ML15097A267

St. Lucie 2015-301 Final SRO Written Exam

ML15097A267
Person / Time
Site:	Saint Lucie
Issue date:	04/07/2015
From:	NRC/RGN-II
To:	Florida Power & Light Co
References
50-335/15-301, 50-389/15-301 50-335/OL-15, 50-389/OL-15
Download: ML15097A267 (149)

Text

HLC 22 SRO NRC EXAM Page 1 of 100 Question 1 Unit 1 is at 45% power steady state. A leak on the upper instrument tap (reference leg) associated with the SELECTED "Pressurizer (Pzr) Level Transmitter," LT-1110X occurs.

Assuming NO Operator actions, which ONE of the following would be the response of the Pressurizer Pressure Level Control System?

Indicated Pzr Level Actual Pzr Level A. lowers rises B. rises rises C. rises lowers D. lowers lowers HLC 22 SRO NRC EXAM Page 2 of 100 Question 2 Given the following conditions on Unit 1:

The reactor has been manually tripped and the crew is implementing 1

-EOP-01, "Standard Post Trip Actions" The Core Heat Removal Safety Function has JUST been completed.

Pressurizer pressure is 1590 psia Containment pressure is 5.5 psig Which ONE of the following completes the statements below:

A Safety Injection Actuation signal __(1)__ occurred.

The required status of the Reactor Coolant pumps at this time is __(2)__ should be secured. A. 1) HAS 2) ONE RCP in each loop

B. 1) HAS 2) ALL four RCPs

C. 1) HAS NOT 2) ONE RCP in each loop

D. 1) HAS NOT 2) ALL four RCPs HLC 22 SRO NRC EXAM Page 3 of 100 Question 3 Given the following conditions on Unit 2:

A Loss of Coolant Accident (LOCA) has occurred Reactor Coolant System pressure is 75 psia Which ONE of the following is monitored or performed with regards to Short and Long Term Core Cooling given the above conditions?

Short Term Cooling Long Term Cooling A. Low Pressure Safety Injection operation/ Align Shutdown Cooling Safety Injection Tanks discharge

B. Low Pressure Safety Injection operation/ Align High Pressure Safety Injection

Safety Injection Tanks discharge hot and cold leg injection with a Recirculation Actuation Signal

C. High Pressure Safety Injection operation/ Align Shutdown cooling Steam Generator steaming

D. High Pressure Safety Injection operation/

Align High Pressure Safety Injection Steam Generator steaming hot and cold leg injection with a Recirculation Actuation Signal

HLC 22 SRO NRC EXAM Page 4 of 100 Question 4 Unit 2 is at 100% power Given the following indications on the 2A1 Reactor Coolant Pump (RCP):

Controlled Bleedoff (CBO) temperature is 225 o F CBO flow is 2.5 gpm Vapor Seal Cavity pressure is 80 psia Upper Seal Cavity pressure is 2235 psia Middle Seal Cavity pressure is 2235 psia Which ONE of the following describes the status of the RCP seals and required action?

A. ONLY One RCP seal has failed; perform a controlled shutdown then secure the 2A1 RCP. B. ONLY Two RCP seals have failed; trip the reactor and secure the 2A1 RCP.

C. ONLY Two RCP seals have failed; perform a controlled shutdown then secure the 2A1 RCP. D. Three RCP seals have failed; trip the reactor and secure the 2A1 RCP.

HLC 22 SRO NRC EXAM Page 5 of 100 Question 5 Unit 1 is operating at 100% power

. The SNPO reports that a break in the Charging header has occurred.

The following indications noted on the RTGB:

Charging Header pressure is 0 psig Charging Header flow is 0 gpm Reactor Cavity leakage is 0.1 gpm and steady Which ONE of the following completes the statements below:

Annunciator __(1)__ should be in alarm for this condition.

Due to the leak location, __(2)___ Charging pump(s) can be used when aligning per 1

-AOP-02.03, "Alternate Charging Flow Path Through the Auxiliary HPSI Header."

(Reference Provided)

A. 1) M-7, "Regenerative Heat Exchanger Letdown P High" 2) either the 1A, 1B OR 1C

B. 1) M-28, "Regenerative Heat Exchanger Outlet Temp High"

2) either the 1A, 1B OR 1C

C. 1) M-7, "Regenerative Heat Exchanger Letdown P High" 2) ONLY the 1A D. 1) M-28, "Regenerative Heat Exchanger Outlet Temp High" 2) ONLY the 1A

HLC 22 SRO NRC EXAM Page 6 of 100 Question 6 Given the following conditions on Unit 1:

The unit is currently shutdown for a refueling outage The Reactor Head is being removed The RCS level 35 feet Time since reactor shutdown is 250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> Reactor Coolant Sy stem (RCS) temperature is 95º F

. Which ONE of the following choices completes the statement below:

If all SDC was lost, with the conditions given above, the Time to Boil is approximately____ minutes.

(References Provided)

A. 28 B. 30 C. 37 D. 40 HLC 22 SRO NRC EXAM Page 7 of 100 Question 7 Given the following conditions on Unit 1:

The 1A and 1B Component Cooling Water (CCW) pumps are running The 1C CCW pump is in standby in accordance with 1

-NOP-14.02, "CCW System Operation," and is aligned to the "B" train electrically and mechanically A Loss of Offsite Power (LOOP) has just occurred The 1B CCW pump failed to start following the LOOP 1 minute later, a Loss of Coolant Accident (LOCA) with SIAS and CIAS actuation occurred Which ONE of the following describes the configuration of the CCW system at this time?

(Assume no operator actions)

A. ONLY 1 CCW pump supplying all CCW loads due to the failure of "1B" CCW pump to start.

B. Two CCW pumps supplying all CCW loads due to SIAS start of the "1C" CCW pump.

C. ONLY 1 CCW pump supplying its own safety header due to ESFAS isolation of the N on-Essential header.

D. Two CCW pumps supplying all CCW loads due to SIAS start of the "

1C" CCW pump until the N on-Essential header isolates on a loss of instrument air

.

HLC 22 SRO NRC EXAM Page 8 of 1 00 Question 8 Given the following conditions on Unit 1: The unit is operating at 100% power PIC-1110X, "Pressurizer (Pzr) pressure controller" is selected Pzr pressure is being maintained at 2250 psia with Pzr Backup Heaters B1, B2, and B5 ON with a 10% output to the Pzr Proportional Heaters PT-1110Y is out of service for I&C calibration PT-1110X begins to slowly fail high.

Which ONE of the following choices completes the statement below:

IAW 1-AOP-01.10 "Pressurizer Pressure and Level," the operator is directed to take manual control of HIC

-1100, "Spray Valve controller" and __(1)__ its output in order to __(2)__ ACTUAL Pzr Pressure.

A. 1) lower 2) lower B. 1) lower 2) raise C. 1) raise 2) raise D. 1) raise 2) lower HLC 22 SRO NRC EXAM Page 9 of 100 Question 9 Given the following conditions on Unit 1:

Reactor power is 100%

A total loss of feedwater event occurred The Reactor Protection System FAILED TO AUTOMATICALLY TRIP the reactor when trip conditions were present No operator actions have been taken

Which ONE of the following describes the expected reactivity change AND the impact on the Reactor Coolant System (RCS) Pressure from this event?

Over the next 5 minutes, reactor power will:

A. Stay the same; an RCS over pressure condition will be prevented due to the event being within the design bases of the Pressurizer Safety valves.

B. Stay the same; an RCS pressure excursion that could potentially challenge the RCS pressure boundary integrity will be prevented by the Diverse Scram System.

C. Lower; an RCS over pressure condition will be prevented due to the event being within the design bases of the Pressurizer Safety valves.

D. Lower; an RCS pressure excursion that could potentially challenge the RCS pressure boundary integrity will be prevented by the Diverse Scram System.

HLC 22 SRO NRC EXAM Page 10 of 100 Question 10 Given the following conditions on Unit 1: The unit was operating at 100% power A Steam Generator Tube Rupture (SGTR) occurs 1-EOP-04, "SGTR" is being implemented SIAS actuation has occurred A Reactor Coolant System (RCS) cool down and depressurization is in progress The crew is evaluating RCS Void Elimination per 1

-EOP-99, Appendix K, "RCS Fill and Drain Method of Void Elimination."

Which ONE of the following is an indication that voids are present in the Reactor Vessel Head?

A. RVLMS indicates segments voided

. B. Pressurizer Level lowering while spraying

. C. Pressurizer level rising while charging to the RCS

.

D. The saturation temperature of the RCS is higher than the temperature in the upper Rx Head region.

HLC 22 SRO NRC EXAM Page 11 of 100 Question 11 Given the following:

The Unit 1 reactor tripped from 100% power 15 minutes ago The 1A and 1B Auxiliary Feedwater (AFW) pump's header flow control valves have been throttled to the desired flow rate for BOTH SGs The 1C AFW pump header flow control valves were closed The 1A and 1B Steam Generator (SG) Narrow Range levels are 10% and slowly rising A Loss of Offsite Power (LOOP) has just occurred and BOTH Emergency Diesel Generators (EDGs) are supplying power to their respective 4.16kVAC busses To maintain Reactor Coolant System temperature stable, which ONE of the following describes the manual operator action that must be taken on the AFW header flow control valves in response to the LOOP?

The 1A and 1B AFW pump header flow control valves __(1)___.

The 1C AFW pump header flow control valves

__(2)__. A. 1) require throttling closed

2) require throttling closed B. 1) remain throttled

2) require throttling closed C. 1) require throttling closed

2) remain closed D. 1) remain throttled

2) remain closed

HLC 22 SRO NRC EXAM Page 12 of 100 Question 12 Given the following conditions on Unit 1:

A Station Blackout has occurred and 1

-EOP-10, "Station Blackout," is being implemented The crew is evaluating Single Phase Natural Circulation criteria The BRCO reports the T between REP CET and Thot is 18 oF and increasing Which ONE of the following choices describes:

1. The contingency action, in 1

-EOP-10, "Station Blackout," that is to be taken if Single Phase Natural Circulation criteria is BEING challenged?

AND

2. The operational implications if the temperature difference between T hot and REP CET exceeds the Single Phase Natural Circulation criteria limits?

A. 1) Verify Two Phase Natural Circulation CRITERIA

. 2) The Hot Legs are becoming thermodynamically uncoupled from the core.

B. 1) Verify Two Phase Natural Circulation CRITERIA

. 2) The Reactor Coolant System is approaching saturated conditions.

C. 1) Ensure proper control of Steam Generator feeding and steaming. 2) The Hot Legs are becoming thermodynamically uncoupled from the core. D. 1) Ensure proper control of Steam Generator feeding and steaming

. 2) The Reactor Coolant System is approaching saturated conditions

.

HLC 22 SRO NRC EXAM Page 13 of 100 Question 13 Given the following conditions for Unit 2:

The unit is operating at 100% power The 2AB 4.16kVA C bus is aligned to the 2B3 4.16kVAC bus HVA/ACC-3C is the running air conditioning unit HVA/ACC-3A and HVA/ACC

-3B control switches are aligned as required per 2

-NOP-25.07, "Control Room Ventilation System" A Loss of Offsite Power (LOOP) has occurred

Which ONE of the following describes the final configuration of HVA/ACC

-3A and HVA/ACC-3 B Air Conditioning units AFTER the EDG loading sequence is complete

? HVA/ACC-3A is __(1)__.

HVA/ACC-3B is __(2)__.

A. 1) runni ng 2) not running B. 1) not running

2) not running C. 1) not running

2) running

D. 1) running

2) running HLC 22 SRO NRC EXAM Page 14 of 100 Question 14 Given the following conditions on Unit 1:

The unit is operating at 100% power A loss of the 1MB 120VAC "Vital Instrument Inverter" occurs Which ONE of the following choices completes the statements below:

The "B" Channel Steam Generator (SG)

Pressure and Level Safety channel indication will be affected on the __(1)__ .

The Reactor Protection System coincidence for a reactor trip will now be __(2)__ on Low SG Pressure or Level.

A. 1) "A" and "B" SGs

2) 1 out of 3 B. 1) "A" and "B" SGs

2) 2 out of 3 C. 1) "B" SG ONLY

2) 1 out of 3 D. 1) "B" SG ONLY

2) 2 out of 3

HLC 22 SRO NRC EXAM Page 15 of 100 Question 15 Given the following conditions on Unit 1 Unit 1 was operating at 100% power The 1AB busses are aligned to the "A" train The unit tripped and the crew is carrying out actions of EOP

-01, "Standard Post Trip Actions

" During the Maintenance of Vital Auxiliaries Safety Function, the DRCO reports that the 1AB DC bus is de

-energized Which ONE of the following actions are required in accordance with EOP-01 AND also satisfies the design basis:

Within ______ , re

-energize the 1AB DC bus from the ________.

A. 10 minutes; 1AB Battery Charger B. 10 minutes; 1B DC bus

C. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; 1AB Battery Charger D. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; 1B DC bus

HLC 22 SRO NRC EXAM Page 16 of 100 Question 16 Given the following: Unit 2 is operating at 100% power

. The 2B3 4.16kVAC bus has been de

-energized due to a differential current lockout The 2AB 4.16kVAC bus is aligned to the "A" train The crew was UNSUCCESSFUL in resetting the differential current lockout relay The US directed that the 2B Intake Cooling Water (ICW) pump control switch be placed in "Pull

-to-Lock" AND the 2C ICW pump MECHANICALLY aligned to the "B" train The US also directed that the 2 B Component Cooling Water pump (CCW) pump control switch be placed in "Pull-to-Lock" AND the 2C CCW pump MECHANICALLY aligned to the "B" train The 2C ICW pump and the 2C CCW pump were then started as directed by 2

-AOP-47.01B, "Loss of a Safety Related AC Bus

-Train B" Which ONE of the following statements describes ALL of the consequences associated with the ICW system AND the CCW system being in this configuration per Ops Policy 503? A. Offsite Power Operability for two ICW pumps running on the same electrical bus; Offsite Power Operability for two CCW pumps running on the same electrical bus.

B. Offsite Power Operability for two ICW pumps running on the same electrical bus.

C. Offsite Power Operability for two ICW pumps running on the same electrical bus; Offsite Power Operability AND Emergency Diesel Generator Operability for two CCW pumps running on the same electrical bus.

D. Offsite Power Operability AND Emergency Diesel Generator Operability for two CCW pumps running on the same electrical bus.

HLC 22 SRO NRC EXAM Page 17 of 100 Question 17 Given the following

An uncomplicated trip from 100% power has occurred on Unit 2 2-EOP-01, "Standard Post Trip Actions" is being implemented Reactor power is 1.0E-6% and lowering as indicated on Wide Range Instrumentation Which ONE of the following describes the status of the Nuclear Startup Channels? A. Energized. They automatically energize d at 1.0 E-5% power. B. NOT energized. They will be manually energized while implementing 2

-EOP-01, "Standard Post Trip Actions."

C. Energized. They automatically energize d on the reactor trip signal.

D. NOT energized. They will be manually energized after 2

-EOP-02, "Reactor Trip Recovery" is entered.

HLC 22 SRO NRC EXAM Page 18 of 100 Question 18 Given the following:

Unit 1 Reactor is at a stable power level of 2% in preparation for plant start up An ESDE on the 1A Steam Generator (SG) inside containment occurred Reactor Coolant System (RCS) T av g is currently 515

°F and lowering RCS pressure is 2220 psia and lowering Pressurizer level is 25% and lowering Both Atmospheric Dump Valves (ADV's) are in service operating in Auto After the reactor is tripped, which ONE of the following describes:

1) The expected plant response.

AND

2) After the 1A SG dries out, operate the 1B ADV at a saturation pressure for

_____. A. 1) BOTH SGs will depressurize at the same rate until MSIS. 2) RCS T av g of 525 oF to 535 o F B. 1) ONLY the 1A SG will depressurize

. 2) the lowest RCS TCOLD C. 1) BOTH SGs will depressurize at the same rate until MSIS

. 2) the lowest RCS TCOLD D. 1) ONLY the 1A SG will depressurize

. 2) RCS T av g of 525 o F to 535 o F HLC 22 SRO NRC EXAM Page 19 of 100 Question 19 Unit 2 is in Mode 2 with the following:

A reactor startup is in progress using 2

-GOP-302, "Reactor Plant Startup

- Mode 3 to Mode 2" Reactor power is 1.0E-5% CEA group 5 is at 52 inches and being withdrawn in manual sequential to a planned stopping height of 60 inches CEA #59 does not move with the rest of the Group 5 CEAs If the CEAs were continued to be withdrawn, which ONE of the following alarms are expected during this evolution?

A. K-29, CEA PDIL (ADS). B. K-18, Auto Withdra w Prohibit. C. K-11, CEA Motion Inhibit. D. K-26, CEA Withdrawal Prohibit.

HLC 22 SRO NRC EXAM Page 20 of 100 Question 20 Given the following:

Unit 2 tripped from 100% due to a Loss of Offsite Power (LOOP)

All "AB" electrical busses are aligned to the "B" side The 2B Charging pump is out of service with its control switch in stop Following the trip

The 2A Emergency Diesel Generator (EDG) tripped on overspee d

Which ONE of the following choices completes the statement below:

If a condition requiring the crew to emergency bora te existed, operator s would be required to start the 2C Chg pump and emergency borate via the ___(1)____ to establish a flowpath.

If a SIAS were to subsequently occur, the 2C Chg pump breaker would __(2)__.

A. 1) 2B Boric Acid Makeup pump and Emergency Borate valve (V2514)

2) open then reclose on the load block sequencer

B. 1) Gravity Feed valves (V2508 and V2509)

2) remain closed

C. 1) 2B Boric Acid Makeup pump and Emergency Borate valve (V2514)

2) remain closed

D. 1) Gravity Feed valves (V2508 and V2509)

2) open then reclose on the load block sequencer

HLC 22 SRO NRC EXAM Page 21 of 100 Question 21 Given the following conditions on Unit 2:

The reactor is operating at 100% power Channel "X" for Pressurizer (Pzr) Level control is SELECTED Channel "Y" for Pzr Level control, LT

-1110Y, failed LOW

Which ONE of the following states

1) the CURRENT status of the Pzr Heaters

AND 2) after selecting the "LEVEL" position on the Back Up Interlock Bypass Key Switch (B/U INTLK BP Key), which Pzr heaters are available

? A. 1) All Pzr heaters off

2) All B. 1) All Pzr heaters off

2) "A" side Pzr heaters ONLY

C. 1) ONLY "B" side Pzr heaters off

2) "A" side Pzr heaters

D. 1) ONLY "B" side Pzr heaters off

2) All HLC 22 SRO NRC EXAM Page 22 of 100 Question 22 Given the following:

Cor e Reload is in progress on Unit 2 32 Fuel Assemblies have been loaded into the core During insertion of the 33rd assembly, the BRCO reports that count rate has increase d from 1 0 CPS to 24 CPS Which ONE of the following describes the action required in accordance with 0-NOP-67.05 , "Refueling Operation," for the stated conditions

? A. Direct Reactor Engineering to assess the nuclear instrument readings used for the 1/M plot and verify that they do NOT extrapolate to "0" when fuel movement resumes

. B. Direct Reactor Engineering to validate the method being used to calculate the 1/M and renormalize the 1/M prior to inserting the next fuel assembly.

C. Stop inserting the fuel assembly and verify Shutdown Margin while maintaining the fuel assembly at the current position.

D. Stop inserting t he fuel assembly and withdraw it into the Refueling Machine Hoist/Mast then verify Shutdown Margin.

HLC 22 SRO NRC EXAM Page 23 of 100 Question 23 Unit 1 is performing a Liquid Release of the 1A Waste Monitor Tank when the following alarm is receiv ed:

LIQUID RELEASE FLOW CONTROL VALVE, FCV-6627X , indicates open and will not close from the RTGB.

IAW 1-AOP-06.02, "Uncontrolled Release Of Radioactive Liquids

," which ONE of the following is a required SUBSEQUENT Operator action?

A. At the 1A Waste Monitor Storage Tank, stop the 1A Waste Monitor pump from the local control box AND at the CCW platform

, lock closed V21462, "Waste Monitor Pumps Discharge to Discharge Canal Isolation valve.

" B. At the 1A Waste Monitor Storage Tank, close FCV

-6627X AND at the CCW platform , lock closed V21462, "Waste Monitor Pumps Discharge to Discharge Canal Isolation valve.

" C. From the Liquid Waste Control panel ONLY, stop the 1A Waste Monitor pump AND close V21462, "Waste Monitor Pumps Discharge to Discharge Canal Isolation valve." D. From the Liquid Waste Control panel, close FCV

-6627X AND at the Waste Monitor Storage Tanks, stop the 1A Waste Monitor pump from the local control box.

LIQUID WASTE RAD HIGH N-37 HLC 22 SRO NRC EXAM Page 24 of 100 Question 24 Given the following on Unit 1:

Several fire detectors have alarmed in the Cable Spreading Room Which ONE of the following describes the expected actuation?

A. Halon will charge the header, but only discharge into the room when the header fuseable link melts.

B. Halon will charge the header and then automatically discharge into the room.

C. Pre-action dry pipe header will be charged with water, and then automatically discharge into the room.

D. Pre-action dry pipe header will be charged with water, but only discharge into the room when the header fuseable link melts.

HLC 22 SRO NRC EXAM Page 25 of 100 Question 25 Given the following conditions on Unit 1:

The reactor is operating at 100% power A full "B" train INADVERTENT CIAS occurred 1-AOP-69.01 "Inadvertent ESFAS Actuation" was entered Section 4.2.2 "Recovery from Inadvertent CIAS" is being performed for "B" train CIAS components "B" train valve V6555 "Waste Gas Containment Isolation valve" (downstream) is indicating OPEN on the RTGB "A" train valve V6554 "Waste Gas Containment Isolation valve" (upstream) is indicating OPEN on the RTGB The affected Containment Penetration is #31 Which ONE of the following MEETS the required action, if any, per 3.6.3.1, "Containment Isolation Valves?" (consider each selection independently

) A. NONE since V6554 is OPERABLE

. B. V6554 must be CLOSED ONLY.

C. V6555 must be CLOSED AND DE

-ENERGIZED.

D. V6555 must be CLOSED ONLY.

.

HLC 22 SRO NRC EXAM Page 26 of 100 Question 26 Given the following conditions on Unit 1: The reactor is at 100% power Increased Reactor Coolant System (RCS) activity has caused entry into 1-AO P-01.06, "Excessive RCS Activity" The specific activity of the RCS has stabilized at 0.15 uCi/gram Dose Equivalent (DEQ) Iodine 131 DEQ XE-133 is at normal levels IAW 1-AOP-01.06, which ONE of the following is a required action based on the current level of DEQ I

-131 and the reason for the action?

A. Isolate letdown to prevent high gamma radiation areas in the RCA.

B. Position V6307, "Flash Tank Divert Valve," to the Flash Tank to strip fission product gasses. C. Commence a plant shutdown due to RCS chemistry limits being exceeded

. D. Place all available CVCS Ion Exchangers in service to provide additional mechanical filtration to reduce RCS activity.

HLC 22 SRO NRC EXAM Page 27 of 100 Question 27 Given the following

Unit 2 is operating at 100% power The 2A Charging (Chg) pump is running The 2B Chg pump switch is in AUTO The Chg pump selector switch is in the 2A

-2B positio n A Small Break Loss of Coolant Accident then occurs with the following:

The Reactor is manually tripped SIAS has actuated Pressurizer level is 25% and slowly rising All Charging pumps are now running Complete the following statements:

(consider each statement independently)

The 2 C CHG pump ___(1)____ following the SIAS signal.

Later in the event, i f Pressurize r Level rises above Chg pump cut off set point, the 2B CHG pump (back-up) will __(2)___.

A. 1) was manually started

2) remain running

B. 1) was manually started

2) auto stop C. 1) automatically started

2) remain running D. 1) remains running 2) auto stop

HLC 22 SRO NRC EXAM Page 28 of 100 Question 28 The following conditions exist on Unit 1:

The Reactor Coolant System (RCS) is solid, preparing for Reactor Coolant Pump sweeps IAW 1

-NOP-01.05, "Filling and Venting the RCS" Shutdown Cooling has been secured RCS temperature is 1 3 0°F RCS pressure is 310 psia Secondary side of the Steam Generator (SG) is 1 6 5°F Based upon the given conditions, which ONE of the following results could occur if an RCP is started?

A. Excessive core uplift.

B. No adverse results should be expected.

C. An RCS pressure transient outside the LTOP system capacity.

D. Allowable brittle fracture stress limits for the SG could be exceeded.

HLC 22 SRO NRC EXAM Page 29 of 100 Question 29 Given the following:

The Unit 1 Reactor Coolant System (RCS) is operating on solid pressure control One train of Shutdown Cooling (SDC) is in service BOTH LCV-2210P & Q, "Letdown Level Control Valves

," are open with their controller in MANUAL BOTH PCV-2201P & Q, "Letdown Pressure Control Valves

," are throttled with their controller in AUTO set at 100 psig Which ONE of the following choices completes the statement below:

If HCV-3657, "SDC Temp Control Valve ," is throttled OPEN , what is the effect on RCS temperature AND how would the Letdown Pressure Control valves respond to maintain

letdown pressure on setpoint

?

RCS temperature will:

A. rise causing PCV

-2201P&Q to throttle open.

B. lower causing PCV

-2201P&Q to throttle closed.

C. rise causing PCV-2201P&Q to throttle closed.

D. lower causing PCV-2201P&Q to throttle open.

HLC 22 SRO NRC EXAM Page 30 of 100 Question 30 Given the following:

Unit 2 is in Mode 5 on Shutdown Cooling (SDC)

The "B" SDC train is in service The "A" SDC train is in standby The following annunciator is received:

Which ONE of the following describes the response of the "2B" Low Pressure Safety Injection pump?

A. Continues in operation

. B. Its control breaker opens, but can be manually closed.

C. Its control breaker opens, but recloses following a time delay.

D. Stops due to loss of AC power and its breaker cannot be reclosed

. 4.16KV SWGR 2B2 CURRENT TRIP A-13 HLC 22 SRO NRC EXAM Page 31 of 100 Question 31 Given the following conditions:

Unit 1 is in MODE 4 1A Shutdown Cooling (SDC) loop is in service for Reactor Coolant System (RCS) cooldown 1B1 and 1B2 Reactor Coolant Pumps (RCP) are running SDC flow rate returning to the core is 3400 gpm as indicated on FI

-3306 RCS temperature is 295°F and being held constant for shift turnover HCV-3657 "SDC Temp Control Valve," is open and FCV

-3306 "SDC Return Flow Valve," is closed 2 of the 4 LPSI header injection valves are open The air supply line breaks on HCV-3657 Which ONE of the following choices completes the statement below:

As a result of the loss of air, HCV-3657 will __(1)__and SDC flow rate returning to the core will __(2)___.

A. 1) close 2) lower to approximately 0 gpm

B. 1) fail as is

2) remain unchanged

C. 1) close 2) lower then return to 3400 gpm D. 1) open 2) rise to approximately 4600 gpm

HLC 22 SRO NRC EXAM Page 32 of 100 Question 32 Unit 2 is performing a cooldown per 2

-GOP-305, "Reactor Plant Cooldown

- Hot Standby To Cold Shutdown

," for a refueling outage with the following conditions:

Time: 11:30 RCS pressure is 1750 psia RCS temperature is 504

°F 2A & 2B S/Gs are 740 psia Time: 11:3 2 2A Steam Line ruptures outside Containment and just upstream of the MSIV RCS pressure is 1 630 psia and rapidly lowering SG pressures are 580 psia and rapidly lowering Which ONE of the following states:

1) What ESFAS actuation(s) must be MANUALLY actuated

? 2) Which procedure will be implemented to mitigate the event?

A. 1) BOTH MSIS, and SIAS

. 2) 2-EOP-0 5 , "ESDE". B. 1) ONLY SIAS. 2) 2-EOP-05 , "ESDE". C. 1) BOTH MSIS, and SIAS

. 2) 2-ONP-01.01 "Plant Condition 1 Steam Generator Heat Removal LTOP Not in Effect". D. 1) ONLY SIAS. 2) 2-ONP-01.01 "Plant Condition 1 Steam Generator Heat Removal LTOP Not in Effect".

HLC 22 SRO NRC EXAM Page 33 of 100 Question 33 Given the following on Unit 1: The unit has just completed drawing a bubble from a solid plant condition Quench Tank pressure was noted to be 1 psig Pressurizer (Pzr) is being maintained at 2 00 psia by cycling backup Pzr heaters RCS temperature is 205°F If a PORV is venting fluid to the Quench Tank (QT), which ONE of the following would apply to both the expected PORV tailpipe temperature AND the Technical Specification Limiting Condition for Operation leakage limit for this type of leakage? (Assume 100% quality.

References provided

)

A. ~310ºF; 1 gpm B. ~310ºF; 10 gpm C. ~380ºF; 1 gpm D. ~380ºF; 10 gpm

HLC 22 SRO NRC EXAM Page 34 of 100 Question 34 Given the following on Unit 1:

Unit 1 is operating at 100% power LS-14-1A ("A" side CCW Surge Tank Level Switch) on the Component Cooling Water (CCW) surge tank fails low causing the following annunciator

Which ONE of the following describes the impact on CCW operation and Reactor Coolant Pump (RCP) Cooling:

A. No Non-Essential header valves isolate, "A" and "B" CCW header supplies flow to the RCPs.

B. "A" side Non

-Essential header valves auto close; "B" CCW header supplies flow to the RCPs. C. "A" side Non

-Essential header valves should be manually closed; All RCPs should be secured. D. All four Non-Essential header valves auto close; All RCPs should be secured.

CCW SURGE TANK LEVEL HIGH/

COMPARTMENT A LEVEL LOW S-6 HLC 22 SRO NRC EXAM Page 35 of 100 Question 35 On Unit 1, which ONE of the following DIRECTLY feeds the Pressurizer PORV OPEN signal when the PORV selector switch is in:

1) NORMAL RANGE

2) LOW RANGE DIRECTLY from the: A. 1) RPS high pressurizer pressure trip bistables

2) Pressurizer pressure instruments PT

-1103, 1104 B. 1) Pressurizer pressure instruments PT

-1102 A through D

2) Pressurizer pressure instruments PT

-1102 A through D

C. 1) RPS high pressurizer pressure trip bistables

2) Pressurizer pressure instruments PT

-1102 A through D

D. 1) Pressurizer pressure instruments PT

-1102 A through D

2) Pressurizer pressure instruments PT

-1103, 1104

HLC 22 SRO NRC EXAM Page 36 of 100 Question 36 Given the following conditions on Unit 1: The unit is operating at 100% power.

Reactor Protection System (RPS) Channel "A" Tcold RTD (TE

-1112CA) has been inadvertently set to the MAXIMUM value of the Tcold range.

Which ONE of the following describes the effect of this adjustment on the given parameters? Channel "A" : TM/LP Trip Setpoint Delta-T Power Indication

A. Lowers Lowers B. Lowers Raises C. Raises Raises

D. Raises Lowers

HLC 22 SRO NRC EXAM Page 37 of 100 Question 37 Given the following conditions on Unit 2: Unit 2 is at 18% power The Main Generator is on

-line The crew is raising turbine load at 1 MW/min IAW 2

-GOP-201, "Reactor Plant "Startup - Mode 2 to Mode 1"

The Main Transformer 2A Differential Current Alarm has annunciated resulting in:

Turbine tripping on a generator lockout Which ONE of the following describes the expected plant response and subsequent actions? The Reactor should

_________.

A. remain CRITICAL; Verify SBCS quick opens to remove reactor heat and enter 2

-AOP-53.03, "Main Generator" B. remain CRITICAL; Ensure SBCS responds in pressure control mode to remove reactor heat and enter 2

-AOP-53.03, "Main Generator" C. have automatically TRIPPED; Manually trip the reactor and enter EOP

-01, "Standard Post Trip Actions" D. have automatically TRIPPED; Manually trip the reactor then enter EOP

-15, "Functional Recovery," due to the Reactivity Control Safety Function not being met

HLC 22 SRO NRC EXAM Page 38 of 100 Question 38 Given the following conditions on Unit 2: The crew has entered 2

-EOP-03, "LOCA" with the following:

Containment Spray Actuation Signal (CSAS) has automatically actuated 2-HVS-1A and 2-HVS-1C, Containment Fan Coolers, are running 2A Containment Spray (CS) pump running with a flow rate of 2600 gpm 2B CS pump failed to auto start Containment Pressure is 7 psig and rising Containment Temperature is 2 20°F and rising Hydrogen Analyzers have just been placed in service Which ONE of the following describes the status of the Containment Temperature and Pressure Safety Function and required actions (if any) per 2

-EOP-03, "LOCA?"

A. Met; based on current Containment Temperature and Pressure.

B. Not Met; but will be if the HVS

-1B Containment Fan Cooler is started.

C. Not Met; but will be if the 2B CS pump is started with a flow rate of 2700 gpm.

D. Met; based on ONLY 2 Containment Fan Coolers running and the 2A CS pump at its current flow rate.

HLC 22 SRO NRC EXAM Page 39 of 100 Question 39 Given the following events and conditions:

Unit 2 is operating at 100%

The 2C Auxiliary Feedwater (AFW) pump is out of service Time: 02 00: A loss of off

-site power (LOOP) occurred The 2A Emergency Diesel Generator (EDG) automatically loaded on the bus The 2B EDG started but its output breaker DID NOT auto close 2A and 2B Steam Generator (S)G levels are 10% NR lowering Time: 0204:

"A" train of Auxiliary Feedwater (AFW) is feeding the 2A SG Time: 0205: The 2B EDG output breaker was manually closed Which ONE of the following statements correctly describes the "B" Train AFW status at Time 0206, and any subsequent actions (if any)

? The 2B AFW pump:

A. is running and feeding the 2B SG. No further action is required.

B. is running but NOT feeding the 2B S G. Open the 2B AFW flow control valves to establish the desired flow rate.

C. is NOT running. Manually initiate AFAS

-2 using all 4 Manual Initiation switches on RTGB-202. D. is NOT running. Manually start the "B" train of AFW in accordance with the operator hard card.

HLC 22 SRO NRC EXAM Page 40 of 100 Question 40 Given the following condition on Unit 2:

Time: 0200 A Small Break Loss of Coolant Accident has occurred A loss of offsite power (LOOP) occurs 2A and 2B Emergency Diesel Generators start and load as expected Time: 0220 Safety Injection Signal Actuates (SIAS)

Which ONE of the following describes the expected condition of the Containment Fan Coolers following the LOOP, then following the SIAS?

__(1)__ Containment Cooling Fans running in ___(2)___ speed.

0200 0220 A. 1) Three Four 2) Fast Fast B. 1) Three Four

2) Fast Slow C. 1) Four Four

2) Fast Fast D. 1) Four Four

2) Fast Slow

HLC 22 SRO NRC EXAM Page 41 of 100 Question 41 Given the following conditions on Unit 2

A Large Break LOCA has occurred The "B" Containment Spray Actuation signal (CSAS) failed to automatically or manually actuate The 2B Containment Spray pump was manually started by the RCO

Which ONE of the following identifies the status of the "B" Train Iodine Removal System at this time?

2B Hydrazine Pu mp SE-07-3B, "2B Hydrazine Pump Discharge Valve" A. OFF CLOSED B. ON CLOSED C. ON OPEN D. OFF OPEN HLC 22 SRO NRC EXAM Page 42 of 100 Question 42 The REGULARLY scheduled QUARTERLY Code Run Test has just been performed on the 2A Containment Spray (CS) pump IAW 2

-OSP-07.04A, "2A Containment Spray and 2A Hydrazine Pump Code Run."

Which ONE of the following describes the specific parameter, from this particular surveillance, that must be satisfied in order to be in compliance with the Unit 2 CONTAINMENT SPRAY and COOLING SYSTEM Technical Specification LCO, "4.6.2.1?"

A. 2A Hydrazine Pump flow as indicated on RTGB

-206 B. 2A CS Pump developed head by a locally installed pressure gauge C. 2A CS Pump vibration by local vibrometer

D. 2A CS Pump discharge flow as indicated on RTGB 206

HLC 22 SRO NRC EXAM Page 43 of 100 Question 43 Which ONE of the following is the function of the 1 03% Turbine Overspeed Protection Circuit (OPC)?

A. Reheat stop valves and extraction non

-return valves are maintained closed to prevent LP turbine overspeed following a turbine trip

. B. Reheat stop valves and extraction non

-return valves momentarily clo se to prevent LP turbine overspeed following a turbine trip

.

C. Governor valves and intercept valves are maintained closed to prevent turbine overspeed following a complete loss of electrical load

.

D. Governor valves and intercept valves momentarily clos e to prevent turbine overspeed following a complete loss of electrical load

.

HLC 22 SRO NRC EXAM Page 44 of 100 Question 44 Given the following:

Unit 1 reactor is at 6 5% power The 1A Main Feedwater pump trips

Which ONE of the following describes the expected plant response BEFORE the automatic Reactor and Turbine Trip on Low Steam Generator (SG)

Level? (Assume no operator action)

Reactor Coolant System (RCS)

Pressure will:

A. increase because the RCS delta T power increases.

B. increase because the RCS temperature increases due to increased SG temperatures.

C. decrease because the increased boiling rate in the SG tube bundle region decreases Tavg.

D. decrease because the SG level initially increases due to swell, causing a contraction of the RCS inventory.

HLC 22 SRO NRC EXAM Page 45 of 100 Question 45 Given the following conditions on Unit 2:

The unit has just tripped from 100% power due to a loss of the 2A 125VDC bus The 2AB 125VDC bus is aligned to the "B" train 2-EOP-01, "Standard Post Trip Actions" is being implemented No contingency actions have been taken Which ONE of the following completes the statements below with regards to the configuration of the 2B and 2C Auxiliary Feedwater pumps (AFW) immediately following AFAS actuation?

The 2B AFW pump is __(1)__. The 2C AFW pump is running feeding __(2)__.

A. 1) running feeding the 2B Steam Generator 2) ONLY the 2A Steam Generator B. 1) locked out due to a Feedwater Header Rupture ID; 2) ONLY the 2A Steam Generator.

C. 1) running feeding the 2B Steam Generator; 2) BOTH the 2A and 2B Steam Generator.

D. 1) locked out due to a Feedwater Header Rupture ID; 2) BOTH the 2A and 2B Steam Generator.

HLC 22 SRO NRC EXAM Page 46 of 100 Question 46 Given the following on Unit 2:

The reactor is operating at 100% power T he 2 A 3 4.16kVAC bus has been de

-energized due to an inadvertent trip of the 2A3-2A2 bus tie breaker, "4.16 KV BUS TIE 2A3

-2A2" The 2A Emergency Diesel Generator (EDG) has started and its output breaker is closed 2-AOP-47.01A, "Loss of a Safety Related AC Bus

-Train-A," is being implemented The SNPO reports that there is NO apparent damage found on the 2A3-2A2 bus tie breaker

For the stated conditions, which ONE of the following completes the statements below:

IAW 2-AOP-47.01A Attachment 7, "Restoration of Offsite Power with 2A EDG in Operation," the 2A EDG synchroscope should be slowly rotating in the __(1)__

direction.

If NON-EMERGENCY EDG trips were locked in AT THIS TIME, they would actuate when the __(2)__.

A. 1) clockwise (fast)

2) 2A3 to 2A2, 4.16kVAC bus tie breaker is closed B. 1) clockwise (fast)

2) Synch Plug switch is placed into the "TIE 2A3/2B3" position C. 1) counterclockwise (slow)

2) 2A3 to 2A2, 4.16kVAC bus tie breaker is closed D. 1) counterclockwise (slow)

2) Synch Plug switch is placed into the "TIE 2A3/2B3" position

HLC 22 SRO NRC EXAM Page 47 of 100 Question 47 Given the following conditions on Unit 1:

The unit is at 100%

An automatic reactor trip occurs Which ONE of the following completes the statement below:

The __(1)___ signal DIRECTLY generates the __(2)__ bus automatic transfer from the auxiliary transformers to the Start

-up transformers.

A. 1) TDM-1 and TDM-2 2) Live B. 1) TDM

-1 and TDM-2 2) Dead C. 1) Generator Lockout

2) Live D. 1) Generator Lockout

2) Dead HLC 22 SRO NRC EXAM Page 48 of 100 Question 48 Given the following conditions on Unit 1:

Unit 1 is at 100%

The 1AA Battery Charger is out of service Annunciator B-20, "125V DC Bus/ 1A Batt Chgr/ Batt Rm Fan Trouble" has just alarmed The SNPO has been dispatched to verify the status of the 1A battery charger Which ONE of the following describes a n indication(s), FROM THE CONTROL ROOM, that can be used to determine if the 1A vital DC bus is powered from the Battery ONLY? A. ONLY t he 1A DC Bus voltmeter on RTGB

-101 indicates 130VDC slowly lowering.

B. ONLY t he 1A DC Bus ammeter on RTGB

-101 indicates a discharge rate

.

C. Both an ammeter on RTGB

-101 indicates a discharge rate AND the voltmeter on RTGB-101 indicates 1 30 VDC slowly lowering

.

D. A white light above the 1A DC Bus voltmeter on RTGB

-101 is lit signifying potential is being supplied from a battery charger.

HLC 22 SRO NRC EXAM Page 49 of 100 Question 49 The Unit 2 SNPO has reported the following local alarm on the 2 A Emergency Diesel Generator (EDG) STARTING AIR PRESS LOW 5-1 The SNPO reports a relief valve lifted and has reseated on the two Air Receiver Tank s with the following pressures being reported:

2A1: 45 psig, 2A2: 50 psig, 2A3: 152 psig, 2A4: 155 psig Which ONE of the following describes the effect of this condition on the 2A EDG OPERABILITY AND if a start signal occurs prior to any operator action?

A. INOPERABLE; 2A EDG would start.

B. OPERABLE; 2A EDG would NOT start.

C. OPERABLE; 2A EDG would start.

D. INOPERABLE; 2A EDG would NOT start.

HLC 22 SRO NRC EXAM Page 50 of 100 Question 50 Given the following:

Unit 1 is at 100% power The SNPO reports that the 1A Diesel Fuel Oil Transfer (DFOT) pump has tripped The Diesel Oil Storage Tanks (DOST) are above the Technical Specification minimum levels For the stated conditions, which ONE of the following completes the statements below:

Technical Specification Limiting Condition for Operation 3.8.1.1, "Electrical Power Systems - AC Sources," is __(1)__.

AND If a Loss of Offsite Power were to occur, the expected system response would be __(2)__. (Assume no operator action)

A. 1) MET 2) The 1A EDG would run for ~47 minutes before running out of fuel B. 1) MET 2) The 1A EDG would run with make

-up via gravity feed

C. 1) NOT MET

2) The 1A EDG would run for ~47 minutes before running out of fuel

D. 1) NOT MET

2) The 1A EDG would run with make

-up via gravity feed

HLC 22 SRO NRC EXAM Page 51 of 100 Question 51 Given the following on Unit 1:

Unit 1 is at 100% power Unit 2 is at 100% power The Unit 1 in

-service waste gas decay tank has ruptured with a gas release in progress Which ONE of the following completes the statements below:

A MINIMUM of___(1)_____ Unit 1 Control Room Outside Air Intake Rad Monitor(s) in HIGH alarm, causes ___(2)_____ control room(s) to go into recirc mode

? A. 1) One 2) ONLY the Unit 1 B. 1) Two 2) ONLY the Unit 1

C. 1) One 2) BOTH Unit 1 and Unit 2

D. 1) Two 2) BOTH Unit 1 and Unit 2

HLC 22 SRO NRC EXAM Page 52 of 100 Question 52 Which ONE of the following describes the function of the TCV 2A & 2B, "1A & 1B Turbine Cooling Water Heat Exchanger Outlet Valves," AND MV 2 & 3, "Intake Cooling Water "A" & "B" Train to Turbine Cooling Water Heat Exchanger Valves?"

TCV-13-2A & 2B controls __(1)__flow through the Turbine Cooling Water heat exchanger.

MV-21-2 & 3 close, to isolate TCW, on receipt of a SIAS signal to __(2)__.

A. 1) Intake Cooling Water

2) provide backpressure for Intake Cooling Water pumps to prevent run

-out flow during accident conditions

B. 1) Turbine Cooling Water

2) provide backpressure for Intake Cooling Water pumps to prevent run

-out flow during accident conditions C. 1) Turbine Cooling Water

2) ensure sufficient cooling flow is available to the Component Cooling Water Heat Exchangers D. 1) Intake Cooling Water

2) ensure sufficient cooling flow is available to the Component Cooling Water Heat Exchangers

HLC 22 SRO NRC EXAM Page 53 of 100 Question 53 Given the following:

Unit 1 is at 100%

power The following Control Room annunciators and indications are received:

• Instrument Air Pressure indication on RTGB-102, Pl-18-9 , indicates 97 psig, lowering slowly The NPO reports that the 1 C and 1 D Instrument Air Compressors are running. For the stated conditions, which ONE of the following completes the statements below:

IAW 1-AOP-18.01 , "Instrument Air Malfunction:"

If Instrument Air header pressure continued to lower, the unit to unit cross

-tie from Unit 2 would open at __(1)__.

If Instrument Air header pressure continued to degrade, the crew should evaluate the need to perform a controlled shutdown when Instrument Air header pressure reaches a MINIMUM of __(2)__

. A. 1) 95 psig

2) 75 psig B. 1) 85 psig

2) 75 psig C. 1) 95 psig

2) 60 psig D. 1) 85 psig

2) 60 psig INSTR AIR COMPR AUTO START F-21 INSTR AIR PRESS HIGH/LOW F-5 HLC 22 SRO NRC EXAM Page 54 of 100 Question 54 Given the following conditions on Unit 1: A loss of offsite power (LOOP) has occurred on Unit 1 The crew is performing actions of 1

-EOP-09, "Loss of Off Site Power / Loss of Forced Circulation" The SM directs the crew to perform a controlled cooldown to 350°F in accordance with 1

-AOP-01.13, "Natural Circulation Cooldown" Which ONE of the following local (field) operator action (s) must be completed to DIRECTLY support the cooldown from the CONTROL ROOM

? A. Reset Non-Essential Load Breakers IAW 1-EOP-99, Appendix P, "Restoration of Components Actuated by ESFAS."

B. Crosstie Unit 1 Condensate Storage T ank with Unit 2 Condensate Storage Tank IAW 1-AOP-09.02, "Auxiliary Feedwater."

C. Perform 1-EOP-99, Appendix X, "Secondary Plant Post Trip Actions

," Section 2.

D. Perform 1-EOP-99, Appendix H, "Operation of the 1A and 1B Instrument Air Compressors."

HLC 22 SRO NRC EXAM Page 55 of 100 Question 55 Which ONE of the following completes the statements below:

IAW 2-NOP-68.01, "Containment Building Access Hatches

-Operation," interlocks that are installed to prevent both airlock doors from being open at the same time must be functional __(1)__. A control room annunciator alarms to alert the control room operators if __(2)__ door(s) is(are) open.

A. 1) in Modes 1 thru 4 AND Mode 6

2) EITHER the "inner" OR "outer"

B. 1) in Modes 1 thru 4 AND Mode 6

2) BOTH the "inner" AND "outer" C. 1) ONLY in Modes 1 thru 4

2) EITHER the "inner" OR "outer"

D. 1) ONLY in Modes 1 thru 4

2) BOTH the "inner" AND "outer"

HLC 22 SRO NRC EXAM Page 56 of 100 Question 56 Given the following on Unit 1:

A plant start

-up is in progress with power stable at 15%

The Main Generator is on line CEAs are at 110 inches on group 7 One CEA in group 7 is 3 inches below the remainder of CEAs The CEDS control is placed in Manual Individual mode to realign the CEA When the RCO initially withdraws the CEA, the CEA moves outward but it continues to WITHDRAW when the control switch is released due to a control switch failure As a result

, which ONE of the following will occur?

(Assume NO Operator action)

As power rises:

A. BOTH T av g and Tref will increase at the same rate and the CEA withdrawal shoul d stop when a group deviation occurs.

B. BOTH T av g and Tref will increase at the same rate and the CEA withdrawal should stop when an Automatic CEA Withdrawal Prohibit occurs.

C. ONLY T av g will increase and the CEA withdrawal should stop when a group deviation occurs. D. ONLY T av g will increase and the CEA withdrawal should stop when an Automatic CEA Withdrawal Prohibit occurs.

HLC 22 SRO NRC EXAM Page 57 of 100 Question 57 Which ONE of the following completes the statements below:

If the external leads of a Core Exit Thermocouple short together, a __(1)___ temperature than actual would be indicated.

In accordance with Ops Policy

-503, "Technical Specification Guidance," a TOTAL of

__(2)___ Core Exit Thermocouples per core quadrant are required to be OPERABLE for Mode 1

- 3 operation.

A. 1) high er 2) 2 B. 1) lower 2) 2 C. 1) lower 2) 4 D. 1) higher

2) 4 HLC 22 SRO NRC EXAM Page 58 of 100 Question 58 Given the following conditions on Unit 2:

The plant is currently in Mode 3 Radiation Protection has requested that a containment purge be performed to reduce particulate activity in Containment Which ONE of the following describes the required method of purging the Containment atmosphere under these conditions?

Operation of:

A. HVE-1&2, airborne radioactivity removal system IAW 2

-NOP-25.05, "Containment Ventilation Systems."

B. HVE-7A/B through the Continuous Purge (mini-purge) mode filter train IAW 2-NOP-25.0 2 , "Continuous Containment / Hydrogen Purge System Operation."

C. HVE-6A/B through the Shield Building Ventilation filter train IAW 2-NOP-25.01, "Shield Building Ventilation System Operation."

D. HVE-8A/B through the normal Containment Purge (main-purge) System filter train IAW 2

-NOP-06.20, "Controlled Gaseous Batch Release to Atmosphere

."

HLC 22 SRO NRC EXAM Page 59 of 100 Question 59 Given the following on Unit 1:

A small break LOCA has occurred 1-EOP-03, "LOCA," was entered and the direction to place both Hydrogen Analyzers in service was given

Which ONE of the following completes the statements below:

IAW with 1-EOP-99, Appendix L, "Placing a Hydrogen Analyzer in Service,"

aligning the sampling point for the Hydrogen Analyzer requires positioning valves at (in) the

__(1)__. AFTER 1-EOP-99, Appendix L, "Placing a Hydrogen Analyzer in Service,"

had been performed, a Loss of Offsite (LOOP) occurred resulting in BOTH Emergency Diesel Generators starting and energizing the 1A3 and 1B3 4.16 kv busses.

Without any operat or action, Hydrogen Analyzer panel operation IN THE CONTROL ROOM __(2)__ be affected

. A. 1) Hydrogen Analyzer Cubicle on the 43 foot elevation in the Fan Room

2) WOULD B. 1) Control Room 2) WOULD C. 1) Hydrogen Analyzer Cubicle on the 43 foot elevation in the Fan Room

2) WOULD NOT

D. 1) Control Room 2) WOULD NOT

HLC 22 SRO NRC EXAM Page 60 of 100 Question 60 IAW 1-NOP-67.04, "Refueling Machine Operation," which ONE of the following would be expected while operating the Refueling Machine (RFM) during a core onload? A. A Bridge and Trolley lockout interlock is present any time the RFM Hoist is being lowered or raised, while on index at a core location, to prevent RFM movement.

B. If fuel movement had to be suspended, the RFM operator should ensure that the fuel transfer carriage is placed in its stored position on the Spent Fuel Pool side.

C. When lowering the RFM Hoist over the core with a fuel assembly grappled on, hoist motion is automatically stopped when the Lower Grapple operate zone is reached.

D. Operation with the "Programmable Logic Controller (PLC)" switch in the "OVRD" position is permitted to override an OVERLOAD condition on a fuel assembly that is being raised out of the core.

HLC 22 SRO NRC EXAM Page 61 of 100 Question 61 Given the following conditions on Unit 1:

The Unit is in Mode 3 Control Element Assembly testing is planned 1-GOP-302, "Reactor Plant Startup

- Mode 3 to Mode 2" Which ONE of the following Reactor Protection System RPS trip s is NOT bypassed during this testing? A. Low Steam Generator Level B. Thermal Margin /

Low Pressure C. Low Steam Generator Pressure D. Low Reactor Coolant System Flow

HLC 22 SRO NRC EXAM Page 62 of 100 Question 62 Given the following Unit 1: Unit 1 is at 12% power with Tavg at 535

°F and Steam Generator pressure at 900 psia The Main Generator has just been synchronized to the grid The Main Generator picked up 40 MWe and then TRIPPED 5 seconds later

Which ONE of the following states the expected plant response? A. Reactor power indicates 12% with Steam Bypass Control System valves opening to control steam generator pressure at 940 psia for 4 minutes then ramp to 900 psia over the next 5 minutes

. B. Reactor power indicates 12% with Steam Bypass Control System valves opening to control steam generator pressure at 900 psia ONLY

.

C. Reactor trips with Steam Bypass Control System closing to control steam generator pressure at 940 psia for 4 minutes then ramp to 900 psia over the next 5 minutes

.

D. Reactor trips with both Atmospheric Dump Valves opening to control steam generator pressure at 900 psia.

HLC 22 SRO NRC EXAM Page 63 of 100 Question 63 Given the following conditions on Unit 2: Annunciator N

-34 "Gas Analyzer Trouble" is in alarm The gas analyzer local panel oxygen monitor and Chemistry samples on the in

-service gas decay tank indicate 2.2%

IAW 2-AOP-06.03, "Waste Gas System," which ONE of the following actions should be taken?

Suspend all additions of waste gases and _______.

A. ensure the Gas Surge header inlet to the Gas SURGE Tank "auto" closes and the nitrogen purge supply to the Gas SURGE Tank "auto" opens B. manually align nitrogen to the Gas SURGE Tank C. ensure the Gas Surge header inlet to the G as DECAY Tank "auto" closes and the nitrogen purge supply to the G as DECAY Tank "auto" opens D. manually align nitrogen to the in

-service Gas DECAY Tank HLC 22 SRO NRC EXAM Page 64 of 100 Question 64 Given the following conditions on Unit 2:

TIME 1200: The unit had to be manually tripped due to a severe DEH leak on Governor Valve #1 1202: A 350 gpm tube rupture developed in the 2A Steam Generator (SG) 1205: SIAS & CIAS actuations occurred on low Reactor Coolant System (RCS) pressure 1210: 2-EOP-01, "SPTA's" are in progress and the crew has just begun to evaluate the Containment Conditions safety function Which ONE of the following rad monitor "alarms" and "trend" indications would be AVAILABLE AT THIS TIME to determine the status of the Containment Conditions safety function (Secondary Activity)

? (ASSUME NO OPERATOR ACTIONS HAVE BEEN TAKEN and no other complications exist post trip)

A. Main Steam Line Rad Monitor AND SG Blowdown Rad Monitor B. Steam Jet Air Ejector AND SG Blowdown Rad Monitor

C. ONLY Main Steam Line Rad Monitor D. ONLY Steam Jet Air Ejector

HLC 22 SRO NRC EXAM Page 65 of 100 Question 65 Unit 1 is at 100% power, steady state.

The 1B Intake Cooling Water (ICW) pump has just tripped unexpectedly It is desired to START the 1C ICW pump to replace the 1B ICW pump In accordance with 1-AOP-21-03B, "1B INTAKE COOLING WATER SYSTEM HEADER ," which ONE of the following answers the questions below:

1) What is the MINIMUM electrical alignment to start the 1C ICW pump for the given plant conditions

? 2) Prior to starting the 1C ICW pump, if Main Generator Average Cold Gas Temperature were to rise to 47.7°C , what is the required action the crew must take at that point in time

? A. 1) The 1AB 4.16 k V AC bus, "1 AB" 480 V bus AND the "1 AB" DC bus aligned to the "B" side. 2) Reduce MVARS to minimum.

B. 1) The 1AB 4.16 k V AC bus, "1 AB" 480 V bus AND the "1 AB" DC bus aligned to the "B" side. 2) Reduce power as necessary to stabilize main generator cold gas temperature.

C. 1) ONLY the 1AB 4.16 k V AC bus aligned to the "B" 4.16 KV side.

2) Reduce MVARS to minimum.

D. 1) ONLY the 1AB 4.16 k V AC bus aligned to the "B" 4.16 KV sid e 2) Reduce power as necessary to stabilize main generator cold gas temperature.

HLC 22 SRO NRC EXAM Page 66 of 100 Question 66 Given the following on Unit 2:

A Core Reload is in progress Both BF 3 Log Startup Channels are in service with the "B" Channel selected for audible count rate monitoring (control room and containment)

While Reactor Engineering was monitoring the indicated count rates for a 1/M plot, it was determined that the "B" Log Startup Channel had failed low IAW 0-NOP-67.05, "Refueling Operation

," which ONE of following describes the impact on the fuel movement?

A. With the "B" Log Startup Channel inoperable, the core reload MUST STOP until it is returned to service.

B. With the "A" Log Startup Channel operable, the core reload can continue as long as audible is selected for that channel.

C. The core reload can continue by substituting a Wide Range Log Safety Channel and selecting the audible count rate to that channel

.

D. The core reload can continue by substituting an Appendix R Wide Range (Excore) and selecting the audible count rate to channel "A"

.

HLC 22 SRO NRC EXAM Page 67 of 100 Question 67 Unit 1 is operating at 100% when the following annunciator alarmed due to a loss of power to the MA Instrument Inverter:

Which ONE of the following Control Room alarms would NOT be expected to annunciate for this event?

A. Q-19 , "1B S/G PRESS MSIS CHANNEL TRI P"

B. Q-16 , "CNTMT RAD HIGH CIS CHANNEL TRIP

"

C. R-10 , "ENGINEERED SAFEGUARDS ATI FAULT

"

D. R-11 , "CNTMT PRESS HIGH CSAS CHANNEL TRIP

" 120V AC INSTR BUS MA INVERTER TROUBLE B-43 HLC 22 SRO NRC EXAM Page 68 of 100 Question 68 Given the following on Unit 2:

Reactor start

-up is in progress Mode 2 has just been declared Reactor Engineering predicts that the reactor will become critical approximately 6 00 pcm earlier than the ECC calculation.

Which ONE of the following describes the correct course of action IAW 2-GOP-302, "Reactor Plant Startup - Mode 3 to Mode 2?" Stop CEA withdrawal, _________.

A. and immediately initiate emergency boration B. and ensure CEAs are inserted to a position equivalent to (-) 500 pcm from the apparent critical position C. maintain the present rod height, and verify that the 1/M predicted rod positio n is greater than minimum rod height for criticality

D. raise the Reactor Coolant System boron concentration until criticality can be predicted within the proper

+/-pcm band. Recalculate the ECC prior to continuing CEA withdrawal

HLC 22 SRO NRC EXAM Page 69 of 100 Question 69 Given the following: Unit 1 is at 100% power An equipment clearance order (ECO) is being developed for a system with the following parameters: pressure - 1 00 psia and temperature

- 1 30°F Due to an equipment deficiency, only a SINGLE CHECK VALVE is available as an isolation boundary

IAW OP-AA-101-1000, "Clearance and Tagging,"

a t a minimum, which ONE of the following describes the Energy classification and whose approval is required for the clearance to allow use of a SINGLE CHECK VALVE as an isolation boundary?

A. High Energy; Nuclear Joint Safety Committee B. Low Energy; Nuclear Joint Safety Committee C. Low Energy; Shift Manager D. High Energy; Shift Manager

HLC 22 SRO NRC EXAM Page 70 of 100 Question 70 Given the following conditions on Unit 1:

Due to equipment unavailability, the Containment Fan Cooler flow weekly surveillance check must be delayed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

To ensure compliance with the Technical Specification Limiting Condition of Operation (LCO), which ONE of the following describes how the surveillance must be tracked?

A. With an Action Request (AR) ONLY. B. the Equipment Out Of Service program AND an Action Request (AR).

C. 1-OP-0010125A, Data Sheet 29, "Surveillance Tracker" (Data Sheet Pink).

D. 1-OP-0010125A, Data Sheet 30, "Unscheduled Surveillances and Evolution Tracking" (Data Sheet Green).

HLC 22 SRO NRC EXAM Page 71 of 100 Question 71 Given the following conditions on Unit 1:

1-GOP-302, "Reactor Plant Startup

- Mode 3 to Mode 2" is being implemented Reactor power is at 1.0E-2% and slowly increasing An oil leak on the 1A2 Reactor Coolant Pump (RCP) is suspected A containment entry is required to check the RCP Oil Collection Tank level No Management Exemptions have been authorized for this entry

IAW ADM- 09.05, "Containment Entries Mode 1

-4 ," which ONE of the following conditions apply?

A Containment entry:

A. cannot occur because reactor power level is beyond the administrative limit for entry inside the biological shield wall.

B. can occur ONLY IF reactor power is lowered to

<1.0E-3%.

C. can occur ONLY IF ALL Regulating Group CEAs are inserted.

D. can occur IF power level is stabilized at the current value.

HLC 22 SRO NRC EXAM Page 72 of 100 Question 72 Given the following:

The Unit 2 reactor is operating 100%

The Radiation Monitoring Computer System (RMCS) is "magenta" for the "B" Main Steam Line (MSL) radiation monitor There is a suspected tube leak in the "B" Steam Generator (SG)

The Unit Supervisor directs use of the Portable RM

-23P at the "B" MSL line RM-80 Microprocessor When the RM

-23P is placed in service, which ONE of the following describes

1) the Control Room (CR) Alarm Function AND

2) the location where the "B" MSL radiation levels can be read

CR Alarm function "B" MSL radiation reading A. None ONLY Local at RM-23P B. RMCS Local at RM-23P AND RM

-23 at PACB

-2 C. None Local at RM-23P AND RM

-23 at PACB

-2 D RMCS RMCS AND Local at RM-23P HLC 22 SRO NRC EXAM Page 73 of 100 Question 73 Given the following:

Unit 1 tripped from 100% power The "A" Steam Generator (SG) has experienced an Excess Steam Demand event due to a failed open Main Steam Safety Valve (MSSV)

The "B" SG has a sheared U

-tube The crew has entered 1

-EOP-15, "Functional Recovery" Which ONE of the following completes the following statement:

The MOST AFFECTED SG is the __(1)__ SG. It will remain the MOST AFFECTED SG until __(2)__. A. 1) "A" 2) the failed open MSSV on the "A" SG is gagged B. 1) "A" 2) 1-EOP-99 , Appendix R, "Steam Generator Isolation,"

is complete on the "A" SG C. 1) "B" 2) 1-EOP-99 , Appendix R, "Steam Generator Isolation,"

is complete on the "B" SG

D. 1) "B" 2) Reactor Coolant System pressure is reduced within 50 psia of the "B" SG pressure.

HLC 22 SRO NRC EXAM Page 74 of 100 Question 74 Given the following on Unit 1:

Time 001 0: The Unit is at 100% power Pressurizer level is 66%

Pressurizer pressure is 2250 psia 2 Charging pumps are running Letdown flow is 84 gpm The 1A Steam Generator (SG) has a known tube leak of 1 5 gallons per day "A" Main Steam Line radiation monitor is reading 0.5 mr/hr "A" containment particulate radiation monitor is reading 210 cpm Time 0020:

Pressurizer level is at 6 4% Pressurizer pressure is 2235 psia 2 Charging pumps are running Letdown flow is 50 gpm "A" Main Steam Line radiation monitor is reading 0.5 mr/hr "A" containment particulate radiation monitor is reading 400 cpm Which ONE of the following completes the following statements

1) The type of event that is occurring at time 00 2 0 is a __(1)__ 2) For the purposes of Emergency Plan classification, the increased RCS leakage at time 00 2 0 is considered __(2)__ leakage.

A. 1) Steam Generator Tube Leak 2) IDENTIFIED B. 1) Steam Generator Tube Leak 2) UNIDENTIFIED C. 1) Reactor Coolant System Leak 2) IDENTIFIED D. 1) Reactor Coolant System Leak 2) UNIDENTIFIED

HLC 22 SRO NRC EXAM Page 75 of 100 Question 75 Given the following conditions on Unit 1:

1-EOP-03, "LOCA" is being implemented Pressurizer Pressure 900 psia and slowly lowering THOT is 508°F and slowly lowering REP CET 515°F and slowly lowering Pressurizer Level is 55% and slowly rising Both Steam Generators are 25% Narrow Range and rising with total AFW flow of 350 gpm Both Steam Generator pressures are 660 psia slowly lowering ECCS flow is 650 gpm Containment Temperature is 185

°F and slowly lowering Which ONE of the following states the strategy that should be implemented AT THIS TIME? (Consider each selection independently)

(References Provided)

Cooldown and ___________.

A. depressurize to maximize ECCS flow B. ensure 1-EOP-99, Figure 2 is being maintained

C. allow Pressurizer level to rise to 68% then throttle ECCS flow and secure Charging

D. throttle ECCS flow and cycle a Charging pump to allow Pressurizer level to stabilize and be maintained between 30% to 68%

HLC 22 SRO NRC EXAM Page 76 of 100 Question 76 Given the following:

Unit 1 is implementing 1

-EOP-02, "Reactor Trip Recovery

" following an inadvertent "A" train SIAS The 1C Charging pump was out of service prior to occurrence of the event The 1A Charging pump did not start on the SIAS an d could not be manually started BRCO reports that for the last five (5) minutes the Quench Tank level has risen approximately 20%

Reactor Coolant System (RCS) pressure is 1950 psia and slowly lowering Minimum subcooling is not being met

Which ONE of the following states

1) The required action to take AT THIS TIME AND 2) T he required Reactor Coolant System Leakage Technical Specification Action Statement that applies for the current conditions

? (References Provided)

A. 1) Re-diagnose the event and enter 1

-EOP-03, "LOCA."

2) Reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

B. 1) Enter 1

-AOP-01.08, "RCS Leakage Abnormal," and perform the Safety Function Status Checks of 1

-ONP-01.01, "Plant Condition 1 Steam Generator Heat Removal LTOP Not in Effect."

2) Reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

C. 1) Re-diagnose the event and enter 1

-EOP-03, "LOCA."

2) Be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> ONLY. D. 1) Enter 1

-AOP-01.08, "RCS Leakage Abnormal," and perform the Safety Function Status Checks of 1

-ONP-01.01, "Plant Condition 1 Steam Generator Heat Removal LTOP Not in Effect."

2) Be in COLD SHUTDOWN withi n the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> ONLY.

HLC 22 SRO NRC EXAM Page 77 of 100 Question 77 Given the following conditions on Unit 1:

A core RELOAD is in progress and is 95% complete The 1A Low Pressure Safety Injection pump (LPSI) is operating and aligned to provide Shutdown Cooling (SDC) to the Reactor Coolant System (RCS) 1B LPSI pump is out of service for pump maintenance The 1A LPSI pump has just tripped due to a motor fault What is the required Tech Spec Action that applies and what is (are) the bases?

The core on load ___(1)____ all operations that would cause an introduction into the RCS, coolant with a boron concentration less than the Tech Spec refueling boron concentration are suspended AND all containment penetrations are CLOSED within the next four hours.

At least one Shutdown Cooling loop in operation ensures __(2)__.

A. 1) may continue for up to one hour provided that

2) adequate mixing

B. 1) may continue for up to one hour provided that

2) sufficient decay heat removal capability AND minimize s the effect of a boron dilution event C. 1) must be suspended and additionally, 2) adequate mixing

D. 1) must be suspended and additionally, 2) sufficient decay heat removal capability AND minimize s the effect of a boron dilution event

HLC 22 SRO NRC EXAM Page 78 of 100 Question 78 Given that Unit 2 is in Mode 1 with the following conditions:

The crew entered 2

-AOP-14.01,"Component Cooling Water Abnormal Operations" due to a leak in the 2B CCW Heat Exchanger The Unit Supervisor has determined that the 2B Component Cooling Water (CCW) Heat Exchanger is to be isolated The 2C CCW pump is in its normal standby alignment The required MECHANICAL alignment of the 2C CCW pump has been performed Complete the following statements :

In accordance with 2

-AOP-14.01, ELECTRICALLY align the 2C CCW pump to the __(1)__. For the given alignment, CCW loads must be isolated to ensure the CCW Heat Exchanger design bases CCW flow limit will not exceed a MAXIMUM flow of __(2)__.

A. 1) "B" train 2) 18,500 gpm B. 1) "A" train 2) 14,600 gpm

C. 1) "B" train 2) 14,600 gpm

D. 1) "A" train 2) 18,500 gpm

HLC 22 SRO NRC EXAM Page 79 of 100 Question 79 Given the following:

At time 0210, a Station Blackout occurred on Unit 2 At time 0225 , the crew entered 2-EOP-10, "Station Blackout" with the following conditions:

Reactor Coolant System (RCS) pressure is ~1820 psia and constant Both SG water levels are being restored with Auxiliary Feedwater (AFW) at 200 gpm from the 2C AFW pump Loop Tcold temperatures are 540°F and lowering Loop Thot temperatures are 575°F and constant REP CET is 587°F and constant Complete the following statements:

IAW the Unit 2 FSAR Station Blackout Analysis, operator control of the Atmospheric Dump Valves is credited to occur NO LATER THAN _(1)__.

For the given conditions, the Atmospheric Dump Valves must be throttled more in the__(2)__ direction.

A. 1) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 2) OPEN B. 1) 30 minutes

2) OPEN C. 1) 30 minutes

2) CLOSED D. 1) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 2) CLOSED HLC 22 SRO NRC EXAM Page 80 of 100 Question 80 A Loss of Offsite Power occurred with the following:

Time 0220 Unit 1 was at 100% power and both Emergency Diesel Generators (EDGs) started Unit 2 is in a refueling outage, DEFUELED and (1) one EDG Generator started and the other EDG is Out of Service Time 0240 On Unit 1, ONE of the running EDG's tripped on Overspeed On Unit 2, the ONLY running EDG tripped on Differential Current For the given times, which ONE of the following identifies the Emergency Classifications that must be reported to the State Watch Office and NRC?

(References Provided)

A. Time 0220 , Alert - notifications required. Time 0240 , No change in classification

- No additional notification required.

B. Time 0220 , Unusual Event

- notifications required.

Time 0240 , Site Area Emergency

- notifications are required. C. Time 0220 , Unusual Event

- notifications required.

Time 0240 , Alert - notifications required.

D. Time 0220 , Alert - notifications required.

Time 0240 , Site Area Emergency

- notifications are required.

HLC 22 SRO NRC EXAM Page 81 of 100 Question 81 Given the following conditions:

Unit 1 is in Mode 3 Switchyard Voltage is 231kV in support of system distribution work The Contingency Analysis program predicts no change in switchyard voltage Maintenance personnel are troubleshooting the control circuit for 1-HVS-1B, "Containment Cooling Fan" Maintenance requests to stop the 1B Containment Cooling Fan and leave the control switch in AUTO and the breaker left ON while troubleshooting continues All other Containment Cooling Fans are in operation In accordance with Ops Policy 503, "Technical Specification Guidance," which ONE of the following describes the administrative requirement for this configuration?

Declare: A. BOTH the 1B Offsite Power Circuit inoperable AND the 1B Emergency Diesel Generator inoperable.

B. BOTH the 1 A Offsite Power Circuit inoperable AND the 1 A Emergency Diesel Generator inoperable.

C. ONLY the 1A Offsite Power Circuit inoperable.

D. ONLY the 1B Offsite Power Circuit inoperable.

HLC 22 SRO NRC EXAM Page 82 of 100 Question 82 Given the following:

Unit 1 is at 100% power All CEA's were at 136 inches when CEA 56 dropped with the rod bottom light lit on the core mimic display Efforts to re

-align CEA 56 have been in progress for 60 minutes, but CEA 56 has not been re

-aligned to the proper height IAW 1

-AOP-66.01, "Dropped or Misaligned CEA Abnormal Operations" Which ONE of the following states:

1) The CEA 56 position indication on the Distributed Control System (DCS) prior to CEA recovery.

2) The procedure requirements of 1

-AOP-66.01, "Dropped or Misaligned CEA Abnormal Operations" AT THIS TIME?

A. 1) DCS would indicate 0 inches. 2) Continue efforts to re

-align CEA 56 and concurrently reduce power to 70% IAW 1-AOP-22.01, "Rapid Downpower."

B. 1) DCS would indicate 0 inches. 2) Suspend efforts to re

-align CEA 56 and reduce power to 70% IAW 1-AOP-22.01, "Rapid Downpower."

C. 1) DCS would indicate 136 inches. 2) Continue efforts to re

-align CEA 56 and concurrently reduce power to 70% IAW 1-AOP-22.01, "Rapid Downpower."

D. 1) DCS would indicate 136 inches.

2) Suspend efforts to re

-align CEA 56 and reduce power to 70% IA W 1-AOP-22.01, "Rapid Downpower."

HLC 22 SRO NRC EXAM Page 83 of 100 Question 83 Given the following:

The Unit 2 operating crew has evacuated the Control Room due to the presence of toxic fumes 2-ONP-100.02 "Control Room Inaccessibility" is being implemented All Operator actions in the Control Room were performed prior to evacuation RCO A is maintaining Hot Standby conditions at the Remote Shutdown Panel Complete the following statements

IAW 2-ONP-100.02 "Control Room Inaccessibility

," Figure 1 , Subcooled margin is determined using the values of Reactor Coolant System ____(1)____

and PRESSURIZER PRESSURE

. If the PRESSURIZER PRESSURE instrument used to calculate subcooling margin failed low, the Remote Shutdown Tech Spec Action that is applicable is:

"Restore the inoperable channel to operable status within __(2)__ days

." (Reference Provided)

A. 1) Thot

2) 7 B. 1) Thot

2) 30 C. 1) Tcold + 50°F 2) 7 D. 1) Tcold + 50°F 2) 30 HLC 22 SRO NRC EXAM Page 84 of 100 Question 84 The following annunciator has just been received on Unit 1:

Per Technical Specification Table 4.4

-4, w h ich ONE of the following describes the required surveillance AND the bases for that action?

The Specific Activity of the Reactor Coolant System shall be determined to be within LCO limits for the stated time interval by performing an isotopic analysis for:

A. Iodine once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to establish a trend to determine that Dose Equivalent Iodine-131 is less than the LCO limit over the duration of the power change.

B. One sample for Iodine between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> due to the expected Iodine peak during the period. C. Xenon once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to determine that Dose Equivalent Xenon

-133 is less than the LCO limit over the duration of the power change.

D. One sample for Xenon between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> due to the expected Xenon peak during the period.

THERMAL POWER CHANGE EXCEEDS 15% PER HOUR L-6 HLC 22 SRO NRC EXAM Page 85 of 1 00 Question 85 Unit 2 is performing a Natural Circulation cooldown per 2-AOP-01.13, "Natural Circulation Cooldown."

At time 0220 the following conditions were noted:

Pressurizer pressure is 1620 psia SIAS has been blocked Reactor Coolant System (RCS) temperature is 490°F and lowering Boric Acid Makeup Tanks and Refueling Water T ank are NOT available for makeup to the RCS Pressurizer level is 26%

and slowly lowering, based on the Pzr Level Accuracy vs. Temperature curve and Pzr Level Cold Cal instrumentation (LI

-1103) Based on the conditions above, Unit 2 must be in HOT SHUTDOWN within the following __(1)___ in accordance with Technical Specifications 3.4.3, "Pressurizer."

In accordance with 2

-AOP-01.13, "Natural Circulation Cooldown," the Unit Supervisor should direct RCS make up alignment FROM the Safety Injection tanks DIRECTLY to the __(2)___. A. 1) 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 2) suction of the Charging Pumps B. 1) 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 2) Volume Control Tank C. 1) 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 2) suction of the Charging Pumps D. 1) 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 2) Volume Control Tank

HLC 22 SRO NRC EXAM Page 86 of 100 Question 86 Given the following:

Unit 1 is in Mode 3 The Reactor Coolant System is at normal operating temperature and pressure A FAILED SOLENOID on the air supply line to 1

-HCV-14-1, "CCW to the Reactor Coolant Pump (RCPs)," has caused a loss of instrument air to 1-HCV-14-1 The Unit Supervisor directs the opening of 1

-HCV-14-1 by installing a nitrogen jumper bypassing the failed solenoid i n accordance with 1-NOP-01.02, "RCP Operation," section 5.2, "Local Restoration of CCW to RCPs

"

Which ONE of the following completes the statements below:

1) What is the impact of the loss of instrument air on RCP operation

? All RCPs _(1)_. 2) Following the above system alteration, 1

-HCV-14-1__(2)__ per Technical Specification 3.6.3.1, "Containment Isolation Valves" A. 1) must be secured due to a total loss of CCW to the RCPs

2) is considered OPERABLE B. 1) may continue to run, but CCW flow to the RCPs will be reduced

2) is considered OPERABLE C. 1) may continue to run, but CCW flow to the RCPs will be reduced

2) must be considered INOPERABLE

D. 1) must be secured due to a total loss of CCW to the RCPs

2) must be considered INOPERABLE

HLC 22 SRO NRC EXAM Page 87 of 100 Question 87 Unit 2 was operating at 100% power. Given the following events and conditions on 8/20 at 1200: Proportional heater bank P1 breaker failed Surveillance 2

-OSP-100.02 "Schedule of Periodic Tests, Checks and Calibrations Week 2

" step 4.4.2.1 (Thursday) was conducted in order to verify adequate Pressurizer Heater Capacity The Distributed Control System (DCS) direct reading point for Backup Heater B1 kW indicates 149 kW Which ONE of the following statements correctly describes the required maintenance actions to allow continued operation at 100%?

Schedule maintenance to repair and have the:

A. backup heater group B1 made operable NO later than 8/20 at 1 800.

B. backup heater group B1 made operable NO later than 8/23 at 1200.

C. proportional heater group made operable NO later than 8/2 0 at 1800.

D. proportional heater group made operable NO later than 8/23 at 1200.

HLC 22 SRO NRC EXAM Page 88 of 100 Question 88 Unit 2 is at 100% power.

LIS-07-2A, "Refueling Water Tank (RWT) level instrument," failed low and has been placed in BYPASS within one hour

1) If OPERABILITY was NOT RESTORE D within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the required action IAW Tech Spec 3.3.2 "ESFAS Instrumentation" would be to __(1)__.

AND 2) ONE of the Bases for the above action is that if __(2)__?

A. 1) place it in the tripped condition; power operation can continue

2) an additional non-associated 120V Vital AC Instrument bus was lost , concurrent with a LOCA, RAS could fail to respond B. 1) place it in the tripped condition; power operation can continue

2) a second RWT level channel failed, RAS actuation could occur prematurel y and align ECCS pumps to an inadequate suction source during accident conditions C. 1) perform a plant shutdown

2) an additional non

-associated 120V Vital AC Instrument bus was lost , concurrent with a LOCA, RAS could fail to respond D. 1) perform a plant shutdown

2) a second RWT level channel failed, RAS actuation could occur prematurely and align ECCS pumps to an inadequate suction source during accident conditions

HLC 22 SRO NRC EXAM Page 89 of 100 Question 89 Given the following on Unit 2:

The unit is at 100% power The 2A & 2B Component Cooling Water (CCW) Hx outlet temperatures rose from 88°F to 98°F over the last hour due to high DP conditions in CCW HX strainers and high ocean injection temperatures The following annunciators have alarmed:

. The standby Containment Fan Cooler had been started IAW 2

-NOP-25.04, "Containment Fan Cooler Operations," but has just tripped 2-AOP-25.01, "Loss of RCB Cooling Fans," has been entered Containment temperature is 121°F and slowly rising

Which ONE of the following identifies:

1) The action that should be directed per 2

-AOP-25.01 "Loss of RCB Cooling Fans" after the reactor is tripped

? Commence a cooldown to:

2) The Bases for the action?

To limit containment air temperature so that:

A. 1) COLD SHUTDOWN ONLY.

2) Containment Vessel Temperature does not exceed its design temperature of 264°F during steam line break and LOCA conditions.

B. 1) COLD SHUTDOWN ONLY.

2) maintain the Reactor Vessel Support Structure within its design basis.

C. 1) AT LEAST HOT SHUTDOWN.

2) Containment Vessel Temperature does not exceed its design temperature of 264°F during steam line break conditions and LOCA conditions.

D. 1) AT LEAST HOT SHUTDOWN.

2) maintain the Reactor Vessel Support Structure within its design basis.

CNTMT FAN CLR HVS-1A/1B TEMP HIGH T

-9 CNTMT FAN CLR HVS-1C/1D TEMP HIGH T

-15 HLC 22 SRO NRC EXAM Page 90 of 100 Question 90 Unit 1 is at 100% power. The crew has entered 1

-AOP-08.02, "Steam Generator Tube Leak" and has been logging the following secondary radiation monitor readings every 15 minutes.

Time: 0105 0120 0135 Blowdown: A S/G 980 cpm A S/G 1090 cpm A S/G 1 620 cpm B S/G 120 cpm B S/G 125 cpm B S/G 125 cpm Air Ejector: 420 cpm 720 cpm 920 cpm Based on the above readings, which ONE of the following states THE EARLIEST TIME for the following actions to be directed IAW 1-AOP-08.02, "Steam Generator Tube Leak"

1) Performing a Rapid Downpower

AND 2) Entering Mode 3 (Reference Provided)

A. 1) 0135 2) 0735 B. 1) 0120 2) 07 35 C. 1) 0120 2) 0 4 20 D. 1) 0135 2) 0420 HLC 22 SRO NRC EXAM Page 91 of 100 Question 91 Given the following on Unit 2:

The unit is at 3% power Main Feedwater and the Steam Bypass Control System are in service Power is being raised to 12% to place the main generator on line IAW 2

-GOP-201, "Reactor Plant Start Up

- Mode 2 to Mode 1" The following annunciators have alarmed:

The Board RCO reports "A" Channel Axial Shape Index is off

-scale HIGH POSITIVE The ONE hour Technical Specification required actions have been completed

Complete the following statements

The __(1)__ on the affected linear range nuclear instrument.

The Unit __(2)__.

A. 1) Lower detector has failed high

2) Up Power can continue to 12%

B. 1) Upper detector has failed high

2) Up Power can continue to 12%

C. 1) Lower detector has failed high

2) must be stabilized until the instrument is repaired

D. 1) Upper detector has failed high

2) must be stabilized until the instrument is repaired REACTOR POWER HIGH CHANNEL TRIP L-9 LOCAL POWER DENSITY CHANNEL TRIP L-22 TM/LP CHANNEL TRIP L-36 HLC 22 SRO NRC EXAM Page 92 of 100 Question 92 Given the following conditions on Unit 1: The unit is in Mode 3 and stable The Containment Atmosphere PARTICULATE radioactivity monitor has been declared inoperable 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> ago.

1) If a loss of instrument air occurred, due to a ruptured airline in Containment, the Containment Atmosphere GASEOUS Radioactivity monitor __(1)__ be AFFECTED? 2) Based on that determination, an inventory balance __(2)__ a containment atmosphere grab sample , must be performed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to satisfy the RCS Leakage Detection system LCO 3.4.6.1, "RCS Leakage Detection Systems" per Ops Policy 503, "Technical Specification Guidance?

" (Reference Provided)

A. 1) WOULD NOT 2) AND B. 1) WOULD NOT

2) OR C. 1) WOULD 2) AND D. 1) WOULD 2) OR HLC 22 SRO NRC EXAM Page 93 of 100 Question 93 Given the following information:

Unit 2 is at 100% power A team has entered the Unit 2 Containment for a valve inspection A blown fuse results in a loss of the power to RIS 3, "A Channel Containment (CIS) Radiation Monitor" The crew has entered 2

-AOP-26.02, "Area Radiation Monitors" The crew has bypassed the failed ESFAS channel Which ONE of the following completes the statements below:

The containment evacuation alarm __(1)__ automatically upon the fuse failure.

Per the Unit 2 Technical Specifications, if RIS 3 is not restored to an operable status WITHIN 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the "A" CIS Radiation bistable __(2)__; restore to operability by the next Cold Shutdown.

A. 1) sounded

2) MAY be maintained in bypass B. 1) did not sound

2) MAY be maintained in bypass

C. 1) sounded

2) MUST be placed in tri p

D. 1) did not sound

2) MUST be placed in trip

HLC 22 SRO NRC EXAM Page 94 of 100 Question 94 The design bases event for Limiting Condition of Operation 3.1.1.1, "Shutdown Margin," is: A. Positive reactivity addition resulting from a Rod Ejection event at beginning of core life from 0% power conditions.

B. Positive reactivity addition resulting from a Rod Ejection event at end of core life from 1 00% power conditions.

C. Excessive cooldown resulting from a Main Steam Break at beginning of core life from 100% power conditions.

D. Excessive cooldown resulting from a Main Steam Break at end of core life from 0% power conditions.

HLC 22 SRO NRC EXAM Page 95 of 100 Question 95 In accordance with 2-GOP-365 "Refueling Operations," to perform Core Alterations on Unit 2, minimum Reactor Vessel water level must be: 1) 23 feet above the ___(1)____. 2) The Technical Specification basis for this minimum water level is to ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of

___(2)____ fuel assembly

. Which ONE of the following completes the statements above:

A. 1) reactor vessel flange

2) an irradiated

B. 1) reactor vessel flange

2) ONLY a RECENTLY irradiated

C. 1) fuel 2) ONLY a RECENTLY irradiated D. 1) fuel

2) a n irradiated

HLC 22 SRO NRC EXAM Page 96 of 100 Question 96 Given the following information:

Unit 1 is at 100% power There is a planned cable repair on Containment Fan Cooler 1

-HVS-1A The planned repair duration is 4 days of the allowed 7 day Limiting Condition for Operation Which ONE of the following completes the statement below:

In accordance with WM

-AA-100-1000 , "Work Activity Risk Management," the work control process would classify this repair activity as ________, a Risk Management Plan ________ mandatory. A. High Risk; IS B. High Risk; IS NOT C. Medium Risk; IS D. Medium Risk; IS NOT

HLC 22 SRO NRC EXAM Page 97 of 100 Question 97 Given the following:

Unit 1 is in Mode 4 making preparations to enter Mode 3 following a 40 day refueling outage In accordance with TS 3.7.1.2, "Auxiliary Feedwater System" and Ops Policy 503, "Technical Specification Guidance" complete the following:

Mode 3 is allowed to be entered providing 1

-OSP-09.01C, "1C AFW Pump Code Run" is performed within __(1)__.

Once the 1C AFW Pump surveillance was commenced, the following annunciator comes in and REMAINS lit: 1C AFW Pump Turbine Failure/Trip/

SS Isol G-46 RTGB-202 indication for MV 3, 1C AFW Pump Throttle/Trip indicates DUAL position.

The cause of the above alarm is due to a(n) __(2)__.

Which ONE of the following completes the statements above:

A. 1) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 2) Electrical overspeed trip

B. 1) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 2) Mechanical overspeed trip

C. 1) 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 2) Electrical overspeed trip D. 1) 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 2) Mechanical overspeed trip

HLC 22 SRO NRC EXAM Page 98 of 100 Question 98 Given the following conditions on Unit 1:

TIME 2000, March 16th

A Work Execution Coordinator (WEC) SRO is performing an observation of a task in a contaminated work area The workers performing the task reported that the WEC SRO is acting erratically and believe he may not be fit for duty The WEC SRO falls on the floor and suffers an injury that requires immediate transportation to an offsite medical facility The fall caused the individual's Protective Clothing to tear exposing his skin During transport, contamination surveys of the WEC SRO's exposed skin indicated a value of 2500 DPM (beta

-gamma)

TIME 2300, March 16th The hospital reported to the Shift Manager that the injured individual's BAC was 0.05%

as determined from a confirmatory blood test drawn at 2100 Investigation revealed that the individual's consumption of alcohol did NOT occur at work that night

Given the conditions above, which ONE of the following is (are) the required NRC notification (s), if any?

(Reference Provided)

A. A contaminated injured person being transported offsite ONLY.

B. A Fitness for Duty violation ONLY.

C. A contaminated injured person being transported offsite AND a Fitness for Duty violation. D. No NRC notifications are required.

HLC 22 SRO NRC EXAM Page 99 of 100 Question 99 Unit 1 has entered EOP

-06, "Total Loss of Feedwater

," with the following indications:

1A Steam Generator (SG) level is 21% wide range 1B Steam Generator (SG) level is 13% wide range With the Atmospheric Dump Valves (ADVs) 100% open, Tcold has increased from 535°F to 541°F over the past few minutes Which ONE of the following describes the course of action that the crew should implement AND the reason

? A. Based on SG levels, initiate once

-through cooling by referring to EOP

-15, "Functional Recovery" Success Path HR-3 while remaining in EOP

-06. B. Based on Tcold rise, exit EOP

-06, go to EOP

-15, "Functional Recovery" Step 1 and initiate once

-through cooling when the Success Path HR-3 step is reached. C. Based on Tcold rise, initiate once

-through cooling by referring to EOP

-15, "Functional Recovery" Success Path HR-3 then exiting EOP

-06 and entering EOP

-15 at step1.

D. Based on SG levels, initiate once

-through cooling by referring to EOP

-15, "Functional Recovery" Success Path HR-3 then exiting EOP

-06 and entering EOP

-15 at step1.

HLC 22 SRO NRC EXAM Page 100 of 100 Question 100 A General Emergency has been declared by the Emergency Coordinator for Unit 1 A Steam Generator Tube Rupture has occurred on the 1A Steam Generator (SG) along with other complications Off-Site Dose Calculations are being performed The following meteorological data has been collected:

o 10 meter wind direction is 170° o 57.9 meter wind direction is 168° The Control Room actions for 1

-EOP-99 Appendix R, "Steam Generator Isolation" have been completed with the exception that MV 13, "SG 1A to Auxiliary FeedWater (AFW) Pump 1C" DID NOT CLOSE The NPO has NOT performed ANY local actions of 1

-EOP-99 Appendix R for the 1A SG The 1C AFW Pump is operating to provide AFW flow to the 1B SG Which ONE of the choices below identifies:

1) the affected sectors for the protective action recommendations?

2) whether a release is occurring?

Wind Sectors From Affected Wind Sectors From Affected Wind Sectors From Affected 348-11 HLK 123-146 PQR 236-258 CDE 11-33 JKL 146-168 QRA 258-281 DEF 33-56 KLM 168-191 RAB 281-303 EFG 56-78 LMN 191-213 ABC 303-326 FGH 78-101 MNP 213-236 BCD 3 26-348 GHU 101-123 NPQ There is no "0" sector There is no "I" sector A. 1) QRAB 2) A release IS occurring B. 1) RAB 2) A release IS occurring

C 1) QRAB

2) A release IS NOT occurring D. 1) RAB 2) A release IS NOT occurring