ML101310324

Initial Exam 2010-301 Final RO Written Exam

ML101310324
Person / Time
Site:	Oconee
Issue date:	05/04/2010
From:	NRC/RGN-II
To:	Duke Energy Carolinas
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Download: ML101310324 (80)

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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 III El IV El Reactor Type: W El CE El BW GE 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.

I have neither given nor received aid.

Applicants Signature Results Examination Value 75 Points Applicants Score Points Applicants Grade Percent ES-401 Name:

Date: 04/07/2010 Site-Specific RO Written Examination Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Facility/Unit: Oconee Form ES-401-7 Region:

IDIIIg] III D IV D Reactor Type: W D CE D BW ~ GE D 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. I have neither given nor received aid.

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

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

Reactor power = 100%

I RC-66 (PORV) is leaking past its seat Pressurizer temperature = 648 °F Quench tank pressure = 5 psig Based on the above conditions, which ONE of the following describes the expected tailpipe temperature (°F) downstream of I RC-66?

A.

162 B.

228 C.

272 D.

648 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 1 Unit 1 plant conditions:

Reactor power = 100%

1 RC-66 (PORV) is leaking past its seat Pressurizer temperature = 648 of Quench tank pressure = 5 psig Based on the above conditions, which ONE of the following describes the expected tailpipe temperature ("F) downstream of 1 RC-66?

A. 162 B. 228 C. 272 D. 648

2010A NRC REACTOR OPERATOR EXAM I POINT Question 2 Unit I plant conditions:

Reactor Trip SBLOCA has occurred Rule 2 (Loss of SCM) in progress 1A & lB Steam Generator levels = 78 XSUR increasing Cooldown rate = 65°F I %hr Based on the above conditions, which ONE of the following describes...

(1) why SG levels are being increased?

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 1 POINT Question 2 Unit 1 plant conditions:

Reactor Trip SBLOCA has occurred Rule 2 (Loss of SCM) in progress 1 A & 1 B Steam Generator levels = 78" XSUR increasing Cooldown rate = 65°F / Y:zhr Based on the above conditions, which ONE of the following describes...

(1 ) why SG levels are being increased?

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 I POINT Question 3 Unit 1 plant conditions:

Reactor trip from 100% power RCS pressure = 88 psig decreasing Reactor Building pressure = 27 psig increasing 1 B LPI Pump failed to start Based on the above conditions, which ONE of the following describes the guidance provided in EOP Enclosure 5.1 (ES Actuation) regarding the LPI pumps and system operation?

FOP Enclosure 5.1 (ES Actuation)....

A. directs continued operation with only the IA LPI pump and no re-alignment of LPI header flows B. directs continued operation with only the IA LPI pump and manually re-aligns LPI flow down both the 1A and 1 B LPI headers C. utilizes the 1A and the 1C LPI Pump and aligns flow down both headers with 1LP-9 and 10 closed D. utilizes only the 1 C LPI Pump and aligns flow down both headers with I LP-9 & 10 open 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 3 Unit 1 plant conditions:

Reactor trip from 100% power RCS pressure = 88 psig decreasing Reactor Building pressure = 27 psig increasing 1 B LPI Pump failed to start Based on the above conditions, which ONE of the following describes the guidance provided in EOP Enclosure 5.1 (ES Actuation) regarding the LPI pumps and system operation?

EOP Enclosure 5.1 (ES Actuation)....

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

2010A NRC REACTOR OPERATOR EXAM I POINT Question 4 Unit I plant conditions:

Reactor power = 100%

ITA and ITB 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 and Tcold would be approximately A. 534 / 532 B. 570 / 540 C. 556 / 554 D. 585 I 555 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 4 Unit 1 plant conditions:

Reactor power = 100%

1 T A and 1 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 / 555

2010A NRC REACTOR OPERATOR EXAM I POINT Question 5 Unit I initial conditions:

Reactor in MODE 5 RCS pressure = 0 psig Normal LPI decay heat removal in service 1C LPI pump operating Unit Blackout occurs Current conditions:

MFBs re-energized from CT-5 Based on the above conditions, which ONE of the following describes actions required by AP126 (Loss of Decay heat Removal)?

A. Start IC LPI pump AND initiate AP/l I (Recovery from Loss of Power)

B. Start 1 C LPI pump AND initiate the Blackout tab of the EOP C. Feed and steam SCs to maintain CETC <246°F AND initiate AP/l 1 (Recovery from Loss of Power)

D. Feed and steam SGs to maintain CETC <246°F AND perform AP/26 End. 5.6 (Venting LPI Pumps and Suction Lines) 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 5 Unit 1 initial conditions:

Reactor in MODE 5 RCS pressure = 0 psig Normal LPI decay heat removal in service 1 C LPI pump operating Unit Blackout occurs Current conditions:

MFB's re-energized from CT-5 Based on the above conditions, which ONE of the following describes actions required by AP/26 (Loss of Decay heat Removal)?

A. Start 1 C LPI pump AND initiate AP/11 (Recovery from Loss of Power)

B. Start 1 C LPI pump AND initiate the Blackout tab of the EOP C. Feed and steam SG's to maintain CETC < 246°F AND initiate AP/11 (Recovery from Loss of Power)

D. Feed and steam SG's to maintain CETC < 246°F AND perform AP/26 Encl. 5.6 (Venting LPI Pumps and Suction Lines)

2010A NRC REACTOR OPERATOR EXAM I POINT Question 6 Unit I plant conditions:

Reactor trip has just occurred Total RCP seal injection flow = 0 gpm Component Cooling is unavailable Based on the above conditions, which ONE of the following describes the procedure whose performance is directed by the EOP and why?

Initiate...

A. API2O (Loss of CC) to restore Component Cooling B. API2O (Loss of CC) to ensure letdown is isolated C. AP/25 (SSF EOP) to align an alternate letdown flowpath D. AP125 (SSF EOP) to align an alternate source of seal injection 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 6 Unit 1 plant conditions:

Reactor trip has just occurred Total RCP seal injection flow = 0 gpm Component Cooling is unavailable Based on the above conditions, which ONE of the following describes the procedure whose performance is directed by the EOP and why?

Initiate...

A. AP/20 (Loss of CC) to restore Component Cooling B. AP/20 (Loss of CC) to ensure letdown is isolated C. AP/25 (SSF EOP) to align an alternate letdown flowpath D. AP/25 (SSF EOP) to align an alternate source of seal injection

2010A NRC REACTOR OPERATOR EXAM I POINT Question 7 Unit 1 initial conditions:

Reactor power = 90%

1 B Main Feedwater pump trips Current conditions:

Reactor power = 70% decreasing RCS pressure = 2165 psig slowly decreasing Pressurizer level = 228 inches slowly decreasing Pressurizer temperature = 640° F slowly decreasing Pressurizer heater bank I (Group A and K) is ON Pressurizer heater banks 2, 3, and 4 are in AUTO and are OFF Based on the above conditions, which ONE of the following describes the status of the 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 1 POINT Question 7 Unit 1 initial conditions:

Reactor power = 90%

1 B Main Feedwater pump trips Current conditions:

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

The pressurizer is ____ AND the pressurizer saturation circuit ___ _

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

2010A NRC REACTOR OPERATOR EXAM I 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 = 0°F stable Rule 1 (ATWS/Unanticipated Nuclear Power Production) in progress 2SA9/D2 (RC Pump Vibration High ) Actuated Rule 2 (Loss of SCM) initiated Based on the above conditions, which ONE of the following describes the required actions regarding Reactor Coolant Pumps (RCPs) and the reason for those actions?

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

2010A NRC REACTOR OPERATOR EXAM 1 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 stable Rule 1 (ATWS/Unanticipated Nuclear Power Production) in progress 2SA9/D2 (RC Pump Vibration High) Actuated Rule 2 (Loss of SCM) initiated Based on the above conditions, which ONE of the following describes the required actions regarding Reactor Coolant Pumps (RCP's) and the reason for those actions?

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

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

SGTR tab in progress 1 B SC isolated 1A loop Tcold = 440°F decreasing lB SIG TUBE/SHELL DT = (-)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 (1)

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 I B SC / de-energizing Pzr heaters and cycling Pzr spray D. compressive stresses in the lB SC I cycling the PORV 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 9 Unit 1 plant conditions:

SGTR tab in progress 1 B SG isolated 1A loop Tcold = 440°F decreasing 1B S/G TUBE/SHELL DT = (-)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,..) _

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

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

2010A NRC REACTOR OPERATOR EXAM I POINT Question 10 Unit 1 plant conditions:

Both 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 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 10 Unit 1 plant conditions:

Both MFB's 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 / will B. HPSW / will C. CCW / will NOT D. HPSW / will NOT

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

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

A. 1201 I 13.8 B. 1202 I 13.8 C. 1201 I 4.16 D. 1202 / 4.16 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 11 Unit 1 initial conditions:

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

A. 1201 I 13.8 B. 1202 I 13.8 C. 1201 I 4.16 D. 1202 I 4.16

2010A NRC REACTOR OPERATOR EXAM I POINT Question 12 Which ONE of the following would indicate that the 2DIC inverter has experienced a loss of AC output voltage AND how 2KVIC panelboard would then receive power?

A. LOAD CONNECTED TO EMERGENCY light on the inverter will be illuminated AND panelboard 2KVIC will automatically 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 will be de-energized until manually aligned to panelboard 2KRA (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 1 POINT Question 12 Which ONE of the following would indicate that the 2DIC inverter has experienced a loss of AC output voltage AND how 2KVIC panelboard would then receive power?

A. LOAD CONNECTED TO EMERGENCY light on the inverter will be illuminated AND panelboard 2KVIC will automatically 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 panel board will be de-energized until manually aligned to panelboard 2KRA (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 I POINT Question 13 Plant conditions:

1 CA Battery Charger fails

- output voltage = 0 VDC I CA Battery voltage = 126 VDC 1 DCB Bus voltage

= 123 VDC Unit 2 DCA/DCB Bus voltage = 124 VDC Unit 3 DCA/DCB Bus voltage = 127 VDC Based on the above conditions, which ONE of the following will automatically supply power to 1 DIA panelboard?

A. 1DCB Bus B. 1CA Battery C. Unit 2 DC Bus D. Unit 3 DC Bus 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 13 Plant conditions:

1 CA Battery Charger fails - output voltage = 0 VDC 1 CA Battery voltage = 126 VDC 1 DCB Bus voltage

= 123 VDC Unit 2 DCAlDCB Bus voltage = 124 VDC Unit 3 DCAlDCB Bus voltage = 127 VDC Based on the above conditions, which ONE of the following will automatically supply power to 1 DIA panelboard?

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

2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 14 Unit I and 2 initial conditions:

A and B LPSW pump operating Current conditions:

ISA9/A9 (LPSW HEADER A PRESS LOW)

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 / Place the Unit 1/2 STANDBY LPSW PUMP AUTO START CIRCUIT in DISABLE then stop LPSW Pump A and start LPSW Pump C B. The A LPSW pump has a sheared shaft 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 / Start LPSW Pump C then stop LPSW Pump A D. The A LPSW pump has a sheared shaft I Start LPSW Pump C then stop LPSW Pump A 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 14 Unit 1 and 2 initial conditions:

A and B LPSW pump operating Current conditions:

1 SA9/A9 (LPSW HEADER A PRESS LOW)

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 PumpC B. The A LPSW pump has a sheared shaft 1 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 Start LPSW Pump C then stop LPSW Pump A

2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 15 Unit 3 initial conditions:

Time=1200 Reactor power = 45% stable Operating Main Feedwater Pump trips IA and AlA are lost to 3FDW-315 Current conditions:

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 s/u level I failed open B. 25 s/U level I controlling SG level at setpoint C. 30 XSUR / failed open D. 30 XSUR I controlling Sc level at setpoint 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 15 Unit 3 initial conditions:

Time = 1200 Reactor power = 45% stable Operating Main Feedwater Pump trips IA and AlA are lost to 3FDW-315 Current conditions:

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" Stu level/failed open B. 25" Stu level/controlling SG level at setpoint C. 30" XSUR / failed open D. 30" XSUR / controlling SG level at setpoint

2010A NRC REACTOR OPERATOR EXAM I POINT Question 16 Unit 1 plant conditions:

Reactor power = 50% stable Units 2 and 3 in MODE 5 AP134 (Degraded Grid) in progress due to grid disturbance BOTH KHUs generating to the 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 Spec3.8.1 ?

AND

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

A. Immediately enter Tech Spec LCO 3.0.3 / KHU High Generator Output Voltage B. Immediately enter Tech Spec LCO 3.0.3 / KHU Low Generator Output Voltage C. Energize BOTH Standby Busses within one hour / KHU High Generator Output Voltage D. Energize BOTH Standby Busses within one hour / KHU Low Generator Output Voltage 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 16 Unit 1 plant conditions:

Reactor power = 50% stable Units 2 and 3 in MODE 5 AP/34 (Degraded Grid) in progress due to grid disturbance BOTH KHU's generating to the 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 by Tech Spec 3.8.1 ?

AND

2) a condition that would require manually separating BOTH 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 NRC REACTOR OPERATOR EXAM 1 POINT Question 17 Unit 1 initial conditions:

Reactor power = 100%

lCHPlpumpOOS Current conditions:

1A and lB Main FDW pumps tripped Condensate Booster Pumps unavailable All EFDW pumps unavailable 1A and lB SG Outlet pressure = 860 psig slowly decreasing RCS pressure = 2317 psig increasing Based on the above conditions, which ONE of the following 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 SG5.

C.

Establish HPI forced cooling and open IHP-410.

D.

Establish HPI forced cooling and open IHP-409.

2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 17 Unit 1 initial conditions:

Reactor power = 100%

1 C HPI pump OOS Current conditions:

1 A and 1 B Main FDW pumps tripped Condensate Booster Pumps unavailable All EFDW pumps unavailable 1 A and 1 B SG Outlet pressure = 860 psig slowly decreasing RCS pressure = 2317 psig increasing Based on the above conditions, which ONE of the following 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.

C. Establish HPI forced cooling and open 1 HP-41 O.

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

2010A NRC REACTOR OPERATOR EXAM I POINT Question 18 Unit I initial conditions:

Reactor power = 100%

lAMSLBoccurs Current conditions:

Reactor has tripped RCS Tave = 544T slowly increasing 1A SG Pressure = 0 psig 1 B SG Pressure = 990 psig slowly increasing Turbine bypass valves in Auto 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...

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 REACTOR OPERATOR EXAM 1 POINT Question 18 Unit 1 initial conditions:

Reactor power = 100%

1 A MSLB occurs Current conditions:

Reactor has tripped RCS Tave = 544°F slowly increasing 1 A SG Pressure = 0 psig 1 B SG Pressure = 990 psig slowly increasing Turbine bypass valves in Auto 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...

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 REACTOR OPERATOR EXAM I POINT Question 19 Unit 1 plant conditions:

Reactor power = 70% stable Pressurizer level = 210 slowly decreasing I HP-i 20 (RC VOLUME CONTROL) failed closed AP/i4 (Loss of Normal HPI Makeup and/or RCP Seal Injection) initiated Based on the above conditions, which ONE of the following describes the initial actions required to control Pressurizer level AND the minimum allowed Pressurizer level (inches) in accordance with AP/i4?

Throttle...

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

1 HP-i 22 (RC VOLUME CONTROL BYPASS I 80 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 19 Unit 1 plant conditions:

Reactor power = 70% stable Pressurizer level = 210" slowly decreasing 1HP-120 (RC VOLUME CONTROL) failed closed AP/14 (Loss of Normal HPI Makeup and/or RCP Seal Injection) initiated Based on the above conditions, which ONE of the following describes the initial actions required to control Pressurizer level AND the minimum allowed Pressurizer level (inches) in accordance with AP/14?

Throttle...

A. 1 HP-26 / 200 B. 1 HP-26 / 80 C. 1 HP-122 (RC VOLUME CONTROL BYPASS) / 200 D. 1 HP-122 (RC VOLUME CONTROL BYPASS / 80

2010A NRC REACTOR OPERATOR EXAM I POINT Question 20 Unit I initial conditions:

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 4D (Fuel Transfer Canal Flooded) of AP126 (Loss of Decay Heat Removal) initiated Based on the conditions above, which ONE of the following describes the fit actions required to be taken in accordance with Section 4D (Fuel Transfer Canal Flooded)?

A. Close I SF-i and I 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 REACTOR OPERATOR EXAM 1 POINT Question 20 Unit 1 initial conditions:

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 (Fuel Transfer Canal Flooded) of AP/26 (Loss of Decay Heat Removal) initiated Based on the conditions above, which ONE of the following describes the first actions required to be taken in accordance with Section 40 (Fuel Transfer Canal Flooded)?

A. Close 1 SF-1 and 1 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 REACTOR OPERATOR EXAM 1 POINT Question 21 Which ONE of the following describes conditions that indicate RIA-54 is unable to perform its function AND if batch releases are allowed while the RIA is inoperable?

A. Counts do not increase when Source Check is performed I Batch releases are allowed.

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

C. Sample pump found OFF I Batch releases are allowed.

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

2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 21 Which ONE of the following describes conditions that indicate RIA-54 is unable to perform its function AND if batch releases are allowed while the RIA is inoperable?

A. Counts do not increase when Source Check is performed I Batch releases are allowed.

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

C. Sample pump found OFF I Batch releases are allowed.

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

2010A NRC REACTOR OPERATOR EXAM I POINT 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 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.

2010A NRC REACTOR OPERATOR EXAM 1 POINT 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 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.

2010A NRC REACTOR OPERATOR EXAM I POINT Question 23 Unit 3 plant conditions:

Loop A and Loop B SCMs = 0°F stable Core SCM = (-)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 POINT Question 23 Unit 3 plant conditions:

Loop A and Loop 8 SCM's = oaF stable Core SCM = (_)5 aF 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 I POINT Question 24 Unit 2 initial conditions:

Reactor power = 100%

Current conditions:

2SA2/B4 (RC AVERAGE TEMP HIGH/LOW) actuated Loop 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 NRC REACTOR OPERATOR EXAM 1 POINT Question 24 Unit 2 initial conditions:

Reactor power = 100%

Current conditions:

2SA2/B4 (RC AVERAGE TEMP HIGH/LOW) actuated Loop '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 NRC REACTOR OPERATOR EXAM I POINT Question 25 Unit I initial conditions:

Reactor power = 25% slowly increasing Turbine trip Current conditions:

Reactor power = 22% 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. UNPPtab I 885 B. UNPP tab I 1010 C. Plant Operating Procedures I 885 D. Plant Operating Procedures I 1010 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 25 Unit 1 initial conditions:

Reactor power = 25% slowly increasing Turbine trip Current conditions:

Reactor power = 22% 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 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 Question 26 Unft I plant conditions:

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 actions directed by AP/lO (Turbine Building Flood)?

Manually trip the reactor 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 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 26 Unit 1 plant conditions:

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 actions directed by AP/1 0 (Turbine Building Flood)?

Manually trip the reactor 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"

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

Core SCM = 0°F LOCA Cooldown tab in progress CETCs = 395°F slowly decreasing 1LP-103 (POST LOCA BORON DILUTE) will 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 flow?

A. 1LP-3 B. 1LP-l9 C. 1LP-I04 D. 1LP-105 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 27 Unit 1 plant conditions:

Core SCM = OaF LOCA Cooldown tab in progress CETC's = 395°F slowly decreasing 1 LP-1 03 (POST LOCA BORON DILUTE) will 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 flow?

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

2010A NRC REACTOR OPERATOR EXAM I POINT Question 28 Unit 3 initial conditions:

Time = 0300 Reactor power = 100%

Reactor trip CT-3 Lockout occurs Current conditions:

MFB re-energized 6900V power still unavailable HPI system leak downstream of 3HP-31 occurs 3A1 RCP SI flow = 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 1 POINT Question 28 Unit 3 initial conditions:

Time = 0300 Reactor power = 100%

Reactor trip CT-3 Lockout occurs Current conditions:

MFB re-energized 6900V power still unavailable HPI system leak downstream of 3HP-31 occurs 3A 1 RCP SI flow = 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 Question 29 Unit 1 plant conditions:

Reactor power = 100%

1 CC-8 (CC RETURN PENT (54) OUTSIDE BLOCK) fails closed 1 LPSW-6 (UNIT I 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?

A.

1 CC-8 I due to high RCP motor stator temperatures B. 1CC-8 I due to high RCP radial bearing temperatures C.

1 LPSW-6 I due to high RCP motor stator temperatures D.

I LPSW-6 I due to high RCP radial bearing temperatures 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 29 Unit 1 plant conditions:

Reactor power = 100%

1CC-8 (CC RETURN PENT (54) OUTSIDE BLOCK) fails closed 1 LPSW-6 (UNIT 1 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?

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

2010A NRC REACTOR OPERATOR EXAM I POINT Question 30 Unit I initial conditions:

Reactor power = 100%

1A CC pump operating Current conditions:

ICC-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 REACTOR OPERATOR EXAM 1 POINT Question 30 Unit 1 initial conditions:

Reactor power = 100%

1 A CC pump operating Current conditions:

1 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 REACTOR OPERATOR EXAM I POINT Question 31 Unit 3 initial conditions:

Reactor in MODE 4 LPI DHR alignment for cooldown in progress Current conditions:

3LP-3 (LPI HOT LEG SUCTION) will not open 3LP-12 (3A LPI COOLER OUTLET) failed closed Based on the above conditions, which ONE of the following describes the effect of the failures on ECCS-LPI train availability?

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

A. Does I Does B. Does I Does NOT C. Does NOT I Does D. Does NOT I Does NOT 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 31 Unit 3 initial conditions:

Reactor in MODE 4 LPI DHR alignment for cooldown in progress Current conditions:

3LP-3 (LPI HOT LEG SUCTION) will not open 3LP-12 (3A LPI COOLER OUTLET) failed closed Based on the above conditions, which ONE of the following describes the effect of the failures on ECCS-LPI train availability?

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

__ impact ECCS-LPI train availability.

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

2010A NRC REACTOR OPERATOR EXAM I POINT Question 32 Unit 1 plant conditions:

RCS pressure = 365 psig An attempt is made to open ILP-1 (LPI RETURN BLOCK FROM RCS)

Based on the above conditions, which ONE of the following describes if 1 LP-1 will open AND the reason I LP-l has an interlock?

A. yes I prevent overpressurizing LPI suction piping B. yes I ensure delta p across I LP-I will allow it to open C. No I prevent overpressurizing LPI suction piping D. No I ensure delta p across 1 LP-1 will allow it to open 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 32 Unit 1 plant conditions:

RCS pressure = 365 psig An attempt is made to open 1 LP-1 (LPI RETURN BLOCK FROM RCS)

Based on the above conditions, which ONE of the following describes if 1 LP-1 will open AND the reason 1 LP-1 has an interlock?

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

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

Reactor power = 100%

Current conditions:

RCS pressure = 1350 psig decreasing Reactor Building pressure = 4.8 psig increasing ES Channel 2 did NOT actuate Based on the above conditions, which ONE of the following describes ALL safety injection pumps that have AUTOMATICALLY started?

A.

1A HPI,IBHPI,1ALPI,IBLPI B. IA HPI, 1C HPI, IA LPI, lB LPI C. 1A HPI, lB HPI, 1A LPI ONLY D. 1A HPI, 1ALPI ONLY 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 33 Unit 1 initial conditions:

Reactor power = 100%

Current conditions:

RCS pressure = 1350 psig decreasing Reactor Building pressure = 4.8 psig increasing ES Channel 2 did NOT actuate Based on the above conditions, which ONE of the following describes ALL safety injection pumps that have AUTOMATICALLY started?

A. 1A HPI, 1B HPI, 1A LPI, 1B LPI B. 1A HPI, 1C HPI, 1A LPI, 1B LPI C. 1A HPI, 1B HPI, 1A LPI ONLY D. 1A HPI, 1A LPI ONLY

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

OP/i/All 103/002, (Filling and Venting RCS) Enclosure 4.14 (Establishing Pzr Steam Bubble And RCS Final Vent) in progress Quench Tank level = 82 inches Quench Tank pressure = 0.5 psig The Pressurizer is vented to the Quench Tank for 30 minutes Based on the above conditions, which ONE of the following 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 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 34 Unit 1 plant conditions:

OP/1/A/1103/002, (Filling and Venting RCS) Enclosure 4.14 (Establishing Pzr Steam Bubble And RCS Final Vent) in progress Quench Tank level = 82 inches Quench Tank pressure = 0.5 psig The Pressurizer is vented to the Quench Tank for 30 minutes Based on the above conditions, which ONE of the following 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

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

A.

1XL I KHU via overhead path B.

1XL I KHU via underground path C. IXS1 I KHU via overhead path D. 1XS1 I KHU via underground path 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 35 Which ONE of the following describes the normal power supply to the 1A CC pump AND the emergency backup source of power that will be supplying the Main Feeder Buses following a Loss of Offsite Power due to a Switchyard Isolation?

A. 1XL / KHU via overhead path B. 1XL / KHU via underground path C. 1XS1 / KHU via overhead path D. 1XS1 / KHU via underground path

2010A NRC REACTOR OPERATOR EXAM I POINT 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 I & 2 actuation?

ASSUME NO OPERATOR ACTIONS A. Variable Low Pressure I 1600 B. Variable Low Pressure I 1810 C. High Pressure I 1600 D. High Pressure I 1810 2010A NRC REACTOR OPERATOR EXAM 1 POINT 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 1 & 2 actuation?

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

2010A NRC REACTOR OPERATOR EXAM I POINT Question 37 Unit 2 plant conditions:

Reactor power = 100%

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

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?

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

A. 0% / Low pressure B. 0% I High pressure C. 100% I Low pressure D. 100% / High pressure 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 37 Unit 2 plant conditions:

Reactor power = 100%

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

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?

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 C. 100% I Low pressure D. 100% I High pressure

2010A NRC REACTOR OPERATOR EXAM I POINT Question 38 Which ONE of the following would result in a trip of the 1 D RPS Channel AND the 1 D CRD Breaker?

A. Reactor Building pressure bistables in the IA and I B RPS channels fail in the tripped state B. Reactor Building pressure bistable in the 1 D RPS channel fails in the tripped state C. RC pressure test module for I D RPS channel placed in Test Operate D. Loss of the 1KVID panelboard 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 38 Which ONE of the following would result in a trip of the 1 D RPS Channel AND the 1 D CRD Breaker?

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

2010A NRC REACTOR OPERATOR EXAM I POINT Question 39 Unit 2 initial conditions:

Reactor power = 100%

Current conditions:

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

A. 2CC-7 B. 2LWD-1 C. 2LPSW-6 D. 2LPSW-1062 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 39 Unit 2 initial conditions:

Reactor power = 100%

Current conditions:

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

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

c. 2LPSW-6 D. 2LPSW-1062

2010A NRC REACTOR OPERATOR EXAM I POINT Question 40 Unit 3 plant conditions:

Reactor power= 100%

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

have actuated.

A.

NO channels B.

Channels 1 thru 4 C.

ONLY channels 2 AND 4 D.

ONLY channels 1 AND 3 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 40 Unit 3 plant conditions:

Reactor power = 100%

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

have actuated.

A.

NO channels B.

Channels 1 thru 4 C.

ONLY channels 2 AND 4 D.

ONLY channels 1 AND 3

2010A NRC REACTOR OPERATOR EXAM I POINT Question 41 Unit iplant conditions:

Time = 03:00 Reactor power = 100%

lB and IC RBCUs operating in HIGH speed 1A RBCU is operable and OFF ES channels 1-6 actuate Based on the above conditions, which ONE of the following describes RBCU status at 03:02?

A. lB and 1C RBCUs operating in HIGH speed and 1A RBCU OFF B. lB and C RBCU5 operating in LOW speed and 1A RBCU OFF C. ALL RBCU5 operating in LOW speed D. ALL RBCUs will be OFF 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 41 Unit 1 plant conditions:

Time = 03:00 Reactor power = 100%

1 Band 1 C RBCUs operating in HIGH speed 1 A RBCU is operable and OFF ES channels 1-6 actuate Based on the above conditions, which ONE of the following describes RBCU status at 03:02?

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

8. 1 Band C RBCUs operating in LOW speed and 1 A RBCU OFF C. ALL RBCUs operating in LOW speed D. ALL RBCUs will be OFF

2010A NRC REACTOR OPERATOR EXAM I POINT Question 42 Which ONE of the following describes the range of BWST levels where RBS pump suction would be aligned to both the RBES and the BWST simultaneously AND what action(s) would be required if 1 LP-22 failed to close when isolating the BWST?

When performing Enclosure 5. 12 (ECCS Suction Swap to RBES) both suction sources are aligned when BWST level is between (feet) AND A. 159 I stop the lB LPI pump AND lB RBS pump B. 159 I Maximize total LPI flow < 3100 gpm C. 9-6 I stop the lB LPI pump AND lB RBS pump D. 9

- 6 I Maximize total LPI flow < 3100 gpm 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 42 Which ONE of the following describes the range of BWST levels where RBS pump suction would be aligned to both the RBES and the BWST simultaneously AND what action(s) would be required if 1 LP-22 failed to close when isolating the BWST?

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

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

2010A NRC REACTOR OPERATOR EXAM I POINT 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 OAC point O3X2060 (ICS TURBINE LOADING STATUS) = FALSE Based on the above conditions, which ONE of the following describes the operation of the Turbine Bypass Valves (TBVs)?

is being compared to Turbine Header Pressure setpoint to develop the controlling error signal AND TBVs are controlling at 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 1 POINT 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 OAC point 03X2060 (ICS TURBINE LOADING STATUS) = FALSE Based on the above conditions, which ONE of the following describes the operation of the Turbine Bypass Valves (TBV's)?

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

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

2010A NRC REACTOR OPERATOR EXAM I POINT Question 44 Unit 1 initial conditions:

Reactor power = 70% stable Current conditions:

1HPE-6 (Heater 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 IHPE-6?

Feedwater flow will stabilize at a value than the pre-transient level AND will be used to reopen I HPE-6.

A. higher I 0P111A11106123 (High and Low Pressure Extraction)

B. higher I 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 1 POINT Question 44 Unit 1 initial conditions:

Reactor power = 70% stable Current conditions:

1 HPE-6 (Heater 1A1 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 1 HPE-6?

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

____ will be used to reopen 1 HPE-6.

A. higher / OP/1/A/1106/23 (High and Low Pressure Extraction)

B. higher / OP/1/A/1106/002 (Condensate and FDW system)

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

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

2010A NRC REACTOR OPERATOR EXAM I POINT Question 45 Unit 1 initial conditions:

Reactor power = 100%

Current conditions:

Reactor trip 1 FDW-33 (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 lB SG level =

A 25 S/U / 25 S/U B

12 S/U / 25 S/U C

30 XSUR / 25 S/U D. 30XSUR / 30XSUR 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 45 Unit 1 initial conditions:

Reactor power = 100%

Current conditions:

Reactor trip 1 FDW-33 (1A 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 SG level = __ _

A. 25" Stu t 25" StU

8. 12" StU t 25" StU C. 30" XSUR t 25" StU D. 30" XSUR t 30" XSUR

2010A NRC REACTOR OPERATOR EXAM I POINT Question 46 Unit 1 initial conditions:

Reactor power = 100%

Unit I TDEFWP unavailable Current conditions:

Both Main FDW pumps trip I 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...

A. Rule 3 (Loss of Main or Emergency Feedwater) and cross connect with an alternate unit to supply the 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 End. 5.9 (Extended EFDW Operation) and feed both SGs with 1A MDEFWP 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 46 Unit 1 initial conditions:

Reactor power = 100%

Unit 1 TDEFWP unavailable Current conditions:

Both Main FDW pumps trip 1B 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...

A. Rule 3 (Loss of Main or Emergency Feedwater) and cross connect with an alternate unit to supply the 1B 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. 5.9 (Extended EFDW Operation) and feed both SG's with 1A MDEFWP

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

Load Shed the inverter.

A.Kl B. DIA C. KSF-1 D. KOAC 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 47 Which ONE of the following describes actions required that will extend the life of the Control Batteries following a loss of all AC power in accordance with EOP Enclosure 5.38 (Restoration of Power)?

Load Shed the inverter.

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

2010A NRC REACTOR OPERATOR EXAM I POINT Question 48 Which ONE of the following describes the normal alignment of the Power Battery busses AND a condition in which SLC 16.8.3 (Power Battery Parameters) would require changing that alignment?

The Oconee units are normally and this would be changed if A. cross-tied I a single power battery becomes inoperable B. cross-tied I two or more power batteries simultaneously become inoperable C. separated I a single power battery becomes inoperable D. separated I two or more power batteries simultaneously become inoperable 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 48 Which ONE of the following describes the normal alignment of the Power Battery busses AND a condition in which SLC 16.8.3 (Power Battery Parameters) would require changing that alignment?

The Oconee units are normally ____ and this would be changed if ___ _

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

2010A NRC REACTOR OPERATOR EXAM I POINT Question 49 Operators are preparing to synchronize KHU-2 to the grid in accordance with OP/OIAI1 106/019, (Keowee Hydro At Oconee)

The operator notes the following indications:

Grid Frequency = 59.9 cycles Keowee Frequency = 60.3 cycles Keowee 2 Line Volts = 13.7 kV Keowee 2 Output Volts = 15.2 kV Based on the above conditions, which ONE 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 will be used to adjust the synchroscope indication AND generator output should be adjusted to A. UNIT2AUTOVOLTAGEADJUSTER I 0 B. UNIT 2 SPEED CHANGER MOTOR I 0 C. UNIT2AUTO VOLTAGE ADJUSTER /10 D. UNIT 2 SPEED CHANGER MOTOR I 10 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 49 Operators are preparing to synchronize KHU-2 to the grid in accordance with OP/O/A/1106/019, (Keowee Hydro At Oconee)

The operator notes the following indications:

Grid Frequency = 59.9 cycles Keowee Frequency = 60.3 cycles Keowee 2 Line Volts = 13.7 kV Keowee 2 Output Volts = 15.2 kV Based on the above conditions, which ONE 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 will be used to adjust the synchroscope indication AND generator output should be adjusted to MWs.

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

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

Time 1159:40 Reactor power = 100% stable KHU-1 OOS ACB-4 closed KHU-2 gets Emergency Start signal from another unit Time = 1200:00 KHU-2 speed reaches 190 RPM Time = 1200:30 KHU-2 speed = 190 RPM Based on the above conditions, which ONE of the following describes the status of KHU-2 and the procedural actions reciuired by Unit 1 (if any) as a result of that status?

A. Emergency locked out / Enter LCO 3.0.3 immediately B. Emergency locked out I Energize BOTH Standby Buses within 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 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 1 POINT Question 50 Unit 1 conditions:

Time = 1159:40 Reactor power = 100% stable 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 KH U-2 speed = 190 RPM Based on the above conditions, which ONE of the following describes the status of KHU-2 and the procedural actions required by Unit 1 (if any) as a result of that status?

A. Emergency locked out / Enter LCO 3.0.3 immediately B. Emergency locked out / Energize BOTH Standby Buses within 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 / No additional actions required D. Energizing CT-4 / Energize EITHER Standby Bus within 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 Question 51 Unit 1 initial conditions:

Time=1200 Reactor power = 35%

IA steam generator tube leak = 2.1 gpd stable RCS activity = 0.25 pCi/mi DEl increasing Current conditions:

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

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

B. IRIA-16 (Main Steam Line Monitor) increased while IRIA-40 (CSAE Off-gas) remained constant.

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

D. 1RIA-59 (N-16 monitor) increased whilelRlA-40 (CSAE Off-gas) remained constant.

2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 51 Unit 1 initial conditions:

Time = 1200 Reactor power = 35%

1 A steam generator tube leak = 2.1 gpd stable RCS activity = 0.25 IJCi/ml DEI increasing Current conditions:

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

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

B. 1RIA-16 (Main Steam Line Monitor) increased while 1RIA-40 (CSAE Off-gas) remained constant.

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

D. 1 RIA-59 (N-16 monitor) increased while1 RIA-40 (CSAE Off-gas) remained constant.

2010A NRC REACTOR OPERATOR EXAM I POINT Question 52 Unit I initial conditions:

Time=1200 Reactor power= 100%

A and B LPSW Pumps operating C LPSW pump in AUTO Blackout Occurs Current conditions:

Time=1230 Both MFBs 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 have re-energized AND the system that will require the use of OP/i /A/1104/0i0 (Low Pressure Service Water) to return it to service once LPSW pressure has been restored?

A. operating I Reactor Building Aux Coolers B. operating I RBCUs C. NOT operating / Reactor Building Aux Coolers D. NOT operating I RBCUs 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 52 Unit 1 initial conditions:

Time = 1200 Reactor power = 100%

A and B LPSW Pumps operating C LPSW pump in AUTO Blackout Occurs Current conditions:

Time = 1230 Both MFB'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 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 once LPSW pressure has been restored?

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

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

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

140

120

100

80

60

40

20

PSI

0 Based on the above conditions, which ONE of the following describes the air compressors that will be operating?

The Primary IA Compressor 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 1 POINT Question 53 Initial plant conditions:

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

140==

120==

100 -

-~==

80 60 40 20 PSI o

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

The Primary IA Compressor 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 I 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 per AP/29 (Rapid Unit Shutdown) 400 D. Initiate unit shutdown at 20%/min per AP/29 (Rapid Unit Shutdown) 380 2010A NRC REACTOR OPERATOR EXAM 1 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 per AP/29 (Rapid Unit Shutdown) 400 D. Initiate unit shutdown at =20%/min per AP/29 (Rapid Unit Shutdown) 380

2010A NRC REACTOR OPERATOR EXAM I POINT Question 55 Unit 3 initial conditions:

3CC-8 has been manually opened due to loss of air to the valve Current conditions:

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

3CC-8 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 REACTOR OPERATOR EXAM 1 POINT Question 55 Unit 3 initial conditions:

3CC-8 has been manually opened due to loss of air to the valve Current conditions:

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

3CC-8 __ be operated from the control room and 3CC-8 ___ automatically close.

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

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

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. LossofMFDW 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 56 Unit 1 initial conditions:

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

2010A NRC REACTOR OPERATOR EXAM I POINT Question 57 Which ONE of the following is the power supply for the Unit 1 Group B Pressurizer heaters?

A. IXH B.

1XI C. 1XSI D. 1XSF 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 57 Which ONE of the following is the power supply for the Unit 1 Group B Pressurizer heaters?

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

2010A NRC REACTOR OPERATOR EXAM I POINT 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 atmosphere in accordance with 0P111021014 (RB Purge System)?

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 1 POINT 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 atmosphere in accordance with OP/1102/014 (RB Purge System)?

A. CRSRO / 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 / 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 / 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 / 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 Question 59 Plant conditions:

Spent Fuel Storage Cask has been dropped in Unit 1&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 ION B.

1 I OFF C.2 ION D. 2 I OFF 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 59 Plant conditions:

Spent Fuel Storage Cask has been dropped in Unit 1 &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 / ON B. 1 / OFF C. 2 / ON D. 2 / OFF

2010A NRC REACTOR OPERATOR EXAM I POINT Question 60 Unit 2 initial conditions:

Reactor power = 100%

Current conditions:

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

The 2A TBVs will fully open AND the 2B 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 Question 60 Unit 2 initial conditions:

Reactor power = 100%

Current conditions:

Reactor trip Controlling 2A Steam Generator Outlet Pressure fails HIGH Based on the above conditions, which ONE of the following describes the 2A AND 2B Turbine Bypass Valves (TBV's) response?

The 2A TBV's will fully open __ AND the 2B TBV's 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 / and remain fully open

2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 61 Unit 3 initial conditions:

Reactor power= 100%

3MS-1 12 & 3MS-1 73 (SSRH 3A13B Controls) are open and in MANUAL 3MS-77, 78, 80, 81 (MS to SSRHs) are open and in AUTO 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 B. 3MS-1 12 & 3MS-173 close AND 3MS-77, 78, 80, and 81 remain open C. 3MS-1 12 & 3MS-173 remains open AND 3MS-77, 78, 80, and 81 close D. 3MS-112, 3MS-173, 3MS-77, 3MS-78, 3MS-80, and 3MS-81 remain open 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 61 Unit 3 initial conditions:

Reactor power = 100%

3MS-112 & 3MS-173 (SSRH 3A13B Controls) are open and in MANUAL 3MS-77, 78, 80, 81 (MS to SSRH's) are open and in AUTO 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 B. 3MS-112 & 3MS-173 close AND 3MS-77, 78,80, and 81 remain open C. 3MS-112 & 3MS-173 remains open AND 3MS-77, 78, 80, and 81 close D. 3MS-112, 3MS-173, 3MS-77, 3MS-78, 3MS-80, and 3MS-81 remain open

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

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

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

iA Hotwell pump is operating with and the lB 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 4

HNP Pk;MP AMPS 1A IC 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 62 Unit 1 plant conditions:

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

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

1 A Hotwell pump is operating with __ and the 1 B Hotwell pump __ automatically start when its control switch is placed in Auto.

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

' ~

1.-

c.J

.\\\\t HVVP PUMP AMPS 1A 18 lC

2010A NRC REACTOR OPERATOR EXAM I POINT Question 63 Unit 3 plant conditions:

Reactor power = 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 REACTOR OPERATOR EXAM 1 POINT Question 63 Unit 3 plant conditions:

Reactor power = 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.

Question 64 2010A NRC REACTOR OPERATOR EXAM I POINT uJ D

C))

C?)

LU U

IAPressurevs.Time 1230 Based on the graph above, which ONE of the following describes the time at which SA 141 (SA to IA Controller) will automatically open?

A. 1207 B. 1210 C. 1212 100 1200 1210 1220 ii rvlE D. 1215 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 64 IA Pressure vs. Time 100~-----------------------------------------'

w 90........................... :........................... :............................

0:::

J (f)

(f)

W 0:::

0..

<t:

80........................... ~.......................................................

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

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

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

2010A NRC REACTOR OPERATOR EXAM I POINT Question 65 Unit 3 initial conditions:

Reactor power = 100%

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

3TE bus is grounded due to water spray Relay 51G actuated Based on the above conditions, which ONE of the following lists ONLY components that remain available?

A. 3A MDEFDWP, 3B MDEFDWP B. 3A MDEFDWP, 3C HPIP C. 3C LPIP, 3B MDEFDWP D. 3C LPIP, 3C HPIP 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 65 Unit 3 initial conditions:

Reactor power = 100%

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

3TE bus is grounded due to water spray Relay 51 G actuated Based on the above conditions, which ONE of the following lists ONLY components that remain available?

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

2010A NRC REACTOR OPERATOR EXAM I POINT Question 66 Unit 2 plant conditions:

Reactor in MODE 6 RCS Boron = 2270 ppmb Based on the above conditions, which ONE of the following describes whether RCS Boron concentration meets the requirements of OP/2/AI1 502/007 (Operations Defueling/Refueling Responsibilities) AND what is the minimum number of OPERABLE Source Range NIs required by the same procedure?

A. meets / 2 B. meets /

1 C. does NOT meet / 2 D. does NOT meet / I 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 66 Unit 2 plant conditions:

Reactor in MODE 6 RCS Boron = 2270 ppmb Based on the above conditions, which ONE of the following describes whether RCS Boron concentration meets the requirements of OP/2/A/1502/007 (Operations Defueling/Refueling Responsibilities) AND what is the minimum number of OPERABLE Source Range Nl's required by the same procedure?

A. meets I 2 B. meets I 1 C. does NOT meet I 2 D. does NOT meet I 1

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

Reactor power = 100%

LDST level = 75 stable Group 7 rod position = 94% withdrawn Makeup to LDST initiated from lB BHUT Neutron error = 0 stable Current conditions:

1 HP-i 5 Bailey controller indicates 470 gallons added to LDST 1 B Bleed Transfer Pump secured Based on the above conditions, which ONE of the following would describe a diverse indication that 470 gallons of I B BHUT had been added to the LDST?

LDST level is approximately inches and neutron error will become A. 90 I positive B. 90 I negative C. 95 I positive D. 95 I negative 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 67 Unit 1 initial conditions:

Reactor power = 100%

LOST level = 75" stable Group 7 rod position = 94% withdrawn Makeup to LOST initiated from 1 B BHUT Neutron error = 0 stable Current conditions:

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

LOST level is approximately ____ inches and neutron error will become ___ _

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

2010A NRC REACTOR OPERATOR EXAM I POINT 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 / RPS trip settings B. 2500 / PORV C. 2750 / RPS trip settings.

D. 2750 / PORV 2010A NRC REACTOR OPERATOR EXAM 1 POINT 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 Question 69 Unit 1 plant conditions:

Reactor power = 100%

IA Core Flood Tank parameters:

o Pressure = 572 psig stable o

Level = 12. 91 feet o

Boron Concentration = 2010 ppmb I B Core Flood Tank parameters:

o Pressure = 590 psig stable o

Level = 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 1A CFT to OPERABLE within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ONLY D. Restore I B CFT to OPERABLE within 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 1 POINT Question 69 Unit 1 plant conditions:

Reactor power = 100%

1A Core Flood Tank parameters:

o Pressure = 572 psig stable o Level = 12. 91 feet o Boron Concentration = 2010 ppmb 1 B Core Flood Tank parameters:

o Pressure = 590 psig stable o Level = 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 A CFT to OPERABLE within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ONLY D. Restore 1 B CFT to OPERABLE within 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 Question 70 Unit 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 feet B.

BWST level = 47.3 feet C.

I D RPS channel in Manual bypass D.

230KV Dacus Black and White lines isolated 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 70 Unit 1 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 feet B.

BWST level = 47.3 feet C.

1 D RPS channel in Manual bypass D.

230KV Dacus Black and White lines isolated

2010A NRC REACTOR OPERATOR EXAM I POINT Question 71 Unit 1 plant conditions:

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.

I RIA-45 reaches ALERT setpoint C. Suction piping pressure = 5 inches of water vacuum D.

I PR-3 (RB PURGE CONTROL) closed 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 71 Unit 1 plant conditions:

Reactor in MODE 5 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 RIA-45 reaches ALERT setpoint C. Suction piping pressure = 5 inches of water vacuum D. 1 PR-3 (RB PURGE CONTROL) closed

2010A NRC REACTOR OPERATOR EXAM I POINT Question 72 Unit 1 plant conditions:

Reactor in MODE 6 LPI DHR in progress using 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.

I Nl-2 SR fails low B. IRIA-4 HIGH alarm C. IRIA-45 HIGH alarm D.

1 Nl-2 WR fails high 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 72 Unit 1 plant conditions:

Reactor in MODE 6 LPI DHR in progress using 1A 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. 1 NI-2 SR fails low B. 1 RIA-4 HIGH alarm C. 1 RIA-45 HIGH alarm D. 1 NI-2 WR fails high

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

A. Exit the area immediately and contact RP / with RP permission B. Exit the area immediately and contact RP / with emergency dose limits in effect C. Move away from the area until alarm clears / with RP permission D. Move away from the area until alarm clears / with emergency dose limits in effect 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 73 For Operations personnel, which ONE of the following describes the required response to an Electronic Dosimeter dose alarm and when it is acceptable to deviate from that requirement?

A. Exit the area immediately and contact RP I with RP permission B. Exit the area immediately and contact RP I with emergency dose limits in effect 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 Question 74 Unit 1 plant conditions:

Blackout tab in progress EOP step gives direction to Initiate AP/1 I (Recovery From Loss of 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/1 I and SRO will wait until AP/1 1 has been completed to continue in the EOP.

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

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

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

2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 74 Unit 1 plant conditions:

Blackout tab in progress EOP step gives direction to "Initiate AP/11 (Recovery From Loss of 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 and SRO will wait until AP/11 has been completed to continue in the EOP.

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

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

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

2010A NRC REACTOR OPERATOR EXAM I POINT Question 75 Unit 1 plant conditions:

Reactor power = 100%

1SA3IB6 (FIRE ALARM) actuated Fire Alarm panel indication o

point 0202071 (Unit 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 1 pipe trench room 348 per the Alarm Response Guide to determine the validity of the alarm AND a method used in RP/1000/029 (Fire Brigade Response) to dispatch the fire brigade when it is required?

A. A Fire Brigade qualified operator I Plant Paging system B. A Fire Brigade qualified operator I Have Security dispatch fire brigade C. The Unit 1 BOP Reactor Operator I Plant Paging system D. The Unit I BOP Reactor Operator I Have Security dispatch fire brigade 2010A NRC REACTOR OPERATOR EXAM 1 POINT Question 75 Unit 1 plant conditions:

Reactor power = 100%

1SA3/B6 (FIRE ALARM) actuated Fire Alarm panel indication o

point 0202071 (Unit 1 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 1 pipe trench room 348 per the Alarm Response Guide to determine the validity of the alarm AND a method used in RP/10001029 (Fire Brigade Response) to dispatch the fire brigade when it is required?

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

Oconee 2010-301 Exam References RO Exam:

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

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

Technical Specification (T/S) 3.4.9 (Pressurizer)

T/S 3.8.8 (Distribution Systems Operating)

Alarm Response Guide 1SA-03 B-6 pages 2-28.

Oconee 2010*301 Exam References RO Exam:

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

RP/O/8/10001001 (Emergency Classification)

Technical Specification (TIS) 3.4.9 (Pressurizer)

TIS 3.8.8 (Distribution Systems - Operating)

Alarm Response Guide 1 SA-03 8-6 pages 2-28.

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