ML090690065

From kanterella
Revision as of 09:05, 27 August 2018 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
North Anna Initial Written Retake Examination, 2009-301 Final RO Written Exam
ML090690065
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 02/10/2009
From:
NRC/RGN-II
To:
References
ES-401-7
Download: ML090690065 (85)
v • d • e


Text

ES-401 Name: Site-Specific RO Written Examination Cover Sheet u.s.Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Form ES-401-7 Date: February 10, 2009 Facility/Unit:

North Anna Units 1&2 Region: Start Time: I D II-[8J III D IV D Reactor Type: W[8J CE D BW D GE D Finish Time: Instructions Use the answer sheets provided to document your answers.Staple this cover sheet on top of the answer sheets.To passtheexamination, you must achieve a final grade of at least 80.00 percent.Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.Applicant Certification All work done on this examination is my own.I have neither given nor received aid.Applicant's Signature Results Examination Value Applicant's Score 75 Points Points Applicant's Grade____Percent NAPS 2009 NRC.RO Re-Take Exam 1.Given the following conditions:

  • RCS T AVE is 572°F.*"0" bank rods are at 190 steps.*Rod control is in AUTOMATIC.

Median/Hi T AVE input to automatic rod control fails LOW.Which ONE of the following identifies the Immediate Operator Action required, and the effect of the transient on Shutdown Margin?A.Verify redundant instrument channel indication NORMAL;Shutdown Margin has increased.

B.Verify redundant instrument channel indication NORMAL;Shutdown Margin has not changed.C.Place Rods in MANUAL;Shutdown Margin has increased.

D.Place Rods in MANUAL;Shutdown Margin has not changed.

NAPS 2009 NRC RO Re-Take Exam 2.Given the following conditions:

  • Unit 1 is at 25%power slowly ramping up following a refueling outage*The"B" Condensate Pump and"B" Main Feedwater Pump are both tagged out*Power is lost to the"8" Station Service Bus As a result of this transient, the GATC should initially expect to see level in the"B" SG_and level in the"A" and"c" SGs------(Assume no operator action)A.increase;increase B.increase;decrease C.decrease;increase D.decrease;decrease NAPS 2009 NRC RO Re-Take Exam 3.With Unit 1 at 100%power, annunciator A-E5, RCP 1A VIBRATION ALERT/DANGER, is received.The Backboards Operator reports the following:
  • "A" RCP Seismic vibration=7 mils*"A" RCP Proximity vibration=12 mils Which ONE ofthefollowing identifies the status of"A" Rep vibration, and the actions required by AR-A-E5, RCP 1A VIBRATION ALERT/DANGER?

A.Seismic vibration is above the ALERT level;Increase frequency of monitoring RCP vibration and consider shutting down"A" RCP if increasing trend continues.

B.Seismic vibration is above the DANGER level;Trip the reactor and perform the immediate operator actions of 1-E-O, Reactor Trip or Safety Injection, then stop"A" RCP.C.Proximity vibration is above the ALERT level;Increase frequency of monitoring RCP vibration and consider shutting down"A" RCP if increasing trend continues.

D.Proximity vibration is above the DANGER level;Trip the reactor and perform the immediate operator actions of 1-E-0, Reactor Trip or Safety Injection, then stop"A" RCP.

NAPS 2009 NRC RO Re-Take Exam 4.As the RCS is cooled down from Hot Standby to Cold Shutdown, RCP seal injection flows will________, and running RCP current will_A.decrease;increase B.increase;increase C.increase;remain the same D.decrease;remain the same NAPS 2009 NRC RO Re-Take Exam 5.Given the following conditions:

  • The OATC has established a 65 gpm dilution in accordance with 1-GOP-8.3.1, Placing the Blender in the Dilute Mode of Operation*The operator has adjusted the flow rate to the desired value, and matched the setpoint on the controller Shortly thereafter, the demand on controller 1-CH-FC-1114A, Primary Water to Blender Flow Controller, fails to 100%.Which ONE of the following identifies the response of the Blender?A.Annunciator B-D7, PG WATER TO BLENDER FLOW DEV, alarms as soon as the failure occurs;1-CH-FCV-1114A, PG to Blender Flow Control Valve, automatically closes.B.Annunciator B-D7, PG WATER TO BLENDER FLOW DEV, alarms as soon as the failure occurs;1-CH-FCV-1114B, Blender Makeup to VCT, automatically closes.C.Annunciator B-D7, PG WATER TO BLENDER FLOW DEV, alarms approximately 20 seconds after the failure occurs;1-CH-FCV-1114A, PG to Blender FlowControlValve, automatically closes.D.Annunciator B-D7, PG WATER TO BLENDER FLOW DEV, alarms approximately 20 seconds after the failure occurs;1-CH-FCV-1114B, Blender Makeup to VCT, automatically closes.

NAPS 2009 NRC RO Re-Take Exam 6.Given the following conditions:

  • RHR is in-service with 1-RH-P-1A running and 1-CC-P-18 running*1-RH-P-18 and 1-CC-P-1 A are available with their respective control switches in AFTER-STOP The normal supply breaker to1H 4160-Volt 8us is inadvertently opened.Which ONE of the foJlowing identifies the pump configuration after EDG loading is complete?A.ONLY 1-RH-P-18 running and ONLY 1-CC-P-18 running.B.ONLY 1-RH-P-18 running and 80TH 1-CC-P-1A&1-CC-P-18 running.C.NO RHR pumps running and ONLY 1-CC-P-1 8 running.D.NO RHR pumps running and 80TH 1-CC-P-1A&1-CC-P-18 running.

NAPS 2009 NRC RO Re-Take Exam 7.Given the following conditions:

  • Rod H-2, Control Bank 0 group 1 is mis-aligned LOW*Operators are preparing to realign the rod in accordance with 1-AP-1.3, Control Rod Out of Alignment 1-AP-1.3 will direct the crew to;as a result of this action, the crew should expect a alarm when Rod H-2 is withdrawn.

A.Open the lift coil disconnect switches for Control Bank 0, Gp 1 rods ONLY, EXCEPT for Rod H-2;Rod Control Non-Urgent Failure.B.Open the lift coil disconnect switches for Control Bank 0, Gp 1 rods ONLY, EXCEPT for Rod H-2;Rod Control Urgent Failure.C.Open the lift coil disconnect switches for ALL Control Bank 0 rods, EXCEPT for Rod H-2;Rod Control Failure.D.Open the lift coil disconnect switches for ALL Control Bank 0 rods, EXCEPT for Rod H-2;Rod Control Urgent Failure.

NAPS 2009 NRC RO Re-Take Exam 8.Unit 1 is in Mode 6.Technical Specifications require ONE RHR loop operable and in operation whenever water level is this LCO A.greater than or equal to 23 feet abovethetop of the reactor vessel flange;proper mixing of RCS coolant to minimize the possibility of localized dilution.B.greater than or equal to 23 feet above the top of the reactor vessel flange;acceptable limits are maintained in the event of a fuel handling accident.C.less than 23 feet above the top of the reactor vessel flange;proper mixing of RCS coolant to the possibility of localized dilution.D.less than 23 feet above the top.of thereactorvessel flange;acceptable limits are maintained in the event of a fuel handling accident.

NAPS 2009 NRC RO Re-Take Exam 9.Operators are responding to a LOCA and are performing Step 12 of 1-E-1, Loss of Reactor or Secondary Coolant, which directs them to"Check if Low-Head SI Pumps Should be Stopped." The following plant conditions exist One charging pUf!lP is running and no others are available to be started RCS pressure is 350 psig and stable Containment pressure is 17 psia and slowly decreasing

  • RWST level is 58%and slowly decreasing Based on these plant conditions, which ONE of the following identifies the action required by 1-E-1, and the basis for the action?A.Leave Low-Head SI pumps running since they are providing core cooling.B.Leave Low-Head SI pumps running to prepare for the transfer to Cold Leg Recirc.C.Stop Low-Head SI pumps to minimize the potential for pump and motor overheating.

D.Stop Low-Head SI pumps to minimize the potential for contaminating the RWST.

NAPS 2009 NRC RO Re-Take Exam 10.During 1000/0 power operation, PRT in-leakage is identified as increasing.

Which ONE of the following identifies a possible source?'A.RCP#2 sealleakoff.*

B.RCP seal return relief valve leakage.C.RCS loop stop valve stem leakoff.D.Reactor vessel head vent valve leakage.

NAPS 2009 NRC RO Re-Take Exam 11.Unit 1 is at 100%power when the following events occur: 0830 An instrument malfunction results in a PORV opening.The OATC attempts to close the affected PORV, but it.remains full open.The'OATC attempts to close the associated PORV block valve, but the PORV block valve breaker trips as soon as the switch is taken to CLOSE.The OATC manually trips the Unit and the crew enters 1-E-0, Reactor trip or Safety Injection.

0845 The Shift Manager classifies the event in accordance with EPIP-1.01, Emergency Manager Controlling Procedure.

Based on reporting requirements, the latest time that state and local authorities must be notified is____, and the latest time that the NRC must be notified is_A.0900;0945 B.0900;1000 C.0930;0930 D.0930;1030 NAPS 2009 NRC RO Re-Take Exam 12.One of the purposes of the CC System is to cool the unit from to 140°F within_assuming a Service Water Temperature of 95°F.A.350°F;16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> B.3500F;24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> C.547°F;16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> D.547°F;24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> NAPS 2009 NRC RO Re-Take Exam 13.Unit 1 was operating at 100%power when a LOCA occurred inside containment.

The following plant conditions exist: The crew is currently implementing 1-E-0, Reactor Trip or Safety Injection*Containment pressure" is 21 psia and stable*Containment pressure peaked at 25 psia*Core Exit TCs indicate 510°F*RCS pressure is 1100 psig Total high-head safety injection flow to the core is 500 gpm Based on these plant conditions, the Reactor Coolant Pumps should_A.not be secured B.be secured because RCS pressure is less than 1275 psig C.be secured due to low subcooling D.be secured due to loss of component cooling flow NAPS 2009 NRC RO'Re-Take Exam 14.Operators are stabilizing the plant following a reactor trip due to a loss of offsite power.The following plant conditions exist: RCS temperature is 551°F and stable.*'PRZR pressure is 2100 psig and stable with one group of heaters energized.

  • PRZR liquid temperature is 600°F and stable.*Charging flow is 40 gpm and constant with 1-CH-FCV-1122 in MANUAL.*Seal injection flows are 8,gpm each.Sealleakoff flows are 3 gpm each.PRZR level increased to 35%;the crew has just placed 1-CH-HCV-1200B in service and letdown flow indicates 73 gpm.Which ONE of the following describes the plant response?A.PRZR level will remain stable;PRZR pressure will remain stable'B.PRZR level will decrease;PRZR pressure will remain stable C.PRZR level will remain stable;PRZR pressure will decrease D.PRZR level will decrease;PRZR pressure will decrease NAPS 2009 NRC RO Re-Take Exam 15.The ensures that the allowable heat generation rate (kw/ft)is not exceeded;the setpoint for this trip is_A.Overpower trip;107.9%B.Overpower trip;126.4%C.Power Range Neutron Flux trip.-High SIP;109°A>D.Power Range Neutron Flux trip-High SIP;11 O°A>

NAPS 2009 NRC RO Re-Take Exam 16.Given the following conditions:

  • Unit 1 is at 1000/0 power Containment Pressure Protection Channel II (1-LM-P-1 008)failed on the previous shift All bistables for the failed channel have been placed in TEST in accordance with 1-MOP-55.75, Containment Pressure Protection Instrument Subsequently, Containment Pressure Protection Channel III (1-LM-P-1 OOC)fails HIGH.Which ONE of the following identifies the response of the Engineered Safeguards Features Actuation System?A.No automatic actuations.

B.Safety Injection actuation ONLY.C.Safety Injection actuation and Main Steam Line Isolation ONLY.D.Safety Injection actuation, Main Steam Line Isolation, and CDA.

NAPS 2009 NRC RO Re-Take Exam 17.Given the following conditions:

A spurious turbine runback occurs and is terminated at 80%power*Operators are stabilizing the unit, and annunciator A-H7, A.F.D MONITOR, has just alarmed Which ONE of the following identifies the MINIMUM number of NI channels with an AFD that exceeds the allowable limits of the Reactor Data book to consider the alarm valid, and the Technical Specification required action?A.1 NI channel;reduce power to<50%within 30 minutes.B.1 NI channel;reduce power to<75%within 30 minutes.C.2 NI channels;reduce power to<50%within 30 minutes.D.2 NI channels;reduce power to<75%within 30 minutes.

NAPS 2009 NRC RO Re-Take Exam 18.Which ONE of the following responses is NOT an indication that the#2 seal has failed on a Reactor Coolant Pump?A.Increasing seal injection flow.B.Increased level in the Primary Drains Transfer Tank.C.#1 sealleakoff is lower than normal.D.RCP Standpipe Hi level alarm lit.

NAPS 2009 NRC RO Re-Take Exam 19.Given the following conditions:

  • Unit 1 was initially at 1000/0 power*The crew started ramping the unit 10 minutes ago to perform a Turbine Valve Freedom Test*T AVE is presently.

3 degrees higher'than T REF 1-MS-PT-1446, Channel.111 First Stage Pressure, is selected for control Based on these plant conditions, which ONE ofthefollowing identifies how the steam dumps will respond if 1-MS-PT-1447, Channel IV First Stage Pressure fails LOW?A.Steam dumps arm but remain closed because there is insufficient demand signal.B.Steam dumps arm and ONLY banks 1&2 modulate open until T AVE matches T REF'C.Steam dumps DO NOT arm and are disabled since the T REF input is failed LOW.D.Steam dumps arm and all valves modulate open until T AVE matches T REF' NAPS 2009 NRC RO Re-Take Exam 20.10 CFR 50.46, ECCS Acceptance Criteria, states that the ECCS is designed to ensure peak cladding temperature is maintained less than or equal to during a Large Break LOCA;The CETC temperature that is used to monitor the Core Cooling CSF Status tree is_A.1200°F;the average temperature of ALL CETCs in that ICCM train.B.1200°F;the average temperature of the five highest CETCs in that ICCM train.C.2200°F;the average temperature of ALL CETCs in that ICCM train.D.2200°F;the average temperature of the five highest CETCs in that ICCM train.

NAPS 2009 NRC RO Re-Take Exam 21.1-ECA-O.O, Loss of All AC Power, Attachment 4 (Attempting to Restore Power to1H[1 J]Emergency Bus)directs the crew to place all charging pumps in Pull-To-Lock if RCP temperature exceeds 235°F;this action is taken

_A.Seal Water Outlet;prevent damage to the RCP seal package B.Seal Water Outlet;prevent damage to the thermal barrier heat exchanger C.Pump Radial.Bearing; prevent damage to the RCP seal package D.Pump Radial Bearing;prevent damage to the thermal barrier heat exchanger NAPS 2009 NRC RORe-Take Exam 22.Given the following conditions:

  • The crew has tripped Unit 1 and initiated Safety Injection due to a loss of RCS inventory*Conditions continue to degrade and COA automatically actuates Based on the above conditions, which ONE of the following identifies the automatic response of the Containment Cooling System?A.CARFs tripped when Safety Injection was initiated; Cooling water to CARFs isolated when Safety was initiated.

B.CARFs tripped when CDA actuated;Cooling water to CARFs isolated when Safety Injection was initiated.

C.CARFs tripped when Safety Injection was'initiated; Cooling water to CARFs isolated when COA actuated.D.CARFs tripped when CDA actuated;Cooling water to CARFs isolated when COA actuated.

NAPS 2009 NRC RO Re-Take Exam 23.Given the following conditions:

  • Following a reactor trip, Unit 1 was stabilized with all parameters on program and stable*The crew initiated emergency boration in accordance with 1-ES-0.1, Reactor Trip Response With 1-CH-P-1 B initially in service, a loss of off-site power occurs.Following the loss of offsite power, the OATC notes the following:
  • 1-CH-P-1A breaker closed with 75 amps indicated*1-CH-P-1 B breaker closed with 10 amps indicated*1-CH-P-1Csecured
  • Annunciator C-G6, RCP 1A-B-C LABYTH SEAL LO FLOW, is lit Annunciator C-C5, CHG PP TO REGEN HX HI-LO FLOW, is lit Annunciator C-A7, CHG PP 1C 15H7 LOCKOUT, is lit*PRZR level 20%and slowly decreasing
  • VCT level 44%and slowly increasing Which ONE of the following identifies the cause of these conditions, and the procedure that should be implemented to correct these conditions?

A.Discharge check valve failure on 1-CH-P-1 B;1-AP-49, Loss of Normal Charging.B.Charging line rupture upstream of.1-CH-FCV-1122; 1-AP-16, Excessive RCS Leakage.C.Alarms are consistent with the loss of offsite power;0-AP-10, Loss of Electrical Power.D.Rupture of RCP seal injection line upstream of 1-CH-HCV-1186; 1-AP-33.2, Loss of RCP Seal Cooling.

NAPS 2009 NRC RO Re-Take Exam 24.Following successful completion of maintenance, Unit 1 is exiting an outage that began 4 days ago.Given the following conditions:

  • The RCS is solid*RCS temperature is 256°F and stable*RCS pressure is 300 psig and stable*RHR is in service A loss of ALL instrument air (inside and outside containment) occurs, and the crew entered 1-AP-28, Loss of Instrument Air, but was unable to restore a source of air.Which ONE of the following identifies the ReS temperature response, and the action required by 1-AP-28 assuming the crew is unable to restore IA pressure?A.RCS temperature will increase;open RHR H/X CC Outlet Isolation Valves 1-CC-TV-103A

&-1038 locally.B.RCS temperature will decrease;open RHR H/X CC Outlet Isolation Valves 1-CC-TV-103A

&-1038 locally.C.RCS temperature will increase;adjust RHR Heat Exchanger Return Valves 1-CC-MOV-100A

&-1008.D.RCS temperature will decrease;adjust RHR Heat Exchanger Return Valves 1-CC-MOV-100A

&-1008.

NAPS 2009 NRC RO Re-Take Exam 25.Unit 1 is at 100%power and a loss of ALL CC flow has occurred.In accordance with 1-AP-15, Loss of Component Cooling, the reactor shall be tripped and affected RCPs stopped if RCP rises to 195°F.A.Motor Bearing temperature B.Pump Radial Bearing temperature C.Stator Winding temperature D.Seal Water Outlet temperature NAPS 2009 NRC RO Re-Take Exam 26.Given the following conditions:*A large-break LOCA occurred with Unit 1 initially at 100%power*A loss of offsite power occurs'*All equipment functioned as designed EXCEPT that1J 1, 480-Volt Emergency Bus in Rod Drive, deenergized' due to an electrical faLilt , Based on these plant conditions, which ONE of the following identifies the Quench Spray and Recirc Spray pumps that have power available?

A.BOTH Quench Spray pum'ps and ONLY three Recirc Spray pumps.B.ONLY one QuenchSpraypump andONL Y three Recirc Spray pumps.C.BOTH Quench Spray pumps and ONLY two Recirc Spray pumps.D.ONLY one QuenchSpraypump and ONLY two Recirc Spray pumps.

NAPS 2009 NRC RO Re-Take Exam 27.Given the following conditions:

A large-break LOCA occurred with Unit 1 initially at 100%power All equipment functions as designed EXCEPT that 1-QS-P-1A,"A" Quench Spray Pump, shaft shears on startup Based on this malfunction, which ONE of the following describes the impact on the Quench Spray System, and on the Recirculation Spray System?A.ONLY ONE QS Spray Ring will receive flow;ONLY ONE Inside Recirc Spray Pump sump will receive design flow from Quench Spray.B.ONLY ONE QS Spray Ring will receive flow;BOTH Inside Recirc Spray Pump sumps will receive design flow from Quench Spray.C.BOTH QS Spray Rings will receive flow;ONLY ONE Inside Recirc Spray Pum.p sump will receive design flow from Quench Spray.D.BOTH QS Spray Rings will receive flow;BOTH Inside Recirc*Spray Pump sumps will receive design flow from Quench Spray.

NAPS 2009 NRC RO Re-Take Exam 28.Which ONE of the following descri.bes the automatic operation of 1-QS-MOV-1 02A, Chemical Addition Tank outlet valve?A.1-QS-MOV-102A will open immediately provided BOTH the"A" Quench Spray Pump breaker is closed AND CDA is actuated.B.1-QS-MOV-102A will open immediately provided EITHER the"A" Quench Spray Pump breaker is closed OR CDA is actuated.C.1-QS-MOV-102A will open after a 5-minute time delay provided BOTH the"A" Quench Spray Pump breaker is closed AND CDA is actuated.D.1-QS-MOV-102A will open after a 5-minute time delay provided EITHER the"A" Quench Spray Pump breaker is closed OR CDA is actuated.

NAPS 2009 NRC RO Re-Take Exam 29.Unit 1 is at 100%power.The OATC notes that all PRZR heaters are energized, and RCS pressure is 2270 psig and rising.Based on these plant conditions, which ONE of the following identifies the failed channel and includes the plant response if no operator action is taken?A.1-RC-PT-1444 failed low;1-RC-PCV-1455C will cycle and closed B.1-RC-PT-1444 failed low;1-RC-PCV-1456 will cycle open and closed C.1-RC-PT-1445 failed low;1-RC-PCV-1456 will cycle open and closed D.1-RC-PT-1445 failed low;1-RC-PCV-1455C will cycle and closed NAPS 2009 NRC RO Re-Take Exam 30.Given the following conditions:

  • Unit 1 is at 100°,fc, power*The Pressurizer Level Channel Defeat Switch is selected to position 461/460*Annunciator 8-G7, PRZ LO LEV HTRS OFF LETDOWN ISOL, alarms The OATC notes the following:

PRZR level isand slowly incre*asing

  • Demand on 1-RC-LC-1459G, PRZR Level is approximately 35%and slowly decreasing 8ased on these plant conditions, which ONE of the following identifies the failed instrument, and the Immediate Operator Action required by 1-AP-3, Loss of Vital Instrumentation?

A.1-RC-LI-1460 is failed low;Place 1-CH-FCV-1122, Charging Flow Control valve, in MANUAL and control level at program.B.1-RC-LI-1460 is failed low;Place Pressurizer Level Channel Defeat Switch in position 459/461, then verify Annunciator 8-G7, PRZ LO LEV HTRS OFF LETDOWN ISOL, clears.C.1-RC-LI-1461 is failed low;Place 1-CH-FCV-1122, Charging Flow Control valve, in MANUAL and control level at program.D.1-RC-LI-1461 is failed low;Place Pressurizer Level Channel Defeat Switch in position 459/460, then verify Annunciator 8-G7, PRZ LO LEV HTRS OFF LETDOWN ISOL, clears.

NAPS 2009 NRC RO Re-Take Exam 31.Unit 1 is in Mode 6 with core off-load in progress.A containment purge exhaust fan is started by the Backboards Operator.As a result of this action, reactor cavity level will and spent fuel pit level will_A.increase slightly;decrease slightly B.increase slightly;not be affected C.not be affected;not be affected D.decrease slightly;increase slightly NAPS 2009 NRC RO Re-Take Exam 32.Which ONE of the following describes the actions required by 2-FR-S.1, Response to Nuclear Power Generation/ATWS, Attachment 4 (Remote Reactor Trip)if attempts to locally trip the reactor from the Rod Drive room are unsuccessful?

A.De-energize BOTH 2A 1 and 2C2 480-Volt Station Service Busses by opening their respective supply breakers.B.De-energizeBOTH 2A1 and 2B2 480-Volt Station Service Busses by opening their respective supply breakers.C.Open BOTH Rod Drive M-G Set Motor Supply Breakers locally at the 2A1 and 2C2 480-Volt Station Service Busses.D.Open BOTH Rod Drive M-G Set Motor Supply Breakers locally at the 2A1 and 282 480-Volt Station Service Busses.

NAPS 2009 NRC RO Re-Take Exam 33.Unit 1 tripped from 1000/0 power 22 minutes ago.The following plant conditions exist:*Intermediate Range Channel N-35 indicates8x 10-10 amps and stable.*Intermediate Range Channel N-36 indicates1x 10-11 amps and stable.*High voltage is de-energized on BOTH Source Range Channels N-31&N-32.1-ES-0.1, Reactor Trip Response, is in effect and the crew is at the step,"Check If Source Range Detectors Should Be Energized." Based on these plant conditions, which ONE of the following identifies the malfunction that has occurred, and the action required by 1-ES-0.1?A.N-35 is under-compensated; Manually energize Source Range Detectors using the Source Range Block and Reset switches.B.N-35 is over-compensated; Manually energize Source Range Detectors using the Source Range Block and Reset switches.C.N-35 is over-compensated; Energize Source Range Detectors by bypassing N-35 and removing the instrument power fuses.D.N-35 is under-compensated; Energize Source Range Detectors by bypassing N-35 and removingtheinstrument power fuses.

NAPS 2009 NRC RO Re-Take Exam 34.Core on-load has commenced.

and Containment Purge is in service on Unit 1.1-RM-RMS-159, Containment Particulate Radiation Monitor, has just pegged high due to a malfunction of the monitor.Which ONE of the following identifies the automatic actuations that will occur, and the impacts of this failure on fuel movement lAW 1-0P-4.1, Controlling Procedure for Refueling?

A.ONLY Containment Purge Isolation; OPS Manager approval is required to resume fuel movement.B.Containment Purge Isolation AND Control Room Bottle Air Dump;OPS Manager approval is required to resume fuel movement.C.ONLY Containment Purge Isolation; Fuel movement may continue without any additional approvals.

D.Containment Purge Isolation AND Control Room Bottle Air Dump;Fuel movement may continue without any additional approvals.

NAPS 2009 NRC RO Re-Take Exam 35.The SG PORV controllers (1-MS-PCV-101A, B,&C)are designed to control RCS T AVE at approximately

___;this is achieved by a controller pot setting of approximately

_A.551°F;5.5 B.551°F;7.0 C.556°F;5.5 D.556°F;7.0 NAPS 2009 NRC RO Re-Take Exam 36.Given the following conditions:

  • Unit 1 generator output breaker G-12 has just been closed following a reactor startup All control systems are aligned per startup procedures
  • "A" train of steam dumps is isolated to repair 1-MS-TCV-1408A, which is de-energized and tagged out Main steam line pressure transmitter 1-MS-PT-1464 fails HIGH Which ONE of the following identifies the ReS temperature response, and the required action?A.RCS temperature increases; Manually insert rods to match T AVE and T REF*B".RCS temperature increases; Verify rods automatically insert to match T AVE and T REF.C.RCS temperature decreases; Close all MSTVs using Appendix R Switch.D.RCS temperature decreases; Place both Steam Dump Interlock Switches to OFF/RESET.

NAPS 2009 NRC RO Re-Take Exam 37.Given the following conditions:

  • Unit 1 was operating at 100%power when a Main Steamline break occurred inside containment
  • 1-E-2, Faulted Steam Generator isolation, has been completed*The team transitioned to 1-ES-1.1, SI Termination, and has just completed isolating the BIT and establishing normal charging The following plant conditions exist Containment pressure is 19 psia and decreasing
  • Intact SG narrow-range levels are 8%and increasing PRZR level is 16%and decreasing 1-CH-FCV-1122, Charging flow control valve is full open Based on these plant conditions, which ONE of the following identifies the action required by 1-ES-1.1, SI Termination?

A.Manually start charging pumps and align the BIT;go to 1-E-1, Loss of Reactor or Secondary Coolant.B.When Containment pressure is less than 13 psig, then stop Quench Spray Pumps;Continue in 1-ES-1.1.C.Isolate letdown;if PRZR level continues to decrease, then manually actuate SI.D.Stop feed flow to SGs;if cooldown continues, then close MSTVs and bypass valves.

NAPS 2009 NRC RO Re-Take Exam 38.Because power is lost to the steam dump'arming circuit, Attachment 24, (Unit 1 CRO Loss of Power Actions), of O-AP-10, Loss at-Electrical Power, directs the operator to"Check SG PORVs controlling in AUTO or MANUAL due to loss of Steam Dumps" in the event of a loss of_A.120-VAC Vital Bus I-I B.120-VAC Vital Bus C.120-VAC Vital Bus I-III D.120-VAC Vital Bus I-IV NAPS 2009 NRC RO Re-Take Exam 39.Given the following conditions:

Unit 1 is at 100%power when the crew notes degrading condenser vacuum*The crew has entered 1-AP-14, Low Condenser Vacuum*The Turbine Building operator has been dispatched to perform Attachment 2, Turbine Building Corrective Actions The Turbine Building'operator checks both condenser air" ejector loop seal drain lines to condenser, and notes that one loop seal drain line is hot to the touch and the other is cool to the touch.Which ONE of the following identifies the action required in accordance with 1-AP-14?A.Isolate the hot loop seal drain line and secure the associated set of main condenser air ejectors.B.Isolate the hot loop seal drain line;when at least 15 minutes have elapsed, then slowly reopen the loop seal drain isC?lation valve.C.Isolate the cool loop seal drain line and secure the associated set of main condenser air ejectors.D.Isolate the cool loop seal drain line;when at least 15 minutes have elapsed, then slowly reopen the loop seal drain isolation valve.

NAPS 2009 NRC RO Re-Take Exam 40.Given the following conditions:

  • Operators have transitioned to 1-FR-H.1, Response to Loss of Secondary Heat Sink.*SG wide-range levels are approximately 50%and slowly decreasing.

Operators are at Step 2 of 1-FR-H.1 and are unable to establish AFW flow to any of the SGs.V\!hich ONE of the following iqentifies the action required by 1 with respect to the RCPs?A.Stop all but ONE RCP.B.Stop all RCPs.c.Maintain RCPs operating unless support conditions degrade.D.Maintain RCPs operating until bleed and feed criteria are met.

NAPS 2009 NRCRO Re-Take Exam 41.Given the following conditions:

  • 80th units are initially at 100%power*2-SW-P-18 is tagged out, and Service Water is throttled A loss of both Unit-1 4160-Volt Emergency buses occurs, and power is eventually restored to the 1H Emergency bus from the S80 diesel.Which ONE of the following identifies how the Unit-1 Service Water pumps are operated in accordance with 1-ECA-0.O, Loss of All AC Power?A.1-SW-P-1A and 1-S'N-P-1 8 control switches are maintained in AUTO during 1-ECA-0.0 recovery actions;.1-SW-P-1A will be started prior to exiting 1-ECA-0.0.

B.1-SW-P-1A and 1-SW-P-1 8 control switches are maintained in AUTO during recovery actions;1-SW-P-1A will be started after exiting 1-ECA-0.0.

C.1-SW-P-1A and 1-SW-P-1 8 control switches are placed in PULL-TO-LOCK during recovery actions;1-SW-P-1A will be started prior to exiting 1-ECA-0.0.

D.1-SW-P-1A and 1-SW-P-18 control switches are placed in PULL-TO-LOCK during recovery actions;.1-SW-P-1A will be started after exiting 1-ECA-0.0.

NAPS 2009 NRC RO Re-Take Exam 42.Given the following conditions:

  • Unit 1 is at 25%power ramping up following a scheduled refueling*Annunciator A-G1, CNDSR La VAC C-9*PERM NOT AVAIL is received*The OATC notes that condenser vacuum is 4 in Hg abs and slowly degrading*The crew enters 1-AP-14, Low Condenser Vacuum Which ONE of the following identifies the action required to mitigate these plant conditions?

A.Go to 1-AP-2.2, Fast Load Reduction, reduce load and remove the main generator from service while continuing with 1-AP-14.B.Exit 1-AP-14, go to Fast Load Reduction, reduce load and remove the main generator from service.C.Trip the reactor and go to 1-E-O, Reactor Trip or Safety Injection, while continuing with 1-AP-14.D.Exit 1-AP-14, trip the reactor and go to 1-E-O, Reactor Trip or Safety Injection.

NAPS 2009 NRC RO Re-Take Exam 43.Given the following conditions:

Unit 1 is at 100%power and stable*Following a lightening strike the OATG has identified that several instruments powered from Vital AC Bus 1-111 have been lost Which ONE of the following failed instruments requires action within 1 Hour in accordance with Technical Specifications?

.A.Pressurizer pressure protection channel III, 1-RC-PT-1457.

B.Pressurizer level channel III, 1-RC-LT-1461.

C."8" SG steam flow channel III, 1-MS-FT-1484 D."A" SG narrow-range level channel III, 1-FW-L T-14 76 NAPS 2009 NRC RO Re-Take Exam 44.Which ONE of the following identifies the power level and sequence for securing a Main Feedwater (MFW)pump in accordance with 1-AP-2.2, Fast Load Reduction?

At approximately 55%power,;at approximately 50%power,_A.open one MFW recirc valve;shutdown one MFW pump.B.shutdown one MFW pump;open one MFW recirc valve.C.close one MFW recirc valve;shutdown one MFW pump.D.shutdown one MFW pump;close one MFW recirc valve.

NAPS 2009 NRC RO Re-Take Exam 45.Given the following conditions:

  • Unit 1 is at 70%power*uB" Main Feedwater (MFW)pump is tagged out The"e" MFW pump trips.Which ONE of the following describes the plant response?(Assume no operator action.)A.MFRVs modulate open, but SG levels continue to decrease.B.MFRVs modulate open and maintain SG levels.C.MFRVs and bypass valves modulate open and maintain SG levels.D.MFRVs and bypass valves fully open, but SG levels continue to decrease.

NAPS 2009 NRC RO Re-Take Exam 46.With AFW in service to supply SG feed-water, ECST level suddenly begins to decrease rapidly due to a rupture in the tank.Which ONE of the following identifies the preferred source of alternate makeup water used to supply AFW pump suction?A.Fire Protection System using motor-driven pump 1-FP-P-1.B.Standby 300,OOO-gallon condensate storage tank.C.In-service 300,OOO-gallon condensate storage tank.D.Fire Protection System using diesel-driven pump 1-FP-P-2.

NAPS 2009 NRC RO Re-Take Exam 47.*Given the following conditions:

Unit 1 is at 100 0 k power*AFW pump 1-FW-P-3A is tagged out for Maintenance A loss of offsite power occurs, and all equipment functions as designed EXCEPT the 1J EDG locked out.Based on these plant conditions, which ONE of the following identifies the realignment that will provide flow to all 3 SGs AND also allows the BOP the ability to control AFW flow rate to each SG from the control board?A.Align 1-FW-P-2 to the MOV header.B.Align 1-FW-P-2 to the HCV header.C.Align 1-FW-P-3B to the MOV header.D.Align 1-FW-P-3B to the HCV header.

NAPS 2009 NRC RO Re-Take Exam 48.The NORMAL source of cooling water for charging pumps is the;in the event of a loss of the normal source, alternate cooling is aligned from the_A.Service Water System;Component Cooling System B.Service Water System;Fire System C.Component Cooling System;PG Water System D.Component Cooling System;Fire Protection System NAPS 2009 NRC RO Re-Take Exam 49.Given the following conditions:

  • Unit 1 is at 50%power 15F3,"F" Transfer Bus Supply to1H Bus, is tagged out for breaker maintenance
  • The1H 4160-Volt Emergency bus.is powered from the1B Station Service Bus.While checking neutral bus volts, the GATe inadvertently takes breaker 15B2, Station Service Transformer Supply to1B Station Service Bus, to TRIP.As a result of this action, final status of the1B Station Service Bus will be , and the final status of the1H 4160-Volt Emergency bus will be_A.de-energized; energized B.energized; energized C.energized; de-energized D.de-energized; de-energized NAPS 2009 NRC'RO Re-Take Exam 50.A Loss of All AC has just occurred on Unit 1.Five minutes have elapsed, and a'source of power has not yet been restored.The operator should expect the voltage, on all four (4)of the 125-Volt DC Busses to be_their pre-event values.Overtime,vital DC bus 1-1 voltage would be expected to drop_as compared to vital DC bus ,1-11 voltage.A.approximately the same as;at approximately the same rate B.approximately the same as;at a slower rate C.approximately 10 volts lower than;at approximately the same rate D.approximately 10 volts lower than;at a slower rate NAPS 2009 NRC RO Re-Take Exam 51.Which ONE of the following methods ensures that only one DC bus at a time is supplied from the swing charger?A.Each swing charger supply breaker to the DC bus has a Key-operated interlock mechanism.

B.The swing charger output breakers are interlocked such that both breakers trip if you attempt to close one with the other one already closed.C.Each swing charger has a single dedicated plug-in type output breaker.D.The swing charger outputbreakersare electrically interlocked to prevent simultaneous closure.

NAPS 2009 NRC RO Re-Take Exam 52.When the emergency diesel generator air compressors are swapped to the Lister diesels, the Lister diesel , and air bank pressure is maintained by the loading and unloading of the air compressor.

A.will run continuously; automatic B.will run continuously; manual C.is manually started each time air pressure drops to 150 psig;automatic D.is manually started each time air pressure drops to 150 psig;manual NAPS 2009 NRC'RO Re-Take Exam 53.Unit 1 is at 100%power.After receiving annunciator J-E8, INSTRUMENT AIR LOW PRESS, operators entered 1-AP-28, Loss of Instrument Air.The BOP notes Instrument Air pressure has decreased to.1-AP-28 directs the crew to trip the reactor and close Main Steam Trip Valves.These actions are taken primarily to_A.68 psig;prevent an undesired automatic Safety Injection.

B.68 psig;prevent an uncontrolled RCS cooldown.C.88 psig;prevent an undesired automatic Safety Injection.

D.88 psig;prevent an uncontrolled RCS cooldown.

NAPS 2009 NRC RO Re-Take Exam 54.If an oil fire occurs in the North Fuel Oil Pump House, a will actuate to suppress the fire;the fire is classified as a_A.pre-action sprinkler system;Class 8 fire B.pre-action sprinkler system;Class A fire C.high-pressure CO 2 system;Class 8 fire D.high-pressure CO 2 system;Class A fire NAPS 2009 NRC RO Re-Take Exam 55.Which ONE ofthefollowing components is automatically affected by a high alarm on 1-GW-RI-178-1, MGP Process Vent Radiation Monitor?A.Containment Vacuum Pump Discharge Valves B.Low Level Liquid Waste Tank Vents C.Boron Recovery Tank Vents D.Containment Purge Exhaust Valves NAPS 2009 NRC RO Re-Take Exam 56.Both units are at 100%power.Breaker 15G10, 1G/2G bus crosstie, will automatically close if power is lost to the_A."A" RSST provided lake level is'greater than 251 feet B."A" RSST provided lake level is less than 251 feet C."G" RSST provided lake level is greater than 251 feet D."G" RSST provided lake level is less than 251 feet NAPS 2009 NRC RO Re-Take Exam 57.Given the following conditions:

  • Both units are at 100%power*1-SW-P-1A and 2-SW-P-1A are running*Unit 1 experiences a large-break LOC,A.Service Water flow to the CCHXs isolates----A.on Unit 1 ONLY, and 3 Service Water pumps will be running.B.on BOTH units, and'3 Service Water pumps will be running.C.on Unit 1 ONLY, and 4 Service Water pumps will be running.D.on BOTH units, and 4 Service Water pumps will be NAPS 2009 NRC RO Re-Take Exam 58.Unit 1 is at 100%power with approximately 960 MW and 100 MVAR OUT.The OATC notes the following conditions:
  • Sustained Generator output voltage increase*MVAR sustainedincreaseconsistent with Generator output voltage*MW stable Which ONE of the following identifies the required operator actions based on these plant conditions?

A.Maintain Voltage Regulator in AUTO.and adjust voltage using Base Adjust;Maintain less than 200 MVAR OUT.B.Maintain*Voltage Regulator in AUTO and adjust voltage using Base Adjust;Maintain less than 200 MVAR IN.C.Place Voltage Regulator control switch in OFF and adjust voltage using Base Adjust;Maintain less than 200 MVAR OUT.D.Place Voltage Regulator controJ switch in OFF and adjust voltage using Base Adjust;Maintain less than 200 MVAR IN.

NAPS 2009 NRC RO Re-Take Exam 59.The Service Air Compressors are powered from their respective unit's and the Instrument Air Compressors are powered*from their repective unit's_A."B" 480-Volt Station Service Bus;"H" 480-Volt Emergency Bus B."B" 480-Volt Station Service Bus;"'J" 480-Volt Emergency Bus C."G" 480v Station Service Bus;"H" 480-Volt Emergency Bus D."G" 480-Volt Station Service Bus;"J" 480-Volt Emergency Bus NAPS 2009 NRC RORe-Take Exam 60.If Chilled Water to Containment is lost, the indicated containment partial air pressure will_and the digital partial air pressure indicators are_A.decrease;inoperable B.decrease;operable C.increase;inoperable D.increase;operable NAPS 2009 NRC RO Re-Take Exam 61.Unit 1 has experienced a DBA LOCA.The following plant conditions exist:*Containment pressure is 25 psia*Containment sump level is 11 feet 4 inches Which ONE of thefollowingidentifies the status of the Containment CSF Status Tree?A.An ORANGE path exists for both Containment Pressure and Containment Sump level.B.An ORANGE path exists for Containment Pressure ONLY..C.An ORANGE path exists for Containment Sump level ONLY.D.An ORANGE path does NOT exist for Containment Pressure or Containment Sump level.

NAPS 2009 NRC RO Re-Take Exam 62.Both units are at 100%power with no equipment out of service (except as noted below).Which ONE of the following events would initiate an automatic start of the SBO diesel?A.With"C""RSST out of service, a loss of 34.5 KV bus#4 occurs.B.With"B" RSST out of service, a loss"of 34.5 KV bus#4 occurs.C.Spurious trip of breaker 15F1,"F" transfer bus supply.D".Spurious trip of breaker 15D1,"D" transfer bus supply.

NAPS 2009 NRC RO Re-Take Exam 63.In order to maintain an active license, a Reactor Operator must stand a MINIMUM of__12-hour shifts per calendar quarter.A.4 B.7 C.5 D.8 NAPS 2009 NRCRO Re-Take Exam 64.Given the following conditions:

  • Unit 1 is at 100%power*Annunciator B-H2, PRZPOWER RELIEF LINE HI TEMP is received*During the next 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, PRT level increases from 72%to 76%*RCS Leakage prior to the event was 0.5 gpm Identified, 0.3 gpm Unidentified Based on the above conditions, which ONE of the following describes the Technical Specification implications of the leaking PORV?(Reference provided)A.The limit for RCS Operational Leakage has NOT been exceeded.B.The limit for Identified Leakage has been exceeded.C.The limit for Pressure Boundary Leakage has been exceeded.D.The limit for RCS Pressure Isolation Valve (PIV)Leakage has been exceeded.

NAPS 2009 NRC RO Re-Take Exam 65.The status of annunciator patch cords is checked on a basis using O-GOP-2.7, Annunciator Patchcord Control, and the is used to track the total number of disabled annunciators.

.A.quarterly; Central Reporting System B.quarterly; OperationsAggregateImpact Report C.weekly;Central Reporting System D.weekly;Operations Aggregate Impact Report NAPS 2009 NRC RO Re-Take Exam 66.The SG N-16 Radiation Monitors are required by Technical Requirements in , and can not be declared functional until reactor power is at least__'A.Modes 1, 2, and3;5.%B.Modes 1, 2, and3;25%C.Modes 1&2;5%D.Modes 1&2;25%

NAPS 2009 NRC RO Re-Take Exam 67.In accordance with VPAP-21 01, Radiation Protection Program, a Radiation Worker's Annual Administrative Dose Limit for Total Effective Dose Equivalent (TEDE)is rem/calendar year at the worker's home site.A.B.2 C.3 D.4 NAPS 2009 NRC RO Re-Take Exam 68.Unit 1 is at 100%power.1-SV-RM-121, Condenser Air Ejector Radiation Monitor, spikes high resulting in a Hi alarm AND a Hi-Hi alarm on the drawer, and then the indication returns to normal.Based on the above, which ONE of the following describes the response of 1-SV-RM-121, Condenser Air Ejector Radiation Monitor?A.The Hi alarm clears when the indication returns to normal;the Hi-Hi alarm remains in and must be reset by the operator.B.The Hi alarm clears when the indication returns to normal;the Hi-Hi alarm remains in and must be reset by I&C.c.The Hi-Hi alarm clears when the indication returns to normal;the Hi alarm remains in and must be reset by the operator.D.The Hi-Hi alarm clears when the indication returns to normal;the Hi alarm remains in and must be reset by I&C.

NAPS 2009 NRC RO Re-Take Exam 69.1-FR-H.1, Response*to Loss of Secondary Heat Sink, is in effect.Whenattemptingto establish SG feed flow from the Condensate System, there is a NOTE prior to the step"Initiate depressurization of all SGs to less than 610 psig by dumping steam to condenser at maximum rate." This NOTE states that each Main Steamlin"e flow should be kept less than 1.0E6 LBM/HR.The purpose of this NOTE is to remind the operator that exceeding 1.0E6 LBM/HR may result in A.aRCS cooldown rate in excess of Technical Specification limits.B.a challenge to the PTS status tree.C.an inadvertant Steamline DP Safety Injection.

D.an undesired Main Steamline Isolation.

NAPS 2009 NRC RO Re-Take Exam 70.Once the TSC is*fully operational, the relief Station Emergency Manager will assume all of the following responsibilities from the on-shift SEM EXCEPT_A.authorizing notification to state and local governments.

B.classifying the emergency (escalation/de-escalation).

C.making protective action recommendations (PAR).D.authorizing deviations to procedures pursuant to 10 CFR 50.54x.

NAPS 2009 NRC RO Re-Take Exam 71.Operators are responding to a large-break LOCA with a loss of offsite power.The team is implementing 1-E-1, Loss of Reactor or Secondary Coolant.The OATC reports that the following alarms have just been received: F-E8, AFW SUPPLY 20 MIN WATER" REMAINING*J-A2, RWST LO LEVEL*H-H1, EMER DIESEL GEN#1 H DIFFERENTL J-F5, LHSI PP1B LOOROL TRIP Based on these alarms, A.verify LHSI pump suction has transferred to containment sump and continue in 1-E-1, Loss of Reactor or Secondary Coolant.B.perform 1-AP-22.5, Loss of Emergency Condensate Storage Tank 1-CN-TK-1, in order to preclude implementing 1-FR-H.1, Loss of Secondary Heat Sink.C.transition to 1-ES-1.3, Transfer to Cold Leg Recirculation, then return to 1-E-1, Loss of Reactor or Secondary Coolant.D.transition to 1-ES-1.3., Transfer to Cold Leg Recirculation, then transition to 1-ECA-1.1, Loss of Emergency Coolant Recirculation.

NAPS 2009 NRC RO Re-Take Exam 72.Operators have entered 1-ECA-1.2, LOCA Outside Containment.

1-ECA-1.2 will have the operator isolate cold leg injection piping from , and if RCS pressure is INCREASING AFTER the isolation, the crew will transition to_A.High-Head SI pumps;1-E-1, Loss of Reactor or Secondary Coolant.B.High-Head SI pumps;1-ECA-1.1, Loss of Emergency Coolant Recirculation.

C.Low-Head SI pumps;1-ECA-1.1, Loss of Emergency Coolant Recirculation.

D.Low-Head SI pumps;1-E-1, Loss of Reactor or Secondary Coolant.

NAPS 2009 NRC RO Re-Take Exam 73.Unit 1 tripped from 100%power, and a loss of secondary heat sink occurred.The following plant conditions exist: The crew is currently in 1-FR-H.1, Response to Loss of Secondary Heat Sink*Bleed and feed has been established*A Main Steamline break occurs inside containment and CDA actuates, but only one Quench Spray pump started*RCS cold-leg temperatures have decreased to 26S o F Based on these conditions, which ONE.of the following identifies the correct operator response?A.Reset COA, reset Phase'B', and place instrument air back in service to PORVs.B.Transition to 1-FR-Z.1, Response to High Containment Pressure.C.Transition to 1-FR-P.1, Response to Imminent Pressurized Thermal Shock Condition.

D.Verify proper alignment of equipment using 1-E-0, Reactor Trip or Safety Injection.

NAPS 2009 NRC RO Re-Take Exam 74.Unit 1 was operating at 100%pow'er when a LOCA occurred.The crew has just transitioned from 1-E-1, Loss of Reactor or Secondary Coolant, to 1-FR-P.1, Response to Imminent Pressurized Thermal Shock Condition.

The following plant conditions exist:*Containment pressure is 15 psia and isslowlytrending down All RCPs are stopped RVLIS Full Range is reading 100%*RCS subcooling based on Core Exit TCs is 105°F*RCS pressure is 850 psig Based on these plant conditions, which ONE of the following identifies the actions the crew will perform in accordance with 1-FR-P.1, and the reason for these actions?A.Remain in 1-FR-P.1, termi"nate SI and depressurize to minimize subcooling in order to limit pressure stress on the vessel.B.Exit 1-FR-P.1 and return to procedure step in effect, pressure is too low for PTS to be a concern.C.Exit 1-FR-P.1 and go to 1-ES-1.1, SI Termination, SI must be terminated promptly to mitigate the PTS condition.

D.Remain in 1-FR-P.1, leave SI in service and determine soak requirements in order to minimize thermal stresses during subsequent recovery actions.

NAPS 2009 NRC RORe-Take Exam 75.Given the following conditions:

  • Unit.1 has experienced a LOCA*After establishing Cold Leg Recirculation, operators observed indication of sump blockage*The crew has just transitioned to 1-ECA-1.1, Loss of Emergency Recirculation Capability The ST A reports an ORANGE path on Containment Pressure.Based on these plant conditions, which ONE of the following identifies the crew response, and the reason for their response?A.Remain in 1-ECA-1.1; FRPs are not implemented until specifically directed by 1-ECA-1.1.

B.Remain in 1-ECA-1.1; 1-FR-Z.1 is not to be performed as long as 1-ECA-1.1 is in effect.C.Immediately transition to 1-FR-Z.1 and operate Containment Depressurization Systems as directed, then return to 1-ECA-1.1precludes a Red Path on the Containment status tree.D.Immediately transition to 1-FR-Z.1;Verify Phase A Isolation and Steam line Isolation, then return to 1-ECA-1.1; precludes a Red Path on the Containment status tree.

VIRGINIA POWER NORTH ANNA POWER STATION Pressurizer Relief Tank l-RC-TK-2 Volume Versus Indicated Level I-se-S.II REVISION 1.PAGE 1 OF7 120 100 80=0.-......5.*."=60...40 20 o 119532 G.Douat 99.5S Indication

...,[J,I* I-' ,,'II 1,1",!Jr'11223 Gallons.at 0%Indicatioll J I I , o 1000 2000 3000 4000 SOOO 6000 7000 8000 9000 10000 Gallons APPROVED BY: CHAIRMAN, STATION'NUCLEAR SAFETY AND OPERATING COMMITTEE

.VIRGINIA POwER NORTH ANNA POWER STATION ,1-SC-5.11 REVISION 1 PAGE 2 OF 7 NOTE:'PRESSURIZER RELIEF TANK l-RC-TK-2 VOLUME VERSUS INDICATED LEVEL*Level transmitter reference leg Calibration temperature is 70 0 P with*density 62.305 Ibm/ff.*Actual tank water temperature is 8SoP With a density of 62.172 Ibmlff.*The transmitter will no longer increase with increasing level after 99.S percent indication

..EQUIV ALENT INDICATED 110°F VOLUME LEVEL (%)(GALLONS)0.0 223.19 0.5 247.91 1.0 273.50 1.5 299.93 2.0 327.17 2.5 355.20 3.0 383.99 3.5 413.51 4.0 443.76 4.5 474.71 5.0 506.34 5.5 538.64 6.0 571.58 6.5 605.16 7.0 639.36 7.5 674.17 8.0 709.56 8.5 745.53 9.0 782.06 9.5 819.15 10.0 856.78 10.5 894.93 11.0 933.60.11.5'972.78 12.0 1012.45 APPROVED BY:CHAIRMAN,'

STA nON NUCLEAR SAFETY AND OPERATING COMMITTEE VIRGINIA POWER NORTH ANNA POWER STATION.."........'*1-SC-5.11 REVISION 1 PAGE 3 OF7 PRESSURIZER RELIEF*TANK l-RC-TK-2 VOLUME*VERSUS INDICATED LEVEL EQUIVALENT INDICATED 110 0 P VOLUME LEVEL(%)(GALLONS)12.5 1052.61 ,13.0 1093.25 13.5 1134.35 14.0 1175.91*14.5 1217.91 15.0 1260.35 15.5 1303.22 16.0 1346.51 16.5 1390.22 17.0 1434.32.17.5 1478.82 18.0 1523.71 18.5 156.8.98.19.0 1614.61 19.5 1660.62 20.0 1706.97 20.5 1753.68*21.0 1800.72 21.5 1848.11 22.0 1895.81 22.5 1943.84.23.0 1992.18 23.5 2040.'82 24.0 2089.77 24.5 2139.00 25.0 2188.53 25.5 2238.33 26.0 2288.40 26.5 2338.74 27.0 2389.34 27.5 2440.20 28.0 2491.30 28.5 2542.64 29.0 2594.22 29.5 2646.02.

..VIRGINIA POwER..NORTH ANNA POWER STATION: 1-SC-5.11 REVISION 1 PAGE40F7 PRESSURIZER RELmF TANK l-RC-TK-2 VOLUME VERSUS INDICATED LEVEL EQUIV ALENT.INDICATED.110 0 P VOLUME LEVEL (%)(GALLONS)30.0 2698.05 30.5 2750.30 31.0 2802.75.31.5 2855.42 32.0'2908.28*32.5 2961.33 33.0 3014.57 33.5 3068.00.34.0 3121.60 34.5*3175.37 35.0 3229.30 35.5 3283.40 36.0 3337.64 36.5 33.92.04 37.0 3446.58 37.5 3501.2,5 38.0 3556.06 38.5 3610.99 39.0 3666.04 39.5 3721.21 40.0 3776.49 40.5 3831.87 41.0 3887.35 41.5 3942.92 42.0 3998.58 42.5 4054.33 43.0 4110.15 43.5 4166.05 44.0 4222.00 44.5 4278.03 45!O 4334.11 45.5 4390.24 46.0 4446.41 46.5 4502..63 47.0 4558.89

"......;a..VIRGINIA POWER NORTH ANNA POWER STATION I-SC-5.11 REVISION 1 PAGES OF7 PRESSURIZER REI,IEF TANK l-RC-TK-2 VOLUME INDICATED LEVEL EQUIVALENT INDICATED.110°F VOLUME LEVEL<Il (GALLONS)47.5 4615.17 48.0 4671.48 48.5 4727.80.'49.0 4784.15 49.5*.4840.50 50.0 4896.85 50.5 4953.20 51.0 5009.55 51.5 5065.89 52.0 5122.21 52.5 5178.51 53.0 5234.78 53.5 5291.02 54.0 5347.22 54;5 5403.37.55.0 5459.49 55.5 5515.54 56.0 5571.54 56.5 5627.48 57.0 5683.33 57.5 5739.13 58.0 5794.84 58.5 5850.46 59.0 5906.00 59.5 5961.43 60.0 6016.78 60.5 6072.00 61.0 6127.12 61.5 6182.13 62.0 6237.00 62.5 6291.76 63.0 6346.37 63.5 6400.85 64.0 6455.18 64..5 6509.36

,.-'-...., VIRGINIA POWER NORTH.ANNA POWER STATION 1-SC-5.11 REVISION 1 PAGE 6 OF 7.PRESSURIZER RELIEF TANK 1..RC-tt-2 VOLUME VERSUS INDICATED LEVEL EQUIVALENT INDICATED.Il00P VOLUME LEVEL (%)(GALLONS>65.0 6563.39 6617.26 66.0 6670.95 66.5 6724.48.67.0 6777.82 67.5 6830.99 68.0 6883.96 68.5 6936.74 69.0 6989.31 69.5 7041.68 70.0 7093.83 70.5 7145.77 71.0.7197.48 71.5 7248.96 72.0 7300.20 72.5 7351.19 73.0 7401.94 73.5 7452.43 74.0 7502.66 74.5 7552.62 75.0 7602.30 75.5 7651.70 76.0 7700*.82 76.5 7749.63 77.0 7798.15 77.5 7846.36 78.0 7894.25 78.5 7941.81 79.0 7989.05 79.5 8035.95 80.0 8082.51 80.5 8128.71 81.0 8174.56 81.5 8220.05 82.0 8265.15 VIRGINIA POWER NORTH ANNA POWER'STATION 1-SC-5.11 REVISION 1 PAGE 7 OF,7 PRESSURIZER RELIEF TANK l-RC-TK-2 VOLUME VERSUS INDICATED LEVEL EQUIVALENT INDICATED 110 0 P VOLUME LEVEL (%)(GALLONS)82.5 8309.87 83.0 83.5 8398.14'84.0 8441.66 84.5 8484.78 85.0 8527.47 85.5 8569.72 86.0.8611.55 86.5.8652.90 87.0 8693.80 87.5 8734.24 88.0 8774.20 88.5 8813.66 89.0 88S2.62 89.5 8891.07 90.0 8929.00 , 90.5 8966.40 91.0 9003.26 91.5 9039.55 92.0 9075.27 92.5." 9110.42 93.0 9144.96 93.5 9178.90 94.0 9212.21 94.5 9244.88 95.0 9276.90 95.5 9308.24 96.0 9338.89 96.5 9368.84 97.0 9398.05 97.5 9426.52 98.0 9454.21 98.5 9481.11'99.0.9507.18 99.5 9532.40

  1. 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 Points 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 ANSWER KEY REPORT NAPS 2009 NRC RO Re-Take Exam--------------

Answers--------------

o D C B B D D D A C B A A C D A C C A A D A D A A A B A D 8 A A C A A A D A C B R C C A A A A B B

  1. 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 Points 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 ANSWER KEY REPORT NAPS 2009 NRC RO Re-Take Exam--------------

Answers--------------

o A o A A A C A o C o A A C A C A B D B A D D D D A A A

Retrieved from "https://kanterella.com/w/index.php?title=ML090690065&oldid=988272"