ML092660895

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08-Final Written Exam
ML092660895
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 08/07/2009
From:
NRC Region 4
To:
Entergy Nuclear Operations
References
50-368/09-008
Download: ML092660895 (103)
v • d • e


Text

sas ea e All work done on this exam is my own. I have neither given, nor received assistance with Questionson this exam. IName: I I have reviewed the correct answers to the questions on

[his exam and have been provided the opportunity to ask questions of my instructors following this exam.

IDate:

/7/2QQ9 NIA

Subject:

RO License Class Test No.:

NRC 2009 1 -

ITotal Points:

I 62 63 64 65 66 NIA 67 68 69 NIA Graded By NIA Regrade By (As Required) 92 43 93 44 94 45 95 46 96 47 97 48 98 49 99 50 100

411 work done on this exam is my own. I have neither given, nor received assistance with questions on this exam.

I have reviewed the correct answers to the questions on ihis exam and have been provided the opportunity to ask questions of my instructors fo!lowing this exam.

MIA TXDOC: 51 2009 IL Exam ~ 52 53

Subject:

54 55 56 NRC 2009 1 - 57 58 59 Total Points:

12 13 I00 14 15 Percent Grade:

16 17 MIA 18 19 20 21 cEs NIA 22 Graded By 23 24 25 N/A 26 Regrade By (As Required) 27 28 29 30 31 32 33 34 35 36 37 38 39 40 CLOSED 41 42 REFERENCE 43 44 45 46 47 48 49 50

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 1 QID: 1610 Rev: 3 Given the following:

  • The reactor has tripped and safety injection has actuated
  • The RCS has a stuck open Pressurizer Safety valve
  • The RCS has rapidly depressurized to saturation conditions during the cool down
  • Pressurizer level initially dropped below zero and now has risen to 46% and is rising rapidly Which one of the following characterizes the relationship between indicated pressurizer level and RCS inventory and the reason for these conditions?

A. Level is NOT an accurate indication of inventory. The cold calibrated pressurizer level channels indicate high during high temperature low pressure conditions.

B. Level is an accurate indication of inventory. Voiding would occur first in the pressurizer steam space due to the higher temperature of the pressurizer walls.

C. Level is NOT an accurate indication of inventory. Reactor vessel voiding may result in a rapidly rising pressurizer level.

D. Level is an accurate indication of inventory. RCP flow would sweep any voids from the RCS to the pressurizer steam space and out the safety.

Page 1

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 2 QID: 1611 Rev: 1 With the plant at 100% power, which one of the following radiation monitors would indicate a small inter-system LOCA starting to develop from the RCS?

A. In service Containment Atmospheric Monitors (CAMS)

B. Loop 1 Service Water return from the SDC Heat Exchanger Radiation Monitor C. Loop 2 Service Water return from the Containment Cooling Coils Radiation Monitor D. Loop 2 Component Cooling Water Radiation Monitor Page 2

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 3 QID: 1612 Rev: 1 Given the following conditions:

  • The plant experienced a Loss of Coolant Accident (LOCA) and has tripped
  • All RCPs have been secured
  • A plant cool down is in progress
  • RCS Thot indicates 553°F and rising
  • RCS Tcold indicates 520°F and lowering
  • RCS Average CET Temperatures indicate 565°F
  • RCS Pressure is 1100 psia and lowering
  • RVLMS level 7 and below are WET Based on the above conditions, the method of RCS heat removal would be:

A. Reflux Boiling natural circulation cooling B. Subcooled nucleate boiling heat removal C. Single Phase natural circulation cooling D. Once through cooling with HPSI and ECCS Vents Page 3

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 4 QID: 1613 Rev: 1 The plant is at 100% power with the following data being observed on "A" Reactor Coolant Pump (RCP):

  • Middle Seal Pressure - 2200 psia
  • Upper Seal Pressure - 2160 psia
  • Vapor Seal pressure - 60 psia Based on these conditions, which seal (s) have failed?

A. Lower seal only B. Lower and Middle seals C. Lower, Middle and Upper seals D. Lower and Upper seals Page 4

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 5 QID: 1614 Rev: 2 Given the following:

  • The plant is at 100% power
  • AOP 2203.036, Loss of Charging AOP, has been entered due to gas binding During the time it takes to vent and restore the Charging system to service, why does reactor power, temperature and pressure need to be maintained as stable as possible?

A. To prevent hydrogen from coming out of solution and adding to the gas binding problem B. To allow Letdown to restore Pressurizer level within the 100% power operating limits C. To minimize the contraction of RCS inventory during any potential RCS cooldown D. To prevent the degradation of RCP seals due to a loss of charging seal injection flow Page 5

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 6 QID: 1615 Rev: 1 While at 100% power, CCW is isolated to the RCPs.

The decision to quickly restore CCW to containment is based on a RCP controlled bleedoff temperature indication of less than ______ °F. If above this limit, then CCW should be restored slowly to cooldown the RCP seals at less than ______ °F per hour.

A. 100; 180 B. 100; 100 C. 180; 180 D. 180; 100 Page 6

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 7 QID: 1616 Rev: 1 The plant is shut down with the following pressurizer conditions:

  • Pressurizer liquid temperature: 587°F
  • Pressurizer vapor temperature: 587°F
  • Pressurizer pressure: 1,400 psia
  • The in-service Pressurizer spray valve fails open
  • When the spray valve is subsequently closed, Pressurizer Pressure is 1200 psia At this point the pressurizer bulk liquid temperature will have ________________________.

A. risen due to evaporation of liquid B. risen due to condensation of vapor C. lowered due to evaporation of liquid D. lowered due to condensation of vapor Page 7

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 8 QID: 1617 Rev: 1 Given the following:

  • A plant startup is in progress and currently at 3% power and steady
  • 120 VAC Instrument Bus 2Y3 feeder breaker fails open and 2Y3 is de-energized
  • After troubleshooting, maintenance estimates it will take 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to restore bus 2Y3 How does this loss of power affect the limiting conditions for operations of the Diverse Scram System (DSS)?

A. These conditions will not affect the limiting conditions for operations for DSS because 2Y3 does not supply power to the DSS.

B. These conditions will not affect the limiting conditions for operations for DSS because the system is not required in this mode.

C. The DSS is required to be operable in this mode so plant power should be reduced to Mode 3 within the next 60 minutes.

D. The DSS is required to be operable in this mode so plant power should be reduced to Mode 2 within the next 60 minutes.

Page 8

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 9 QID: 1618 Rev: 1 Which one of the following states the basis for lowering RCS T-hot less than 535°F prior to isolating the Steam Generator (SG) with a tube rupture?

A. Prevents lifting Steam Generator safety valves on the isolated SG B. Corresponds to a secondary side pressure of 1078 psig, the SG safety valves lift setpoint C. Minimizes primary inventory loss by stabilizing at a high SG pressure D. Minimizes any dilution of the RCS when primary pressure is decreased to below the isolated SG pressure Page 9

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 10 QID: 1619 Rev: 1 Given the following plant conditions:

  • Plant was operating at 100% power
  • AFW Pump 2P75 is OOS for pump bearing replacement
  • Both Main Feedwater Pumps tripped on low suction pressure
  • EFW Pump 2P7B fails to start
  • CRS has completed SPTAs and diagnosed entry into EOP 2202.006, Loss of Feedwater
  • All other components operate as designed Given these conditions, the crew should:

A. Secure all running RCPs to minimize the amount of heat input into the RCS B. Maintain two (2) RCPs running with one in each loop to balance SG heat removal C. Cooldown and depressurize the RCS to maximize margin to saturation D. Maximize steam generator blowdown to increase the heat removal rate from the RCS Page 10

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 11 QID: 1620 Rev: 1 Given the following:

  • The plant has been shutdown due to Loss Of Offsite Power (LOOP)
  • Station Blackout conditions exist and all attempts to restore AC power to the safety buses have failed
  • The Vital DC batteries are discharging at their normal rated capacity If NO loads are removed from the batteries, the maximum expected duration of available DC power would be ______ hours before the batteries would be fully discharged.

A. 2 B. 4 C. 6 D. 8 Page 11

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 12 QID: 1621 Rev: 1 Given the following plant conditions:

  • Reactor is in Mode 3 due to a Loss Of Offsite Power (LOOP)
  • RCS pressure is 2000 psia
  • Tcold is 550°F and constant
  • Thot is 588°F and slowly lowering
  • Average CET temperature is 597°F
  • Steam Generator "A" & "B" levels are 26% NR and slowly rising Currently the amount of subcooling margin is ______ °F and natural circulation conditions ________

satisfied at this time.

A. 39; are NOT B. 39; are C. 48; are NOT D. 48; are Page 12

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 13 QID: 1622 Rev: 1 Given the following plant conditions:

  • Plant is in Mode 2 performing a reactor startup
  • CEA Regulating Group "P" is currently 65 inches withdrawn
  • Reactor power is currently 1.0 E-8% power
  • 120 Vital AC Electrical Bus 2RS1 is inadvertently de-energized Which ONE of the following sets of instruments should be used to monitor the status of the reactor?

A. Startup Channel Number 1 and Excore Log Safety Channel A B. Startup Channel Number 2 and Excore Log Safety Channel A C. Startup Channel Number 1 and Excore Log Safety Channel B D. Startup Channel Number 2 and Excore Log Safety Channel B Page 13

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 14 QID: 1623 Rev: 1 Given the following:

  • The plant is at full power
  • Annunciator 2K01 A-10 "CONT CENTER 2D01 UNDERVOLT" alarms
  • The CRS has entered AOP 2203.037, Loss of 125 VDC, due to a loss of 2D01
  • The Reactor has not tripped
  • The CRS has given direction to place ALL PPS points on the appropriate PPS channel(s) in bypass Which ONE of the following would be the appropriate PPS channel(s) to bypass?

A. PPS Channel 1 AND PPS Channel 2 B. PPS Channel 1 OR PPS Channel 3 C. PPS Channel 3 AND PPS Channel 4 D. PPS Channel 2 OR PPS Channel 4 Page 14

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 15 QID: 1624 Rev: 1 Given the following plant conditions:

  • The plant is 10 minutes post trip from full power operation
  • RCS pressure is 1800 psia and lowering
  • Both SG pressures just went below 750 psia
  • Containment pressure is 14.7 psia and steady
  • All 4 RCPs are running Which ONE of the following actions will restore the heat sink for the RCP Heat Exchangers?

A. Override and Restore CCW to RCPs B. Override and Restore SW to ACW C. Override and Restore SW to CCW D. Override and Restore SW Returns to the Lake Page 15

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 16 QID: 1625 Rev: 1 Given the following:

  • The plant is at full power at 250 EFPD and Arkansas is under a tornado watch
  • RCS Tave is currently 579°F
  • Unit 1 is shutdown for a refueling outage
  • The system dispatcher calls the Control Room to inform them the Pleasant Hill 500 KV transmission line has been removed from service due to tornado damage
  • The Grid has become unstable and 500 KV Voltage has risen to 525 KV
  • The system dispatcher requests the Control Room to reduce generator load to 900 MW immediately
  • The CBOT lowers Generator load to 900 MW using the turbine load pot
  • No other operator action has been taken When conditions stabilize, Reactor Power will be ___________ than before the grid disturbance and RCS Tcold will be __________ than before the grid disturbance.

A. lower; higher B. lower; lower C. higher; lower D. higher, higher Page 16

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 17 QID: 1626 Rev: 1 Given the following:

  • The plant has tripped from 100% power
  • RCS Pressure is 1700 psia and dropping
  • Containment pressure is 19.3 psia and rising What equipment status would the Control Room Operators expect to see when checking Containment Cooling (CC) Fan operations?

A. Chilled Water isolated by CCAS signal, 3 CC fans running, Service Water aligned, and bypass dampers Open B. Chilled Water isolated by CIAS signal, all CC fans running, Service Water aligned, and bypass dampers Open C. Chilled Water aligned for cooling, 3 CC fans running, Service Water isolated, and bypass dampers Closed D. Chilled Water aligned for cooling, all CC fans running, Service Water aligned, bypass dampers Closed Page 17

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 18 QID: 1627 Rev: 1 Consider the following for an ESD event in progress:

  • 'A' SG pressure is 800 psia and slowly rising
  • 'B' SG pressure is 20 psia and stable
  • RCS pressure is 1500 psia and slowly rising
  • Pressurizer level is 35% and slowly rising
  • Containment temperature is 233 °F and lowering
  • Average CET temperature is 480 °F and rising
  • SG 'A' level is 25% Narrow Range and steady
  • SG 'B' level is 30 inches Wide Range and lowering Concerning HPSI termination, which of the following statements is TRUE and what action needs to be taken?

A. HPSI termination criteria satisfied; raise steaming rate from 'A' SG B. HPSI termination criteria satisfied; lower steaming rate from 'A' SG C. HPSI termination criteria NOT satisfied; raise steaming rate from 'A' SG D. HPSI termination criteria NOT satisfied; lower steaming rate from 'A' SG Page 18

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 19 QID: 1628 Rev: 2 The plant was at steady state and now the following plant conditions exist:

  • No operator actions have been taken
  • Power level is 80% and rising
  • Tave is rising
  • Containment pressure and temperature are normal
  • Pressurizer pressure and level are rising
  • All systems are in their normal mode Which of the following can cause these conditions?

A. Continuous rod withdrawal B. Partial loss of feedwater heating C. Steam leak outside containment D. Slow closure of an MSIV Page 19

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 20 QID: 1629 Rev: 1 Given the following at full power:

  • Both CEA MG Sets are in service with TCB 9 closed Which ONE of the following combinations of actuated PPS trip paths relays would cause the CEAs to drop into the core?

A. Trip Path K1 and Trip Path K2 B. Trip Path K2 and Trip Path K3 C. Trip Path K3 and Trip Path K4 D. Trip Path K4 and Trip Path K5 Page 20

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 21 QID: 1630 Rev: 1 Given the following conditions:

  • The plant is in Mode 6 with core alterations in progress
  • A complete Station Blackout occurs due to severe weather
  • Directions are given to secure core alterations Which of the following indications would be an available and most accurate monitor to detect changes in core reactivity if core alterations are not secured properly?

A. All 4 log power meters on 2C03 B. Refueling Bridge portable area radiation monitor C. Containment low range radiation monitors D. Boron Dilution Monitors 1 and 2 on 2C09 Page 21

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 22 QID: 1631 Rev: 1 The following plant conditions exist:

  • Mode 6 with core re-load in progress
  • The Control Room receives a report that as a spent fuel assembly was being inserted into the core, the refueling machine started moving on its own
  • A lot of bubbles are rising around the fuel assemblies in the core
  • Containment Low Range Rad Monitors on the 404 elevation are indicating a large rise in radiation To warn the individuals in Containment of this accident, the Evacuation Warning Handswitch, 2HS-EVAC on panel ________ should be taken to ______________?

A. 2C22; CNTMT AUX B. 2C14; CNTMT AUX C. 2C22; CNTMT D. 2C14; CNTMT Page 22

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 23 QID: 1632 Rev: 2 The plant was at full power when the following occurred:

  • Circulating Water Pump 2P3A tripped and its associated discharge valve went closed
  • Outside ambient air temperature is 96°F
  • Current plant power is 93% and Condenser Pressure is 7.2 inches of HgA Which ONE of the following actions are REQUIRED to be taken? (Reference Provided)

A. Trip the Reactor and perform Standard Post Trip Actions B. Trip the Main Turbine and perform actions for Loss of Turbine Load C. Verify all ADVs in AUTO and open the Upstream ADV isolation valves D. Verify both Condenser Vacuum pumps running and vacuum lowering Page 23

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 24 QID: 1633 Rev: 1 Given the following:

  • The plant is at full power
  • A gaseous radwaste release from Gas Decay Tank 2T-18A is in progress
  • An inadvertent electrical signal causes both Radwaste Exhaust Fans (2VEF8A/B) to stop Which of the following actions should occur to prevent an accidental gaseous radwaste release without dilution air flow?

A. Release flow will be diverted back to the in service Gas Decay Tank 2T-18B or 2T-18C B. Waste Gas Decay Tanks Discharge Isolation 2CV-2428 will automatically close C. The WCO will be sent to locally close Release Path Isolation Needle Valve 2GZ-15 D. The Control Room will remotely close Waste Gas Decay Tanks Discharge Isolation 2CV-2428 Page 24

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 25 QID: 1634 Rev: 1 Given the following:

  • The plant was tripped from full power due to lowering RCS pressure
  • Pressurizer level is 9% and lowering slowly
  • RCS pressure is 1575 psia and lowering slowly
  • Containment pressure is 24.7 psia and rising
  • Containment Low Range radiation monitors are rising Which of the following is the MAIN reason the High Pressure Safety Injection (HPSI) pumps are actuated during these conditions?

A. To provide adequate core Shutdown Margin (SDM) during RCS depressurization B. To provide adequate RCS subcooling margin during RCS depressurization C. To restore RCS pressure control by refilling the pressurizer during depressurization D. To restore RCS inventory control when RCS pressure goes below HPSI shut off head Page 25

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 26 QID: 1635 Rev: 1 Given the following conditions:

  • Reactor tripped, SIAS, CCAS, CIAS, CSAS and MSIS have actuated
  • RCS Pressure is 1475 psia and dropping
  • 'A' SG pressure is 900 psia and dropping slowly
  • 'B' SG pressure is 200 psia and dropping rapidly
  • All non-vital electrical busses are deenergized
  • All other systems are operating as designed Which of the following correctly describes how RCS temperature will be maintained post SG blowdown?

A. Depressurize the RCS and allow HPSI injection flow to cool the RCS B. Open the SDBCS Upstream ADV and throttle the Upstream ADV isolation on 'A' SG C. Open the SG blowdown valves on 'A' SG and maintain SG level with 'A' EFW pump D. Bypass 'A' MSIV and open a SDBCS bypass valve to the condenser Page 26

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 27 QID: 1636 Rev: 1 Given the following conditions:

  • Plant tripped due to a Loss Of Offsite Power (LOOP)
  • A 300 gpm LOCA develops
  • Pressurizer pressure 1600 psia and stable
  • RCS Tcold is 525°F and stable
  • Steam Generator 'B" level is 65 inches wide range level At this time, "Once Through Cooling" with HPSI injection flow ________ required because

______________________inches wide range level.

A. is NOT; only one SG is below 70 B. is ; one SG is below 70 C. is NOT; both SGs are above 60 D. is; both SGs are below 80 Page 27

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 28 QID: 1637 Rev: 1 Given the following:

  • The plant was tripped from full power due a Main Turbine trip
  • Just after the trip RCS Tcold is 546°F
  • Just after the trip RCS Thot is 548°F
  • 15 minutes after the trip, a loss of offsite power occurs
  • All systems operate as designed Based on these conditions, RCS Tave will __________ and the reason we use Core Exit Thermocouples (CETs) for calculation of Margin to Saturation (MTS) is _______________.

A. lower; CETs are always used since they are the most accurate indications of core temperature B. lower; lower flow past the RCS Thot and Tcold RTDs could cause an error in MTS calculation C. rise; CETs are always used since they are the most accurate indications of core temperature D. rise; lower flow past the RCS Thot and Tcold RTDs could cause an error in MTS calculation Page 28

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 29 QID: 1638 Rev: 1 The plant status is as follows:

  • Reactor power is 72% and stable
  • Tave = Tref at 570°F
  • Pressurizer Level indicates 49%
  • Pressurizer Level Controller is in Remote Auto
  • Letdown Flow Controller is in Automatic
  • All three Charging Pump hand switches are in Automatic
  • Charging Pump Selector switch is in the "B & C" position The correct alignment regarding the status of Charging and Letdown for this condition would be:

(References Provided)

A. Three (3) Charging Pumps will be running with maximum letdown flow B. Two (2) Charging Pumps will be running with maximum letdown flow C. Three (3) Charging Pumps will be running with minimum letdown flow D. Two (2) Charging Pumps will be running with minimum letdown flow Page 29

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 30 QID: 1639 Rev: 1 Given the following:

  • The plant has been shutdown for a refueling outage
  • PZR level is 41%
  • The last 2 RCPs have been secured If Instrument Air is lost to the SDC Temperature Control Valve 2CV-5093 and SDC Flow Control Valve 2CV-5091, which of the following would be the correct response of the SDC system?

A. SDC flow would lower and RCS heat removal would rise B. SDC Flow would lower and RCS heat removal would lower C. SDC flow would rise and RCS heat removal would rise D. SDC flow would rise and RCS heat removal would lower Page 30

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 31 QID: 1640 Rev: 1 Given the following conditions:

  • An unisolable Design Basis LOCA has occurred
  • RCS pressure is 150 psia and lowering
  • One hour has elapsed since the LOCA EOP has been entered
  • RWT level is 5.8% on all indicators
  • All components are actuated and operate as designed At this time the ________ pumps are injecting into the RCS ________ legs.

A. HPSI; cold B. HPSI; hot C. LPSI; cold D. LPSI; hot Page 31

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 32 QID: 1641 Rev: 1 During a quench tank feed and bleed, the makeup water source to the quench tank will come from the ___________ and the Quench Tank will be drained to the _________________.

A. Reactor Makeup Water Tank; Reactor Drain Tank B. Boric Acid Makeup Tank ; Containment Sump C. Boric Acid Makeup Tank ; Reactor Drain Tank D. Reactor Makeup Water Tank; Containment Sump Page 32

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 33 QID: 1642 Rev: 1 Given the following:

  • The plant is at 100% power
  • RCS Tave is 580°F
  • The Instrument Air (IA) supply to the Letdown Temperature Control Valve is inadvertently isolated and the valve fails open With no operator action, RCS Tave and Reactor power would ___________ due to excessive

__________ flow through the Letdown Heat Exchanger.

A. rise; Letdown B. lower; CCW C. rise; CCW D. lower; Letdown Page 33

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 34 QID: 1643 Rev: 1 Given the following:

  • Unit 2 has a small break LOCA in progress
  • Pressurizer Proportional Heaters Bank #1 and #2 are in Automatic
  • Backup Heater Bank #1 Handswitch is in ON When Pressurizer level drops to ________________________ to prevent damage to the heaters.

A. Less than 30%, all PZR HTRs will be de-energized except BU HTR Bank #1 B. Less than 30%, all PZR HTRs will be de-energized C. Less than 29%, all PZR HTRs will be de-energized except BU HTR Bank #1 D. Less than 29%, all PZR HTRs will be de-energized Page 34

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 35 QID: 1644 Rev: 1 When operating a Pressurizer Spray valve in MANUAL, the AMBER light above the control switch being ON indicates the valve is approximately ________ Open and when the RED light above the control switch is the only light ON, the spray valve is _____________.

A. 40%; 100% Closed B. 40%; 100% Open C. 25%; 100% Closed D. 25%; 100% Open Page 35

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 36 QID: 1645 Rev: 1 Which of the following channels of PPS bistables have auctioneered power supplies from multiple 120V Vital AC power panels 2RS1 through 2RS4?

A. Channels A and B B. Channels A and C C. Channels B and C D. Channels B and D Page 36

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 37 QID: 1646 Rev: 1 The following conditions exist:

  • PZR pressure is 1575 psia
  • 'A' SG pressure is 1025 psia
  • 'B' SG pressure is 1000 psia
  • 'A' SG level is 46% Narrow Range
  • 'B' SG level is 35% Narrow Range Which of the following ESF signals should be actuated and what manual operator action should be taken in the SGTR EOP to minimize any release to the atmosphere?

A. SIAS; Override SW to ACW B. SIAS; Override SW to CCW C. EFAS; Override SW to ACW D. EFAS; Override SW to CCW Page 37

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 38 QID: 1647 Rev: 1 An EFAS 2 signal will be present and feeding the 'B' Steam Generator for which of the following indications? (consider each answer separately).

A. SG "A" Level = 20% NR & Press = 700 psia SG "B" Level = 21.5% NR & Press = 700 psia B. SG "A" Level = 20% NR & Press = 575 psia SG "B" Level = 26% NR & Press = 700 psia C. SG "A" Level = 20% NR & Press = 400 psia SG "B" Level = 15% NR & Press = 200 psia D. SG "A" Level = 20% NR & Press = 375 psia SG "B" Level = 18% NR & Press = 500 psia Page 38

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 39 QID: 1648 Rev: 1 Given the following:

  • Unit 2 is at full power
  • Containment Cooling Fans 2VSF-1A, 2VSF-1B AND 2VSF-1D are in service Which one of the following alarms would be the MOST DIRECT confirmation of a loss or malfunction of the containment cooling water supply pump?

A. Annunciator 2K06 H-7 "CNMT CLG COILS A/B SW FLOW LOW" B. Annunciator 2K12 A-7 "CCW LOOP 2 FLOW LO" C. Annunciator 2K13 B-4 "CONTAINMENT COOLING COILS WATER FLOW LOW" D. Annunciator 2K13 C-2 "CHILLED WATER FLOW LOW" Page 39

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 40 QID: 1649 Rev: 1 Given the following:

  • Unit 2 is at full power
  • The "CTMT BLDG CLG FANS C/D TROUBLE" alarms and locks in solid when acknowledged
  • All indicating lights on 2VSF-1D are extinguished
  • The Inside AO reports that the thermal overloads on 2VSF-1D Supply Breaker 2B63 J2 are tripped and will not reset
  • Containment pressure and temperature has risen to 15.7 psia and 118°F Based on these conditions, which of the following will ensure compliance with the Containment Internal Pressure and Temperature Technical Specification action 3.6.1.4 to prevent a shutdown?

(Reference Provided)

A. Containment Cooling Fan 2VSF-1C automatically starts and Containment temperature and pressure must be restored to within TS limits within 30 minutes.

B. Manually start Containment Cooling Fan 2VSF-1C and Containment temperature and pressure must be restored within TS limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

C. Manually start Containment Cooling Fan 2VSF-1C and Containment temperature and pressure must be restored within TS limits within 30 minutes.

D. Containment Cooling Fan 2VSF-1C automatically starts and Containment temperature and pressure must be restored to within TS limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Page 40

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 41 QID: 1650 Rev: 1 Given the following:

  • The reactor has tripped due to a Design Basis LOCA
  • Containment Pressure peaked at 49 psia and is trending down
  • Four Containment Cooling Units are in operation in the emergency mode
  • All other ECCS components are operating as designed After the Recirculation Actuation Signal (RAS), the conditions are as follows:
  • Containment Pressure is 34 psia and lowering
  • Four Containment Cooling Units are in operation in the emergency mode
  • All other ECCS components are operating as designed Considering the above conditions, all Containment Safety Functions ________ satisfying the design basis requirements because ____________________________________________.

A. are NOT; containment pressure has NOT been reduced to within 10 psia of the CSAS reset value B. are; four containment cooling units are sufficient to remove the energy in the containment C. are NOT; a containment spray pump is required to be running following a RAS for iodine removal D. are, containment pressure has been reduced by greater than 10 psia from the peak pressure Page 41

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 42 QID: 1651 Rev: 1 Given the following:

  • The plant is at full power
  • The Main Steam Supply Valve to MFW Pump Turbine 2K-2A, 2CV-0320 goes closed Which one of the following would be the correct response of the MFW pumps and the final plant conditions?

A. The 'A' MFW Pump would go to zero speed and the plant would be in mode 3.

B. The 'A' MFW Pump speed would not change and the plant would be at full power.

C. The 'A' MFW Pump would go to zero speed and the plant would be at ~ 90% power.

D. The 'B' MFW Pump speed would rise to compensate and the plant would be at full power.

Page 42

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 43 QID: 1652 Rev: 1 Which one of the following ESFAS actuations will cause the Main Feedwater Isolation (Block) Valves to automatically close?

A. SIAS B. CCAS C. EFAS D. CSAS Page 43

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 44 QID: 1653 Rev: 1 At full power, if the Main Feedwater Pump suction pressure drops below ______ psig, the standby Condensate pump will automatically start and if Main Feedwater Pump suction pressure drops below

______ psig, the Main feedwater pumps will trip. (assume all time delays have been completed and any associated logic has been satisfied)

A. 425; 325 B. 450; 300 C. 425; 350 D. 450; 375 Page 44

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 45 QID: 1654 Rev: 1 Given the following:

  • The plant has tripped due to a Loss of Off Site Power (LOOP)
  • The plant had been at 100% power for the last 100 days
  • SPTAs are in progress
  • SG A level is 8% NR
  • SG B level is 7% NR
  • All EFW components actuated as designed Which ONE of the following combinations of EFW flow would be the MINIMUM required to meet the RCS Heat Removal Safety Function just after the trip? (assume no EFW recirculation flow)

A. A SG 150 gpm; B SG 150 gpm B. A SG 315 gpm; B SG 155 gpm C. A SG 211 gpm; B SG 275 gpm D. A SG 250 gpm; B SG 260 gpm Page 45

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 46 QID: 1655 Rev: 1 Given the following:

  • Unit 2 is at full power
  • Electrical loads transfer to offsite as designed
  • Red Vital 480V Bus (2B5) is reading 426 VAC (lowest reading)
  • Green Vital 480V Bus (2B6) is reading 441 VAC (lowest reading)
  • No operator action is taken One minute after these conditions are established, what would be the status of the Emergency Diesel Generators?

A. Both Emergency Diesels would be running and neither of the Emergency Diesels would have its output breaker Closed.

B. Both Emergency Diesels would be running but only the Red Emergency Diesel Generator (2DG1) would have its output breaker Closed.

C. Only the Red Emergency Diesel Generator (2DG1) would start and it would be running with its output breaker Open.

D. Only the Red Emergency Diesel Generator (2DG1) would start and it would be running with its output breaker Closed.

Page 46

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 47 QID: 1656 Rev: 1 Which ONE of the following would be a function of 125 VDC Green Electrical Bus 2D02?

A. Provides DC power input to the PMS Inverter 2Y25 B. Provides DC power to EFW Pump 2P-7A governor control C. Provides DC power input to the SPDS Inverter 2Y26 D. Provides DC control power to Vital 4160 VAC Electrical Bus 2A3 Page 47

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 48 QID: 1657 Rev: 1 Given the following:

  • The plant is at full power
  • Green Vital Electrical DC Bus 2D02 voltage is 130V DC
  • Battery Charger 2D32A load is 135 amps
  • The Green Vital Battery 2D12 Disconnect is now opened by maintenance personnel without informing the Control Room Given these conditions, the ____________________ alarm would annunciate in the Control Room and the Battery Charger load would _______________________.

A. 2D02 undervoltage; rise significantly B. 2D02 undervoltage; stay approximately the same C. Battery NOT Available; rise significantly D. Battery NOT Available; stay approximately the same Page 48

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 49 QID: 1658 Rev: 2 Given the following:

  • Unit 2 is at normal full power operation
  • 2DG1 local engine control switch is in "AUTO"
  • 2DG2 local engine control switch is in "AUTO"
  • All other systems and components function as designed
  • Assume NO operator action Given these conditions 2DG1 would be ______________ and 2DG2 would be _________________.

A. shutdown; running at NO load B. running at NO load; shutdown C. running at NO load; running at NO load D. shutdown; shutdown Page 49

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 50 QID: 1659 Rev: 2 Given the following:

  • Unit 2 is at full power
  • 2DG1 is currently tied to the grid and is consuming 2.2 gallons of fuel oil each minute
  • Fuel oil transfer pump 2P-16A is running and filling 2DG1 Day Tank 2T-30A
  • At 500 gallons in 2T-30A, 2P-16A breaker trips open on thermal overload and fuel oil flow stops
  • NO operator action is taken Based on these conditions, approximately how long can 2DG1 continue to operate at the current load until the T.S. Minimum Day Tank Volume is reached?

A. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> C. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> D. 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Page 50

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 51 QID: 1660 Rev: 2 With an inoperable Liquid Radwaste Discharge Radiation Monitor (2RITS-2330), which of the following actions is REQUIRED to be performed in addition to the actions normally performed to release a liquid radwaste tank?

A. Perform an independent verification of proper Unit 1 Circ Water flow B. Perform an independent verification of discharge valve lineup C. Process the contents of the tank through the vendor processing skid twice D. Recirculate the contents of the tank for twice the required time before sampling Page 51

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 52 QID: 1661 Rev: 2 Given the following:

  • The plant is at full power
  • The WCO calls the Control Room and informs them of a large SW leak just upstream of the Loop 2 ESF Supply Header Isolation Valve 2CV-1406-2
  • The CRS enters AOP 2203.022, Loss of Service Water Based on the actions in the AOP, what would be the status of the Service Water System and the correct contingency action to take?

A. Loop 2 SW and ACW isolated; start a plant down power and take the Main Turbine off line B. Loop 2 SW and CCW HX cooling isolated; trip the Reactor/Turbine and secure all 4 RCPs C. Loop 2 SW isolated; place Emergency Diesel 2DG2 Engine Start Handswitch in Pull to Lock D. Loop 2 SW and Cooling Tower make up isolated; commence a rapid plant shutdown to Mode 3 Page 52

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 53 QID: 1662 Rev: 1 Which of the following are the power supplies to Instrument Air Compressors 2C-27A and 2C-27B?

A. Vital 480 Volt Load Centers 2B5 and 2B6.

B. Non-Vital 480 Volt Load Centers 2B7 and 2B8.

C. Vital 480 Volt Motor Control Centers 2B54 and 2B64.

D. Non-Vital 480 Volt Load Centers 2B1 and 2B2.

Page 53

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 54 QID: 1663 Rev: 1 Given the following:

  • The plant is at full power
  • On 2C343-1 Detector 1-4-4-T, the South Containment Cable Spreading Area is in alarm
  • The Shift Manager has determined that an immediate emergency Containment entry is required to assess the potential fire in Containment
  • The Containment entry is made and it is determined that a false alarm has occurred
  • When exiting Containment, the Personnel Hatch air lock door interlocks fail allowing both doors to be opened at the same time In accordance with Technical Specifications, which one of the following actions is required to be taken?

A. Verify at least one Personnel Hatch air lock door is Operable and Closed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

B. Verify the interlock for the Personnel Hatch air lock doors is Operable within 30 minutes.

C. Commence placing the plant in Hot Standby conditions within the next 30 minutes.

D. Start the Containment Purge and verify a negative pressure in Containment within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Page 54

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 55 QID: 1664 Rev: 1 Given the following:

  • Unit 2 has tripped from full power due to a Design Basis LOCA
  • RCS Pressure is 52 psia and slowly lowering
  • Containment pressure is 47 psia and slowly lowering

____________ and this required flow is based on _____________.

A. 2000 gpm; providing adequate flow through the reactor core B. 1875 gpm; providing adequate flow through the reactor core C. 2000 gpm; cooling containment and associated components D. 1875 gpm; cooling containment and associated components Page 55

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 56 QID: 1665 Rev: 1 Given the following conditions:

  • A manual reactor trip is attempted but the reactor does NOT trip after depressing ALL the manual trip pushbuttons including DSS
  • A SPTA contingency action requires the power supply to the CEDM MG Sets to be de-energized Which ONE of the following will accomplish this action from the Control Room?

A. Open 480V Load Center 2B5 and 2B6 feeder breakers (2B-512 and 2B-612).

B. Open 480V Load Center 2B7 and 2B8 feeder breakers (2B-712 and 2B-812).

C. Open 480V MCC 2B31 and 2B41 feeder breakers (2B-321 and 2B-421).

D. Open 480V MCC 2B71 and 2B81 feeder breakers (2B-732 and 2B-823).

Page 56

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 57 QID: 1666 Rev: 0 During an approach to criticality in Manual Sequential (MS) Mode, a CEA Withdrawal Prohibit (CWP) will stop subgroup misalignment if one subgroup within a regulating group is deviated by

_______________________________ and will stop an individual CEA deviation within a subgroup if a CEA is deviated by ________________________________.

A. 4.95 inches as detected by CPCs; 5.0 inches as detected by CEACs B. 5.0 inches as detected by CPCs; 4.95 inches as detected by CEACs C. 4.95 inches as detected by CEACs; 5.0 inches as detected by CPCs D. 5.0 inches as detected by CEACs; 4.95 inches as detected by CPCs Page 57

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 58 QID: 1667 Rev: 2 Consider the following:

  • Unit 2 is at 50% power during a power ascension
  • FWCS is in Automatic
  • The Red and Blue pens on the 'A' SG Narrow Range Level Recorder (2LR-1033/1034) are indicating 66%
  • The Red and Blue pens on the 'B' SG Narrow Range Level Recorder (2LR-1133/1134) are indicating 64%

Based on these conditions, the Level Deviation alarm for the 'A' SG on 2K03 __________ be in alarm and the Level Deviation alarm for the 'B' SG on 2K03 __________ be in alarm.

A. would; would NOT B. would NOT; would C. would; would D. would NOT; would NOT Page 58

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 59 QID: 1668 Rev: 1 If some of the Core Exit Thermocouples (CETs) were to fail, how many CET indications must be left to monitor the core temperature during post accident conditions before a T.S. LCO entry must be made?

A. Greater than 75% of 42 or 32 total CETs available B. At least 6 CETs per core quadrant available C. At least 2 CETs per core quadrant available D. Greater than 19% of 42 or 8 total CETs available Page 59

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 60 QID: 1669 Rev: 1 Given the following:

  • The plant has tripped due to a Loss of Coolant Accident
  • Containment temperature is 178°F
  • Containment Pressure is 23 psia
  • Prior to the accident, Containment temperature was 115°F
  • Prior to the accident, Containment pressure was 14.6 psia
  • Hydrogen Recombiner 2M-55A has been started for hydrogen control Once 2M-55A is warmed up, which of the following would be the power requirement for these conditions? (Reference Provided)

A. 65 MW B. 66 MW C. 65 KW D. 66 KW Page 60

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 61 QID: 1670 Rev: 1 Given the following plant condition:

  • The plant is in Mode 6 with a refueling shuffle in progress from the core to the Spent Fuel Pool To allow continued fuel movement, _______ source range neutron flux monitor(s) must be operating with visual indication in the control room and ______ source range neutron flux monitor(s) must be operating with audible indication in the containment and control room.

A. 1; 1 B. 2; 1 C. 1; 2 D. 2; 2 Page 61

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 62 QID: 1671 Rev: 1 With no operator action, which of the following sets of parameters match plant response to a turbine trip from 50% Reactor Power?

A. Reactor tripped, Tave approximately 545°F B. Reactor tripped, Tave approximately 562°F C. Reactor power approximately 50%, Tave approximately 545°F D. Reactor power approximately 50%, Tave approximately 562°F Page 62

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 63 QID: 1672 Rev: 1 Given the following:

  • Unit 2 is at normal full power operation
  • Unit 1 has 3 Circulating Water (CW) pumps operating
  • Liquid Waste Condensate Tank 2T-21A release has just started at 50 gpm
  • Annunciator 2K11 C-10 "PROC LIQUID RADIATION HI/LO" alarms
  • A check of BMS/LRW Radiation Monitor 2RE-2330 shows a rising radiation trend prior to the annunciator alarming
  • The setpoint of BMS/LRW Radiation monitor 2RE-2330 was exceeded Which one of the following conditions could have caused this rise in activity and what action should be taken?

A. Unit 1 secured a CW pump reducing dilution flow; verify the release terminated until adequate CW flow is established B. The radiation monitor setpoint was set too high prior to the release; reset the radiation monitor to the correct setpoint and restart release C. The 2T-21A tank was not adequately recirculated prior to chemistry sample; verify the release terminated and obtain a new sample after adequate recirculation time D. The 2T-21A discharge pump recirculation valve, 2LRW-32A was inadvertently opened; throttle the recirculation valve closed until activity lowers Page 63

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 64 QID: 1673 Rev: 1 Given the following:

A. open; less B. close; more C. open; more D. close; less Page 64

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 65 QID: 1674 Rev: 1 Given the following:

  • Unit 2 is in a refueling outage
  • A report comes in from the fire brigade leader that a Class 'C" fire is in progress on the 372 elevation in containment What kind of hazards exist to the personnel during this fire and which action can be taken to reduce this hazard?

A. Smoke inhalation from burning trash; evacuate the containment building B. Intense heat from burning oil; align fire water to the containment building C. Potential electrocution; de-energize the applicable power supply to containment D. Flying sparks from burning metal; evacuate the local area on the 372 elevation Page 65

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 66 QID: 1675 Rev: 0 When conducting shift turnover, night and standing orders should be reviewed up to the last time the watch was stood or for the last ______ days whichever is shorter.

A. 5 B. 7 C. 14 D. 30 Page 66

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 67 QID: 1676 Rev: 1 Given the following:

  • The plant is at full power
  • An ECCS pump becomes inoperable Which ONE of the following contains all of the required information that should be included when making entries onto the Plant/Safety System Status Board in the Control Room?

A. Component name/number, component status, date and time, initials of person making entry B. Component name/number, date and time, last name of the CRS, plant power level C. Plant power level, component name/number, last name of the CRS, date of TS entry D. Component status, plant power level, initials of person making entry, component name/number Page 67

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 68 QID: 1677 Rev: 1 Which one of the following evolutions requires an Infrequently Performed Test or Evolution (IPTE) brief prior to conducting and also list the appropriate management oversight for the IPTE?

A. Turbine Generator Valve Stroke Test offline; the onshift Shift Manager B. Beginning of cycle Reactor Startup from outage; the onshift Shift Manager C. Turbine Generator Valve Stroke Test online; Assistant OPS Manager (AOM)

D. Mid cycle Reactor Startup from post trip; Assistant OPS Manager (AOM)

Page 68

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 69 QID: 1678 Rev: 1 Given the following:

  • The plant is at full power
  • The Service Water Outlet Valve from 2DG1, 2CV-1503-1, needs to be repacked due to leakage Prior to performing maintenance on 2CV-1503-1, the valve should be ________________________

and after maintenance on 2CV-1503-1, the valve should be _____________stroked to ensure operability with the new packing.

A. isolated and tagged out; manually B. placed on the backseat; electrically C. placed on the backseat; manually D. isolated and tagged out; electrically Page 69

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 70 QID: 1679 Rev: 1 Given the following:

  • The plant is at full power at 0900 on dayshift
  • Charging Pump 2P-36C is tagged out for cracked plunger block replacement
  • Charging Pump 2P-36A has been declared inoperable for maintenance to perform pulsation damper checks prior to the upcoming quarterly surveillance
  • Total estimated time prior to returning 2P-36A back to operable status is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Which one of the following list the required documentation needed to track the Technical Requirements for Operation (TRO) entry and exit for this maintenance?

A. Inoperable Equipment Checklist, Station Log entry, and a Status Board entry B. Station Log entry, LCO Tracking Record, and a Status Board entry C. LCO Tracking Record , Station Log entry, and an Inoperable Equipment Checklist D. Status Board entry, Station Log entry, and a TRO Tracking Record Page 70

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 71 QID: 1680 Rev: 1 Given the following:

  • Plant has been shutdown for refueling
  • Acid reducing chemistry has created a large RCS crud burst
  • Whole body general area dose rates are 3 Rem/hr in the "B" ESF Room A female WCO who is NOT declared pregnant with complete exposure records is assigned to align the "B" SDC train for decay heat removal. This job is expected to take 30 minutes.

The WCO has a radiation history of 1000 mrem exposure for this year.

Which of the following statements is correct for the additional dose that will be received by performing this system alignment with the above conditions?

A. WCO will NOT exceed routine annual ANO Admin whole body (TEDE) limits for radiation workers B. WCO will NOT exceed routine annual ANO Admin whole body (TEDE) limits for female radiation workers C. WCO will exceed annual Federal whole body (TEDE) limits for female radiation workers D. WCO will exceed routine annual ANO Admin whole body (TEDE) limits for radiation workers Page 71

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 72 QID: 1681 Rev: 2 Given the following:

  • Standard Attachment 19, Control of Secondary Contamination, has been implemented Which of the following actions will be performed by Attachment 19 to prevent an inadvertent radiological release?

A. Isolating the Unit 1 Oily Water Separator discharge B. Isolate make-up water to the Hotwell C. Securing the Circulating Water System D. Securing the Steam Generator Blowdown system Page 72

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 73 QID: 1682 Rev: 2 Given the following:

  • Unit 2 is in Mode 6 with a fuel off-load in progress
  • Containment Purge is in the continuous ventilating mode
  • The SRO in charge of refueling notifies the Control Room that an incident has caused damage to a spent fuel assembly in the Containment building
  • Airborne activity is rising in Containment Which of the following is the FIRST action for the Control Room to take in accordance with Attachment "M", Refueling Accident, of OP-2502.001, Refueling Shuffle?

A. Ensure Containment Closure is set B. Ensure Containment Evacuated C. Verify Containment Purge is secured D. Verify Containment Fan coolers secured Page 73

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 74 QID: 1683 Rev: 2 Which of the following list the safety functions from the highest to lowest hierarchy?

A. Reactivity Control, Maintenance of Vital Auxiliaries, RCS Pressure Control, RCS Inventory Control, Core Heat Removal, RCS Heat Removal, Containment Isolation, Containment Temperature and Pressure Control B Reactivity Control, Maintenance of Vital Auxiliaries, RCS Inventory Control, RCS Pressure Control, Core Heat Removal, RCS Heat Removal, Containment Isolation, Containment Temperature and Pressure Control C. Reactivity Control, Maintenance of Vital Auxiliaries, RCS Inventory Control, RCS Pressure Control, Core Heat Removal, Containment Isolation, RCS Heat Removal Containment Temperature and Pressure Control D. Reactivity Control, Maintenance of Vital Auxiliaries, RCS Inventory Control, RCS Heat Removal, RCS Pressure Control, Core Heat Removal, Containment Isolation, Containment Temperature and Pressure Control Page 74

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 75 QID: 1684 Rev: 1 Given the following:

  • A small fire has started due to burning insulation inside breaker cubicle 2B52-A4
  • Power to the breaker cannot be interrupted With the exception of the Fire Brigade Leader, which one of the following describes the makeup of the Fire Brigade Members for this event and the best type of extinguisher to use on this fire?

A. Unit 1 Operators; CO2 extinguisher B. Unit 1 Operators; H2O extinguisher C. Unit 2 Operators; CO2 extinguisher D. Unit 2 Operators; H2O extinguisher Page 75

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 76 QID: 1685 Rev: 1 Given the following:

  • The plant is at full power
  • There are indications of a rising RCS leak
  • Current RCS leak rate is 50 gpm Which of the following is the correct action to take and the correct implementing procedure?

A. Commence a Plant Shutdown; AOP 2203.016, Excess RCS Leakage B. Commence a Plant Shutdown; AOP 2203.038, Primary to Secondary Leakage C. Trip the Reactor and perform SPTAs; EOP 2202.003, Loss of Coolant Accident D. Trip the Reactor and perform SPTAs; EOP 2202.004, Steam Generator Tube Rupture Page 76

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 77 QID: 1686 Rev: 1 Given the following:

  • 'A' SDC Loop was placed in service 5 minutes ago with a normal system lineup
  • PZR level is 37% and dropping
  • RCS temperature is 280°F and constant
  • PZR pressure is 260 psia and dropping
  • RWT level is rising slowly
  • VCT level is constant
  • Hold Up Tank (2T-12) levels are constant Based on these conditions, the correct procedure to enter would be the ________________and the RCS draining would be stopped by closing _____________________.

A. Lower Mode Functional Recovery EOP; 2P-60A Normal LPSI Recirc Valve (2CV-5123-1)

B. Lower Mode Functional Recovery EOP; Letdown Divert Valve (2CV-4826)

C. Loss of Shutdown Cooling AOP; 2P-60A Normal LPSI Recirc Valve (2CV-5123-1)

D. Loss of Shutdown Cooling AOP; Letdown Divert Valve (2CV-4826)

Page 77

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 78 QID: 1687 Rev: 1 Given the following plant conditions:

  • Ten (10) minutes post trip from full power
  • Pressurizer pressure is 1400 psia and lowering
  • Containment Temperature and Pressure are normal and stable
  • All ESFAS signals and components have actuated as designed
  • The only operator actions taken are those directed by the SPTA procedure Which of the following would be the correct procedure to diagnose after SPTAs, and the correct action to take for the given conditions?

A. EOP 2205.005, Excess Steam Demand; close MSIVs (2CV-1010-1 and 2CV-1060-2)

B. EOP 2205.005, Excess Steam Demand; close Main Steam to EFW Pump 2P-7A (2CV-1000-1 and 2CV-1050-2)

C. AOP 2203.001, RCS Overcooling; close MSIVs (2CV-1010-1 and 2CV-1060-2)

D. AOP 2203.001, RCS Overcooling; close Main Steam to EFW Pump 2P-7A (2CV-1000-1 and 2CV-1050-2)

Page 78

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 79 QID: 1688 Rev: 1 Given the following plant conditions at full power:

  • The plant has experienced a loss of Green DC Bus 2D02
  • Subsequently a complete Loss of Offsite Power (LOOP) trips the plant
  • SPTAs are entered and all required actions are taken
  • EFW pump 2P-7B starts on EFAS signal then trips on motor overload
  • Steam Generator Levels are 20% and slowly lowering Which of the following procedures should be entered after SPTAs and which of the following actions can be taken FROM the CONTROL ROOM to mitigate this event?

A. EOP 2202.006, Loss of Feedwater; tie AACG to 4160 VAC Bus 2A1 and commence feeding SGs with AFW Pump 2P-75 at less than 150 gpm B. EOP 2202.007, Loss of Offsite Power; tie AACG to 4160 VAC Bus 2A4 and commence feeding SGs with EFW Pump 2P-7A at less than 150 gpm C. EOP 2202.006, Loss of Feedwater; tie AACG to 4160 VAC Bus 2A4 and commence feeding SGs with EFW Pump 2P-7A at full EFW flow D. EOP 2202.007, Loss of Offsite Power; tie AACG to 4160 VAC Bus 2A1 and commence feeding SGs with AFW Pump 2P-75 at full AFW flow Page 79

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 80 QID: 1689 Rev: 1 Given the following plant conditions:

  • Unit 2 at 100% power
  • The CBOT reports that Instrument Air (IA) Header Pressure is 53 psig and dropping
  • Unit 1 reports that their IA Header Pressure is 59 psig and also dropping Which of the following is the required procedure to implement mitigating actions for these conditions and the correct course of action?

A. AOP 2203.021, Loss of Instrument Air; close the cross-connect valves with Unit 1 to prevent a loss of IA on Unit 1 B. AOP 2203.021, Loss of Instrument Air; open the cross-connect valves with Unit 1 to prevent a loss of IA on Unit 2 C. EOP 2202.001 SPTAs; close the cross-connect valves with Unit 1 to prevent a loss of IA on Unit 1 D. EOP 2202.001 SPTAs; open the cross-connect valves with Unit 1 to prevent a loss of IA on Unit 2 Page 80

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 81 QID: 1690 Rev: 1 Given the following plant conditions at full power:

  • The plant is tripped due to power > 100% and rising rapidly
  • Pressurizer Pressure is 1625 psia and dropping during SPTAs
  • RCS T-hot is 520°F and dropping during SPTAs
  • Electrical bus 2A1 lockout alarm actuates during SPTAs
  • Containment Pressure is 26 psia and rising during SPTAs
  • Emergency Feedwater Pump 2P-7A, over speeds and cannot be reset during SPTAs
  • All other components operate as designed Following completion of the Standard Post Trip Actions (SPTA's), which of the following procedures should be entered and which of the following concerns should be addressed to prevent core damage?

A. EOP 2202.005, Excess Steam Demand; restoring power to electrical bus 2A3 B. EOP 2202.006, Loss of Feedwater; restoring RCS Margin to Saturation (MTS) to > 30°F C. EOP 2202.010, Functional Recovery; restoring power to electrical bus 2A3 D. EOP 2202.010, Functional Recovery; restoring RCS Margin to Saturation (MTS) to > 30°F Page 81

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 82 QID: 1691 Rev: 1 Given the following at full power:

  • These indications have been rising from 75 GPD to these levels over the past hour Which one of the following is correct concerning Technical Specification (TS) 3.4.6.2 RCS Leakage and also the correct action to take?

A. TS 3.4.6.2 would NOT apply; enter AOP 2203.038, Primary to Secondary Leakage and commence a plant shutdown due to a tube leak B. TS 3.4.6.2 would apply; enter AOP 2203.038, Primary to Secondary Leakage and commence a plant shutdown due to a tube leak C. TS 3.4.6.2 would NOT apply; continue to monitor for a SG tube leak or failure and commence a plant shutdown when leakage exceeds the limits D. TS 3.4.6.2 would apply; trip the Reactor and enter EOP 2202.004, Steam Generator Tube Rupture after SPTAs due to a tube failure Page 82

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 83 QID: 1692 Rev: 1 Given the following conditions:

  • Plant operating at full power
  • Leak has been determined to be from the RCPs
  • At 1200, Loop I CCW Surge Tank Level is 45% and Loop II CCW Surge Tank is 44%
  • At 1202, Loop I CCW Surge Tank Level is 47.5% and Loop II CCW Surge Tank is 46.5%
  • A plant shutdown has been commenced Which of the following is the approximate RCS leak rate and the appropriate Emergency Action Level (EAL) classification? (References Provided)

A. ~ 12 gpm; declare a Notice of Unusual Event (NUE)

B. ~ 23 gpm; declare a Notice of Unusual Event (NUE)

C. ~ 47 gpm; declare an ALERT D. ~93 gpm; declare an ALERT Page 83

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 84 QID: 1693 Rev: 1 Given the following:

  • A confirmed fire has developed in the Cable Spreading Room (elevation 372)
  • The carpet in the Unit 2 Control Room "At The Controls Area" is getting warm Which procedure should be entered AND which action should be taken to ensure an adequate heat sink with a feed source is available for plant cooldown after a Reactor Trip?

A. Enter 2203.049, Fires in Areas Affecting Safe Shutdown; ensure Main Feedwater (MFW) system is in Reactor Trip Override (RTO) prior to leaving the Control Room B. Enter 2203.049, Fires in Areas Affecting Safe Shutdown; trip the MFW pumps and start both Emergency Feedwater (EFW) pumps from the Remote Shutdown Panel 2C-80 C. Enter 2203.014, Alternate Shutdown; ensure Main Feedwater system is in Reactor Trip Override (RTO) prior to leaving the Control Room D. Enter 2203.014, Alternate Shutdown; trip the Main Feedwater pumps and start both EFW pumps by actuating EFAS prior to leaving the Control Room Page 84

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 85 QID: 1694 Rev: 2 Given the following:

  • The plant was tripped due to low RCS pressure 10 minutes ago
  • RCS pressure is 1150 psia and dropping rapidly
  • Containment Pressure is 27 psia and rising
  • Containment and 'A' ESF room radiation levels are rising Which of the following is the correct procedure to enter following SPTAs and the correct action to take for the above conditions to protect Containment integrity after 2P-35A is secured ?

A. EOP 2202.010, Functional Recovery; close 2CV-5612-1 using Handswitch 2HS-5612-1 on 2C17 B. EOP 2202.010, Functional Recovery; close 2CV-5612-1 using CLOSE contactors inside its associated breaker cubicle then open the breaker C. EOP 2202.003, Loss of Coolant Accident; close 2CV-5612-1 using Handswitch 2HS-5612-1 on 2C17 D. EOP 2202.003, Loss of Coolant Accident; close 2CV-5612-1 using CLOSE contactors inside its associated breaker cubicle then open the breaker Page 85

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 86 QID: 1695 Rev: 1 Given the following:

  • The plant is at full power
  • Outside ambient air temperature is 10°F
  • Heat Tracing (HT) Panel 2C322 has lost power
  • This panel supplies the NaOH Tank, the CSTs (2T41A/B) and all RWT level transmitter sensing lines
  • RWT water temperature is 58°F
  • RWT level is reading 98% on all level instruments If ALL the RWT sensing lines were to freeze, which one of the following would be the correct T.S LCO action to implement and the correct action to take?

A. T.S 3.0.3, LCOs for Operation and Surveillance Requirements; take action to restore power to 2C322 and restore RWT level instrumentation to an operable status B. T.S 3.3.2.1, ESFAS Instrumentation; place the inoperable channels for these level transmitters in bypass and/or trip using Technical Specifications C. T.S. 3.5.4, ECCS - Refueling Water Tank; take action to restore power to 2C322 and restore RWT level instrumentation to an operable status D. T.S. 3.6.2.1, Containment Systems - Containment Spray System; place the inoperable channels for these level transmitters in bypass and/or trip using Technical Specifications Page 86

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 87 QID: 1696 Rev: 1 Given the following conditions:

  • The plant is at 100% Power
  • #2 CEAC was placed in INOP in CPCs five hours ago
  • #1 CEAC just now failed
  • #2 CEAC cannot be returned to service Which of the following procedures should be used and the correct response to be taken for these conditions to remain at power? (Reference Provided)

A. AOP 2203.050, Loss of CPC/CEAC Channel; set CEANOP flag CPC PID 062 to 3 in all four PC channels within 80 minutes B. AOP 2203.050, Loss of CPC/CEAC Channel; verify each CEA is within 7 inches of all other CEAs in its group every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> C. OP 2105.001, CPC/CEAC Operations; set CPC PID 062 to 3 in all four CPC channels within 80 minutes D. OP 2105.001, CPC/CEAC Operations; verify each CEA is within 7 inches of all other CEAs in its group every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Page 87

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 88 QID: 1697 Rev: 1 Given the following plant conditions:

  • S/U #2 Transformer is out of service for maintenance
  • The plant has tripped from 100% power
  • S/U #3 Transformer sustains a fault and is locked out
  • RCS pressure is 2100 psia and slowly dropping
  • Steam Generator pressure is 935 psia and slowly dropping in both SGs Which ONE of the following actions should be taken to prevent further pressure reduction and which event should be diagnosed based on current plant conditions?

A. Close the MSR 2nd stage reheat isolations valves in SPTAs; EOP 2202.007 Loss of Offsite Power B. Close the MSIVs in SPTAs; EOP 2202.007 Loss of Offsite Power.

C. Close the MSR 2nd stage reheat isolations valves in SPTAs; EOP 2202.005 Excess Steam Demand D. Close the MSIVs in SPTAs; EOP 2202.005 Excess Steam Demand Page 88

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 89 QID: 1698 Rev: 1 Given the following plant conditions:

  • Plant is operating at 100% power
  • 125 VDC Panel 2D26 supply breaker trips open due to a fault on the bus
  • 10 minutes later, the plant trips due to a breaker fault on one RCP
  • Both SG pressures have stabilized at 1050 psia
  • All systems operate as designed under these conditions Which of the following would be the response of the Emergency Feedwater System and which procedure should be diagnosed after SPTAs?

A. 2P-7A automatically starts and feeds both SG's; EOP 2202.002, Reactor Trip Recovery B. 2P-7B automatically starts and feeds both SG's; EOP 2202.002, Reactor Trip Recovery C. 2P-7A automatically starts and feeds both SG's; AOP 2203.013, Natural Circulation Operations D. 2P-7B automatically starts and feeds both SG's; AOP 2203.013, Natural Circulation Operations Page 89

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 90 QID: 1699 Rev: 1 Given the following:

  • The plant is at 100% power
  • Outside ambient air temperature is 99°F
  • A through wall Instrument Air (IA) leak has developed on the 2 inch IA line just downstream of 2IA-407 located on Turbine Building 368 elevation
  • Emergency Maintenance has patched the leak to within acceptable limits
  • A work order package has been developed to replace the leaking section of pipe
  • The work order requires that 2IA-407 be closed and the downstream line depressurized
  • The maintenance is expected to last approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Analyze this maintenance request and determine if 2IA-407 could be isolated or not with the plant online without any adverse effects and select the correct response below. (References Provided)

A. Can be isolated as long as Steam Generator Blowdown is isolated prior to closing B. Can be isolated as long as makeup water to the CSTs is isolated prior to closing C. Cannot be isolated because it could cause Containment Pressure and Temperature to rise above T.S LCO Limits D. Cannot be isolated because it could cause an Atmospheric Dump Valve (ADV) to fail open causing a plant transient Page 90

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 91 QID: 1700 Rev: 1 Given the following:

  • The plant has been shutdown for refueling
  • The chart recorder for VCT Pressure shows that pressure in the VCT went up to 72 psig and then dropped rapidly to 40 psig and stabilized
  • VCT level is currently 70% and steady
  • VCT Vent Valve 2SV-4837 is Closed and has not been Opened Which of the following caused the drop in pressure in the VCT, how can the diagnosis be confirmed and what action, if any, should be done about these indications?

A. Temporary stuck Open VCT relief valve; rise in the in-service Hold UP Tank (2T-12) pressure; secure all addition of Gas to the VCT in accordance with the ACA and re-brief the evolution B. Temporary stuck Open VCT relief valve; rise in the in-service Gas Surge Tank (2T-17)

Pressure; secure all addition of Gas to the VCT and enter AOP 2203.010, H2O2 Concentration High C. WCO manually venting the VCT in accordance with the RCS DEGAS procedure OP 2104.002, CVCS, Attachment E, RCS Degas; rise in the in-service Gas Decay Tank, no action required D. WCO manually venting the VCT in accordance with the RCS DEGAS procedure OP 2104.002, CVCS, Att. E; rise in plant stack radiation readings; have Chemistry perform dose assessment Page 91

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 92 QID: 1701 Rev: 1 Given the following:

  • The plant is at 100% Power steady state
  • Technical Specification 3.4.6.2, RCS Leakage, requires a RCS Water Inventory Balance surveillance be completed once every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in Modes 1 through 4
  • Chemistry is not available to perform any samples at this time Which ONE of the following radiation monitors being inoperable would REQUIRE the frequency of the RCS Water inventory balance surveillance to be increased to once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to avoid a plant shutdown?

A. Containment High Range Radiation Monitors 2RITS-8925-1 and 2RITS-8925-2 B. Containment elevation 404 South West end of the Refueling Deck 2RITS-8912 C. Containment Atmosphere Monitors (CAMS) 2RITS-8231-1 and 2RITS-8271-2 D. Containment Purge Exhaust, 2VEF-15 Discharge, Radiation Monitor 2RITS-8233 Page 92

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 93 QID: 1702 Rev: 1 Given the following:

  • The plant is in Mode 6 with Core Alterations in progress
  • The Containment Purge system is in operation continuously ventilating
  • The Equipment and Personnel Hatches are Open but capable of being Closed
  • I&C is performing maintenance on the Auxiliary Building 2VEF8A/B Exhaust Radiation Monitor 2RE-8245 when they inadvertently de-energize the Containment Purge Exhaust Radiation Monitor 2RE-8233
  • All attempts to restore power to 2RE-8233 have failed
  • Containment Purge Exhaust SPING 5 is Operable and in service In accordance with OP 2104.033, Containment Atmospheric Control, which one of the following actions should be taken for these conditions?

A. Secure Containment Purge, close the isolation valves and continue with Core Alterations and movement of irradiated fuel in the Containment building and SFP B. Continue with Containment Purge and Core Alterations since the Containment Purge isolations will automatically close on a high activity signal from SPING 5 C. Suspend Core Alterations and movement of irradiated fuel in the Containment building because the Containment Purge rad monitor is inoperable D. Suspend Core Alterations and movement of irradiated fuel in the Containment building and SFP because the Containment Purge rad monitor is inoperable Page 93

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 94 QID: 1703 Rev: 1 Which of the following would prompt entry into the Severe Accident Management Guidelines (SAMG)?

A. SGTR with concurrent steam line break on same Steam Generator B. Partial core uncovery with Core Exit Thermocouples indicating >1200°F C. Large break LOCA with vessel level at centerline of hot legs D. Partial core uncovery with all the EOP critical safety functions satisfied Page 94

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 95 QID: 1704 Rev: 0 To prevent boron stratification in Mode 6, the Technical Specification minimum RCS flow is

__________ gpm and in Mode 5, the Technical Specification minimum RCS flow to reduce boron concentration is __________ gpm.

A. 2000; 2400 B. 2400; 2000 C. 2000; 2000 D. 2400; 2400 Page 95

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 96 QID: 1705 Rev: 1 Given the following:

  • System Engineering has determined that connecting a contaminated and non-contaminated system with a rubber hose would be a Temporary Modification Before the hose is installed between these two systems, who must authorize installation AND what is the minimum number of check valves that must be installed in series to satisfy procedural requirements?

A. System Engineering Manager; 2 check valves B. Shift Manager; 3 check valves C. System Engineering Manager; 3 check valves D. Shift Manager; 2 check valves Page 96

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 97 QID: 1706 Rev: 1 Given the following:

  • An annunciator has been determined to be a Nuisance Alarm and has become a distraction to the Control Room operating staff
  • The Shift Manager has given permission to pull the annunciator card per 1015.001 "Conduct of Operations" Whose concurrence must be obtained to ensure that pulling the annunciator card has no effect on continued system operability and what type of tag is required to be installed on the pulled annunciator card stored inside the annunciator panel?

A. System Engineer; Equipment Out of Service or Caution tag B. Shift Technical Advisor; Equipment Out of Service or Caution tag C. System Engineer; Work Incomplete or Temporary Services and Equipment tag D. Shift Technical Advisor; Work Incomplete or Temporary Services and Equipment tag Page 97

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 98 QID: 1707 Rev: 1 Unless there is a written justification, a gas decay tank should be isolated for ______ days prior to release approval because this _________________________________________________.

A. 30; allows short lived gaseous activity present in the tank to decay B. 30; prevents purging high activity RCS gas to the tank prior to release C. 60; allows short lived gaseous activity present in the tank to decay D. 60; prevents purging high activity RCS gas to the tank prior to release Page 98

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 99 QID: 1708 Rev: 0 Given the following:

  • Mode 6 core off-load in progress
  • Refueling canal and SFP levels are normal Which one of the following fuel handling evolutions would result in extremely high radiation levels?

A. Raising a spent fuel assembly to the up limit in the New Fuel Elevator B. Raising a new fuel assembly to the up limit in the Spent Fuel Handling Machine C. Raising a spent fuel assembly to the up limit in the Main Refueling Machine D. Raising a new fuel assembly to vertical in the Refueling Upender Machine Page 99

ANO UNIT 2 - 2009 INITIAL RO/SRO NRC EXAM QUESTION: 100 QID: 1709 Rev: 0 Given the following:

  • During the use of the Functional Recovery Procedure, an assessment of safety functions has been completed
  • The RCS Inventory Control safety function has been diagnosed as "Challenged"
  • The RCS/Core Heat Removal safety function has been diagnosed as "Jeopardized"
  • All other safety function acceptance criteria are "Satisfied" Which of the following is the order for which success paths should be implemented?

A. RCS Inventory Control; RCS/Core heat removal; Reactivity Control B. RCS/Core heat removal; RCS Inventory Control; Reactivity Control C. Reactivity Control; RCS Inventory Control; RCS/Core heat removal D. Reactivity Control; RCS/Core heat removal; RCS Inventory Control Page 100

ANO Unit 2 2009 NRC Written Exam Reference Handout List, Rev. 1 RO Exam

1. Question # 23: AOP 2203.019, Loss of Condenser Vacuum, Rev. 8, Attachment

'A' Backpressure Limits

2. Question # 29: OP 2102.004, Power Operations, Rev. 41, Attachments C and E
3. Question # 40: Technical Specification 3.6.1.4, Amendment 225, Figure 3.6-1
4. Question # 60: OP 2104.044, Containment Hydrogen Control Operations, Rev.

31, Attachment F

5. Steam Tables
6. Calculator SRO Exam
1. Question # 83: OP 1903.010, EAL Classification, Rev. 4, Attachments 2 and 4 AND OP 2305.002, RCS leak Detection, Rev. 19, Exhibit 1
2. Question # 87: Technical Specification 3.3.1.1, Reactor Protective Instrumentation, Amendment 189
3. Question # 90: AOP 2203.021, Loss of Instrument Air, Rev. 11, Attachment G; Page 3 of 6 of Attachment F; Pages 14, 15, 18, 19, and 20 of Attachment E
4. Steam Tables
5. Calculator
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