Page 56 of 75

Catawba Nuclear Station IL T16 CNS RO NRC Examination Question: 57 (1 point)

Given the following conditions on Unit 1:

• Unit is operating at 100% RTP

• Control Bank D rods are reading 222 steps on DRPI Subsequently:

• Control Bank D rod M-6 indicates 192 steps on DRPI

• Annunciator 1AD-2 DuO RPI URGENT FAILURE alarms

• DRPI background for Control Bank D turns ORANGE To determine that rod M-6 is actually misaligned, the operator would expect to see AFD in that quadrant to become (1) negative.

The 1AD-2 DuO Annunciator Response states that a rod with > (2) steps deviation within a bank is a probable cause for this alarm.

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

A. 1. less

2. 24 B. 1. less

2. 12 C. 1. more

2. 24 D. 1. more

2. 12 Page 57 of 75

Catawba Nuclear Station ILTJ6 CNSRO NRC Examination Question: 58 (1 point)

Given the following:

The following instrument diagram represents a typical CET measuring circuit:

EEl I Hot If the thermocouple measuring junction experiences an open circuit, the associated CET will indicate (1) temperature.

If the thermocouple reference junction temperature decreases by 50°F, the associated CETs will indicate 50°F (2)

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

A. 1. HIGH

2. HIGHER B. 1. HIGH

2. LOWER C. 1. LOW

2. HIGHER D. 1. LOW

2. LOWER Page 58 of 75

Catawba Nuclear Station ILTJ6 CNS RO NRC Examination Question: 59 (1 point)

Which ONE (1) of the following is the power supply for the 1A VE Fan?

A. 1MXJ B. 1MXK C. 1EMXI D. 1EMXB Page 59 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 60 (1 point)

Concerning the Containment Purge System (VP):

During refueling mode of operation, airborne contaminants are directed to (1) Containment.

This is accomplished by changing the (2) fan discharge alignment.

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

A. 1. Upper

2. Supply B. 1. Lower

2. Supply C. 1. Upper

2. Exhaust D. 1. Lower

2. Exhaust Page 60 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 61 (1 point)

Given the following conditions on Unit 1:

• A large break LOCA has occurred

• Unit 2 BOP is performing EP/1/N5000/E-0 (Reactor Trip or Safety Injection) step to monitor Spent Fuel Pool level and temperature using G-1 Enclosure 1

• BOP notices that KF pump 1A has tripped and that Spent Fuel Pool level on 1 KFP51 20 has failed low

• The Unit Supervisor and the Unit 2 BOP enter API1/N55001041 (Loss of Spent Fuel Pool Cooling or Level)

• Spent Fuel Pool temperature on 1kFP5130 is reading 105°F

• An AC dispatched to monitor Spent Fuel Pool Level locally reports that level is one foot below the top of the skimmer loop trough Per E-0, Spent Fuel Pool level and temperature monitoring (1) required within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the event.

The MAXIMUM KF flow allowed by AP-41 when the 1 B KF pump is placed in service is (2) GPM.

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

REFERENCE PRO VIDED A. 1. is NOT

2. 2310 B. 1. is

2. 2310 C. 1. is NOT

2. 2840 D. 1. is

2. 2840 Page 61 of75

Catawba Nuclear Station ILTJ6 CNS RO NRC Examination Question: 62 (1 point)

The reactor building fuel hoist mechanical overload switch opens at a MINIMUM of (1) pounds.

This interlock (2) be bypassed.

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

A. 1. 2700

2. can NOT B. 1. 1200

2. can NOT C. 1. 2700

2. can D. 1. 1200

2. can Page 62 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 63 (1 point)

Given the following conditions on Unit 1:

• A 1C S/G tube rupture has occurred

• Total CA flow is 1200 GPM and stable

• Containment pressure is 0.2 PSIG and stable Per EPI1IN5000/E-0 (Reactor Trip or Safety Injection) Enclosure 1 (Foldout Page),

the LOWEST S/G N/R level that will require CA flow to be isolated to 1 C S/G is Which ONE (1) of the following completes the statement above?

A. 11%

B. 16%

C. 29%

D. 39%

Page 63 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 64 (1 point)

Given the following plant conditions:

• A Waste Gas release is in progress

• A system lineup issue has resulted in an unintentional release of radioactive gas into the Auxiliary Building

• The following EMF Trip 2 lights are lit:

o OEMF-41 (Auxiliary Building Ventilation Monitor) o 1 EMF-6 (Waste Gas and Spent Resin Area) o 1 EMF-35 (Unit Vent Particulate Monitor) o OEMF-50L (Waste Gas Discharge Low Range)

• The operator notes the following for the VA system on Unit 1:

o 1A & 1 B Exhaust trains are operating in the FILTER mode of operation o 1A & 1 B Unfiltered Exhaust fans have tripped o 1A & 1 B Supply fans have tripped With no operator actions, which ONE (1) of the following EMFs being in Trip 2 automatically caused the VA alignment listed above?

A. OEMF-41 B. 1EMF-6 C. 1EMF-35 D. OEMF-50L Page 64 of 75

Catawba Nuclear Station ILTJ6 CNS RO NRC Examination Question: 65 (1 point)

Given the following plant conditions:

• A Loss of Instrument Air has occurred

• VI pressure is 75 PSIG and slowly decreasing Based on the given conditions, and per APIOIN5500/022 (Loss of VI):

Operators (1) required to be dispatched to ensure 1VI-499 (VI Comp D to VS Hdr) is closed.

1VS-78 (VS Auto Backup to VI) (2) automatically opened.

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

A. 1. are

2. has B. 1. are

2. has NOT C. 1. are NOT

2. has D. 1. are NOT

2. has NOT Page 65 of 75

Catawba Nuclear Station ILT16 CNS RO NRC Examination Question: 66 (1 point)

Given the following conditions on Unit 1:

• Control rods are in manual

• The plant is at 30% RTP when a loss of 1 ETA occurs

• The 1A DIG starts and is carrying the 1ETA bus

• Tave has decreased to 563.5° F and Tref is 565.5°F and stable

• Reactor power has increased from 30% to 34%

Per AD-OP-ALL-0203, Reactivity Management, which ONE (1) of the following describes the required crew actions, if any, to address the power increase?

A. The crew should emergency borate using 1 NV-236B (Boric Acid To NV Pumps Suct), to establish power at or below the pre-transient power level B. Crew should reduce turbine load to establish power at or below the pre transient power level C. No actions required by AD-OP-ALL-0203, because reactor power was maintained less than 100% throughout the transient D. Operate control rods to restore Tave within 1 .5°F of Tref Page 66 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 67 (1 point)

Given the following conditions on Unit 1:

• Unit is in Mode 6 perForming total core unload 5 days following shutdown Which ONE (1) of the following conditions would require that Core Alterations be suspended IMMEDIATELY per Tech Specs?

A. The equipment hatch is off B. Refueling Cavity Boron concentration is <COLR minimum C. Source Range N31 inoperable with N32 and both BDMS channels OPERABLE D. Refueling Cavity water level at 23 feet above the reactor vessel flange with ONLY one ND loop OPERABLE Page 67 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 68 (1 point)

Given the following conditions on Unit 1:

• Unit tripped 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago (0800 yesterday) after a 200 day run at 100% RTP

• An Estimated Critical Position (ECP) of Control Bank D at 90 steps was calculated for a reactor startup at 0800 today

• The reactor startup has been delayed until 1300 today while waiting to clear a Tech Spec Action Statement If there is no change to NC system boron concentration:

Per PT101N41501019 filM Approach To Criticality), the existing ECP (0800 startup)

(1) be used for the 1300 Reactor startup.

The actual critical rod height for the 1300 Reactor startup will be (2) than Control Bank D at 90 steps.

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

A. 1. can

2. higher B. 1. can

2. lower C. 1. can NOT

2. higher D. 1. can NOT

2. lower Page 68 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 69 (1 point)

Concerning the inservice valve testing (IWV) program:

Valves with remote position indication shall be observed locally at least once every (1)

When performing IWV testing of a valve in the closed direction, the stop watch will be started when the associated valve E30 switch (2)

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

A. 1. quarter

2. CLOSE pushbutton is depressed B. 1. quarter

2. position indicating light changes state C. 1. 2 years

2. CLOSE pushbutton is depressed D. 1. 2 years

2. position indicating light changes state Page 69 of 75

Catawba Nuclear Station ILTJ6 CNS RO NRC Examination Question: 70 (1 point)

Given the following conditions on Unit 2:

• Mode 3 with startup in progress Subsequently:

• A loss of offsite power occurs

• The plant stabilizes with Pressurizer level stable at 90%, and only 2ETA powered from its Diesel Generator Which ONE (1) of the following identifies the status of LCO 3.4.9 (PRESSURIZER)?

A. LCD 3.4.9 is met.

B. LCD 3.4.9 is NOT met, because Pzr level is too high ONLY.

C. LCD 3.4.9 is NOT met, because of insufficient Pzr Heater Capacity ONLY.

D. LCD 3.4.9 is NOT met, because of insufficient Pzr Heater Capacity AND because Pzr level is too high.

Page 70 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 71 (1 point)

Given the following conditions on Unit 1:

• You are to perform a valve lineup in the Letdown Heat Exchanger Room

• The dose rate in the room is 3000 mREM/HR In accordance with PD-RP-ALL-0001 (RADIATION PROTECTION):

The Letdown Heat Exchanger Room must be posted as a (1) Area.

An EXCLUDE flag is a notification that an individual has reached (2) or greater of the established administrative limit.

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

A. 1. Locked High Radiation

2. 80%

B. 1. Locked High Radiation

2. 90%

C. 1. Very High Radiation

2. 80%

D. 1. Very High Radiation

2. 90%

Page 71 of 75

Catawba Nuclear Station ILT16 CNS RO NRC Examination Question: 72 (1 point)

Given the following conditions on Unit 2:

• Mode 4 valve checklist PT is being performed

• The PT calls for independent verification of a single valve located in a room

• with a general dose rate of 110 mR/hr

• The time to independently verify the valves position is 5 minutes In accordance with NSD-700 (VERIFICATION TECHNIQUES), independent verification of the valve above (1) be waived because (2)

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

A. 1. may

2. the general area dose rate is greater than 100 mR/hr B. 1. may NOT

2. the general area dose rate is less than 10 R/hr C. 1. may

2. the radiation exposure for a single verification exceeds the allowable limit D. 1. may NOT

2. the radiation exposure for a single verification is within the allowable limit Page 72 of 75

Catawba Nuclear Station IL T16 CNS RO NRC Examination Question: 73 (1 point)

Given the following conditions on Unit 1:

Operators have entered EPI1IN5000IFR-P.1 (Response To Imminent Pressurized Thermal Shock Condition) due to a valid ORANGE path status for NC Integrity

/

In accordance with OMP 1-7 (Emergency/Abnormal Procedure Implementation Guidelines):

If the NC Integrity status turns RED during performance of FR-P.1, the CRS (1) required to return to step 1.

lithe Core Cooling status turns ORANGE during performance of FR-P.1 (while NC Integrity is ORANGE), the CRS (2) required to go to EP/1/N5000/FR-C.2 (Response to Degraded Core Cooling).

Which ONE (1) of the following completes the statements above? (Consider each statement separately as it relates to the initial condition)

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 73 of 75

Catawba Nuclear Station IL Ti 6 CN$ RO NRC Examination Question: 74 (1 point)

During an emergency event:

The on-site emergency facility that assumes responsibility for communications with offsite agencies including the NRC once it is activated is the (1)

The MINIMUM level of emergency classification that always REQUIRES an evacuation of all non-essential personnel from the site is a (2)

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

A. 1. Technical Support Center (TSC)

2. Site Area Emergency B. 1. Technical Support Center (TSC)

2. General Emergency C. 1. Operations Support Center (OSC)

2. Site Area Emergency D. 1. Operations Support Center (OSC)

2. General Emergency Page 74 of 75

Catawba Nuclear Station IL Ti 6 CNS RO NRC Examination Question: 75 (1 point)

Given the following conditions on Unit 1:

• I B DIG is tagged out

• The control room has been evacuated per AP/1/N5500/O1 7 (Loss of Control Room) due to a fire in the Auxiliary Buildirig

• Following control room evacuation, a loss of offsite power occurred AP/1 7 requires a reactor operator to be dispatched to the (1) to maintain Hot Standby conditions on Unit 1.

The emergency sound powered phone circuit (2) be available for communications.

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

A. 1. Auxiliary Shutdown Panels

2. will B. 1. Auxiliary Shutdown Panels

2. will NOT C. 1. Standby Shutdown Facility

2. will D. 1. Standby Shutdown Facility

2. will NOT Page 75 of 75

Unit 1 Data Book Source: CNM-1 300.001 53, Fig. 17-3, Dwg 435HA148 (Rev. 2)

ATB 4 POLE, 1,450,000 KVA, 1800 RPM, 2200 VOLTS 0.9 PF, 0.50 SCR, 75 PSIG HYDROGEN PRESSURE, 545 VOLTS EXCITATION 1500 1250 1000 750 500 Cl)

> 250 0

0 0

-250

-500

-750

-1000 1000 kilowatts I 30 PSIG -45 PSIG 60 PSIG 75 PSIG Figure 43 Generator Capability Curves Page 1

CNS I LOSS OF SPENT FUEL COOLING OR LEVEL I

PAGE NO.

35 of 97 I API1IA/5500/041 Enclosure 2 Page 1 of 1 Revision 1 1 Allowable KF Flowrates

1. IF Spent Fuel Pool level instruments are unavailable, THEN locally determine level.

REFER TO Enclosure 19 (Spent Fuel Pool Local Level Determination).

NOTE

• Flow rates decrease at 140°F due to removing the purification loop from service at 125°F.

1KFP513O only goes to 200°F, therefore the 21 2°F value is obtained by local observation.

2. Refer to the following table for allowable KF flows (GPM) verses Spent Fuel Pool temperature and level.

Spent Fuel Spent Fuel Pool Level ( 1KFP5Y2O)

Pool Tern p

( 1KFP5130) 42 37 38 38.6 39 39.5 40 40.5 41 41.5 100 0 0 750 2310 2840 2840 2840 2840 2840 2840 120 0 0 750 2310 ?840 2840 2840 2840 2840 2840 140 0 0 750 2310 2310 2310 2310 2310 2310 2310 160 0 0 750 2310 2310 2310 2310 2310 2310 2310 180 0 0 750 2310 2310 2310 2310 2310 2310 2310 190 0 0 750 2170 2170 2170 2170 2310 2310 2310 195 0 0 750 2170 2170 2170 2170 2170 2170 2170 200 0 0 750 1420 1420 1420 1420 2170 2170 2170 212 0 0 750 750 750 750 750 1000 1200 1420

CNS LOSS OF SPENT FUEL COOLING OR LEVEL PAGE NO.

APII/A15500/041 Enclosure 19 Page 1 of 1 Revioni 1 Spent Fuel Pool Local Level Determination

1. Obtain Radiation Protection assistance as required for entry to the Unit I Spent Fuel Pool area.

2. Determine approximate Unit I Spent Fuel Pool water level as follows:

NOTE The following reference points can be used to determine approximate Unit 1 SFP level by visual inspection.

a. Refer to the table below to determine approximate pool level.

SEP Reference Point Approximate Unit 1 SEP level SEP Underwater Light 41 0 Receptacles Top of Skimmer Trough 40 0 1st Horizontal SEP Liner 40 0 Plate Angle-Iron Cover Bottom of Skimmer Trough 38 10 Centerline of KE pump 37 6 Suction Strainers 2nd Horizontal SEP Liner 30 0 Plate Angle-Iron Cover 3rd Hon zontal SEP Li ner 20 0 Plate Angle-Iron Cover Top of Spent Fuel 14 6 Storage Racks

b. Notify Control Room Supervisor of approximate Unit 1 Spent Fuel Pool water level.

ILT 2016 NRC RO Written Exam Answer Key 1 D 26 0 51 B 2 0 27 C 52 B 3 C 28 A 53 A 4 D 29 A 54 D 5 A 30 B 55 A C

6 A 31 D 56 D

7 0 32 B 57 8 B 33 C 58 C 59 C 9 B 34 D 10 A 35 C 60 B 61 B A 36 A 11 12 A 37 B 62 A 13 0 38 A 63 A 64 C D 39 A 14 15 B 40 D 65 A 16 C - 41 B 66 B 17 A 42 D 67 B 18 B 43 C 68 0 C

19 A 44 A 69 20 C 45 B 70 C 21 C 46 C 71 B 22 C 47 A 72 D 23 C D 73 C 24 A 49 A 74 B 25 D 50 D 75 D