ML101310324

From kanterella
Jump to navigation Jump to search
Initial Exam 2010-301 Final RO Written Exam
ML101310324
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 05/04/2010
From:
NRC/RGN-II
To:
Duke Energy Carolinas
References
Download: ML101310324 (80)
v • d • e


Text

ES-401 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:

Date: 04/07/2010 Facility/Unit: Oconee Region: I El II IDIIIg] El IIIIII D IV El D Reactor Type: W DEl CE D El BW ~ GE D El Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, 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. II have neither given nor received aid.

Applicants Applicant's Signature Results Examination Value 75 Points Applicants Applicant's Score Points Applicants Applicant's Grade Percent

NRC REACTOR OPERATOR 2010A NRC 2010A OPERATOR EXAM EXAM I1 POINT Question I1 Unit 1 Unit I plant conditions:

  • Reactor power == 100%100%
  • Pressurizer temperature == 648 °F of pressure ==55 psig
  • Quench tank pressure psig Based on the above conditions, which ONE of the following describes the expected Based

("F) downstream of I1RC-66?

tailpipe temperature (°F)

A. 162162 B. 228 C. 272 D. 648

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 2 Unit 1I plant conditions:

  • Rule 2 (Loss of SCM) in progress

lB 78 XSUR increasing

= 78"

=

  • Cooldown rate = 65°F I/ Y:zhr

%hr Based on the above conditions, which ONE of the following describes describes...

(1)) why SG levels are being increased?

(1 AND (2) how EFDW flows will be controlled in accordance with Rule 2?

A. (1) Ensure secondary inventory available for heat transfer if SG feed is lost (2) EFDW flow should be stopped until cooldown rate is in compliance with Tech Spec limits B. (1) Ensure secondary inventory available for heat transfer if SG feed is lost (2) EFDW flow will be reduced in an effort to comply with Tech Spec limits but SG levels must continue to increase C. (1) Ensure boiler-condenser heat transfer is established (2) EFDW flow should be stopped until cooldown rate is in compliance with Tech Spec limits D. (1) Ensure boiler-condenser heat transfer is established (2) EFDW flow will be reduced in an effort to comply with Tech Spec limits but SG levels must continue to increase

2010A NRC REACTOR OPERATOR EXAM 2010A NRC EXAM I1 POINT POINT Question 33 Unit 11 plant conditions:

  • RCS pressure == 88 psig decreasing decreasing Building pressure == 27
  • Reactor Building 27 psig increasing
  • 11BB LPI Pump failed to start Based onon the above conditions, which ONE of the following describes the guidance guidance provided in EOP Enclosure 5.1 (ES Actuation) regarding the LPI pumps and system operation?

FOP Enclosure 5.1 (ES Actuation)....

EOP Actuation) ....

A. directs continued operation with only the 1 A LPI pump and no re-alignment of LPI IA header flows B. directs continued operation with only the 1 A LPI pump and manually re-aligns LPI IA flow down both the 11A 1 B LPI headers A and 1 C. utilizes the 1A and the 1 1A 1C C LPI Pump and aligns flow down both headers with 1 1LP-9 LP-9 and 10 closed D. utilizes only the 11 C LPI Pump and aligns flow down both headers with 1I LP-9 & 10 open

2010A NRC REACTOR OPERATOR EXAM 1

I POINT Question 4 Unit 1I plant conditions:

  • Reactor power = = 100%
  • 1ITATA and 1ITB TB de-energized Based on the above conditions, which ONE of the following indicates the Thot and Tcold values expected approximately 15 minutes after the Reactor trip?

Thot would be approximately _ _ _ oF and Tcold would be approximately _ _ _ oF.

A. 534 / 532 B. 570 / 540 C. 556 / 554 D. 585 /I 555

2010A NRC REACTOR OPERATOR 2010A NRC OPERATOR EXAM EXAM I1 POINT Question 55 Unit I1 initial initial conditions:

  • Reactor in MODE 55
  • RCS pressure == 00 psig Normal LPI decay
  • Normal decay heat in service heat removal in
  • 1C pump operating 1C LPI pump Blackout occurs
  • Unit Blackout Current conditions:

MFBs re-energized from CT-5

  • MFB's Based on the above conditions, which ONE of the following describes actions required AP/26 (Loss of Decay heat Removal)?

by AP126 A. Start 1 IC AP/11I (Recovery from Loss of Power)

C LPI pump AND initiate AP/l B. Start 1 1 C LPI pump AND initiate the Blackout tab of the EOP C. Feed and steam SG's SCs to maintain CETC < 246°F AND initiate AP/l

<246°F AP/111 (Recovery from Loss of Power)

D.

D. Feed and steam SG's SGs to maintain CETC < 246°F AND perform AP/26 Encl.

<246°F End. 5.6 (Venting LPI Pumps and Suction Lines)

2010A NRC 2010A NRC REACTOR OPERATOR EXAM REACTOR OPERATOR EXAM I1 POINT POINT Question 66 Question Unit I1 plant Unit plant conditions:

Reactor trip

  • Reactor trip has just occurred has just occurred Total RCP
  • Total RCP seal flow ==00 gpm injection flow seal injection gpm Cooling is Component Cooling
  • Component is unavailable unavailable Based on Based on the the above conditions, which ONE ONE of describes the procedure of the following describes performance is whose performance is directed directed by the EOP and and why?

Initiate ...

Initiate...

AP/20 (Loss of CC) to restore Component Cooling A. API2O AP/20 (Loss of B. API2O of CC)

CC) to to ensure ensure letdown letdown is is isolated isolated C. AP/25 (SSF EOP) to align an alternate letdown flowpath AP/25 (SSF EOP) to align an alternate source of seal injection D. AP125

2010A NRC 2010A REACTOR OPERATOR NRC REACTOR OPERATOR EXAM EXAM I1 POINT POINT Question 77 Question Unit 11 initial Unit initial conditions:

conditions:

  • Reactor power ==90%

Reactor power 90%

Current conditions:

  • Reactor power == 70% decreasing decreasing
  • RCS pressure == 2165 psig psig slowly slowly decreasing decreasing
  • Pressurizer level level == 228 inches slowly slowly decreasing decreasing temperature ==640°
  • Pressurizer temperature 640°F slowly decreasing F slowly decreasing
  • Pressurizer heaterheater bank 1 I (Group A and K) is ONON
  • Pressurizer heater banks 2, 3, and and 4 are in AUTO and are OFF Based on the aboveabove conditions, which ONE describes the status of the ONE of the following describes pressurizer and the pressurizer saturation circuit?

The pressurizer is _ _ _ _ AND the pressurizer saturation circuit _ _ __

A. subcooled I/ is responding as expected B. subcooled I/ has failed C. saturated I/ is responding as expected D. saturated /I has failed

2010A NRC REACTOR OPERATOR EXAM 1I POINT Question 8 Unit 2 initial conditions:

  • Time = = 1200:00
  • Reactor power = = 100%
  • Both MFDW Pumps tripped Current conditions:
  • Time = = 1201 :45
  • Reactor power = = 30% decreasing
  • Loop A SCM = O°F 0°F stable
  • Rule 1 1 (ATWS/Unanticipated Nuclear Power Production) in progress
  • 2SA9/D2 (RC Pump Vibration High)High ) Actuated
  • Rule 2 (Loss of SCM) initiated Based on the above conditions, which ONE of the following describes the required (RCPs) and the reason for those actions?

actions regarding Reactor Coolant Pumps (RCP's)

A. Leave RCP's RCPs operating to minimize core damage from an increase in DNBR that would occur if secured RCPs operating to provide flow through the core for heat removal B. Leave RCP's C. Secure RCP's RCPs to reduce the amount of RCS inventory lost D. Secure RCP's RCPs before the RCS can evolve to a Void fraction of> 70%

2010A NRC REACTOR OPERATOR EXAM 1I POINT Question 9 Unit 11 plant conditions:

  • SGTR tab in progress
  • 1 SC isolated 1 B SG
  • 1A loop Tcold = 440°F decreasing
  • 1B SIG TUBE/SHELL DT =

lB S/G = (-)72°F Based on the above conditions, which ONE of the following describes:

(1) the reason the SGTR tab directs minimizing core SCM during cooldown AND (2) the initial method used to reduce the SCM?

To reduce the _--l(....:,1J,..)

(1) _ (2)

AND reducing SCM would initially be attempted by _-,,(2=..)<---,-

A. primary to secondary leak rate /I de-energizing Pzr heaters and cycling Pzr spray B. primary to secondary leak rate /I cycling the PORV C. compressive stresses in the 1 I B SG SC / de-energizing Pzr heaters and cycling Pzr spray D. compressive stresses in the 1 lB SC /I cycling the PORV B SG

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 10 1 plant conditions:

Unit 1

  • Both MFB's MFBs de-energized
  • TDEFWP operating Based on the above conditions, which ONE of the following describes the status of bearing oil cooling water supply to the TDEFWP?

TDEFWP bearing oil cooling is currently provided by and it _ _ __

provide adequate cooling water flow until AC power has been re-established.

A. CCW I/ will B. HPSW /I will C. CCW /I will NOT D. HPSW /I will NOT

NRC REACTOR OPERATOR 2010A NRC 2010A OPERATOR EXAM EXAM I1 POINT POINT Question II 11 Unit 1 1 initial conditions:

  • Station Blackout occurred
  • Neither KHU automatically started Start of BOTH KHUs Emergency Start Manual Emergency
  • Manual is required KHU's is Time == 1201 1201 switch placed in START Emergency Start Channel A control room switch
  • Keowee Emergency Time = 1202 1202
  • Keowee Emergency Start Channel B B control room switch placed in START Based on the above conditions, which ONE of the following describes the time at which KHUs have received an Emergency Start signal AND the Generator Output BOTH KHU's KHUs that would indicate proper operation?

Voltage (KV) of the KHU's 1201 I 13.8 A. 1201 B. 1202 I 13.8 1201 I 4.16 C. 1201 1202 I/ 4.16 D. 1202

NRC REACTOR OPERATOR EXAM 2010A NRC 2010A I POINT 1

Question 1212 has experienced aa Which ONE of the following would indicate that the 2DIC inverter has panelboard would then receive power?

loss of AC output voltage AND how 2KVIC panelboard loss LOAD CONNECTED TO A. LOAD EMERGENCY light on the inverter will be illuminated TO EMERGENCY illuminated AND panelboard 2KVIC will automatically be panelboard be energized from panelboard 2KRA (regulated power).

B. LOAD CONNECTED TO EMERGENCY light on the inverter will be illuminated AND panelboard 2KVIC will automatically be energized from Unit 3.

C. INVERTER OUTPUT LOW light on the Inverter be illuminated AND the 2KVIC panelboard panel until manually aligned to panelboard 2KRA board will be de-energized until (regulated power).

D. INVERTER OUTPUT LOW light on the Inverter be illuminated AND the 2KVIC panelboard will be de-energized until manually aligned to receive power from Unit 3.

2010A NRC REACTOR OPERATOR EXAM 1I POINT Question 13 Plant conditions:

  • 1 CA Battery Charger fails - output voltage =

1 - = 0 VDC

  • 1I CA Battery voltage =

= 126 VDC

  • 11 DCB Bus voltage = 123 VDC

=

  • DCA/DCB Bus voltage =

Unit 2 DCAlDCB = 124 VDC

  • DCA/DCB Bus voltage =

Unit 3 DCAlDCB = 127 VDC Based on the above conditions, which ONE of the following will automatically supply power to 11 DIA panelboard?

A. 1DCB Bus B. 11CA CA Battery C. Unit 2 DC Bus D. Unit 3 DC Bus

2010A NRC REACTOR OPERATOR EXAM 11 POINT Question 14 I and 2 initial conditions:

Unit 1

  • A and B LPSW pump operating Current conditions:
  • A LPSW pump amps = 15 - 35 fluctuating
  • B LPSW pump amps = = 55 stable
  • LPSW HDR PRESS = = rapidly fluctuating between 60 & & 75 psig Based on current conditions, which ONE of the following describes the status of the LPSW pumps and what actions are directed by AP/24 (Loss of LPSW)?

A. The A LPSW pump is cavitating 1/ Place the Unit 1/2 STANDBY LPSW PUMP AUTO START CIRCUIT in DISABLE then stop LPSW Pump A and start LPSW Pump C PumpC B. The A LPSW pump has a sheared shaft 1 I Place the Unit 1/2 STANDBY LPSW PUMP AUTO START CIRCUIT in DISABLE then stop LPSW Pump A and start LPSW Pump C C. The A LPSW pump is cavitating 1 / Start LPSW Pump C then stop LPSW Pump A D. The A LPSW pump has a sheared shaft 1 I Start LPSW Pump C then stop LPSW Pump A

2010A NRC REACTOR OPERATOR EXAM 2010A NRC EXAM 1 POINT 1 POINT Question 15 15 Unit 33 initial Unit initial conditions:

  • Time=1200 Time = 1200
  • Reactor power == 45% stable
  • IA and AlA are lost to 3FDW-315 Current conditions:

Time=1300

  • Time = 1300
  • RCS Tave = = 550°F stable Based on the above conditions, which ONE of the following describes the expected SG level and the status of 3FDW-315?

ASSUME NO OPERATOR ACTIONS HAVE OCCURRED A. 25" 25 Stu s/u level/failed level I failed open B. 25 25" Stu level I controlling SG level at setpoint s/U level/controlling C. 30" 30 XSUR / failed open 30 XSUR I/ controlling SG D. 30" Sc level at setpoint

2010A NRC REACTOR OPERATOR EXAM 2010A NRC EXAM I1 POINT POINT Question 1616 1 plant conditions:

Unit 1

  • Reactor power == 50% stable
  • Units 2 and 33 in MODE 55 AP/34 (Degraded Grid)
  • AP134 in progress due Grid) in due to grid disturbance disturbance
  • BOTH KHU's generating to BOTH KHUs to the grid grid
  • All but ONE of the Offsite Sources required by Tech Spec 3.8.1 (AC Sources-Operating) are lost Based on the above conditions which ONE of the following describes ...
1) actions required byTech
1) 3.8.1 ?

Spec3.8.1 by Tech Spec AND

2) a condition that would require manually separating BOTH KHUs KHU's from the electrical grid in accordance with AP/34?

A. Immediately enter Tech Spec LCO 3.0.3 I/ KHU High Generator Output Voltage B. Immediately enter Tech Spec LCO 3.0.3 I/ KHU Low Generator Output Voltage C. Energize BOTH Standby Busses within one hour I/ KHU High Generator Output Voltage D. Energize BOTH Standby Busses within one hour I/ KHU Low Generator Output Voltage

2010A 2010A NRC OPERATOR EXAM NRC REACTOR OPERATOR EXAM 11 POINT POINT Question 17 17 Unit 11 initial conditions:

  • Reactor power == 100% 100%
  • lCHPlpumpOOS 1C HPI pump OOS Current conditions:
  • 1A 1A and lB Main FDW pumps tripped 1B Main
  • Condensate Booster Pumps unavailable
  • All EFDW pumps unavailable
  • 1 1AA and 1 B SG Outlet pressure == 860 psig slowly decreasing lB
  • RCS pressure == 2317 psig increasing Based on the above conditions, which ONE of the following describes describes the required operator action(s) in accordance with the EOP?

A. Establish SSF ASW flow to the SG and establish SG levels at 240 inches.

B. Establish SSF ASW flow to the SG and do NOT establish a level in the SGs.

SG5.

C. Establish HPI forced cooling and open 1 IHP-410.

HP-41 O.

D. Establish HPI forced cooling and open 1IHP-409.

HP-409.

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 18 Unit 1I initial conditions:

  • Reactor power = = 100%
  • 1 lAMSLBoccurs A MSLB occurs Current conditions:
  • Reactor has tripped
  • RCS Tave = 544T slowly increasing

= 544°F

  • 1 1A A SG Pressure = 0 psig
  • 11 B SG Pressure = = 990 psig slowly increasing
  • Reactor Building pressure = = 0.2 psig stable Based on the above conditions, which ONE of the following describes the status of the TDEFWP and how subsequent operation of the TDEFWP would be performed?

TDEFWP is is...

A. operating and can be secured with TDEFWP control switch before AFIS is reset B. operating and can be secured with TDEFWP control switch ONLY after AFIS is reset C. NOT operating and can be started with TDEFWP control switch before AFIS is reset D. NOT operating and can be started with TDEFWP control switch ONLY after AFIS is reset

2010A NRC 2010A OPERATOR EXAM REACTOR OPERATOR NRC REACTOR EXAM I1 POINT POINT Question 19 Question 19 Unit 11 plant Unit plant conditions:

  • Reactor power 70% stable power == 70% stable level == 210
  • Pressurizer level slowly decreasing 210" slowly decreasing

(RC VOLUME HP-i 20 (RC failed closed CONTROL) failed AP/14 (Loss of

  • AP/i4 Normal HPI of Normal Makeup and/or RCP HPI Makeup RCP Seal Injection) initiated Seal Injection) initiated Based on Based on the above conditions, which ONE ONE of the following describes of the initial actions describes the initial required toto control control Pressurizer AND the minimum allowed Pressurizer level level AND Pressurizer level level in accordance with AP/i4?

(inches) in AP/14?

Throttle ...

Throttle...

1HP-26 I/ 200 A. 1HP-26 200 B. 1 HP-26 I/ 80 1HP-26 C. 1 HP-122 (RC VOLUME CONTROL BYPASS) I/ 200 IHP-i22(RC D. 1 HP-i 22 (RC VOLUME CONTROL BYPASS I/ 80 1 HP-122

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 20 I initial conditions:

Unit 1

  • Reactor in MODE 6 Current conditions:
  • Fuel Transfer Canal level decreasing
  • East fuel carriage is in the RB and empty
  • West fuel carriage is in the SFP and empty
  • Reactor Building Main Fuel Bridge in transit to the upender with a spent fuel assembly in the mast
  • Section 40 4D (Fuel Transfer Canal Flooded) of AP126 AP/26 (Loss of Decay Heat Removal) initiated fit actions Based on the conditions above, which ONE of the following describes the first required to be taken in accordance with Section 40 4D (Fuel Transfer Canal Flooded)?

A. Close 1 I SF-1 SF-i and 1I SF-2 (East/West Transfer Tube Isolations)

B. Verify SF system aligned for refueling cooling mode and stop 2B SF cooling pump C. Place the fuel assembly into the East Upender and position the West Fuel Carriage to the RB D. Place the fuel assembly into the East Upender and position the East Fuel Carriage to the SFP

2010A NRC 2010A OPERATOR EXAM REACTOR OPERATOR NRC REACTOR EXAM 11 POINT POINT Question 21 Question 21 Which ONE Which ONE of of the conditions that describes conditions the following describes indicate RIA-54 that indicate RIA-54 is unable to is unable to perform its perform its function function AND releases are batch releases AND ifif batch allowed while are allowed RIA is while the RIA is inoperable?

inoperable?

A. Counts A. Counts dodo not not increase increase when Source Check when Source Check is performed II Batch is performed releases are Batch releases are allowed.

allowed.

B. Counts B. Counts dodo not increase when not increase when Source Check is Source Check performed I Batch releases are is performed are NOT NOT allowed.

allowed.

C. Sample pumppump found OFF Batch releases are allowed.

OFF I Batch Sample pump found OFF I Batch releases are NOT D. Sample D. NOT allowed.

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 22 Unit 2 plant conditions:

  • 3 of the 5 fire detectors in the West penetration room will be simultaneously removed for repair and/or replacement Based on the above conditions, which ONE of the following describes the compensatory actions required by SLC 16.9.6 (Fire Detection Instrumentation)?

Within 1 detectors....

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of removing the detectors ....

A. Perform Channel Functional Test on remaining fire detectors ONLY B. Establish a fire watch ONLY C. Perform Channel Functional Test on remaining fire detectors AND stage 4 additional fire extinguishers in the West Penetration Room.

D. Establish a fire watch AND stage 4 additional fire extinguishers in the West Penetration Room.

NRC REACTOR OPERATOR EXAM 2010A NRC 2010A I POINT 1

Question 23 Unit 33 plant conditions:

  • Loop A and Loop B SCM's == 0°F 8 SCMs oaF stable a
  • Core SCM == (-)5°F

(_)5 F flashing with a red background Based on the above conditions, which ONE of the following describes the status of the reactor core?

A. saturated and covered B. saturated and partially uncovered C. superheated and covered D. superheated and partially uncovered

2010A NRC REACTOR OPERATOR EXAM 1

I POINT Question 24 Unit 2 initial conditions:

  • Reactor power = = 100%

Current conditions:

  • 2SA2/B4 (RC AVERAGE TEMP HIGH/LOW) actuated
  • Loop 'A' A Controlling Thot fails high (620°F)

Based on the above conditions, which ONE of the following describes the initial ICS response AND requirements placed on the operator when stabilizing the plant?

ICS will Feedwater flow AND SRO approval required prior to making the initial manual adjustment to Feedwater flow in accordance with OMP 1-18 (Implementation Standard During Abnormal And Emergency Events).

A. increase / is B. increase / is NOT C. decrease / is D. decrease / is NOT

2010A 2010A NRC OPERATOR EXAM NRC REACTOR OPERATOR EXAM I1 POINT POINT Question 25 Unit I1 initial initial conditions:

  • Reactor power == 25% slowly increasing

Current conditions:

  • Reactor power == 22% decreasing decreasing Based on the above conditions, which ONE of the following describes the procedure(s) that will be utilized to direct plant activities AND the expected Steam Generator pressure (psig)?

A. UNPP UNPPtab tab I 885 B. UNPP tab I 1010 C. Plant Operating Procedures I 885 D. Plant Operating Procedures I 1010

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 26 Unft 1I plant conditions:

Unit

  • Reactor power = = 100%
  • 2SA-18/A11 (TURBINE BSMT WATER EMERGENCY HIGH LEVEL) actuated
  • NEO reports water level in Turbine Building basement increasing Based on the above conditions, which ONE of the following describes the required AP/lO0 (Turbine Building Flood)?

actions directed by AP/1 Manually trip the reactor and...

and ...

A. align Station ASW pump for use B. secure all LPSW pumps C. secure all operating CCW pumps D. place all HPSW pump switches to "OFF"OFF

2010A NRC REACTOR OPERATOR EXAM 2010A NRC EXAM I1 POINT POINT Question 27 Unit I1 plant conditions:

Unit

  • Core SCM == 0°F OaF
  • LOCA Cooldown tab in progress CETC's == 395°F slowly decreasing
  • 1 LP-1 03 (POST LOCA BORON DILUTE) will NOT 1LP-103 NOT open Based on the above conditions, which ONE of the following valves is required to be opened in accordance with the LOCA CD tab to establish post LOCA boron dilution dilution flow?

A. 1LP-3 1LP-3 1LP-l9 B. 1LP-19 C. 1LP-104 1LP-I04 D. 1LP-105

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 28 Unit 3 initial conditions:

  • Time = 0300
  • Reactor power = = 100%
  • CT-3 Lockout occurs Current conditions:
  • MFB re-energized
  • 6900V power still unavailable
  • 3A = 3.9 gpm slowly decreasing
  • 3A2 RCP SI flow = = 3.7 gpm slowly decreasing
  • 3B1 RCP SI flow = = 3.5 gpm slowly decreasing
  • 3B2 RCP SI flow = = 3.4 gpm slowly decreasing
  • Seal Inlet Header Flow = 40 gpm stable Based on the above conditions, which ONE of the following describes the status of the following RCP support systems valve(s) two minutes later?

A. ONLY 3HP-21 has closed B. ONLY 3HP-21 AND 3HP-31 have closed C. ONLY ALL individual seal return valves and 3HP-21 have closed D. ALL individual seal return valves, 3HP-21, and 3HP-31 have closed

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 29 1 plant conditions:

Unit 1

  • Reactor power = = 100%

1 CC-8 (CC RETURN PENT (54) OUTSIDE BLOCK) fails closed

  • 1 1 LPSW-6 (UNIT 1I RCP COOLERS SUPPLY) fails closed Based on the above conditions, which ONE of the failed valves will require ALL RCPs to be secured in accordance with AP/16 (Abnormal Reactor Coolant Pump Operation) and why?

1 CC-8 /I due to high RCP motor stator temperatures A. 1 CC-8 /I due to high RCP radial bearing temperatures 1CC-8 B. 1 1 LPSW-6 /I due to high RCP motor stator temperatures C. 1 I LPSW-6 /I due to high RCP radial bearing temperatures D. 1

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 30 Unit 1 I initial conditions:

  • Reactor power = = 100%
  • 1 1A A CC pump operating Current conditions:
  • 1 ICC-7 CC-7 fails closed Based on the above conditions, which ONE of the following describes the expected plant response?

A. Letdown must be manually isolated and NEITHER CC Pump will be operating B. Letdown must be manually isolated and BOTH CC Pumps will be operating C. Letdown will be automatically isolated and NEITHER CC Pump will be operating D. Letdown will be automatically isolated and BOTH CC Pumps will be operating

2010A NRC 2010A NRC REACTOR OPERATOR EXAM REACTOR OPERATOR EXAM I1 POINT POINT Question 31 Question 31 Unit 33 initial Unit initial conditions:

conditions:

Reactor in

  • Reactor in MODE MODE 44
  • LPI LPI DHR DHR alignment for cooldown alignment for in progress cooldown in progress Current conditions:

Current (LPI HOT 3LP-3 (LPI

HOT LEG not open SUCTION) will not open 3LP-12 (3A

  • 3LP-12 (3A LPI COOLER OUTLET) failed closed LPI COOLER closed Based on Based on the above ONE of above conditions, which ONE the following describes the of the the effect of of the ECCS-LPI train availability?

failures on ECCS-LPI 3LP-3 failure The 3LP-3 impact availability and the failure of 3LP-12 impact ECCS-LPI train availability 3LP-12

_ _ impact ECCS-LPI train availability.

A. Does I/ Does B. Does I/ Does NOT NOT C. Does NOT I/ Does D. Does NOT I/ Does NOT

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 32 Unit 11 plant conditions:

  • RCS pressure = = 365 psig
  • An attempt is made to open 1 ILP-1 LP-1 (LPI RETURN BLOCK FROM RCS) 1 LP-1 will open Based on the above conditions, which ONE of the following describes if 1 AND the reason 1 I LP-1 LP-l has an interlock?

A. yes /I prevent overpressurizing LPI suction piping B. yes I/ ensure delta p across 1 I LP-1 LP-I will allow it to open C. No /I prevent overpressurizing LPI suction piping D. No /I ensure delta p across 1 1 LP-1 will allow it to open

2010A NRC REACTOR OPERATOR EXAM 2010A NRC EXAM I1 POINT Question 33 Unit 11 initial initial conditions:

  • Reactor power == 100% 100%

Current conditions:

  • RCS pressure = 1350 psig decreasing

= 1350

  • Reactor Building pressure == 4.8 psig increasing
  • ES Channel 22 did NOT actuate Based on the above conditions, which ONE of the following describes ALL safety injection pumps that have AUTOMATICALLY started?

A. 1A 1A HPI, 1B HPI, 1A LPI, 1B LPI HPI,IBHPI,1ALPI,IBLPI B. 1A IA HPI, 1C 1C HPI, 1A IA LPI, 1B lB LPI C. 1A HPI, 1B lB HPI, 1A LPI ONLY D. 1A HPI, 1A LPI ONLY 1ALPI

NRC REACTOR OPERATOR 2010A NRC 2010A OPERATOR EXAM EXAM I1 POINT POINT Question 34 Unit I1 plant conditions:

  • OP/i/All 103/002, (Filling and Venting RCS) Enclosure 4.14 (Establishing Pzr OP/1/A/1103/002, Steam Bubble And RCS Final Vent) in progress
  • Quench Tank level level == 82 82 inches
  • Quench Tank pressure = 0.5 psig

= 0.5 psig

  • The Pressurizer is is vented toto the Quench Tank for 30 30 minutes minutes Based on the above conditions, which ONE of the following describes describes QT parameters that would indicate that Pzr Steam Bubble Formation is complete?

QT level (inches) QT pressure (psig)

A. 82.1 0.6 B. 84.1 0.6 C. 82.1 2.5 D. 84.1 2.5

NRC REACTOR 2010A NRC 2010A REACTOR OPERATOR EXAM EXAM I1 POINT POINT Question 35 normal power supply to the 1A describes the normal Which ONE of the following describes 1ACC CC pump pump AND the emergency backup source of power that will be supplying the Main Main Feeder Offsite Power due Buses following aa Loss of Offsite to aa Switchyard Isolation?

due to 1XL I/ KHU via A. 1XL via overhead path path B. 1XL I/ KHU via underground path B. 1XL 1XS1 I/ KHU via overhead path C. IXS1 1XS1 I/ KHU via underground path D. 1XS1 D.

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 36 Unit 3 plant conditions:

  • Reactor power = = 100%
  • Channel A AND Channel E narrow range RCS pressure fails HIGH Based on the above conditions, which ONE of the following describes the RPS trip that will trip the reactor AND the RCS pressure that will result in an ES digital channels 1I & 2 actuation?

ASSUME NO OPERATOR ACTIONS A. Variable Low Pressure I/ 1600 1810 B. Variable Low Pressure /I 1810 C. High Pressure I/ 1600 D. High Pressure /I 1810

2010A NRC 2010A REACTOR OPERATOR EXAM NRC REACTOR EXAM I1 POINT POINT Question 37 Unit 22 Unit plant conditions:

  • Reactor power == 100%

100%

  • Pressure Bistable 2B RPS Channel Low RCS Pressure "tripped" state Bistable failed in tripped
  • 2B RPS Channel Channel in "Manual Bypass in Manual Bypass" Current conditions:

Current "Shutdown Bypass

  • 2C RPS Channel inadvertently placed in Shutdown Bypass" Based on the above conditions, which ONE of the following describes the impact (if any) on reactor power and control room alarms?

on With NO additional operator actions, reactor power will be and the associated RPS Channel C statalarm for bistable trip will be actuated.

A. 0% /I Low pressure B. 0% I High pressure 100% I Low pressure C. 100%

D. 100% I/ High pressure

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 38 Which ONE of the following would result in a trip of the 11 D RPS Channel AND the 11 D CRD Breaker?

A. Reactor Building pressure bistables in the 1AIA and 1I B RPS channels fail in the "tripped" tripped state tripped state B. Reactor Building pressure bistable in the 11 D RPS channel fails in the "tripped" C. RC pressure test module for 1I D RPS channel placed in "Test Operate Test Operate" D. Loss of the 11KVID KVID panelboard

NRC REACTOR OPERATOR EXAM 2010A NRC 2010A I1 POINT Question 39 Unit 22 initial initial conditions:

  • Reactor power == 100% 100%

Current conditions:

Current

  • MSLBMSLB occurs occurs pressure == 1580
  • RCS pressure slowly increasing 1580 psig slowly
  • RB peak pressure pressure == 2.8 psig Based on the above conditions, which ONE of the following describes valves that have received aa signal to CLOSE?

A. 2CC-7 B. 2LWD-1 c.

C. 2LPSW-6 D. 2LPSW-1062

2010A NRC 2010A NRC REACTOR OPERATOR EXAM REACTOR OPERATOR EXAM I1 POINT Question 40 Unit 33 plant conditions:

  • Reactor power=

power = 100%

100%

  • breaker trips OPEN 3KVIA AC Vital Power Panelboard supply breaker
  • "C" WR ES Analog Channel C RCS pressure signal fails LOW pressure signal Based on the above conditions, which ONE of Based of the following describes which (if any) ES ES digital channels have actuated?

digital

- - - - have actuated.

A. NO channels B. Channels 11 thru 4 C. ONLY channels 2 AND 4 D. ONLY channels 1 1 AND 3

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 41 iplant Unit 1 plant conditions:

  • Time = 03:00
  • Reactor power = = 100%
  • 1 lB and 1IC Band C RBCUs operating in HIGH speed
  • ES channels 1-6 actuate Based on the above conditions, which ONE of the following describes RBCU status at 03:02?

A. 1B lB and 1C RBCUs operating in HIGH speed and 1A RBCU OFF B. 1lB

8. and C RBCUs Band RBCU5 operating in LOW speed and 11A A RBCU OFF C. ALL RBCUs RBCU5 operating in LOW speed D. ALL RBCUs will be OFF

2010A NRC REACTOR OPERATOR EXAM 2010A NRC EXAM I1 POINT POINT Question 42 Question Which ONE of the following describes the range of BWST BWST levels where RBS pump pump suction would be aligned to both the RBES and the BWST simultaneously AND what action(s) would be required if 11 LP-22 failed to close when isolating the BWST?

BWST?

When performing Enclosure 5. 12 12 (ECCS Suction suction sources Suction Swap to RBES) both suction are aligned when BWST level are level is between (feet) AND _ _ _ __

15 - 9 I/ stop the lB A. 159 1B LPI pump AND 1 lBB RBS pump B. 15 159- 9 I/ Maximize total LPI flow << 3100 gpm 9 - 6 I/ stop the 1 C. 9-6 B LPI pump AND lB lB 1B RBS pump D. 99 - 6 I/ Maximize total LPI flow <

- < 3100 gpm

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 43 Unit 3 initial conditions:

  • Reactor power = = 35% slowly increasing Current conditions:
  • Reactor power = = 30% decreasing
  • PCB 58 and PCB-59 (Unit 3 Generator Output Bkrs) OPEN
  • Turbine master in HAND O3X2060 (ICS TURBINE LOADING STATUS) = FALSE
  • OAC point 03X2060 Based on the above conditions, which ONE of the following describes the operation of the Turbine Bypass Valves (TBV's)?

(TBVs)?

____ is being compared to Turbine Header Pressure setpoint to develop the TBVs are controlling at controlling error signal AND TBV's psig?

A. Turbine Header Pressure /I 885 B. Turbine Header Pressure /I 935 C. Steam Generator Outlet Pressure /I 885 D. Steam Generator Outlet Pressure /I 935

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 44 Unit 11 initial conditions:

  • Reactor power = = 70% stable Current conditions:
  • 1 1HPE-6 HPE-6 (Heater 1A1 IA1 Bleed Inlet) closed Based on the above conditions, which ONE of the following predicts the impact of the malfunction on Feedwater flow assuming no operator action AND the procedure which will be used to reopen 1IHPE-6?

HPE-6?

Feedwater flow will stabilize at a _ ____:_--- value than the pre-transient level AND

____ will be used to reopen 1 I HPE-6.

0P111A11106123 (High and Low Pressure Extraction)

A. higher /I OP/1/A/1106/23 B. higher I/ OP/1/A/1106/002 OPI1/A111061002 (Condensate and FDW system)

C. lower I/ OP/1/A/1106/23 (High and Low Pressure Extraction)

D. lower /I OP/1/A/1106/002 (Condensate and FDW system)

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 45 Unit 11 initial conditions:

  • Reactor power = = 100%

Current conditions:

  • 1 1 FDW-33 (1A(IA SU FDW Block) FAILS closed Based on the above conditions, which ONE of the following describes the expected Steam Generator levels 20 minutes after the trip?

ASSUME NO OPERATOR ACTIONS 1A SG level =

___ AND 1B lB SG level

= ___

A 25" A. 25 StuS/U t/ 25" 25 StU S/U 8.

B 12" 12 StUS/U t/ 25" 25 StU S/U C. 30 XSUR t/ 25" C 30" S/U 25 StU D. 30" XSUR t/ 30" 30XSUR XSUR 30XSUR

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 46 Unit 11 initial conditions:

  • Reactor power = = 100%
  • Unit 1 I TDEFWP unavailable Current conditions:
  • Both Main FDW pumps trip
  • 1BI B MDEFWP fails to start Based on the above conditions, which ONE of the following describes actions directed by the EOP to remove core decay heat?

Initiate...

Initiate ...

A. Rule 3 (Loss of Main or Emergency Feedwater) and cross connect with an alternate unit to supply the 1B 1 B Steam Generator B. Rule 3 (Loss of Main or Emergency Feedwater) to decrease SG pressure and feed with Condensate Booster pumps C. Rule 4 (Initiation of HPI Forced Cooling) if RCS pressure reaches 2300 psig D. EOP Encl. End. 5.9 (Extended EFDW Operation) and feed both SG's SGs with 1A MDEFWP

2010A NRC 2010A REACTOR OPERATOR EXAM NRC REACTOR I1 POINT Question 47 Which ONE of the following describes actions required that will extend the life of the Control Batteries following aa loss of all AC power in accordance with FOP EOP Enclosure 5.38 (Restoration of Power)?

Load Shed Shed the inverter.

A.Kl A. KI B.DIA B. DIA C. KSF-1 D. KOAC

2010A NRC 2010A NRC REACTOR OPERATOR EXAM REACTOR OPERATOR EXAM I1 POINT POINT Question 48 Question 48 Which ONE Which ONE ofof the describes the the following describes the normal alignment of normal alignment the Power of the Power Battery Battery busses AND a condition in which SLC busses AND a condition in which SLC 16.8.316.8.3 (Power (Power Battery Battery Parameters)

Parameters) would require would require changing that changing that alignment?

alignment?

Oconee units are normally The Oconee normally ____ and and this would be changed ifif _ _ __

be changed cross-tied I/ aa single power battery A. cross-tied becomes inoperable battery becomes B. cross-tied I/ two or more batteries simultaneously become inoperable more power batteries inoperable C. separated I/ aa single power battery becomes inoperable separated I/ two or more power batteries simultaneously become inoperable D. separated

NRC REACTOR OPERATOR 2010A NRC 2010A OPERATOR EXAM EXAM I1 POINT POINT Question 49 Question Operators are preparing to synchronize KHU-2 to the grid in accordance with OP/O/A/1106/019, OP/OIAI1 Hydro At Oconee) 106/019, (Keowee Hydro The notes the following indications:

The operator notes indications:

  • Grid Frequency == 59.9 59.9 cycles
  • Keowee Keowee Frequency = 60.3 cycles

=

  • Keowee 2 Line =

Line Volts = 13.7 13.7 kV

  • Keowee 22 Output Volts == 15.2 15.2 kV Based onon the above conditions, which ONE of of the following describes the control that will be used to adjust the synchroscope indication and after ACB-2 is closed, generator output should be adjusted to  ?

The used to adjust the synchroscope indication AND generator output will be used should be adjusted to MWs.

A. UNIT 2 AUTO VOLTAGE ADJUSTER I 0 UNIT2AUTOVOLTAGEADJUSTER B. UNIT 2 SPEED CHANGER MOTOR I 0 C. UNIT 2 AUTO VOLTAGE ADJUSTER /10 UNIT2AUTO I 10 D. UNIT 2 SPEED CHANGER MOTOR I 10

2010A NRC REACTOR OPERATOR EXAM 1I POINT Question 50 Unit 1 1 conditions:

Time = 1159:40 1159:40

  • Reactor power == 100% stable
  • KHU-1 OOS KHU-100S
  • ACB-4 closed
  • KHU-2 gets Emergency Start signal from another unit Time == 1200:00
  • KHU-2 speed reaches 190 RPM Time = 1200:30

= 1200:30

  • KHKHU-2 U-2 speed = 190 RPM Based on the above conditions, which ONE of the following describes the status of reciuired by Unit 11 (if any) as a result of that status?

KHU-2 and the procedural actions required A. Emergency locked out / Enter LCO 3.0.3 immediately B. Emergency locked out /I Energize BOTH Standby Buses within 1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. Energizing CT-4 I/ No additional actions required D. Energizing CT-4 / Energize EITHER Standby Bus within 1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 51 Unit 1 1 initial conditions:

Time=1200

  • Time = 1200
  • Reactor power = = 35%

IA = 2.1 gpd stable

  • RCS activity = pCi/mi DEI

= 0.25 IJCi/ml DEl increasing Current conditions:

  • Time Time=1400

= 1400

  • NO change in 1A SG tube leak rate
  • RCS activity = = 0.65 IJCi/ml DEl and increasing pCi/mI DEI Based on the above conditions, which ONE of the following describes the response of the radiation monitors between 1200 and 1400?

A. 1IRIA-16 RIA-16 (Main Steam Line Monitor) and 1 1R1A-40 RIA-40 (CSAE Off-gas) increased.

B. 1RIA-16 IRIA-40 (CSAE Off-gas)

IRIA-16 (Main Steam Line Monitor) increased while 1RIA-40 remained constant.

C. 1 RIA-59 (N-16 monitor) and 1 IRIA-59 IRIA-40 RIA-40 (CSAE Off-gas) increased.

D. 11RIA-59 RIA-59 (N-16 monitor) increased while1whilelRlA-40 RIA-40 (CSAE Off-gas) remained constant.

2010A 2010A NRCNRC REACTOR OPERATOR EXAM EXAM I1 POINT POINT Question 52 Unit 1 initial conditions:

I initial

  • Time=1200 Time = 1200 power = 100%
  • Reactor power= 100%
  • A andand B B LPSW Pumps operating operating
  • C C LPSW pump in in AUTO Blackout Occurs
  • Blackout Current conditions:
  • Time=1230 Time = 1230
  • Both MFBsMFB's re-energized Based on the above conditions, which ONE of the following describes the status of the C LPSW pump 5 seconds after the MFBs MFB's have re-energized AND the system that will require the use of OP/1 IA/11 04/01 0 (Low Pressure Service Water) to return it to service OP/i /A/1104/0i0 once LPSW pressure has been restored?

A. operating 1 I Reactor Building Aux Coolers B. operating 1 I RBCU's RBCUs C. NOT operating 1 C. / Reactor Building Aux Coolers D. NOT operating 1 RBCUs I RBCU's

NRC REACTOR OPERATOR 2010A NRC 2010A OPERATOR EXAM I1 POINT Question 53 Initial plant conditions:

  • Large IA IA leak occurs
  • pressure == 87 psig decreasing Service air header pressure
  • Building air header pressure per gage below Turbine Building TlJRS TURB BLDG 160 160 ==

140 140 ==

120 120 ==

100 100 -

- ~==

80 80 -

60 60 -

40 40 20 20 PSI PSI o0 Based on the above conditions, which ONE of the following describes the air compressors that will be operating?

The Primary IA Compressor AND ...

AND...

A. Diesel Air Compressors ONLY B. Diesel Air Compressors AND AlA Compressors ONLY C. AlA Compressors AND Backup IA Compressors ONLY D. Backup IA Compressors ONLY

2010A NRC REACTOR OPERATOR EXAM 1I POINT Question 54 Unit 2 initial conditions:

  • Reactor power = = 100%
  • 2HP-5 failed closed Current conditions:
  • Operator dispatched to manually open 2HP-5
  • Pressurizer level 245 inches slowly increasing Based on the above conditions, which ONE of the following describes actions required in accordance with AP/32 (Loss of Letdown) AND the MINIMUM Pressurizer level (inches) at which a manual reactor trip would be required?

A. Maintain constant communication with operator dispatched to open 2HP-5 400 B. Maintain constant communication with operator dispatched to open 2HP-5 380 C. Initiate unit shutdown at =20%/min 20%/min per AP/29 (Rapid Unit Shutdown) 400 20%/min per AP/29 (Rapid Unit Shutdown)

D. Initiate unit shutdown at =20%/min 380

NRC REACTOR OPERATOR EXAM 2010A NRC 2010A I1 POINT POINT Question 55 Unit 33 initial Unit initial conditions:

  • 3CC-8 has has been manually opened due loss of air to the valve due to loss Current conditions:
  • Instrument air has been restored to 3CC-8 3CC-8 remains manually open
  • 3CC-8 Based on the above conditions, which ONE of the following describes whether 3CC-8 3CC-8's response to an ES 1-6 can be operated from the control room and 3CC-8s 1-6 actuation?

3CC-8 _ _be operated from the control room and 3CC-8 ___ automatically close.

A. can I/ will B. can I/ will NOT C. can NOT I/ will D. can NOT I/ will NOT

2010A NRC 2010A OPERATOR EXAM NRC REACTOR OPERATOR EXAM I1 POINT Question 56 Unit 1 Unit I initial conditions:

  • 100%

100% power

  • 450 EFPD Based on the above conditions, which ONE of the following events is the cause of the indications on the attached PIT display?

ASSUME NO OPERATOR ACTIONS A. SBLOCA B. LBLOCA C. MSLB D. Loss of MFDW LossofMFDW

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 57 Which ONE of the following is the power supply for the Unit 11 Group B Pressurizer heaters?

IXH A. 1XH B. 1XI C. 1XS1 1XSI D. 1XSF

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 58 Which ONE of the following describes who determines that a RB Continuous Release is allowed and after it is started what are the requirements for sampling the RB 0P111021014 (RB Purge System)?

atmosphere in accordance with OP/1102/014 A. CRSRO I/ Release may continue indefinitely after initial 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> without submitting daily sample requests.

B. CRSRO /I Release may continue indefinitely provided RP assigns a new GWR number and sample results are entered in the Unit Log every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

C. Shift RP I/ Release may continue indefinitely after initial 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> without submitting daily sample requests.

D. Shift RP /I Release may continue indefinitely provided RP assigns a new GWR number and sample results are entered in the Unit Log every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 59 Plant conditions:

  • Spent Fuel Storage Cask has been dropped in Unit 1 1&2

&2 SFP

  • Spent Fuel damage is visible
  • RIA-6 and RIA-41 HIGH alarm actuates
  • Spent Fuel Pool level = -3.5 feet decreasing Based on the above conditions, which ONE of the following describes which filters will be used to reduce off site releases and the status of the SF Pumps?

Unit Reactor Building Purge filters and the Spent Fuel Cooling pumps will be A.1 A. 1 /ION ON 1 I/ OFF B. 1 C.

C.22 ION

/ ON D. 2 I/ OFF

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 60 Unit 2 initial conditions:

  • Reactor power = 100%

Current conditions:

  • Controlling 2A Steam Generator Outlet Pressure fails HIGH Based on the above conditions, which ONE of the following describes the 2A AND 2B (TBVs) response?

Turbine Bypass Valves (TBV's)

The 2A TBV's TBVs will fully open _ _ AND the 2B TBV's TBVs will fully open _ _

A. then return to throttled position / then return to throttled position B. then return to throttled position / and remain fully open C. and remain fully open / then return to throttled position D. and remain fully open I/ and remain fully open

2010A NRC REACTOR OPERATOR EXAM 1 POINT 1

Question 61 Unit 3 initial conditions:

  • power== 100%

Reactor power 100%

  • SSRHs) are open and in AUTO 3MS-77, 78, 80, 81 (MS to SSRH's)

Current conditions:

  • Reactor trips Based on the above conditions, which ONE of the following describes the plant response?

A. 3MS-112, 3MS-173, 3MS-77, 3MS-78, 3MS-80, and 3MS-81 close 3MS-1 12 & 3MS-173 close AND 3MS-77, 78,80, B. 3MS-112 78, 80, and 81 remain open 3MS-1 12 & 3MS-173 remains open AND 3MS-77, 78, 80, and 81 close C. 3MS-112 D. 3MS-112, 3MS-173, 3MS-77, 3MS-78, 3MS-80, and 3MS-81 remain open

2010A OPERATOR EXAM 2010A NRC REACTOR OPERATOR EXAM 1I POINT POINT Question 62 Unit 11 plant conditions:

  • OP/1/A OP/i/A 1106/002A i 106/002A (Condensate And FDW System Startup And Shutdown) Encl. End.

42 (Condensate And FDW System Startup) in progress 4.2

  • 1iA A Hotwell pump (HWP) operating
  • CBP suction pressure = 45 psig slowly decreasing
  • The 3 square amber lights located above the HWP HWP PUMP PUMP AMP gages are "ON" ON Procedure directs placing a standby Hotwell
  • Procedure Hotwell pump to "AUTO" AUTO Based on the above conditions, which ONE of the following describes what the Hotwell pump amber lights indicate AND the 1lB B Hotwell pump response once the control switch is placed in AUTO?

1iAA Hotwell pump is operating with _ _ and the 1lB B Hotwell pump _ _ automatically start when its control switch is placed in Auto.

A. low suction pressure /I will B. low discharge pressure /I will C. low suction pressure /I will NOT D. low discharge pressure /I will NOT qB' ~

c.J . . . .. . .. , ",

. 1

.\ \t 4

Pk;MP AMPS HNP PUMP HVVP 1A 18 IC lC

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 63 Unit 3 plant conditions:

  • Reactor power = 100%

= 100%

  • Fuel movement in progress in SFP
  • 3RIA-6 (Spent Fuel Pool) in HIGH alarm Based on the above conditions, which ONE of the following describes action(s) that will occur?

A. 3RIA-6 audible alarm will automatically sound.

B. the Spent Fuel Pool Ventilation system will be automatically isolated.

C. the Spent Fuel Filtered Exhaust fans will be manually started from the Control Room.

D. the Outside Air Booster Fans will be manually started from the Spent Fuel Pool entrance area.

2010A NRC 2010A NRC REACTOR OPERATOR OPERATOR EXAM EXAM I1 POINT POINT Question 64 IAPressurevs.Time IA Pressure vs. Time 100~-----------------------------------------'

100 w

uJ 90 .... .. ... . . . . . .. .... .. ... .. :... ... .... ... ... .. . .. . ... .. : ..... ... .. .. .. . . .. . . ... . .. . .

0:::

J D

(f)

C))

(f)

C?)

W LU 0:::

0..

U

<t: 80 . .. .. . . . . .. . .. ... ... . . .. .. . .... .... .. ... ..... .. ..........

~

70~----~~-----4-------+------~------------~

1200 1210 1220 1230 ii rvl E TIME Based on the graph above, which ONE of the following describes the time at which SA- SA 141 (SA to IA Controller) will automatically open?

A. 1207 B. 1210 C. 1212 D. 1215

2010A NRC 2010A NRC REACTOR REACTOROPERATOR OPERATOR EXAM EXAM POINT 1I POINT Question 65 Question 65 Unit 33 initial Unit initial conditions:

conditions:

  • Reactor power
  • Reactor power == 100%

100%

  • Fire in progress
  • Fire in progress in area in area of of 3TE 3TE switchgear switchgear Current conditions:

Current conditions:

    • 3TE 3TE busbus isis grounded grounded duedue to to water water spray spray
  • Relay
  • Relay 51 51G actuated G actuated Based on Based on the the above above conditions, conditions, which which ONE ONE ofof the the following following lists lists ONLY ONLY components components that that remain available?

remain available?

A. 3A A. 3A MDEFDWP, MDEFDWP, 3B 3B MDEFDWP MDEFDWP B. 3A B. 3A MDEFDWP, MDEFDWP, 3C HPIP 3C HPIP C. 3C C. LPIP, 3B 3C LPIP, 3B MDEFDWP MDEFDWP D. 3C LPIP, 3C HPIP D. HPIP

2010A NRC REACTOR OPERATOR 2010A NRC OPERATOR EXAM EXAM I1 POINT POINT Question 66 Unit 22 plant conditions:

  • Reactor in MODE 66
  • RCS Boron == 2270 ppmb Based on the above conditions, which ONE of the following describes whether RCS Based meets the requirements of OP/2/AI1 Boron concentration meets 502/007 (Operations OP/2/A/1502/007 (Operations number of OPERABLE Responsibilities) AND what is the minimum number Defueling/Refueling Responsibilities)

Source Range NIsNl's required by the same procedure?

A. meets I/ 22 B. meets /I 1 1 C. does NOT meet /I 22 D. does NOT meet I/ 1 I

2010A NRC REACTOR OPERATOR EXAM EXAM 1I POINT Question 67 Unit 1I initial conditions:

  • Reactor power = 100%

LDST level =

  • LOST 75 stable

= 75"

  • Group 7 rod position = = 94% withdrawn
  • Makeup to LOST LDST initiated from 1lB B BHUT
    • Neutron error = = 0 stable Current conditions:

HP-i 5 Bailey controller indicates 470 gallons added to LOST

  • 11 HP-15 LDST
  • 11 B Bleed Transfer Pump secured Based on the above conditions, which ONE of the following would describe a diverse indication that 470 gallons of 1I B BHUT had been added to the LOST?

LDST?

LDST level is approximately ____ inches and neutron error will become _ _ __

LOST A. 90 I positive B. 90 I negative C. 95 I positive D. 95 I negative O.

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 68 Which ONE of the following states the RCS Pressure Safety Limit (psig) AND which of the listed items is credited with ensuring the limit is NOT exceeded?

A. 2500 I/ RPS trip settings B. 2500 I/ PORV C. 2750 I/ RPS trip settings.

D. 2750 I/ PORV

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 69 1 plant conditions:

Unit 1

  • Reactor power = 100%

= 100%

  • 1AIA Core Flood Tank parameters:

o Pressure = = 572 psig stable o Level = = 12. 91 feet o Boron Concentration = = 2010 ppmb

  • 1 I B Core Flood Tank parameters:

o Pressure = 590 psig stable o Level = 12.51 12.51 feet o Boron Concentration = = 1895 ppmb Based on the above condition, which ONE of the following describes the action(s) required (if any) in accordance with Tech Spec 3.5.1 (Core Flood Tanks)?

A. NO actions required B. Enter LCO 3.0.3 immediately C. Restore 1 1A A CFT to OPERABLE within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> ONLY D. Restore 1 IB B CFT to OPERABLE within 1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ONLY

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 70 Unit 1 I plant conditions:

  • Reactor power = = 100%

Based on the above condition, which ONE of the following describes a condition that would require entry into a Tech Spec ACTIONS table?

A. UST level ==5.6 5.6 feet B. BWST level == 47.3 feet C. 1 I D RPS channel in Manual bypass D. 230KV Dacus Black and White lines isolated

2010A NRC REACTOR OPERATOR EXAM 1

I POINT Question 71 Unit 1 1 plant conditions:

  • Reactor in MODE 5 ReactorinMODE5
  • Reactor Building Main Purge in operation Based on the above conditions, which ONE of the following will cause the RB Purge fan to trip?

A. Inadvertent actuation of ES Channel 5 B. 1 I RIA-45 reaches ALERT setpoint C. Suction piping pressure = = 5 inches of water vacuum D. 1I PR-3 (RB PURGE CONTROL) closed

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 72 Unit 11 plant conditions:

  • Reactor in MODE 6 IA LPI pump
  • Fuel movement in progress
  • NI-3 and 4 SR out of service
  • RB Purge in progress Based on the above conditions, which ONE of the following describes when Reactor Building evacuation is required?

A. 1I NI-2 Nl-2 SR fails low B. 1IRIA-4 RIA-4 HIGH alarm C. 1IRIA-45 RIA-45 HIGH alarm D. 11 NI-2 Nl-2 WR fails high

2010A NRC 2010A OPERATOR EXAM NRC REACTOR OPERATOR EXAM I1 POINT POINT Question 73 ONE of the following describes the required response For Operations personnel, which ONE to an Electronic Electronic Dosimeter dose alarm and when it isis acceptable to deviate from that requirement?

immediately and A. Exit the area immediately RP /I with RP permission and contact RP immediately and contact RP /I with emergency dose limits in effect B. Exit the area immediately B.

C. Move away from the area until alarm clears I/ with RP permission D. Move away from the area until alarm clears /I with emergency dose limits in effect

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 74 1 plant conditions:

Unit 1

  • Blackout tab in progress Initiate AP/1
  • EOP step gives direction to "Initiate AP/11I (Recovery From Loss of Power)"

Power)

Based on the above conditions, which ONE of the following describes the actions required to perform the EOP step?

A. RO will perform AP/11 AP/1 I and SRO will wait until AP/11 AP/1 1 has been completed to continue in the EOP.

B. SRO will direct steps in AP/l AP/111 and then return to the EOP once AP/1 AP/11I is complete.

AP/1 I actions. SRO will continue in the EOP. SRO can re-direct RO C. RO will begin AP/11 actions.

D. RO will begin AP/1 AP/11I actions. SRO will continue in the EOP. RO must remain in AP/1 1 until the procedure is complete.

AP/11

2010A NRC REACTOR OPERATOR EXAM I POINT 1

Question 75 1 plant conditions:

Unit 1

  • Reactor power = = 100%

1SA3IB6 (FIRE ALARM) actuated

  • 1SA3/B6
  • Fire Alarm panel indication o point 0202071 (Unit 1 I pipe trench room 348 north end) actuated Based on the above conditions, which ONE of the following describes who will be dispatched to the Unit 11 pipe trench room 348 per the Alarm Response Guide to determine the validity of the alarm AND a method used in RP/10001029 RP/1000/029 (Fire Brigade Response) to dispatch the fire brigade when it is required?

A. A Fire Brigade qualified operator 1 I Plant Paging system B. A Fire Brigade qualified operator 1 I Have Security dispatch fire brigade C. The Unit 11 BOP Reactor Operator 1 I Plant Paging system D. The Unit 1I BOP Reactor Operator 1 I Have Security dispatch fire brigade

Oconee Ocone e 2010-301 2010*301 Exam Exam Refere nces References RO Exam:

Steam Tables Unit 1 Unit 1 Loop A Narrow Range Plot Range PT Plot SRO Exam:

RP/O/8/10001001 RP/O/B/1000 /OO1 (Emergency Classification))

(Emergency Classification Technical Specification (TIS) (Pressurizer)

(T/S) 3.4.9 (Pressurizer)

TIS T/S 3.8.8 (Distribution System Systemss -

Operating)

Response Guide 11SA-03 Alarm Response B-6 pages 2-28.

SA-03 8-6

Exam Question # 56 UNIT 1 LOOP A NARROW RANGE PT PLOT 1

JcLj Main Alarms Graphics Trends F List Zoom Print Help 1QOCT-2003 09 [1 *ls

[1 FT tIN Ei 01 TURN ON 0L[ F TLMJk -$PT NI IIOIAIEr I.

[

119% IFOkI 10 LOOP A - IF_I

[

- - ii 1 t 25O0 A

2500-

- F - -Il ID II 11:11 I 2400

.5 I R E1 L[VEL

.5 2300-- 7 / )

5 1 INCH E .7

/ EC EINCH S

v *. IIITL [Fl U .JOO p I II

..ooo E $ I 5 ,.

1900 0.2 I i6

//

p 00-

- I I I- I I I

Ill I INCII I __

7 / 7 ./ 7 rH INCH 1 1. 0 S 7 /

  • v /

C H / 7 / P LLrI IE.LF I 1 4 1 INCH I -iso I 0 WI I I I I I I I I 0U 55 650 00 51 DEGF TH [HELJ S5 DEGF I J 5 [EOF U 14IIFI NR r

4 E TEMPEIA I URE DEGI LR CORE CUll. ET TEMF 950 DEGJ S t T TEMP 448 DEGF -.

I I II it, I UI II lilt IL I Ft 1 F I t TUE E I It I F OT 9 DFtI TH I NI I LI I T I oN ro lIE C\N( Fl 111 [. - [I r

J 1=

TTO1O WK= AN0NYIUS SEC LVL= 15 PR Ocoriee Sim C I

OConee ZO~O -301 C

rn 1

>w>>o Q# KEY 1 B 2 0 3 A 4 0 5

(3) A 6

0) 0 7 B 8

CO B 9

(0 A B

0 0 03 C 0) 0 Cl > 0 Cl Cl Cl > 03 0 > 03 10

..I 11 - A 12 C 13 B 14 A 15(31 0 16CO 0 17-1 0 18CO C 19(0 A 200 0 21 - C 22 B 23L.3 0 24 B 25(31 C 26CO C 27-4 0 28CO 0 C) 0) C D> > 0) > > C) 0 0 29D C 30C C 31 C 32r A 33C.5 A 34 .. B 35 A 36CO A 37-4 0 38CO 0 39 B 40 C 41 0 C) 0 0 42 C 43 C 44 C 45 0 46CO 0 A

C) > 03 0) 0>

47-.1 48CO C 49 B 50 B 51 A 52 C 53 0 54 B 0)

~ joi 0

OConee 2010-301 c\J 0 0

Q# KEY (51 0) C 56 UI 57 0 (Ii 58 C) C 01 59 C) 0 0) 60 0 C C) 61 -

A C) 62 1%) B C) 63

(.3 A C) .

0 64 C) 65 Ui B C) 66

0) A C) 67

-1 B C) 68 C) C C) 69 C) B 4

70 0 A

-1 71 0

-4 72t) B 4

73W B

4 74 C 75UI A

Retrieved from "https://kanterella.com/w/index.php?title=ML101310324&oldid=2558064"