ML101310308
| ML101310308 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/04/2010 |
| From: | NRC/RGN-II |
| To: | Duke Energy Carolinas |
| References | |
| Download: ML101310308 (28) | |
Text
ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:
Date: 04107/2010 Facility/Unit: Oconee Region:
I II III IV Reactor Type: W LICE E1BWGE LI 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 overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.
Applicant Certification All work done on this examination is my own.
I have neither given nor received aid.
Applicants Signature Results RO/SRO-Only/Total Examination Values 75
/
25
/
100 Points Applicants Scores
/
/
Points Applicants Grade I
/
Percent ES-401 Site-Specific SRO Written Examination Cover Sheet Form ES-401-8 U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:
Date: 04/07/2010 Facility/Unit: Oconee Region:
I D II ~ III D IV D Reactor Type: W DeE DBw~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 overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results RO/SRO-OnlylTotal Examination Values 75
/ ~
/ 100 Points Applicant's Scores
/ -- / --
Points Applicant's Grade
/ -- / --
Percent
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 76 Unit 2 initial conditions:
Time=1300 Reactor power = 100%
Current conditions:
Time=1310 RCS pressure = 52 psig slowly decreasing Reactor Building pressure = 52 psig slowly decreasing All SCMs = 0°F 2RIA-57 = 92 R/hr slowly increasing 2RIA-58 = 45 R/hr slowly increasing Average of 5 highest CETCs = 312°F decreasing NO RBCUs can be started NO RBS Pumps can be started Based on the above conditions, which ONE of the following is the Emergency Action Level Classification?
REFERENCE PROVIDED A. Alert based on Loss of Fuel Clad Barrier and Potential Loss of Containment Barrier B. Alert based on Loss of RCS Barrier and Potential Loss of Containment Barrier C. Site Area Emergency based on Loss of RCS Barrier and Loss of Containment Barrier D. Site Area Emergency based on Loss of Fuel Clad Barrier and Loss of Containment Barrier 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 76 Unit 2 initial conditions:
Time = 1300 Reactor power = 100%
Current conditions:
Time = 1310 RCS pressure = 52 psig slowly decreasing Reactor Building pressure = 52 psig slowly decreasing All SCM's = OaF 2RIA-57 = 92 Rlhr slowly increasing 2RIA-58 = 45 Rlhr slowly increasing Average of 5 highest CETC's = 312°F decreasing NO RBCU's can be started NO RBS Pumps can be started Based on the above conditions, which ONE of the following is the Emergency Action Level Classification?
REFERENCE PROVIDED A. Alert based on Loss of Fuel Clad Barrier and Potential Loss of Containment Barrier B. Alert based on Loss of RCS Barrier and Potential Loss of Containment Barrier C. Site Area Emergency based on Loss of RCS Barrier and Loss of Containment Barrier D. Site Area Emergency based on Loss of Fuel Clad Barrier and Loss of Containment Barrier
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 77 Unit 1 plant conditions:
Reactor power = 100%
CC CRD Return Flow = 125 gpm slowly decreasing CC Return Flow = 563 gpm decreasing Letdown Temperature = 138°F stable The following alarms have actuated:
o 1SA-91B-1 (CC CRD Return Flow Low).
o ISA-21C-1 (HP Letdown Temperature High) o 1SA-91C-1 (CC Component Cooling Return Flow Low)
Based on the above conditions:
(1) Which ONE of the following describes a required action from the associated ARG(s) to mitigate this event?
AND (2) If the ARG directed actions are NOT successful, which Abnormal Procedure is required to be entered first?
A. (1) Decrease letdown flow using I HP-7 (LETDOWN CONTROL)
(2) AP/32 (Loss of Letdown)
B. (I) Decrease letdown flow using 1 HP-7 (LETDOWN CONTROL)
(2) AP/20 (Loss of Component Cooling)
C. (1) Verify CC Surge Tank level> 12 inches and start the standby CC pump (2) AP/32 (Loss of Letdown)
D. (1) Verify CC Surge Tank level> 12 inches and start the standby CC pump (2) AP/20 (Loss of Component Cooling) 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 77 Unit 1 plant conditions:
Reactor power = 100%
CC CRD Return Flow = 125 gpm slowly decreasing CC Return Flow = 563 gpm decreasing Letdown Temperature = 138°F stable The following alarms have actuated:
o 1SA-9/B-1 (CC CRD Return Flow Low).
o 1 SA-2/C-1 (HP Letdown Temperature High) o 1 SA-9/C-1 (CC Component Cooling Return Flow Low)
Based on the above conditions:
(1) Which ONE of the following describes a required action from the associated ARG(s) to mitigate this event?
AND (2) If the ARG directed actions are NOT successful, which Abnormal Procedure is required to be entered first?
A. (1) Decrease letdown flow using 1 HP-7 (LETDOWN CONTROL)
(2) AP/32 (Loss of Letdown)
B. (1) Decrease letdown flow using 1 HP-7 (LETDOWN CONTROL)
(2) AP/20 (Loss of Component Cooling)
C. (1) Verify CC Surge Tank level> 12 inches and start the standby CC pump (2) AP/32 (Loss of Letdown)
D. (1) Verify CC Surge Tank level> 12 inches and start the standby CC pump (2) AP/20 (Loss of Component Cooling)
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 78 Unit I initial conditions:
Datel2/0I TimeO800 Reactor Power = 100%
All Pressurizer heater breakers trip open and cannot be reclosed Current conditions:
Date 12/04 Time 2200 Based on the above conditions, which ONE of the following is the HIGHER RCS temperature (degrees F) that is in compliance with the requirements of Tech Specs AND the bases for the Pzr heater power supply requirements in TS 3.4.9 (Pressurizer)?
REFERENCE PROVIDED A.
320 I ensure ability to perform a subcooled cooldown while on natural circulation during an extended loss of power B. 320 / ensure ability to control pressure and remain subcooled during an extended loss of power C. 375 I ensure ability to perform a natural circulation cooldown during an extended loss of power D. 375 / ensure ability to control pressure and remain subcooled during an extended loss of power 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 78 Unit 1 initial conditions:
Date = 12/01 Time = 0800 Reactor Power = 100%
All Pressurizer heater breakers trip open and cannot be reclosed Current conditions:
Date = 12/04 Time = 2200 Based on the above conditions, which ONE of the following is the HIGHER RCS temperature (degrees F) that is in compliance with the requirements of Tech Specs AND the bases for the Pzr heater power supply requirements in TS 3.4.9 (Pressurizer)?
REFERENCE PROVIDED A. 320 / ensure ability to perform a subcooled cooldown while on natural circulation during an extended loss of power B. 320 / ensure ability to control pressure and remain subcooled during an extended loss of power C. 375 / ensure ability to perform a natural circulation cool down during an extended loss of power D. 375 / ensure ability to control pressure and remain subcooled during an extended loss of power
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 79 Unit 1 initial conditions:
Reactor power = 75% stable ICSinMANUAL lB HPIP tagged out The following alarms actuate:
o ISA-I/Al (RPCHANNELATRIP) o 1SA-l/Bl (RPCHANNELBTRIP)
Current conditions:
Reactor power = 34% slowly decreasing BOTH Main Feedwater pumps are operating All SCMs = 0°F stable Based on the above conditions, which ONE of the following describes the EOP tab that will be directed first AND the guidance the SRO will provide to the RO?
A. UNPP I Trip the Main Turbine B. UNPP / Throttle Feedwater to control RCS temperature C. LOSCM / Fully depressurize BOTH Steam Generators D. LOSCM / Throttle Feedwater to control RCS temperature 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 79 Unit 1 initial conditions:
Reactor power = 75% stable ICS in MANUAL 1 B HPIP tagged out The following alarms actuate:
o 1SA-1/A1 (RP CHANNEL A TRIP) o 1SA-1/B1 (RP CHANNEL B TRIP)
Current conditions:
Reactor power = 34% slowly decreasing BOTH Main Feedwater pumps are operating All SCM's = OaF stable Based on the above conditions, which ONE of the following describes the EOP tab that will be directed first AND the guidance the SRO will provide to the RO?
A. UNPP I Trip the Main Turbine B. UNPP I Throttle Feedwater to control RCS temperature C. LOSCM I Fully depressurize BOTH Steam Generators D. LOSCM I Throttle Feedwater to control RCS temperature
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 80 Unit 3 plant conditions:
Date 4/5 Time1100 3KVID panelboard de-energized Current conditions:
Timel200 DC panelboard 3DIC is de-energized Based on the above conditions, which ONE of the following states the actions required by Tech Spec 3.8.8 (Distribution Systems-Operating) AND the bases behind the different Completion Times for inoperable Vital Instrument and Control panelboards?
REFERENCE PROVIDED A. Restore either 3KVIC OR 3KVID within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> I KVIA AND KVIB have shorter completion times due to being the source of power for the ES Digital Channels B. Restore either 3KVIC OR 3KVID within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> I KVIA AND KVIB have shorter completion times due to providing power for SK and SL breakers protective relaying C. Enter LCO 3.0.3 immediately I KVIA AND KVIB have shorter completion times due to being the source of power for the ES Digital Channels D. Enter LCO 3.0.3 immediately I KVIA AND KVIB have shorter completion times due to providing power for SK and SL breakers protective relaying 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 80 Unit 3 plant conditions:
Date 4/5 Time = 1100 3KVID panelboard de-energized Current conditions:
Time = 1200 DC panelboard 3DIC is de-energized Based on the above conditions, which ONE of the following states the actions required by Tech Spec 3.8.8 (Distribution Systems-Operating) AND the bases behind the different Completion Times for inoperable Vital Instrument and Control panelboards?
REFERENCE PROVIDED A. Restore either 3KVIC OR 3KVID within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / KVIA AND KVIB have shorter completion times due to being the source of power for the ES Digital Channels B. Restore either 3KVIC OR 3KVID within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / KVIA AND KVIB have shorter completion times due to providing power for SK and SL breakers protective relaying C. Enter LCO 3.0.3 immediately / KVIA AND KVIB have shorter completion times due to being the source of power for the ES Digital Channels D. Enter LCO 3.0.3 immediately / KVIA AND KVIB have shorter completion times due to providing power for SK and SL breakers protective relaying
2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 81 Unit I initial conditions:
Reactor trip from 100% power Both Main Feedwater pumps trip EFDW pumps will not start Current conditions:
Rule 3 in progress LOHT tab initiated ALL SCMs> 0°F Based on the above conditions, which ONE of the following would result in a transfer out of the LOHT tab?
A. Pressurizer level = 375 inches B. RCS heats up and results in ANY SCM = 0°F C. HPI Forced Cooling is established and verified D. Condensate Booster Pump feed is established 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 81 Unit 1 initial conditions:
Reactor trip from 100% power Both Main Feedwater pumps trip EFDW pumps will not start Current conditions:
Rule 3 in progress LOHT tab initiated ALL SCM's> OaF Based on the above conditions, which ONE of the following would result in a transfer out of the LOHT tab?
A. Pressurizer level = 375 inches B. RCS heats up and results in ANY SCM = OaF C. HPI Forced Cooling is established and verified D. Condensate Booster Pump feed is established
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 82 Unit 1 initial conditions:
Startup in progress Reactor in MODE 3 Source Range NIs 2 & 4 OOS Source Range NIs 1 & 3 = 834 cps increasing Wide Range NIs I thru 4 = 5E-5% increasing Current conditions:
Source Range NI-I = 0 cps 1SA-051A8 (NI-i TEST/FAIL) actuates Based on the above conditions, which ONE of the following describes the reason for the NI-i indications AND the Tech Specs impact on the startup?
A. Loss of +1 5V Power supply / Suspend the startup B. Loss of +1 5V Power supply I Startup may continue C. Source range becomes saturated I Suspend the startup D. Source range becomes saturated I Startup may continue 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 82 Unit 1 initial conditions:
Startup in progress Reactor in MODE 3 Source Range Nl's 2 & 4 OOS Source Range Nl's 1 & 3 = 834 cps increasing Wide Range NI's 1 thru 4 = 5E-5% increasing Current conditions:
Source Range NI-1 = 0 cps 1 SA-05/A8 (NI-1 TEST/FAIL) actuates Based on the above conditions, which ONE of the following describes the reason for the NI-1 indications AND the Tech Specs impact on the startup?
A. Loss of +15V Power supply / Suspend the startup B. Loss of +15V Power supply / Startup may continue C. Source range becomes saturated / Suspend the startup D. Source range becomes saturated / Startup may continue
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 83 Unit I plant conditions:
ALL SCM = 0°F stable RCS pressure = 855 psig slowly decreasing LOCA CD tab in progress LPI suction source is the RBES HPI aligned for piggyback operation 1LP-15 failed closed Based on the above conditions, which ONE of the following states...
(1) if LPI ES analog channels are allowed to be manually bypassed in accordance with the LOCA CD tab?
AND (2) the MAXIMUM allowed HPI flow if ILP-15 will not open?
LPI ES be bypassed AND the MAXIMUM allowed HPI flow is gpm.
A. may I 750 B. may NOT I 750 C. may I 500 D. may NOT I 500 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 83 Unit 1 plant conditions:
ALL SCM = O°F stable RCS pressure = 855 psig slowly decreasing LOCA CD tab in progress LPI suction source is the RBES HPI aligned for piggyback operation 1 LP-15 failed closed Based on the above conditions, which ONE of the following states...
(1) if LPI ES analog channels are allowed to be manually bypassed in accordance with the LOCA CD tab?
AND (2) the MAXIMUM allowed HPI flow if 1LP-15 will not open?
LPI ES __ be bypassed AND the MAXIMUM allowed HPI flow is __ gpm.
A. may / 750 B. may NOT / 750 C. may / 500 D. may NOT / 500
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 84 Unit 1 initial conditions:
Reactor power = 70% stable 1B1 RCP has been secured ICS is in manual Current conditions:
Group 2 Rod 4 drops into core Based on the above conditions, which ONE of the following describes the direction that will be provided to the RO AND the maximum time allowed by APII (Unit Runback) to carry out the directions?
Reduce Core Thermal Power to <
within hour(s).
A. 60% I I B. 60% I 2 C. 45% I 1
D. 45% I 2 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 84 Unit 1 initial conditions:
Reactor power = 70% stable 1 B1 RCP has been secured ICS is in manual Current conditions:
Group 2 Rod 4 drops into core Based on the above conditions, which ONE of the following describes the direction that will be provided to the RO AND the maximum time allowed by AP/1 (Unit Runback) to carry out the directions?
Reduce Core Thermal Power to ~ ___ within ___ hour(s).
A. 60% I 1 B. 60% I 2 C. 45% I 1 D. 45% I 2
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 85 Unit 2 initial conditions:
Reactor power = 100% stable Current conditions:
Reactor trip occurs Main Turbine does NOT trip Manual Turbine trip is unsuccessful Based on the above conditions, which ONE of the following describes actions required by the EOP AND the MAXIMUM time allowed by NSD 202 (Reportability) prior to notifying the NRC?
A. Place BOTH EHC pumps in PULL TO LOCK I eight hours B. Place BOTH EHC pumps in PULL TO LOCK I four hours C. Initiate Rule 5 (MSLB)
I eight hours D. Initiate Rule 5 (MSLB)
I four hours Question 85 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Unit 2 initial conditions:
Reactor power = 100% stable Current conditions:
Reactor trip occurs Main Turbine does NOT trip Manual Turbine trip is unsuccessful Based on the above conditions, which ONE of the following describes actions required by the EOP AND the MAXIMUM time allowed by NSD 202 (Reportability) prior to notifying the NRC?
A. Place BOTH EHC pumps in PULL TO LOCK I eight hours B. Place BOTH EHC pumps in PULL TO LOCK I four hours C. Initiate Rule 5 (MSLB) I eight hours D. Initiate Rule 5 (MSLB) I four hours
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 86 Unit I initial conditions:
Reactor in MODE 3 1A2 and 1B2 RCP5 operating Current conditions:
RCS leakage = 140 gpm All SCMs = 45°F stable Pressurizer level = 200 inches stable 1A2 RCP Motor Upper Guide Bearing temperature = 195°F slowly increasing 1 B2 RCP Motor Stator Temperature = 235°F slowly increasing Based on the above conditions, which ONE of the following describes the actions required by AP/1 6 (Abnormal Reactor Coolant Pump Operation) AND which EOP tab would provide guidance for a plant cooldown if ALL RCPs are secured?
Trip the A. 1A2 RCP / Forced Cooldown B. 1A2 RCP / LOCA Cooldown C. 1B2 RCP / Forced Cooldown D.
I B2 RCP / LOCA Cooldown 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 86 Unit 1 initial conditions:
Reactor in MODE 3 1 A2 and 1 B2 RCPs operating Current conditions:
RCS leakage = 140 gpm All SCM's = 45°F stable Pressurizer level = 200 inches stable 1A2 RCP Motor Upper Guide Bearing temperature = 195°F slowly increasing 1 B2 RCP Motor Stator Temperature = 235°F slowly increasing Based on the above conditions, which ONE of the following describes the actions required by AP/16 (Abnormal Reactor Coolant Pump Operation) AND which EOP tab would provide guidance for a plant cooldown if ALL RCP's are secured?
Trip the...
A. 1 A2 RCP / Forced Cooldown B. 1 A2 RCP / LOCA Cooldown C. 1 B2 RCP / Forced Cooldown D. 1 B2 RCP / LOCA Cooldown
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 87 Unit 3 plant conditions:
Reactor power = 100%
3A RBCU tagged out Based on the above conditions, which ONE of the following would require immediate entry into LCO 3.0.3 AND describes actions that are required once LCO 3.0.3 is entered in accordance with OMP 2-23 (Operations Shift Manager Rules Of Practice)?
A. 3LPSW-19 (3B RBCU INLET) fails closed I Must determine a time to begin power reduction within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. 3LPSW-19 (3B RBCU INLET) fails closed I Must actually initiate a power reduction within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. 3A RBS Pump declared inoperable I Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine a time to initiate power reduction D. 3A RBS Pump declared inoperable I Must actually initiate a power reduction within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Question 87 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Unit 3 plant conditions:
Reactor power = 100%
3A RBCU tagged out Based on the above conditions, which ONE of the following would require immediate entry into LCO 3.0.3 AND describes actions that are required once LCO 3.0.3 is entered in accordance with OMP 2-23 (Operations Shift Manager Rules Of Practice)?
A. 3LPSW-19 (3B RBCU INLET) fails closed / Must determine a time to begin power reduction within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. 3LPSW-19 (3B RBCU INLET) fails closed / Must actually initiate a power reduction within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. 3A RBS Pump declared inoperable / Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine a time to initiate power reduction D. 3A RBS Pump declared inoperable / Must actually initiate a power reduction within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 88 Plant initial conditions:
All three ONS units reactor power = 100%
STBY Buses 1 AND 2 energized from Central Switchyard Current conditions:
STBY Bus 1 locks out Based on the above conditions, which ONE of the following describes the operability of the Keowee Underground power path AND if Oconee Unit 1 experienced a LOCA/LOOP from where would the MFB5 receive power?
Keowee Underground Power path is and Unit Is MFBs would be energized from A. OPERABLE / CT-I B. OPERABLE ICT-5 C. NOT OPERABLE / CT-l D. NOT OPERABLE I CT-5 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 88 Plant initial conditions:
All three ONS units reactor power = 100%
STBY Buses 1 AND 2 energized from Central Switchyard Current conditions:
STBY Bus 1 locks out Based on the above conditions, which ONE of the following describes the operability of the Keowee Underground power path AND if Oconee Unit 1 experienced a LOCAILOOP from where would the MFBs receive power?
Keowee Underground Power path is ___ and Unit 1 s MFBs would be energized from ---
A. OPERABLE / CT-1 B. OPERABLE / CT-5 C. NOT OPERABLE / CT-1 D. NOT OPERABLE / CT-5
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 89 Unit I plant conditions:
Reactor power = 20% stable IA Main Feedwater Pump in service Based on the above conditions, which ONE of the following will require entry into the EOP AND describes the initial actions directed by the EOP if the NEO dispatched to verify ALL MSRVs have reseated reports that one of the MSRVs is still passing steam?
A. FDWPT Exhaust Vacuum = 23.2 inches HG I Transfer to EHT tab B. FDWPT Exhaust Vacuum = 23.2 inches HG I Manually decrease SG pressure C. Feedwater pump bearing oil pressure = 3.1 psig I Transfer to EHT tab D. Feedwater pump bearing oil pressure = 3.1 psig I Manually decrease SC pressure Question 89 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Unit 1 plant conditions:
Reactor power = 20% stable 1 A Main Feedwater Pump in service Based on the above conditions, which ONE of the following will require entry into the EOP AND describes the initial actions directed by the EOP if the NEO dispatched to verify ALL MSRV's have reseated reports that one of the MSRV's is still passing steam?
A. FDWPT Exhaust Vacuum = 23.2 inches HG / Transfer to EHT tab B. FDWPT Exhaust Vacuum = 23.2 inches HG / Manually decrease SG pressure C. Feedwater pump bearing oil pressure = 3.1 psig / Transfer to EHT tab D. Feedwater pump bearing oil pressure = 3.1 psig / Manually decrease SG pressure
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 90 Unit 1 initial conditions:
Reactor in MODE 6 Spent Fuel Pool in Refueling Cooling Mode alignment Defueling in progress Current conditions:
Fuel Transfer Canal level decreasing Based on the above conditions, which ONE of the following describes why AP/26 directs stopping all LPI pumps AND the reason the AP only requires establishing Containment Closure (vs. restoring containment to OPERABLE)?
A. Determine if leak is on discharge of LPI pumps / fuel handling accidents will NOT result in significant Containment pressurization B. Determine if leak is on discharge of LPI pumps I with an OPERABLE Containment the Main Purge system cannot be used to clean up RB atmosphere C. Allow closing of 1SF-I and 1SF-2 I fuel handling accidents will NOT result in significant Containment pressurization D. Allow closing of 1SF-I and I SF-2 I with an OPERABLE Containment the Main Purge system cannot be used to clean up RB atmosphere 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 90 Unit 1 initial conditions:
Reactor in MODE 6 Spent Fuel Pool in Refueling Cooling Mode alignment Defueling in progress Current conditions:
Fuel Transfer Canal level decreasing Based on the above conditions, which ONE of the following describes why AP/26 directs stopping all LPI pumps AND the reason the AP only requires establishing Containment Closure (vs. restoring containment to OPERABLE)?
A. Determine if leak is on discharge of LPI pumps / fuel handling accidents will NOT result in significant Containment pressurization B. Determine if leak is on discharge of LPI pumps / with an OPERABLE Containment the Main Purge system cannot be used to clean up RB atmosphere C. Allow closing of 1 SF-1 and 1 SF-2 / fuel handling accidents will NOT result in significant Containment pressurization D. Allow closing of 1 SF-1 and 1 SF-2 / with an OPERABLE Containment the Main Purge system cannot be used to clean up RB atmosphere
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 91 Unit I plant conditions:
Reactor power = 100%
1RC-1 fails open 1 RC-3 will NOT close Based on the above conditions, which ONE of the following describes the initial response of I HP-120 (RC VOLUME CONTROL) valve position AND the action(s) required by AP144 (Abnormal Pressurizer Pressure Control)?
IHP-120 valve position will initially AND AP144 will direct actions to A. remain approximately the same I trip the reactor and secure the IAI and 1A2 RCPs B. remain approximately the same I enter AP129, decrease power to <70%, and secure the IAI RCP C. fully open I trip the reactor and secure the IA1 and 1A2 RCPs D. fully open I enter AP/29, decrease power to <70%, and secure the 1AI RCP Question 91 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Unit 1 plant conditions:
Reactor power = 100%
1 RC-1 fails open 1 RC-3 will NOT close Based on the above conditions, which ONE of the following describes the initial response of 1HP-120 (RC VOLUME CONTROL) valve position AND the action(s) required by AP/44 (Abnormal Pressurizer Pressure Control)?
1 HP-120 valve position will initially ___ AND AP/44 will direct actions to __ _
A. remain approximately the same I trip the reactor and secure the 1A1 and 1A2 RCP's B. remain approximately the same I enter AP/29, decrease power to <70%, and secure the 1 A 1 RCP C. fully open I trip the reactor and secure the 1A1 and 1A2 RCP's D. fully open I enter AP/29, decrease power to <70%, and secure the 1A1 RCP
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 92 Unit 3 initial conditions:
Reactor power= 100%
The volume of active TSP required by SLC 16.6.10 (Trisodium Phosphate) is NOT met Current conditions:
LOCA/LOOP occurs Based on the above conditions, which ONE of the following describes the consequence of the inadequate TSP volume AND when TSP performs its credited function?
A. ECCS acceptance criteria may be exceeded I During the injection phase B. ECCS acceptance criteria may be exceeded I During the recirculation phase C. Acceptable offsite dose limits may be exceeded I During the injection phase D. Acceptable offsite dose limits may be exceeded I During the recirculation phase Question 92 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Unit 3 initial conditions:
Reactor power = 100%
The volume of active TSP required by SLC 16.6.10 (Trisodium Phosphate) is NOT met Current conditions:
LOCAILOOP occurs Based on the above conditions, which ONE of the following describes the consequence of the inadequate TSP volume AND when TSP performs its credited function?
A. ECCS acceptance criteria may be exceeded / During the injection phase B. ECCS acceptance criteria may be exceeded / During the recirculation phase C. Acceptable offsite dose limits may be exceeded / During the injection phase D. Acceptable offsite dose limits may be exceeded / During the recirculation phase
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 93 Unit 3 initial conditions:
Reactor power= 100%
Fuel movement in Unit 3 Spent Fuel Pool Current conditions:
3RIA-6 (SFP) in HIGH alarm 3RIA-41 (SFP Gas) in HIGH alarm 3SA-81B9 (PROCESS MONITOR RADIATION HIGH) in alarm Based on the above conditions, which ONE of the following describes the Abnormal Procedure of the highest priority and the Outside Air Booster Fans that will be started as part of the mitigating actions?
A. AP/9 (Spent Fuel Damage) I Unit 3 Outside Air Booster Fans ONLY B. API9 (Spent Fuel Damage) I Unit I and 2 AND Unit 3 Outside Air Booster Fans C. APII8 (Abnormal Release of Radioactivity) I Unit 3 Outside Air Booster Fans ONLY D. API18 (Abnormal Release of Radioactivity) I Unit 1 and 2 AND Unit 3 Outside Air Booster Fans Question 93 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Unit 3 initial conditions:
Reactor power = 100%
Fuel movement in Unit 3 Spent Fuel Pool Current conditions:
3RIA-6 (SFP) in HIGH alarm 3RIA-41 (SFP Gas) in HIGH alarm 3SA-8/B9 (PROCESS MONITOR RADIATION HIGH) in alarm Based on the above conditions, which ONE of the following describes the Abnormal Procedure of the highest priority and the Outside Air Booster Fans that will be started as part of the mitigating actions?
A. AP/9 (Spent Fuel Damage) / Unit 3 Outside Air Booster Fans ONLY B. AP/9 (Spent Fuel Damage) / Unit 1 and 2 AND Unit 3 Outside Air Booster Fans C. AP/18 (Abnormal Release of Radioactivity) / Unit 3 Outside Air Booster Fans ONLY D. AP/18 (Abnormal Release of Radioactivity) / Unit 1 and 2 AND Unit 3 Outside Air Booster Fans
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 94 Which ONE of the following describes a condition that would require making a plant page to implement Emergency Dose Limits AND whether that leakage would be included when calculating RCS Pressure Boundary leakacie (gpm) as defined in Tech Spec 3.4.13 (RCS Operational Leakage)?
A. 45 gpm SGTR / no B. 45gpmSGTR / yes C. 125 gpm RCS leak in RCP suction pipe weld / no D. 125 gpm RCS leak in RCP suction pipe weld / yes Question 94 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Which ONE of the following describes a condition that would require making a plant page to implement Emergency Dose Limits AND whether that leakage would be included when calculating RCS Pressure Boundary leakage (gpm) as defined in Tech Spec 3.4.13 (RCS Operational Leakage)?
A. 45 gpm SGTR / no B. 45 gpm SGTR / yes C. 125 gpm RCS leak in RCP suction pipe weld / no D. 125 gpm RCS leak in RCP suction pipe weld / yes
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 95 Unit 2 initial conditions:
Refueling in progress FTC level = 22 feet stable No water additions are being made to the system 2A LPI train is operable and in service Current conditions:
Refueling SRO desires stopping the 2A LPI Pump to aid in inserting a fuel assembly 2A LPI pump has been in continuous operation for the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Based on the above conditions, which ONE of the following describes whether the 2A LPI pump may be stopped in accordance with OPI2IA/1502/007 (Operations Defueling
/Refueling Responsibilities) and the Tech Spec bases for requiring only I OPERABLE DHR loop in this condition?
A. 2A LPI Pump may be stopped for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
FTC level is within TS limits and provides adequate backup decay heat removal.
B. 2A LPI Pump may be stopped for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
Spent Fuel Cooling system provides adequate backup decay heat removal.
C. 2A LPI Pump may NOT be stopped FTC level is below TS limits and cannot provide adequate backup decay heat removal.
D. 2A LPI Pump may NOT be stopped Spent Fuel Cooling system can NOT provide adequate backup decay heat removal.
Question 95 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Unit 2 initial conditions:
Refueling in progress FTC level = 22 feet stable No water additions are being made to the system 2A LPI train is operable and in service Current conditions:
Refueling SRO desires stopping the 2A LPI Pump to aid in inserting a fuel assembly 2A LPI pump has been in continuous operation for the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Based on the above conditions, which ONE of the following describes whether the 2A LPI pump may be stopped in accordance with OP/21A11502/007 (Operations Defueling IRefueling Responsibilities) and the Tech Spec bases for requiring only 1 OPERABLE DHR loop in this condition?
A. 2A LPI Pump may be stopped for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
FTC level is within TS limits and provides adequate backup decay heat removal.
B. 2A LPI Pump may be stopped for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
Spent Fuel Cooling system provides adequate backup decay heat removal.
C. 2A LPI Pump may NOT be stopped FTC level is below TS limits and cannot provide adequate backup decay heat removal.
D. 2A LPI Pump may NOT be stopped Spent Fuel Cooling system can NOT provide adequate backup decay heat removal.
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 96 Unit I plant conditions:
Reactor power = 75% stable Regulating rods positioned in the Unacceptable region of the rod curves provided in the COLR Which ONE of the following describes the (1) direction that will be given to the OATC based on the above plant conditions...
AND (2) consequences of continued power operations while in the Unacceptable Operation region of the rod curves in the COLR in accordance with the bases forTS 3.2.1 (Regulating Rods Position Limits)?
RCS boration using is reciuired to begin within 15 minutes AND...
A. 1A BHUT I required shutdown margin may not exist B.
1A BHUT I Quadrant Power Tilt limits may be exceeded C. Unit I CBAST I required shutdown margin may not exist D. Unit 1 CBAST I Quadrant Power Tilt limits may be exceeded 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 96 Unit 1 plant conditions:
Reactor power = 75% stable Regulating rods positioned in the Unacceptable region of the rod curves provided in the COLR Which ONE of the following describes the...
(1) direction that will be given to the OATC based on the above plant conditions...
AND (2) consequences of continued power operations while in the Unacceptable Operation region of the rod curves in the COLR in accordance with the bases for TS 3.2.1 (Regulating Rods Position Limits)?
RCS boration using __ is required to begin within 15 minutes AND...
A. 1A BHUT / required shutdown margin may not exist B. 1A BHUT / Quadrant Power Tilt limits may be exceeded C. Unit 1 CBAST / required shutdown margin may not exist D. Unit 1 CBAST / Quadrant Power Tilt limits may be exceeded
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 97 Unit 3 plant conditions:
LPI aligned to normal DHR mode using 3A LPI pump Both SG levels = 65% OR increasing using 3A and 3B MDEFWPs LR Cooldown pressure = 290 psig stable 3TA and 3TB de-energized CETCs = 196°F stable RCS Tcold = 205°F stable 3A LPI Cooler Outlet temperature = 195°F stable Based on the above conditions, which ONE of the following describes the current plant MODE AND if the SGs can be used as a backup method of heat removal in accordance with Tech Specs?
A. MODE4 I no B. MODE 4 I yes C. MODE5 I no D. MODE 5 I yes Question 97 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Unit 3 plant conditions:
LPI aligned to normal DHR mode using 3A LPI pump Both SG levels = 65% OR increasing using 3A and 3B MDEFWP's LR Cooldown pressure = 290 psig stable 3T A and 3TB de-energized CETC's = 196°F stable RCS Tcold = 205°F stable 3A LPI Cooler Outlet temperature = 195°F stable Based on the above conditions, which ONE of the following describes the current plant MODE AND if the SG's can be used as a backup method of heat removal in accordance with Tech Specs?
A. MODE 4 / no B. MODE 4 / yes C. MODE 5 / no D. MODE 5 / yes
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 98 Which ONE of the following describes the maximum dose (TEDE) that a non-volunteer can receive while saving a life and whose approval is required per RP/0/BI1 000/11 (Planned Emergency Exposure).
A. 10 rem / Emergency Coordinator B. 10 rem / Site Vice President C. 25 rem / Emergency Coordinator D. 25 rem / Site Vice President 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 98 Which ONE of the following describes the maximum dose (TEDE) that a non-volunteer can receive while saving a life and whose approval is required per RP/O/B/1000/11 (Planned Emergency Exposure).
A. 10 rem 1 Emergency Coordinator B. 10 rem 1 Site Vice President C. 25 rem 1 Emergency Coordinator D. 25 rem 1 Site Vice President
2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT Question 99 Plant conditions:
All 3 Units reactor power = 100%
1SA-3/B6 (FIRE ALARM) actuated NEDs dispatched to the Turbine Building Basement (Unit I and 2 Powdex area)
Current conditions:
NEO reports: Fire location is TBB/K28. Heavy smoke and rolling flames (5-loft.)
spreading out from the Powdex Alarm Panel Based on the above conditions, which ONE of the following describes the unit(s) requiring a reactor trip AND who is allowed to serve as a Fire Brigade leader in accordance with the bases of SLC 16.13.1 (Minimum Station Staffing Requirements)?
REFERENCE PROVIDED A. ALL units / SRO ONLY B. Unit 2 (only) / SRO ONLY C. ALL units / SRO OR an NED with appropriate qualifications D. Unit 2 (only)
I SRO OR an NED with appropriate qualifications 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 99 Plant conditions:
All 3 Units reactor power = 100%
1 SA-3/B6 (FIRE ALARM) actuated NEO's dispatched to the Turbine Building Basement (Unit 1 and 2 Powdex area)
Current conditions:
NEO reports: Fire location is TBB/K28. Heavy smoke and rolling flames (5-1 Oft.)
spreading out from the Powdex Alarm Panel Based on the above conditions, which ONE of the following describes the unit(s) requiring a reactor trip AND who is allowed to serve as a Fire Brigade leader in accordance with the bases of SLC 16.13.1 (Minimum Station Staffing Requirements)?
REFERENCE PROVIDED A. ALL units I SRO ONLY B. Unit 2 (only) I SRO ONLY C. ALL units I SRO OR an NEO with appropriate qualifications D. Unit 2 (only) I SRO OR an NEO with appropriate qualifications
2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Question 100 Unit 1 initial conditions:
Reactor power = 100%
1 RIA-59 reading 2 gpm slowly increasing AP/31 (Primary to Secondary Leakage) in progress Current conditions:
Reactor power = 75% decreasing 1RIA-59 reading 28 gpm increasing Based on the above conditions, which ONE of the following describes how the SRO will proceed AND the actions required if during the subsequent RCS cooldown if the isolated steam generator approaches overfill conditions (285 XSUR)?
A. Continue shutdown under the direction of AP/31 I Initiate SG Blowdown B. Continue shutdown under the direction of API3I
/ Steam the SG to the condenser C. Go directly to SGTR tab / Initiate SG Blowdown D. Go directly to SGTR tab I Steam the SG to the condenser Question 100 2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT Unit 1 initial conditions:
Reactor power = 100%
1 RIA-59 reading 2 gpm slowly increasing AP/31 (Primary to Secondary Leakage) in progress Current conditions:
Reactor power = 75% decreasing 1 RIA-59 reading 28 gpm increasing Based on the above conditions, which ONE of the following describes how the SRO will proceed AND the actions required if during the subsequent RCS cooldown if the isolated steam generator approaches overfill conditions (285" XSUR)?
A. Continue shutdown under the direction of AP/31 I Initiate SG Blowdown B. Continue shutdown under the direction of AP/31 I Steam the SG to the condenser C. Go directly to SGTR tab I Initiate SG Blowdown D. Go directly to SGTR tab I Steam the SG to the condenser
Oconee 2010-301 Exam References RO Exam:
Steam Tables Unit 1 Loop A Narrow Range PT Plot SRO Exam:
RPIOIBII 000/001 (Emergency Classificalion)
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 SROExam:
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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