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| number = ML14310A408 | | number = ML14310A408 | ||
| issue date = 10/24/2014 | | issue date = 10/24/2014 | ||
| title = | | title = 2014-10 - Draft Written Exam | ||
| author name = Gaddy V | | author name = Gaddy V | ||
| author affiliation = NRC/RGN-IV/DRS/OB | | author affiliation = NRC/RGN-IV/DRS/OB | ||
Line 15: | Line 15: | ||
=Text= | =Text= | ||
{{#Wiki_filter:Examination Outline Cross | {{#Wiki_filter:Examination Outline Cross-Reference Level RO 295001 Partial or Complete Loss of Forced Tier # 1 Core Flow Circulation Group # 1 K/A # 295001 AK1.04 Knowledge of the operational implications Rating 2.5 of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION : | ||
-Reference Level RO 295001 Partial or Complete Loss of Forced Core Flow Circulation Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION : | Limiting cycle oscillation: Plant Specific Question 1 The plant is operating on the 100 percent rod line at rated thermal power. Operation is in accordance with Backup Stability Protections due to the inoperability of OPRMs. Then: | ||
. Operation is in accordance with Backup Stability Protections due to the inoperability of OPRMs. Then: | * Both reactor recirc pumps unexpectedly downshift to slow speed | ||
: | * Reactor power stabilizes at 45 percent of rated thermal power With these conditions, in order to limit thermal hydraulic induced power oscillations ONEP 05-01-02-III-3, Reduction in Recirculation Flow Rate, directs the crew to immediately: | ||
A. begin inserting control rods. | A. begin inserting control rods. | ||
B. place the reactor mode switch in SHUTDOWN. | B. place the reactor mode switch in SHUTDOWN. | ||
C. trip the recirculation pump | C. trip the recirculation pump with the lowest flow. | ||
D. maximize reactor recirc pump | D. maximize reactor recirc pump flows . | ||
Since the core is operating in the scram region of the power | Answer: B Explanation: | ||
-flow curve with OPRMS inoperable, step 4.1 requires an immediate scram. | Since the core is operating in the scram region of the power-flow curve with OPRMS inoperable, step 4.1 requires an immediate scram. | ||
A would be correct if in the controlled entry region of the power | A would be correct if in the controlled entry region of the power-flow curve. | ||
-flow curve. | |||
C would be correct for trip of a single Recirc pump. | C would be correct for trip of a single Recirc pump. | ||
D would be correct if the pumps are manually downshifted Technical | D would be correct if the pumps are manually downshifted Technical | ||
Line 33: | Line 32: | ||
05-01-02-III-3, , Reduction in Recirculation Flow Rate References to be provided to applicants during exam: Figure 1 from 05-01-02-III-3, Power-flow map. | 05-01-02-III-3, , Reduction in Recirculation Flow Rate References to be provided to applicants during exam: Figure 1 from 05-01-02-III-3, Power-flow map. | ||
Learning Objective: | Learning Objective: | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
New X | |||
Last NRC Exam No | |||
Memory/Fundamental Comprehensive/Analysis X | |||
55.41(b)(7) 55.43 | |||
According to 05-1-02-I-4, Loss of AC Power | Examination Outline Cross-Reference Level RO 295003 - Partial or complete loss of AC Tier # 1 Group # 1 Knowledge of abnormal condition K/A # 295003 - 2.4.11 procedures. Rating 4.0 Question 2 According to 05-1-02-I-4, Loss of AC Power, which of the following 2 buses would constitute a station blackout if power was lost? | ||
, which of the following 2 buses would constitute a station blackout if power was lost? | A. 15AA and 16AB B. 15AA and 17AC C. 16AB and 13AD D. 16AB and 14AE Answer: A Explanation: | ||
A. 15AA and 16AB | A is correct because of the note 05-1-02-I-4, Loss of AC Power, Rev 45. | ||
B. 15AA and 17AC C. 16AB and 13AD D. 16AB and 14AE Answer: A | |||
A is correct because of the note 05 02-I-4, Loss of AC Power, Rev 45. | |||
B is wrong because both buses are ESF buses but 17AC is not the Div 3 bus. | B is wrong because both buses are ESF buses but 17AC is not the Div 3 bus. | ||
C is wrong because 13AD is not an ESF but does carry a recirc pump MG set which could be plausible if an applicant | C is wrong because 13AD is not an ESF but does carry a recirc pump MG set which could be plausible if an applicant doesnt understand what safety related means. | ||
D is wrong because 14AE is not an ESF but does carry a recirc pump MG set which could be plausible if an applicant | D is wrong because 14AE is not an ESF but does carry a recirc pump MG set which could be plausible if an applicant doesnt understand what safety related means. | ||
Technical | Technical | ||
==References:== | ==References:== | ||
05-1-02-I-4, Loss of AC Power, Revision 45, Section 5.0 Automatic Actions References to be provided to applicants during exam: | 05-1-02-I-4, Loss of AC Power, Revision 45, Section 5.0 Automatic Actions References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: Document learning objective if possible. | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis | ||
New X | |||
Last NRC Exam No | |||
Memory/Fundamental X | |||
This event happened at GGNS as documented in LER 95 | 10CFR Part 55 Content: 55.41(b)(10) | ||
-005-00 | Examination Outline Cross-Reference Level RO 295004 Partial or Total Loss of DC Power Tier # 1 Group # 1 Ability to recognize abnormal indications K/A # 295004 2.4.4 for system operating parameters that are Rating 4.5 entry-level conditions for emergency and abnormal operating procedures. | ||
Question 3 The plant is operating at rated thermal power when an unplanned automatic actuation of the following ESF systems occurs: | |||
Control Room Standby Fresh Air A initiation Combustible Gas Control System A initiation Containment/Drywell Division I isolation Auxiliary Building Division I isolation Standby Service Water System A initiation Standby Gas Treatment System A initiation Auxiliary Building Division I Ventilation isolation At this time, the crew should: | |||
A. restore AC power and enter 05-1-02-V-11 Loss of Plant Service Water. | |||
B. restore DC power and enter 05-1-02-V-11 Loss of Plant Service Water. | |||
C. restore AC power and enter 05-1-02-III-5, Automatic Isolations. | |||
D. restore DC power and enter 05-1-02-III-5, Automatic Isolations. | |||
Answer: D Explanation: | |||
These actuations could not result from a loss of AC, only DC. The affected systems can only be restored by the actions of ONEP 05-1-02-III-5, which resets the affected signals. Plant service water is affected, but 05-1-02-V-11 contains no instructions that will restore service water in this condition. | |||
This event happened at GGNS as documented in LER 95-005-00 Technical | |||
==References:== | ==References:== | ||
Grand Gulf Nuclear Station LER 95 | Grand Gulf Nuclear Station LER 95-005-00. | ||
-005-00. 05-1-02-III-5, Automatic Isolations References to be provided to applicants during exam: | 05-1-02-III-5, Automatic Isolations References to be provided to applicants during exam: None | ||
Learning Objective: GLP-OPS-L1100 Discuss the interrelationships of the following systems with the Plant DC System. (10) ESF Power Distribution System- R21 (10.2) | |||
GLP-OPS-R2100 Describe the interrelationship between the following systems and the ESF Distribution System: (25) 125 Volt DC System - L11 (25.1) | |||
Question Source: New Bank # | |||
(note changes; attach parent) Modified Bank # | |||
New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | |||
D. Main steam isolation valve closure Answer: A | Examination Outline Cross-Reference Level RO 295005 Main Turbine Generator Trip Tier # 1 Group # 1 Knowledge of the interrelations between K/A # 295005 - AK2.02 MAIN TURBINE GENERATOR TRIP and Rating 3.8 the following: RPS Question 04 Which of the following RPS signals also generates a turbine trip signal? | ||
A. Reactor high water level B. Reactor low water level C. High reactor pressure D. Main steam isolation valve closure Answer: A Explanation: | |||
A is correct because this signal generates a turbine trip to protect the turbine from carryover. | A is correct because this signal generates a turbine trip to protect the turbine from carryover. | ||
B is wrong because this signal does not directly generate a turbine trip. | B is wrong because this signal does not directly generate a turbine trip. | ||
Line 112: | Line 87: | ||
==References:== | ==References:== | ||
05-1-02-I-2, Turbine and Generator Trips, Rev 34 References to be provided to applicants during exam: | 05-1-02-I-2, Turbine and Generator Trips, Rev 34 References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: Document learning objective if possible. | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) | ||
New X | |||
Last NRC Exam No | Examination Outline Cross-Reference Level RO 295016 Control Room Abandonment Tier # 1 Group # 1 Knowledge of surveillance procedures K/A # 295016 2.2.12 Rating 3.7 Question 5 All automatic starts of 1P41-C001A, SSW A Pump will at least be momentarily disabled by performance of surveillance procedure: | ||
Memory/Fundamental X | |||
55.41(b)(7) | |||
Examination Outline Cross | |||
-Reference Level RO 295016 Control Room Abandonment | |||
-C001A, SSW A Pump will at least be momentarily disabled by performance of surveillance procedure: | |||
A. 06-OP-1P41-Q-004, SSW Loop A Valve and Pump Operability Test. | A. 06-OP-1P41-Q-004, SSW Loop A Valve and Pump Operability Test. | ||
B. 06-OP-1P41-M-004, SSW Loop A Operability Check. | B. 06-OP-1P41-M-004, SSW Loop A Operability Check. | ||
C. 06-OP-1C61-M-001, Remote Shutdown Panel and Accident Monitoring Instrument Channel Check. | C. 06-OP-1C61-M-001, Remote Shutdown Panel and Accident Monitoring Instrument Channel Check. | ||
D. 06-OP-1C61-R-0002, Remote Shutdown Panel Control Check. | D. 06-OP-1C61-R-0002, Remote Shutdown Panel Control Check. | ||
Answer: D - We will have to check at GG but I am thinking there may be parts of | Answer: D - We will have to check at GG but I am thinking there may be parts of A that will render the SSW pump inoperable. Leave it as is and we will check on it later. | ||
Explanation: | Explanation: | ||
Of these, only the Remote Shutdown Panel Control Check disables auto starts. | Of these, only the Remote Shutdown Panel Control Check disables auto starts. | ||
Line 137: | Line 106: | ||
==References:== | ==References:== | ||
Surveillance Procedure 06 | Surveillance Procedure 06-OP-1C61-R-002, Remote Shutdown Panel Control Check, Table 1, p. 11. | ||
-OP-1C61-R-002, Remote Shutdown Panel Control Check, Table 1, p. 11. | References to be provided to applicants during exam: None GLP-OPS-C6100 Learning Objective: GLP-OPS-C6100 Describe the reason for disabling the Control Room controls by activating the Lockout Transfer Relays on H22-P152 and LOCAL/REMOTE switches on Alternate Shutdown Panels during a fire emergency in the Main Control Room. | ||
References to be provided to applicants during exam: | (11) | ||
-P152 and LOCAL/REMOTE switches on Alternate Shutdown Panels during a fire emergency in the Main Control Room. (11) | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No | ||
New X | |||
Last NRC Exam No | |||
Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | |||
A. Scram the reactor; one CCW pump cannot maintain RRC motor temperatures within specification so manual action is required B. Isolate CCW to FPCCU heat exchangers; maximize cooling to RRC pumps C. Isolate CCW to RWCU heat exchangers; maximize cooling to RRC pumps D. Reduce core flow to 70 mlbm/hr; | Examination Outline Cross-Reference Level RO 295018 Partial or Total Loss of CCW Tier # 1 Group # 1 Knowledge of the reasons for the following K/A # 295018 - AK3.03 responses as they apply to PARTIAL OR Rating 3.1 COMPLETE LOSS OF COMPONENT COOLING WATER: Securing individual components (prevent equipment damage) | ||
Question 06 The plant has been operating full power for 5 months following a refueling outage. One of the 2 running CCW pumps has tripped and the standby pump will not start. What does ONEP 05-1-02-V-1, Loss of Component Cooling Water, direct you to do? What is the reason this action is taken? | |||
A. Scram the reactor; one CCW pump cannot maintain RRC motor temperatures within specification so manual action is required B. Isolate CCW to FPCCU heat exchangers; maximize cooling to RRC pumps C. Isolate CCW to RWCU heat exchangers; maximize cooling to RRC pumps D. Reduce core flow to 70 mlbm/hr; reduce the heat load on RRC pumps Answer: B Explanation: | |||
A is wrong because this would be the appropriate response if this was a complete loss of CCW. Plausible because if the applicant believes this constitutes a complete instead of a partial loss of CCW this is the correct answer. | A is wrong because this would be the appropriate response if this was a complete loss of CCW. Plausible because if the applicant believes this constitutes a complete instead of a partial loss of CCW this is the correct answer. | ||
B is correct because this is specified in step 3.2.2 of the procedure and the note before step 3.2.2 gives the reason for the step. Also, step 3.2.1 was already accomplished because an attempt to start the standby pump was already attempted. | B is correct because this is specified in step 3.2.2 of the procedure and the note before step 3.2.2 gives the reason for the step. Also, step 3.2.1 was already accomplished because an attempt to start the standby pump was already attempted. | ||
Line 159: | Line 124: | ||
==References:== | ==References:== | ||
ONEP 05-1-02-V-1, Loss of Component Cooling Water, Rev. 24, p. 3 | ONEP 05-1-02-V-1, Loss of Component Cooling Water, Rev. 24, p. 3-4 References to be provided to applicants during exam: None. | ||
-4 | Learning Objective: N/A | ||
None. Learning Objective: | |||
Bank # | Question Source: Bank # | ||
Modified Bank # | (note changes; attach parent) Modified Bank # | ||
New X | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(10) | ||
Last NRC Exam No | |||
Memory/Fundamental Comprehensive/Analysis X | Examination Outline Cross-Reference Level RO 295019 Partial or Total Loss of Inst. Air Tier # 1 Group # 1 Ability to obtain and interpret station K/A # 295019 2.2.41 electrical and mechanical drawings. Rating 3.5 Question 7 When TBCW is not available to plant air compressors, aligning SSW to supply cooling water to plant air compressors requires opening valve: | ||
55.41(b)(10) | A. P41-F155A B. P41-F159A C. P41-F160B D. P41-F042 Answer: A Explanation: | ||
Examination Outline Cross | |||
-Reference Level RO 295019 Partial or Total Loss of Inst. Air | |||
A. P41-F155A B. P41-F159A C. P41-F160B | |||
B is wrong because this valve supplies the A drywell purge compressor C is wrong because this is the return from the B drywell purge compressor D is wrong because this is the supply to DRWL CLRS/CCW HXS The valve descriptions are omitted because the purpose of this question is to require use of the P & ID. Giving the valve descriptions makes use of the reference unnecessary. | B is wrong because this valve supplies the A drywell purge compressor C is wrong because this is the return from the B drywell purge compressor D is wrong because this is the supply to DRWL CLRS/CCW HXS The valve descriptions are omitted because the purpose of this question is to require use of the P & ID. Giving the valve descriptions makes use of the reference unnecessary. | ||
Technical | Technical | ||
==References:== | ==References:== | ||
Step 3.3 of ONEP 05 02-V-9, Loss of Instrument Air Standby Service Water System P & I Diagrams M | Step 3.3 of ONEP 05-1-02-V-9, Loss of Instrument Air Standby Service Water System P & I Diagrams M-1061D (G-2) | ||
-1061D (G-2) | References to be provided to applicants during exam: | ||
Standby Service Water System P & I Diagrams M | Standby Service Water System P & I Diagrams M-1061A, B, C, and D Learning Objective: | ||
-1061A, B, C, and D Learning Objective: | Question Source: Bank # | ||
Question Source: | (note changes; attach parent) Modified Bank # | ||
Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X | ||
Modified Bank # | |||
New X | 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Last NRC Exam No | |||
Memory/Fundamental Comprehensive/Analysis X | |||
10CFR Part 55 Content: | |||
55.41(b)(7) 55.43 | |||
What is the current maximum heatup rate? | Examination Outline Cross-Reference Level RO 295021 Loss of Shutdown Cooling Tier # 1 Group # 1 Ability to determine and/or interpret the K/A # 295021 - AA2.01 following as they apply to LOSS OF Rating 3.5 SHUTDOWN COOLING: Reactor water heatup/cooldown rate Question 08 The plant is shut down for 5 days for RF19 with RHR B in service and DIV 1 ESF bus out of service for maintenance. Initial conditions are: | ||
A. 50° | * RPV temperature is 110°F | ||
Since the temperature is 110 | * Fuel shuffling has not commenced | ||
°F the applicant should use the 120 | * Reactor vessel is flooded up to below the flange What is the current maximum heatup rate? | ||
°F curve of Attachment 1, Figure 3, of 05 02-III-1, Inadequate Decay Heat Removal, Rev. 39. Using this curve the difference between 200 | A. 50° B. 80° C. 100° D. 120° Answer: B Explanation: | ||
°F and 120°F is 80°F and the time 5 days after shutdown is 1 hr. All other rates are plausible if the applicant chooses the wrong graph. | Since the temperature is 110°F the applicant should use the 120°F curve of Attachment 1, Figure 3, of 05-1-02-III-1, Inadequate Decay Heat Removal, Rev. 39. Using this curve the difference between 200°F and 120°F is 80°F and the time 5 days after shutdown is 1 hr. All other rates are plausible if the applicant chooses the wrong graph. | ||
Technical | Technical | ||
==References:== | ==References:== | ||
05-1-02-III-1, Inadequate Decay Heat Removal, Rev. 39 References to be provided to applicants during exam: | 05-1-02-III-1, Inadequate Decay Heat Removal, Rev. 39 References to be provided to applicants during exam: All attachments from 05-1-02-III-1, Inadequate Decay Heat Removal, Rev. 39 Learning Objective: Document learning objective if possible. | ||
All attachments from 05 02-III-1, Inadequate Decay Heat Removal, Rev. 39 Learning Objective: | Question Source: Bank # | ||
Question Source: | (note changes; attach parent) Modified Bank # | ||
Bank # | |||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(5) | ||
New X | |||
Last NRC Exam No | Examination Outline Cross-Reference Level RO 295023 Refueling Accident Tier # 1 Group # 1 Ability to determine and/or interpret the K/A # 295023 AA2.01 following as they apply to REFUELING Rating 3.6 ACCIDENTS : Area radiation levels. | ||
Memory/Fundamental X | Question 9 Refueling activities are in progress. A CONTAINMENT FUEL HDLG AREA RADIATION HIGH alarm is received. No other alarms are received at this time. This condition could be caused by: | ||
55.41(b)(5) | |||
Examination Outline Cross | |||
-Reference Level RO 295023 Refueling Accident | |||
A. a fuel assembly being inadvertently raised too high at the refueling platform. | A. a fuel assembly being inadvertently raised too high at the refueling platform. | ||
B. drop of a spent fuel assembly from the refueling platform. | B. drop of a spent fuel assembly from the refueling platform. | ||
C. a fuel assembly being inadvertently raised too high at the fuel handling platform. | C. a fuel assembly being inadvertently raised too high at the fuel handling platform. | ||
D. drop of a spent fuel assembly from the fuel handling platform. | D. drop of a spent fuel assembly from the fuel handling platform. | ||
Answer: A | Answer: A Explanation: | ||
Raising an irradiated fuel assembly too high could result in reduced shielding with a subsequent rise in area radiation levels. | Raising an irradiated fuel assembly too high could result in reduced shielding with a subsequent rise in area radiation levels. | ||
B and D are wrong because if release of gaseous activity from a damaged fuel assembly is the cause of the area radiation alarm, this would be accompanied by gaseous process radiation alarms. C and D are wrong because the fuel handling platform is not in the containment building. | B and D are wrong because if release of gaseous activity from a damaged fuel assembly is the cause of the area radiation alarm, this would be accompanied by gaseous process radiation alarms. | ||
C and D are wrong because the fuel handling platform is not in the containment building. | |||
Technical | Technical | ||
Line 228: | Line 177: | ||
ARI 04-1-02-1H13-P844-1A-A3, CONTAINMENT FUEL HDLG AREA RADIATION HIGH. | ARI 04-1-02-1H13-P844-1A-A3, CONTAINMENT FUEL HDLG AREA RADIATION HIGH. | ||
Lesson plan GLP | Lesson plan GLP-RF-F1101, Fuel handling/Refueling Platform References to be provided to applicants during exam: | ||
-RF-F1101, Fuel handling/Refueling | None Learning Objective: GLP-OPS-D1721 Given applicable Alarm Response Instructions (ARIs) and plant conditions, state/identify the probable causes for any alarm listed in the System Alarm Index of SOI 04-1-01-D17-1 and SOI 04-1-01-D21-1 (NLOs responsible for LOCAL Panels only). (19) | ||
None | Question Source: Bank # | ||
Question Source: | (note changes; attach parent) Modified Bank # | ||
Bank # | New X | ||
Modified Bank # | |||
New X | |||
B. tripped on no minimum flow path. | Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
C. received a close signal and is tripped. | |||
D. received a close signal and is running. | Examination Outline Cross-Reference Level RO 295024 High Drywell Pressure Tier # 1 Group # 1 Ability to operate and/or monitor the K/A # 295024 - EA1.04 following as they apply to HIGH Rating 4.1 DRYWELL PRESSURE: RHR/LPCI Question 10 The plant has scrammed after receiving a high drywell pressure signal. The amber light above the RHR A pump is lit indicating the A RHR pump breaker has A. tripped on a load shed. | ||
Answer: C | B. tripped on no minimum flow path. | ||
A is wrong because there would not be a reason for the pump to trip on a load shed. The applicant should assume all equipment was in a normal position, so the pump | C. received a close signal and is tripped. | ||
D. received a close signal and is running. | |||
Answer: C Explanation: | |||
A is wrong because there would not be a reason for the pump to trip on a load shed. The applicant should assume all equipment was in a normal position, so the pump wouldnt trip. | |||
The pump should load after LSS is complete. | The pump should load after LSS is complete. | ||
B is wrong because there is no trip on no minimum flow path, but plausible since this should be an immediate action for operators. Applicants may confuse the immediate action with preventing an automatic action from occurring. | B is wrong because there is no trip on no minimum flow path, but plausible since this should be an immediate action for operators. Applicants may confuse the immediate action with preventing an automatic action from occurring. | ||
C is correct because this is the meaning of the light per Table 1 of GFIG | C is correct because this is the meaning of the light per Table 1 of GFIG-OPS-E1200. | ||
-OPS-E1200. D is wrong because of C. | D is wrong because of C. | ||
Technical | Technical | ||
==References:== | ==References:== | ||
Comprehensive/Analysis 10CFR Part 55 Content: | GFIG-OPS-E1200, Residual Heat Removal (RHR) System - Figures, Rev 1 References to be provided to applicants during exam: None. | ||
55.41(b)(7) | Learning Objective: Document learning objective if possible. | ||
Examination Outline Cross | Question Source: Bank # | ||
-Reference Level RO 295025 High Reactor Pressure Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE: Reactor pressure. | (note changes; attach parent) Modified Bank # | ||
New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental | |||
Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) | |||
Examination Outline Cross-Reference Level RO 295025 High Reactor Pressure Tier # 1 Group # 1 Ability to determine and/or interpret the K/A # 295025 EA2.01 following as they apply to HIGH REACTOR Rating 4.3 PRESSURE: Reactor pressure. | |||
Question 11 A reactor vessel steam dome high pressure scram signal should be the signal that first generates a reactor scram on a: | |||
A. single MSIV closure with reactor power at 75%. | A. single MSIV closure with reactor power at 75%. | ||
B. closure of all MSIVs at full power. | B. closure of all MSIVs at full power. | ||
C. turbine trip at full power. | C. turbine trip at full power. | ||
D. pressure controller failing closed with reactor power at 75%. | D. pressure controller failing closed with reactor power at 75%. | ||
Answer: D | Answer: D Explanation: | ||
Interpreting reactor pressure involves determining if it is responding as expected. | Interpreting reactor pressure involves determining if it is responding as expected. | ||
A is wrong because this should not result in a scram. | A is wrong because this should not result in a scram. | ||
Line 281: | Line 223: | ||
==References:== | ==References:== | ||
Mitigating of Core Damage (EPTS | Mitigating of Core Damage (EPTS-2) Pressure Increase Events, GLP-OPS-MCD12 References to be provided to applicants during exam: None. | ||
-2) Pressure Increase Events, GLP | Learning Objective: GLP-OPS-MCD12 Given a pressure increase event and associated plant parameter curves, explain the behavior of the plant parameters.(2) | ||
-OPS-MCD12 | Question Source: Bank # | ||
None. Learning Objective: | (note changes; attach parent) Modified Bank # | ||
New X Question History: Last NRC Exam No | |||
Bank # | |||
Modified Bank # | Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
New X | |||
Last NRC Exam No Question Cognitive Level: | Examination Outline Cross-Reference Level RO 295026 Suppression Pool High Water Temp Tier # 1 Group # 1 Knowledge of the reasons for the following K/A # 295026 - EK3.05 responses as they apply to SUPPRESSION Rating 3.9 POOL HIGH WATER TEMPERATURE: | ||
Memory/Fundamental X | Reactor SCRAM Question 12 The reason for transitioning out of EP-3, Containment Control, before suppression pool temperature reaches 110oF is to ensure: | ||
55.41(b)(7) 55. | |||
-Reference Level RO 295026 Suppression Pool High Water Temp Knowledge of the reasons for the following responses as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Reactor SCRAM | |||
-3, Containment Control, before suppression pool temperature reaches | |||
A. There is an adequate NPSH for all pumps taking suction off of the suppression pool. | A. There is an adequate NPSH for all pumps taking suction off of the suppression pool. | ||
B. All pumps taking suction from the suppression pool will not become gas bound. | B. All pumps taking suction from the suppression pool will not become gas bound. | ||
C. Containment pressure remains below 10 psig during a design basis accident. | C. Containment pressure remains below 10 psig during a design basis accident. | ||
D. EP-2, RPV Control, is initiated before reaching maximum boron injection | D. EP-2, RPV Control, is initiated before reaching maximum boron injection initiation temperature. | ||
Answer: D | Answer: D Explanation: | ||
A is wrong because NPSH is only referenced for level and not temperature. This is plausible since NPSH is a combination of both. | A is wrong because NPSH is only referenced for level and not temperature. This is plausible since NPSH is a combination of both. | ||
B is wrong because gas binding of pumps is not mentioned for high suppression pool temperatures. | B is wrong because gas binding of pumps is not mentioned for high suppression pool temperatures. | ||
Line 307: | Line 246: | ||
==References:== | ==References:== | ||
05-S-01-PSTG, Plant Specific Technical Guidelines, Rev 05 References to be provided to applicants during exam: | 05-S-01-PSTG, Plant Specific Technical Guidelines, Rev 05 References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: Document learning objective if possible. | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis | ||
New X | |||
Last NRC Exam No | |||
Memory/Fundamental X | |||
10CFR Part 55 Content: | 10CFR Part 55 Content: 55.41(b)(7);(8) | ||
55.41(b)(7);(8) | Examination Outline Cross-Reference Level RO 295027 High Containment Temperature Tier # 1 Group # 1 Knowledge of the reasons for the following K/A # 295027 EK3.02 responses as they apply to HIGH Rating 3.2 CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) : Containment spray: | ||
Examination Outline Cross | Plant specific. | ||
-Reference Level RO 295027 High Containment Temperature Knowledge of the reasons for the following responses as they apply to HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) : Containment spray: | Question 13 The reason containment sprays are used to mitigate high containment temperature ONLY when containment pressure is relatively high is this: | ||
A. ensures the steam formation will not over-pressurize containment. | |||
A. ensures the steam formation will not over | |||
-pressurize containment. | |||
B. prevents an excessive rate of depressurization. | B. prevents an excessive rate of depressurization. | ||
C. ensures RHR pump discharge pressure is adequate to prevent runout. | C. ensures RHR pump discharge pressure is adequate to prevent runout. | ||
D. prevents excessive flow through the RHR heat exchanger. | D. prevents excessive flow through the RHR heat exchanger. | ||
Answer: B | Answer: B Explanation: | ||
The CSIPL does not allow spray to be initiated when temperature is high and pressure is low. | The CSIPL does not allow spray to be initiated when temperature is high and pressure is low. | ||
Spray with high temperature and low pressure results in a rapid cooldown/depressurization which may lead to forming a negative pressure in containment with subsequent loss of containment integrity. | Spray with high temperature and low pressure results in a rapid cooldown/depressurization which may lead to forming a negative pressure in containment with subsequent loss of containment integrity. | ||
Line 339: | Line 272: | ||
BWROG EP Guidelines section 17.9. | BWROG EP Guidelines section 17.9. | ||
References to be provided to applicants during exam: | References to be provided to applicants during exam: | ||
Learning Objective: GLP-OPS-EP3 7. State/identify the basis associated with each individual step in EP | Learning Objective: GLP-OPS-EP3 | ||
-3. Question Source: | : 7. State/identify the basis associated with each individual step in EP-3. | ||
Bank # | Question Source: Bank # | ||
(note changes; attach parent) Modified Bank # | |||
New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) 55.43 | |||
Examination Outline Cross-Reference Level RO 295028 High Drywell Temperature Tier # 1 Group # 1 Knowledge of EOP entry conditions and K/A # 295028 - 2.4.1 immediate action steps. Rating 4.3 Question 14 Which of the following would require an entry into 05-S-01-EP-3, Containment Control? | |||
If you were required to enter 05-S-01-EP-2, RPV Control, based on not being able to control a parameter in EP-3, what would your immediate action be upon entry into EP-2? | |||
A. Suppression Pool temperature at 85oF Maximize Suppression Pool cooling B. Drywell pressure at 1.15 psig Prevent ECCS injection C. Drywell temperature at 145oF Verify the Reactor Mode Switch in Shutdown D. Suppression Pool level at 18.45 ft Inhibit ADS Answer: C Explanation: | |||
A wrong because this temperature would not require entry into the EOP. The immediate action is not an action required when entering EP-2, but is reasonable for a high temperature. | |||
-Reference Level RO 295028 High Drywell Temperature Knowledge of EOP entry conditions and | B is wrong because the pressure would not require entry into the EOP. The immediate action is a step in EP-2 for high drywell pressure but pressure has to be above 1.39 psig. | ||
C is correct because this temperature is above the entry criteria of 135oF. The immediate action is correct upon entry into EP-2. | |||
-S-01-EP-3, Containment Control? | D is wrong because the level would not require entry into an EOP. The immediate action is a step in the EP-2 procedure that should be second nature to an applicant so they could believe it is an immediate action. | ||
If you were required to enter 05 | |||
-S-01-EP-2, RPV Control, based on not being able to control a parameter in EP | |||
-3, what would your immediate action be upon entry into EP | |||
-2? | |||
A wrong because this temperature would not require entry into the EOP. The immediate action is not an action required when entering EP | |||
-2, but is reasonable for a high temperature. | |||
B is wrong because the pressure would not require entry into the EOP. The immediate action is a step in EP | |||
-2 for high drywell pressure but pressure has to be above 1.39 psig. | |||
C is correct because this temperature is above the entry criteria of | |||
-2. D is wrong because the level would not require entry into an EOP. The immediate action is a step in the EP | |||
-2 procedure that should be second nature to an applicant so they could believe it is an immediate action. | |||
Technical | Technical | ||
==References:== | ==References:== | ||
05-S-01-EP-3, Containment Control 05-S-01-EP-2, RPV Control References to be provided to applicants during exam: | 05-S-01-EP-3, Containment Control 05-S-01-EP-2, RPV Control References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(10) | ||
New X | |||
Last NRC Exam No | |||
Memory/Fundamental X | |||
55.41(b)(10) | |||
Examination Outline Cross | Examination Outline Cross-Reference Level RO 295030 Low Suppression Pool Wtr Lvl Tier # 1 Group # 1 Knowledge of the reasons for the following K/A # 295030 EK3.06 responses as they apply to LOW Rating 3.6 SUPPRESSION POOL WATER LEVEL: | ||
-Reference Level RO 295030 Low Suppression Pool Wtr Lvl Knowledge of the reasons for the following responses as they apply to LOW SUPPRESSION POOL WATER LEVEL: Reactor SCRAM | Reactor SCRAM Question 15 The reason a reactor scram is required on a low suppression pool level is: | ||
A. the drywell to containment suppression pool vents will become uncovered. B. the SRV sparger will become uncovered C. the ECCS pumps may fail due to vortexing. | A. the drywell to containment suppression pool vents will become uncovered. | ||
B. the SRV sparger will become uncovered C. the ECCS pumps may fail due to vortexing. | |||
D. a LOCA may result in a loss of containment.. | D. a LOCA may result in a loss of containment.. | ||
Answer: | Answer: D Explanation: | ||
The EP technical basis states that the reason is to preserve containment integrity | The EP technical basis states that the reason is to preserve containment integrity because the SP may not adequately condense steam on a primary system break.. | ||
Technical | Technical | ||
==References:== | ==References:== | ||
EP-2, RPV Control EP-3, Containment control EP Technical Basis, Step References to be provided to applicants during exam: None | EP-2, RPV Control EP-3, Containment control EP Technical Basis, Step References to be provided to applicants during exam: None Learning Objective: GLP-OPS-EP3 | ||
: 7. State/identify the basis associated with each individual step in EP-3. | |||
-3. Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No | ||
New X | |||
Last NRC Exam No Question Cognitive Level: | Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Memory/Fundamental X | |||
55.41(b)(7) 55.43 Examination Outline Cross | Examination Outline Cross-Reference Level RO 295031 Reactor Low Water Level Tier # 1 Group # 1 Knowledge of the reasons for the following K/A # 295031 - EK3.01 responses as they apply to REACTOR LOW Rating 3.9 WATER LEVEL: Automatic depressurization system actuation Question 16 The reason for the 105 second time delay before ADS initiation is to allow enough time A. To inhibit ADS if not desired. | ||
-Reference Level RO 295031 Reactor Low Water Level Knowledge of the reasons for the following responses as they apply to REACTOR LOW WATER LEVEL: Automatic depressurization system actuation | B. To ensure systems are aligned for an emergency depressurization. | ||
B. To ensure systems are aligned for an emergency depressurization. | C. For RCIC to recover RPV level. | ||
C. For RCIC to recover RPV level. | D. For HPCS to recover RPV level. | ||
D. For HPCS to recover RPV level. | Answer: D Explanation: | ||
Answer: D | |||
A is wrong because it is not the reason for the timer exists but plausible if an applicant believes the system initiation is based on the emergency procedure. | A is wrong because it is not the reason for the timer exists but plausible if an applicant believes the system initiation is based on the emergency procedure. | ||
B is wrong because emergency depressurization does use the ADS valves and proper alignment is needed but an emergency depressurization occurs much later in the emergency | B is wrong because emergency depressurization does use the ADS valves and proper alignment is needed but an emergency depressurization occurs much later in the emergency procedure and it is not the basis for the timer. | ||
procedure and it is not the basis for the timer. | |||
C is wrong because it is the incorrect high pressure system but plausible if an applicant confuses RCIC for an ECCS system. | C is wrong because it is the incorrect high pressure system but plausible if an applicant confuses RCIC for an ECCS system. | ||
D is correct because the reason is specified in the training manaual. | D is correct because the reason is specified in the training manaual. | ||
Line 411: | Line 330: | ||
GLP-OPS-E2202, Automatic Depressurization System (ADS) | GLP-OPS-E2202, Automatic Depressurization System (ADS) | ||
References to be provided to applicants during exam: | References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: Describe the signals and setpoints for the initiation of the ADS System for both automatic and manual initiation. | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No | ||
New X | |||
Last NRC Exam No Question Cognitive Level: | Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(8),(10) | ||
Memory/Fundamental X | |||
55.41(b)(8),(10) | |||
A. to -70 | Examination Outline Cross-Reference Level RO 295037 SCRAM Condition Present Tier # 1 and Reactor Power Above APRM Downscale Group # 1 or Unknown K/A # 295037 2.4.6 Rating 3.7 Knowledge of EOP mitigation strategies Question 17 The plant was at rated thermal power when a turbine trip occurred. Multiple control rods remained at the fully withdrawn position. Currently; | ||
-70 | * Reactor power is 10% | ||
B. until power is below 5% or level drops to | * RPV level is 18 | ||
-167 | * Reactor pressure is 935 psig being controlled by the turbine bypass valves. | ||
-191 | According to EP-2A, ATWS RPV Control, the crew should lower RPV level: | ||
-191 | A. to -70 and maintain it as close to -70 as possible. | ||
A is wrong because, while level is initially lowered to | B. until power is below 5% or level drops to -167. | ||
-70 | C. to between -191 and -167 D. to between -191 and -70. | ||
-191 | Answer: D Explanation: | ||
A is wrong because, while level is initially lowered to -70 in step 7.1, step 9 subsequently directs a level band of -191 and -70 B and C are correct only if SRVs are open. | |||
Technical | Technical | ||
==References:== | ==References:== | ||
EP-2A, Revision Date 5/15/12 References to be provided to applicants during exam: | EP-2A, Revision Date 5/15/12 References to be provided to applicants during exam: None Learning Objective: | ||
None | Question Source: Bank # | ||
Question Source: | (note changes; attach parent) Modified Bank # | ||
Bank # | New X | ||
Modified Bank # | |||
New X | |||
08-S-03-22, INSTALLED RADIATION MONITORING SYSTEM ALARM SETPOINT DETERMINATION AND CONTROL, Rev 114. | Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(10) 55.43 | ||
Examination Outline Cross-Reference Level RO 295038 High Off-site Release Rate Tier # 1 Group # 1 Knowledge of the interrelations between K/A # 295038 - EK2.02 HIGH OFF-SITE RELEASE RATE and the Rating 3.6 following: Offgas System Question 18 To prevent an off-site release greater than allowable limits, the Offgas system isolates when (a) __________ Upscale HI-HI-HI trip channel is(are) received. The Upscale HI-HI-HI alarm setpoint is ____________ throughout an operating cycle by Chemistry. | |||
A. single; fixed B. single; varied C. both; fixed D. both; varied Answer: D Explanation: | |||
A is wrong because it takes both Upscale HI-HI-HI alarms to isolate Offgas but it takes a single alarm to take the system out of bypass which makes this answer plausible. This value can be varied throughout an operating cycle at management discretion according to procedure 08-S-03-22, INSTALLED RADIATION MONITORING SYSTEM ALARM SETPOINT DETERMINATION AND CONTROL, Rev 114. | |||
B is wrong because the first answer is false but the second is true C is wrong because it takes both channels to generate a trip but the setpoint can be varied at any time throughout the cycle. | B is wrong because the first answer is false but the second is true C is wrong because it takes both channels to generate a trip but the setpoint can be varied at any time throughout the cycle. | ||
D is correct because it takes both channels to isolate and the setpoint can be varied. | D is correct because it takes both channels to isolate and the setpoint can be varied. | ||
Line 461: | Line 368: | ||
==References:== | ==References:== | ||
Procedure 08-S-03-22, INSTALLED RADIATION MONITORING SYSTEM ALARM SETPOINT DETERMINATION AND CONTROL, Revision 114 References to be provided to applicants during exam: | Procedure 08-S-03-22, INSTALLED RADIATION MONITORING SYSTEM ALARM SETPOINT DETERMINATION AND CONTROL, Revision 114 References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: Discuss the types of alarms received on the Radiation Monitoring Systems. (8) | ||
Describe the automatic actions initiated by the Process Radiation Monitoring. (15) | Describe the automatic actions initiated by the Process Radiation Monitoring. (15) | ||
Question Source: Bank # | Question Source: Bank # | ||
Modified Bank # | (note changes; attach parent) Modified Bank # | ||
New X | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(11) | ||
Last NRC Exam No | |||
Memory/Fundamental X | |||
55.41(b)(11) | |||
B. | Examination Outline Cross-Reference Level RO 600000 Plant Fire On Site Tier # 1 Group # 1 Ability to operate and / or monitor the following K/A # 600000 AA1.06 as they apply to PLANT FIRE ON SITE: Fire Rating 3.0 Alarm Question 19 A rate-of-rise heat detector in the B RPS MG room triggers a local fire alarm. The expected fire system response is a: | ||
A. CO2 discharge occurs immediately. | |||
B. CO2 discharge occurs after a 30 second delay. | |||
C. halon discharge occurs immediately. | C. halon discharge occurs immediately. | ||
D. halon discharge occurs after a 30 second delay. Answer: B | D. halon discharge occurs after a 30 second delay. | ||
Answer: B Explanation: | |||
C and D are wrong because this room is not protected by Halon. | C and D are wrong because this room is not protected by Halon. | ||
A is wrong because the discharge is delayed to allow for evacuation. | A is wrong because the discharge is delayed to allow for evacuation. | ||
Line 483: | Line 388: | ||
==References:== | ==References:== | ||
GFIG-OPS-P6400 Figure 11, Typical | GFIG-OPS-P6400 Figure 11, Typical CO2 Control Station. | ||
References to be provided to applicants during exam: | References to be provided to applicants during exam: | ||
Learning Objective: GLP-OPS-P6400 Describe the automatic actions/features associated with each of the following Fire Protection System components, including setpoints and bypasses (if applicable): | Learning Objective: GLP-OPS-P6400 Describe the automatic actions/features associated with each of the following Fire Protection System components, including setpoints and bypasses (if applicable): (6.0) Fire Protection C02 System, including automatic and manual start (6.6) | ||
Question Source: Bank # | |||
Question Source: | (note changes; attach parent) Modified Bank # | ||
Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis | ||
Modified Bank # | |||
New X | 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Last NRC Exam No | |||
Memory/Fundamental X | |||
Examination Outline Cross-Reference Level RO 700000 Generator Voltage and Electric Grid Tier # 1 Disturbances Group # 1 K/A # 700000 - AA1.03 Ability to operate and/or monitor the Rating 3.8 following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Voltage regulator controls Question 20 What is the maximum allowable reactive load allowed during normal and emergency conditions? | |||
Which pushbuttons are used to change reactive load? | |||
-Reference Level RO 700000 Generator Voltage and Electric Grid Disturbances Ability to operate and/or monitor the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Voltage regulator controls | A. +253 MVARS; TVR raise/lower B. +253 MVARS; Load Demand raise/lower C. +297.5 MVARS; TVR raise/lower D. +297.5 MVARS; Load Demand raise/lower Answer: C Explanation: | ||
A. | A is wrong because the maximum reactive load is listed in 04-1-01-N40-1 as +297.5 in P&L 3.8. A -253 corresponds to the minimum reactive load allowed by procedure. This is plausible if the applicant reverses the signs on maximum load. | ||
A is wrong because the maximum reactive load is listed in 04 01-N40-1 as +297.5 in P&L 3.8. A -253 corresponds to the minimum reactive load allowed by procedure. This is plausible if the applicant reverses the signs on maximum load. | B is wrong because this does not meet the maximum specified in procedure. Also, changing the load with the load demand pushbuttons changes actual load and not reactive load. This is plausible if an applicant doesnt understand the difference in grid/turbine load. | ||
B is wrong because this does not meet the maximum specified in procedure. Also, changing the load with the load demand pushbuttons changes actual load and not reactive load. This is plausible if an applicant | |||
C is correct because this is the correct value and the correct button D is wrong because the incorrect pushbutton is listed. | C is correct because this is the correct value and the correct button D is wrong because the incorrect pushbutton is listed. | ||
Technical | Technical | ||
Line 505: | Line 407: | ||
==References:== | ==References:== | ||
04-1-01-N40-1, Main Generator and Auxiliaries, Rev 37, p.4, P&L 3.8 Describe how the output voltage of the Main Generator is varied, including any limitations. (8) | 04-1-01-N40-1, Main Generator and Auxiliaries, Rev 37, p.4, P&L 3.8 Describe how the output voltage of the Main Generator is varied, including any limitations. | ||
None. Learning Objective: | (8) | ||
Bank # | References to be provided to applicants during exam: None. | ||
Modified Bank # | Learning Objective: Identify precautions, limitations, cautions, warnings and notes which apply to a given situation and are related to the Main Generator. (14.1). | ||
Question Source: Bank # | |||
(note changes; attach parent) Modified Bank # | |||
New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(10) | |||
Examination Outline Cross-Reference Level RO 295002 Loss of Main Condenser Vac Tier # 1 Group # 2 Knowledge of the interrelations between LOSS K/A # 295002 AK2.07 OF MAIN CONDENSER VACUUM and the Rating 3.1 following: Offgas system Question 21 With the plant at rated power, for which of the following alarms would a slow, gradual loss of condenser vacuum be expected? | |||
A. OG POST-TREAT RAD HI-HI-HI/INOP. | |||
Examination Outline Cross | |||
-Reference Level RO 295002 Loss of Main Condenser Vac Knowledge of the interrelations between LOSS | |||
A. OG POST-TREAT RAD HI | |||
-HI-HI/INOP. | |||
B. OG RADWST VENT RAD HI. | B. OG RADWST VENT RAD HI. | ||
C. OG CHAR VAULT RAD HI. | C. OG CHAR VAULT RAD HI. | ||
D. MSL B/MSL C RAD HI | D. MSL B/MSL C RAD HI-HI/INOP. | ||
-HI/INOP. Answer: A | Answer: A Explanation: | ||
OG POST-TREAT RAD HI | OG POST-TREAT RAD HI-HI-HI/INOP isolates condenser off-gas, which, according to 05 02-V-8 Loss of Condenser Vacuum should lead to a slow, gradual reduction in condenser vacuum. | ||
-HI-HI/INOP isolates condenser off | OG RADWST VENT RAD HI has no automatic actions. | ||
-gas, which, according to 05 02-V-8 | OG CHAR VAULT RAD HI has no automatic actions. | ||
MSL B/MSL C RAD HI | MSL B/MSL C RAD HI-HI/INOP only results in a half-trip. | ||
-HI/INOP only results in a half | Technical | ||
-trip. Technical | |||
==References:== | ==References:== | ||
05-1-02-V-8, Loss of Condenser Vacuum 05-1-02-II-2, Off-Gas Activity High References to be provided to applicants during exam: | 05-1-02-V-8, Loss of Condenser Vacuum 05-1-02-II-2, Off-Gas Activity High References to be provided to applicants during exam: | ||
Learning Objective: GLP-OPS-N6200 13. Discuss the interrelationships of the following systems with the Condenser Air Removal System. h. Process Radiation Monitoring System, D17 | Learning Objective: GLP-OPS-N6200 | ||
Bank # | : 13. Discuss the interrelationships of the following systems with the Condenser Air Removal System. h. Process Radiation Monitoring System, D17 i. Offgas System, N64 Question Source: Bank # | ||
Modified Bank # | (note changes; attach parent) Modified Bank # | ||
New X | New X Question History: Last NRC Exam No | ||
Last NRC Exam No Question Cognitive Level: | |||
Memory/Fundamental Comprehensive/Analysis X | Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
55.41(b)(7) 55.43 Examination Outline Cross | |||
-Reference Level RO Low Reactor Water Level | Examination Outline Cross-Reference Level RO Low Reactor Water Level Tier # 1 Group # 2 Knowledge of the interrelations between K/A # 295009 - AK2.04 LOW REACTOR WATER LEVEL and the Rating 2.6 following: Reactor water cleanup Question 22 Which of the following would result in the isolation of Reactor Water Cleanup? | ||
A. Reactor vessel water level at | A. Reactor vessel water level at -50. | ||
-50 | B. Main steam line tunnel temperature at 165oF. | ||
Answer: A | C. RWCU heat exchanger room at 110oF. | ||
-41.6 | D. RWCU differential flow at 70 gpm for 30 seconds. | ||
Answer: A Explanation: | |||
A is correct because it is less than the setpoint of -41.6 B is wrong because the setpoint is at 185oF C is wrong because the setpoint is 120oF D is wrong because the setpoint is 79 gpm for 45 seconds Technical | |||
==References:== | ==References:== | ||
GLP-OPS-G3336, Rev 16, Reactor Water Cleanup System References to be provided to applicants during exam: | GLP-OPS-G3336, Rev 16, Reactor Water Cleanup System References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: 8.6 Describe automatic actions associated with system isolation valves. | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b) 55.43 | ||
Last NRC Exam No | |||
Memory/Fundamental X | |||
55.41(b) | |||
Examination Outline Cross | Examination Outline Cross-Reference Level RO 295010 High Drywell Pressure Tier # 1 Group # 2 Ability to operate and/or monitor the following K/A # 295010 AA1.01 as they apply to HIGH DRYWELL Rating 3.4 PRESSURE: Drywell ventilation/cooling Question 23 An energized white light above the associated drywell chiller hand switch in the control room indicates the chiller: | ||
-Reference Level RO 295010 High Drywell Pressure | |||
A. is in standby. | A. is in standby. | ||
B. is in local control. | B. is in local control. | ||
C. has tripped. | C. has tripped. | ||
D. has auto started. | D. has auto started. | ||
Answer: | Answer: A Explanation: | ||
B , C, and D are wrong because A is correct. | B, C, and D are wrong because A is correct. | ||
Technical | Technical | ||
==References:== | ==References:== | ||
04-1-02-1H13-P601- | 04-1-02-1H13-P601-16A-B4, ARI for DRWL PRESS HI GLP-OPS-M5100, Drywell Cooling and Drywell Chilled Water Systems References to be provided to applicants during exam: None Learning Objective: GLP-OPS-M5100. 04 State/identify the locations from which the following components of the Drywell Cooling and Drywell Chilled Water Systems can be found. Drywell Coolers Drywell Chillers Obj 6, Describe the automatic actions . . . Drywell Chillers Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis | ||
Last NRC Exam No | |||
Memory/Fundamental X | |||
10CFR Part 55 Content: | 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
55.41(b)(7) 55.43 Examination Outline Cross | |||
-Reference Level RO 295011 High Containment Temp Knowledge of the interrelations between HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) and the following: Containment ventilation/cooling: Mark | Examination Outline Cross-Reference Level RO 295011 High Containment Temp Tier # 1 Group # 2 Knowledge of the interrelations between K/A # 295011 - AK2.01 HIGH CONTAINMENT TEMPERATURE Rating 3.7 (MARK III CONTAINMENT ONLY) and the following: Containment ventilation/cooling: Mark-III. | ||
-III. | Question 24 What is/are the MINIMUM number of fan coolers required to be in service per SOI 04-1 M41, Containment Cooling System? Will containment fan coolers receive an auto start signal if a high containment temperature alarm is received? | ||
A. 1/Yes | A. 1/Yes B. 2/No C. 1/No D. 2/Yes Answer: B Explanation: | ||
A is wrong because the minimum number required is 2 and there is no auto start on high containment temperature. | A is wrong because the minimum number required is 2 and there is no auto start on high containment temperature. | ||
B is correct because the minimum required is 2 and the only auto start for the fan coolers is on low flow across a fan. | B is correct because the minimum required is 2 and the only auto start for the fan coolers is on low flow across a fan. | ||
Line 590: | Line 481: | ||
==References:== | ==References:== | ||
GLP-OPS-M4100, Containment Cooling System M41, Rev 5 Note from 04 01-M41, Containment Cooling System: | GLP-OPS-M4100, Containment Cooling System M41, Rev 5 Note from 04-1-01-M41, Containment Cooling System: | ||
The following operations are performed at 1H13-P842, Unless otherwise noted. Two OR three Containment coolers Should be in service during normal operations. | |||
References to be provided to applicants during exam: None. | |||
None. Learning Objective: | Learning Objective: 10.1 State/identify the interlocks associated with starting and stopping of fans. | ||
Question Source: | |||
Bank # | Question Source: Bank # | ||
Modified Bank # | (note changes; attach parent) Modified Bank # | ||
New X | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(10) | ||
Last NRC Exam No | |||
Memory/Fundamental X | Examination Outline Cross-Reference Level RO 295012 High Drywell Temperature Tier # 1 Group # 2 Knowledge of the operational implications of K/A # 295010 AK1.01 the following concepts as they apply to HIGH Rating 3.3 DRYWELL TEMPERATURE : | ||
55.41(b)(10) | Pressure/temperature relationship Question 25 The purpose of the RPV Saturation Temperature (RPVST) curve is to evaluate the effect of drywell temperature on: | ||
Examination Outline Cross | |||
-Reference Level RO 295012 High Drywell Temperature Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL TEMPERATURE : Pressure/temperature relationship | |||
A. reactor vessel integrity. | A. reactor vessel integrity. | ||
B. containment integrity. | B. containment integrity. | ||
C. RPV level instrumentation accuracy. | C. RPV level instrumentation accuracy. | ||
D. RPV pressure instrumentation accuracy. | D. RPV pressure instrumentation accuracy. | ||
Answer: | Answer: C Explanation: | ||
The RPV Saturation Temperature is a plot of the saturation temperature of water as a function of pressure. If the temperature of the water in an RPV water level instrument run exceeds this temperature, the water may start to boil, resulting in unreliable level indication. | The RPV Saturation Temperature is a plot of the saturation temperature of water as a function of pressure. If the temperature of the water in an RPV water level instrument run exceeds this temperature, the water may start to boil, resulting in unreliable level indication. | ||
Technical | Technical | ||
Line 615: | Line 503: | ||
02-S-01-40, p. 42 of 45. | 02-S-01-40, p. 42 of 45. | ||
References to be provided to applicants during exam: | References to be provided to applicants during exam: none Learning Objective: GLP-OPS- Describe the system interrelationship between the Drywell Cooling and Drywell Chilled Water Systems and the following: (10) Containment and Drywell Instrumentation and Control System (10.6) | ||
none | Question Source: Bank # | ||
Question Source: | (note changes; attach parent) Modified Bank # | ||
Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X | ||
Modified Bank # | |||
New X | 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Last NRC Exam No | |||
Memory/Fundamental Comprehensive/Analysis X | Examination Outline Cross-Reference Level RO 295013 High Suppression Pool Temperature Tier # 1 Group # 2 Ability to operate and/or monitor the K/A # 295013 - AA1.01 following as they apply to HIGH Rating 3.9 SUPPRESSION POOL TEMPERATURE: | ||
10CFR Part 55 Content: | Suppression pool cooling Question 26 RHR B is in service in suppression pool cooling mode due to high temperature in the suppression pool from RCIC operability testing. According to procedure 04-1-01-E12-1, Residual Heat Removal System, the RHR system flow must be maintained greater than | ||
55.41(b)(7) 55.43 Examination Outline Cross | _________. At what minimum temperature should suppression pool cooling be secured? | ||
-Reference Level RO 295013 High Suppression Pool Temperature Ability to operate and/or monitor the following as they apply to HIGH SUPPRESSION POOL TEMPERATURE: Suppression pool cooling | A. 7300 gpm; 65oF B. 7300 gpm; 70oF C. 7450 gpm; 65oF D. 7450 gpm; 70oF Answer: A Explanation: | ||
A. 7300 gpm; | A is correct because as referenced in the procedure this is the minimum flow and a caution in the procedure has you secure suppression pool cooling before you go below 65oF. | ||
A is correct because as referenced in the procedure this is the minimum flow and a caution in the procedure has you secure suppression pool cooling before you go below | B is wrong because it is the correct flow but temperature is incorrect. This is plausible because the note references 70oF but it doesnt explicitly have you shutdown suppression pool cooling until below 65oF. | ||
C is wrong because the flow requirements are incorrect but plausible since this is the tech spec value for flow. The temperature is correct D is wrong because both flow and temperature are incorrect but plausible. | |||
Technical | Technical | ||
==References:== | ==References:== | ||
04-1-01-E12-1, Residual Heat Removal System, Rev. 143, p.26 References to be provided to applicants during exam: | 04-1-01-E12-1, Residual Heat Removal System, Rev. 143, p.26 References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: Document learning objective if possible. | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No | ||
New X | |||
Last NRC Exam No Question Cognitive Level: | Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(8) | ||
Memory/Fundamental X | |||
55.41(b)(8) | Examination Outline Cross-Reference Level RO 295015 Incomplete SCRAM Tier # 1 Group # 2 Knowledge of the operational implications of K/A # 295015 AK1.01 the following concepts as they apply to Rating 3.6 INCOMPLETE SCRAM : Shutdown margin Question 27 Select the statement(s) that correctly complete(s) this sentence. | ||
Examination Outline Cross | Following a reactor scram with two control rods at the fully withdrawn position, the crew may make a transition from EP-2A, ATWS, to EP-2, RPV control relying on the negative reactivity from: | ||
-Reference Level RO 295015 Incomplete SCRAM Knowledge of the operational implications of the following concepts as they apply to INCOMPLETE SCRAM : Shutdown margin | : 1. inserted control rods. | ||
Following a reactor scram with two control rods at the fully withdrawn position, the crew may make a transition from EP | |||
-2A, ATWS, to EP | |||
-2, RPV control relying on the negative reactivity from: | |||
: 2. injected boron. | : 2. injected boron. | ||
: 3. current xenon concentration. | : 3. current xenon concentration. | ||
A. 1, 2 and 3 B. 1 and 2 only C. 1 and 3 only D. 1 only Answer: D Explanation: | |||
A. 1, 2 and 3 B. 1 and 2 only C. 1 and 3 only D. 1 only | BWROG EPGs/SAGs, Appendix B Revision 2 says Note that the instruction requires a positive determination, not only that the reactor is shutdown, but that it will remain shutdown, without reliance upon boron, under worst-case cold shutdown conditions. The phrase without boron does not imply that the condition cannot be met if boron has been injected, but that credit cannot be taken for the negative reactivity contributed by the boron. Control rod insertion alone must provide the necessary shutdown margin. | ||
BWROG EPGs/SAGs, Appendix B Revision 2 says | Technical | ||
-case cold shutdown conditions. The phrase | |||
==References:== | ==References:== | ||
BWROG EPGs/SAGs, Appendix B Revision 2 References to be provided to applicants during exam: | BWROG EPGs/SAGs, Appendix B Revision 2 References to be provided to applicants during exam: | ||
Learning Objective: | Learning Objective: GLP-OPS-EP02A 7. State/identify the basis associated with each | ||
GLP-OPS-EP02A 7. State/identify the basis associated with each individual step in EP | |||
-2A. | individual step in EP-2A. | ||
Bank # | Question Source: Bank # | ||
Modified Bank # | (note changes; attach parent) Modified Bank # | ||
New X | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Last NRC Exam No | |||
Memory/Fundamental X | |||
55.41(b)(7) 55.43 | |||
If the RHR A INJ DISABLE handswitch is placed in the ENABLE position at the Remote Shutdown Panel, F042A, RHR A Injection Shutoff Valve, will not automatically ______: | Examination Outline Cross-Reference Level RO 203000 RHR/LPCI: Injection Mode Tier # 2 Group # 1 Knowledge of RHR/LPCI: INJECTION K/A # 203000 - K4.14 MODE (PLANT SPECIFIC) design feature(s) Rating 3.6 and/or interlocks which provide for the following: Operation from remote shutdown panel Question 28 If the RHR A INJ DISABLE handswitch is placed in the ENABLE position at the Remote Shutdown Panel, F042A, RHR A Injection Shutoff Valve, will not automatically ______: | ||
A. Open on a LOCA signal concurrent with low reactor pressure AND no containment spray initiation signal. | A. Open on a LOCA signal concurrent with low reactor pressure AND no containment spray initiation signal. | ||
B. Close on containment spray initiation signal. | B. Close on containment spray initiation signal. | ||
C. Open on LOCA signal concurrent with low reactor pressure OR no containment spray initiation signal. | C. Open on LOCA signal concurrent with low reactor pressure OR no containment spray initiation signal. | ||
D. Open on LOCA signal. | D. Open on LOCA signal. | ||
Answer: A | Answer: A Explanation: | ||
A is correct | A is correct because it is listed as a caution in 05-1-02-II-1 B is wrong because it is not defeated. The valve can still be opened manually with the signal present but it will auto close C is wrong because this does not meet the caution in 05-1-02-II-1 D is wrong because the valve does not get an open signal solely on initiation. Plausible if an applicant believes it does Technical | ||
==References:== | ==References:== | ||
05-1-02-II-1, Shutdown from the Remote Shutdown Panel, Attachment XIV References to be provided to applicants during exam: | 05-1-02-II-1, Shutdown from the Remote Shutdown Panel, Attachment XIV References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No | ||
New X | |||
Last NRC Exam No Question Cognitive Level: | Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(8) | ||
Memory/Fundamental X | |||
55.41(b)(8) | |||
Examination Outline Cross-Reference Level RO 205000 Shutdown Cooling Tier # 2 Group # 1 Knowledge of the operational implications of K/A # 295000 K5.02 the following concepts as they apply to Rating 2.8 SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) :Valve operation Question 29 Shutdown cooling is being established using RHR loop A per SOI-04-1 E12-2, Shutdown Cooling and Alternate Decay heat Removal Operations. | |||
After starting RHR pump A, the operator is procedurally directed to open a valve and immediately establish a minimum flow in order to prevent: | After starting RHR pump A, the operator is procedurally directed to open a valve and immediately establish a minimum flow in order to prevent: | ||
A. cavitation in RHR pump A. | A. cavitation in RHR pump A. | ||
B. discharging reactor vessel coolant to the suppression pool. | B. discharging reactor vessel coolant to the suppression pool. | ||
C. reactor pressure vessel thermal stratification. D. lifting the RHR pump A discharge relief valve. | C. reactor pressure vessel thermal stratification. | ||
Answer: | D. lifting the RHR pump A discharge relief valve. | ||
According to the note prior to the pump start, | Answer: B Explanation: | ||
According to the note prior to the pump start, Failure to establish greater than 1154 gpm within 8 seconds of pump start automatically opens F064A, establishing flow from Reactor to Suppression Pool. | |||
A is wrong because, while inadequate pump flow could eventually lead to pump cavitation, F064A operation will prevent this. | A is wrong because, while inadequate pump flow could eventually lead to pump cavitation, F064A operation will prevent this. | ||
C is wrong because, while stratification is a concern when flow is inadequate, F064A operation will prevent this. | C is wrong because, while stratification is a concern when flow is inadequate, F064A operation will prevent this. | ||
Line 703: | Line 581: | ||
==References:== | ==References:== | ||
Shutdown Cooling and Alternate Decay Heat Removal Operation, SOI 04 01-E12-2, Revision 116. Caution prior to step 4.1.2c(17) | Shutdown Cooling and Alternate Decay Heat Removal Operation, SOI 04-1-01-E12-2, Revision 116. Caution prior to step 4.1.2c(17) | ||
References to be provided to applicants during exam: | References to be provided to applicants during exam: None | ||
Question Source: | Learning Objective: | ||
Bank # | Question Source: Bank # | ||
Modified Bank # | (note changes; attach parent) Modified Bank # | ||
New X | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Last NRC Exam No | |||
Memory/Fundamental Comprehensive/Analysis X | Examination Outline Cross-Reference Level RO 205000 Shutdown Cooling Tier # 2 Group # 1 Knowledge of SHUTDOWN COOLING K/A # 205000 - K4.02 SYSTEM (RHR SHUTDOWN COOLING Rating 2.6 MODE) design feature(s) and/or interlocks which provide for the following: High pressure isolation Question 30 Which NSSSS group isolation provides protection against high reactor pressure for the RHR system in the Shutdown Cooling Mode of Operation? | ||
55.41(b)(7) 55.43 Examination Outline Cross | A. 2 B. 3 C. 4 D. 5 Answer: B Explanation: | ||
-Reference Level RO 205000 Shutdown Cooling Knowledge of SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) design feature(s) and/or interlocks which provide for the following: | |||
A. 2 | |||
A is wrong because Group 2 isolations protect for RHR to Radwaste B is correct because Group 3 isolations protect the RHR in shutdown cooling C is wrong because Group 4 isolations were part of steam condensing mode of RHR D is wrong because Group 5 isolations protect RHR test lines Technical | A is wrong because Group 2 isolations protect for RHR to Radwaste B is correct because Group 3 isolations protect the RHR in shutdown cooling C is wrong because Group 4 isolations were part of steam condensing mode of RHR D is wrong because Group 5 isolations protect RHR test lines Technical | ||
==References:== | ==References:== | ||
Table 2 of GFIG | Table 2 of GFIG-OPS-E1200; GLP-OPS-M701 p.36 References to be provided to applicants during exam: None. | ||
-OPS-E1200; GLP | Learning Objective: Describe the signals, setpoints and valves actuated by the RHR Shutdown Cooling Isolation Logic. (7.3) | ||
-OPS-M701 p.36 | Question Source: Bank # | ||
None. Learning Objective: Describe the signals, setpoints and valves actuated by the RHR Shutdown Cooling Isolation Logic. (7.3) | (note changes; attach parent) Modified Bank # | ||
Question Source: | New X Question History: Last NRC Exam No | ||
Bank # | |||
Modified Bank # | Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
New X | |||
Last NRC Exam No Question Cognitive Level: | Examination Outline Cross-Reference Level RO 209001 LPCS Tier # 2 Group # 1 Knowledge of the effect that a loss or K/A # 209001 K6.01 malfunction of the following will have on the Rating 3.4 LOW PRESSURE CORE SPRAY SYSTEM : A.C. power Question 31 Following a loss of MCC 15B11, an ECCS initiation signal would result in the LPCS pump: | ||
Memory/Fundamental X | |||
55.41(b)(7) | |||
-Reference Level RO 209001 LPCS Knowledge of the effect that a loss or malfunction of the following will have on the LOW PRESSURE CORE SPRAY SYSTEM : A.C. power | |||
A. failing to start. | A. failing to start. | ||
B. starting and running at shutoff head (zero flow) regardless of RCS pressure. | B. starting and running at shutoff head (zero flow) regardless of RCS pressure. | ||
C. starting, and running on mini | C. starting, and running on mini-flow only regardless of RCS pressure. | ||
-flow only regardless of RCS pressure. | D. starting and running without mini-flow protection, but will inject into the core when RCS pressure drops low enough. | ||
D. starting and running without mini | Answer: C Explanation: | ||
-flow protection, but will inject into the core when RCS pressure drops low enough. | |||
Answer: C | |||
MCC 15B11 powers all system MOVs but not the pump. The pump will start, but no MOV can be repositioned. | MCC 15B11 powers all system MOVs but not the pump. The pump will start, but no MOV can be repositioned. | ||
A is wrong because the pump has not lost power. | A is wrong because the pump has not lost power. | ||
B is wrong because the mini | B is wrong because the mini-flow valve has no power but it is normally open. | ||
-flow valve has no power but it is normally open. | D is wrong because the injection flowpath is normally isolated with an MOV that has no power. | ||
D is wrong because the injection flowpath is normally isolated with an MOV that has no power. Technical | Technical | ||
==References:== | ==References:== | ||
GLP-OPS-E2100 | GLP-OPS-E2100 References to be provided to applicants during exam: None Learning Objective: GLP-OPS-E2100 Rev. 10, Obj. 7.1 State/identify the power supplies for the following LPCS system components: Motor Operated Valves Obj 16 Upon recognition of the following abnormal plant indications, predict system response and potential consequences - AC power disturbances Question Source: Bank # | ||
GLP-OPS-E2100 Rev. 10, Obj. 7.1 State/identify the power supplies for the following LPCS system components: | (note changes; attach parent) Modified Bank # | ||
- AC power disturbances Question Source: | New X Question History: Last NRC Exam No | ||
Bank # | |||
Modified Bank # | |||
New X | |||
Last NRC Exam No | |||
Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | |||
A. Yes/Yes | Examination Outline Cross-Reference Level RO 209001 LPCS Tier # 2 Group # 1 Ability to determine operability and/or K/A # 209001 - 2.2.37 availability of safety related equipment Rating 3.6 Question 32 The plant is in Mode 4 with Electrical Bus 16AB OOS for planned maintenance. Youve been asked to perform 06-OP-1E21-M-01, LPCS Monthly Functional Test, and the LPCS valves are in the following position: | ||
LPCS Injection valve - Closed LPCS Suction Valve - Open LPCS Minimum flow to suppression Pool - Open LPCS Testable Check Valve - Closed Is the LPCS system operable? Are the minimum required systems for TS 3.5.2 met? | |||
A. Yes/Yes B. No/Yes C. Yes/No D. No/No Answer: A Explanation: | |||
A is correct because this lineup meets the requirements of LPCS Monthly Functional Test, and since LPCS, RHR A and HPCS are all operable and only 2 are required this meets the LCO for 3.5.2. | A is correct because this lineup meets the requirements of LPCS Monthly Functional Test, and since LPCS, RHR A and HPCS are all operable and only 2 are required this meets the LCO for 3.5.2. | ||
B is wrong because the system is not operable but plausible since it is counterintuitive to have the min flow valve should be in the open position for the system to be operable. | B is wrong because the system is not operable but plausible since it is counterintuitive to have the min flow valve should be in the open position for the system to be operable. | ||
Line 773: | Line 634: | ||
==References:== | ==References:== | ||
06-OP-1E21-M-01, LPCS Monthly Functional Test, Revision 106 TS SR 3.5.2 References to be provided to applicants during exam: | 06-OP-1E21-M-01, LPCS Monthly Functional Test, Revision 106 TS SR 3.5.2 References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: Document learning objective if possible. | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7);(8) | ||
New X | |||
Last NRC Exam No | Examination Outline Cross-Reference Level RO 209002 HPCS Tier # 2 Group # 1 Ability to predict and/or monitor changes in K/A # 209002 A1.09 parameters associated with operating the Rating 2.6 HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) controls including: Condensate storage tank level: BWR-5,6 Question 33 The reactor is shutdown with RHR A in shutdown cooling. A full flow test (CST to CST) of HPCS is in progress when E22-FIS-N656, HPCS Pump Discharge Flow fails downscale. | ||
Memory/Fundamental Comprehensive/Analysis X | |||
55.41(b)(7);(8) | |||
Examination Outline Cross | |||
-Reference Level RO 209002 HPCS Ability to predict and/or monitor changes in parameters associated with operating the HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) controls including: | |||
Condensate storage tank level: BWR-5,6 | |||
-FIS-N656, HPCS Pump Discharge Flow fails downscale. | |||
Following the instrument failure, CST level will: | Following the instrument failure, CST level will: | ||
A. drop and RPV level will rise. | A. drop and RPV level will rise. | ||
B. drop and suppression pool level will rise. | B. drop and suppression pool level will rise. | ||
C. rise and suppression pool level will drop. | C. rise and suppression pool level will drop. | ||
D. remain steady. | D. remain steady. | ||
Answer: | Answer: B Explanation: The full flow test is recirculating the CST. Transmitter FT-N056 feeds FIS-N656. With measured flow < 1206 gpm, F012, HPCS recirc. opens, moving water from the CST to the suppression pool. | ||
The full flow test is recirculating the CST. Transmitter FT | |||
-N056 feeds FIS | |||
-N656. With measured flow < 1206 gpm, F012, HPCS recirc. opens, moving water from the CST to the suppression pool. | |||
A would be correct if the recirc valve discharged to the RCS. | A would be correct if the recirc valve discharged to the RCS. | ||
C would be correct if the full flow test was recirculating the suppression pool and the recirc discharged to the CST. | C would be correct if the full flow test was recirculating the suppression pool and the recirc discharged to the CST. | ||
Line 805: | Line 655: | ||
==References:== | ==References:== | ||
GFIG-OPS-E2201, HPCS figures, Figure 2, HPCS System Overview References to be provided to applicants during exam: None | GFIG-OPS-E2201, HPCS figures, Figure 2, HPCS System Overview References to be provided to applicants during exam: None Learning Objective: The HPCS lesson plan was not provided Question Source: Bank # | ||
The HPCS lesson plan was not provided Question Source: | (note changes; attach parent) Modified Bank # | ||
Bank # | New X | ||
Modified Bank # | |||
New X Question History: | Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Last NRC Exam No | |||
Memory/Fundamental Comprehensive/Analysis X | Examination Outline Cross-Reference Level RO 211000 SLC Tier # 2 Group # 1 Knowledge of the operational implications K/A # 211000 - K5.05 of the following concepts as they apply to Rating 2.5 STANDBY LIQUID CONTROL SYSTEM: | ||
55.41(b)(7) 55.43 Examination Outline Cross | Explosive valve operation Question 34 Following an initiation of SLC A, which of the following sets of indications would be observed if the A squib valve fails to open? | ||
-Reference Level RO 211000 SLC Knowledge of the operational implications of the following concepts as they apply to STANDBY LIQUID CONTROL SYSTEM: Explosive valve operation | A. SLC storage tank level decreasing, SLC pump discharge pressure higher than reactor pressure, and reactor power decreasing. | ||
A. SLC storage tank level decreasing, SLC pump discharge pressure higher than reactor pressure, and reactor power decreasing. | B. SLC storage tank level decreasing, SLC pump discharge pressure lower than reactor pressure, and reactor power constant. | ||
B. SLC storage tank level decreasing, SLC pump discharge pressure lower than | C. SLC storage tank level constant, SLC pump discharge pressure higher than reactor pressure, and reactor power decreasing. | ||
C. SLC storage tank level constant, SLC pump discharge pressure higher than reactor pressure, and reactor power decreasing. | D. SLC storage tank level constant, SLC pump discharge pressure higher than reactor pressure, and reactor power constant. | ||
D. SLC storage tank level constant, SLC pump discharge pressure higher than reactor pressure, and reactor power constant. | Answer: D Comments: An applicant could reasonably argue B and D are correct. | ||
Answer: D Comments: | |||
Explanation: | Explanation: | ||
A is wrong because it describes a good start of the SLC system B is wrong because if SLC pump discharge pressure is less than reactor pressure SLC would not be able to inject, therefore it is not indicative of a failure of the squib to fire but of the system not developing pressure C is wrong because SLC storage tank level would not remain constant if SLC was initiated. | A is wrong because it describes a good start of the SLC system B is wrong because if SLC pump discharge pressure is less than reactor pressure SLC would not be able to inject, therefore it is not indicative of a failure of the squib to fire but of the system not developing pressure C is wrong because SLC storage tank level would not remain constant if SLC was initiated. | ||
Line 826: | Line 675: | ||
==References:== | ==References:== | ||
GLP-OPS-C4100 Rev 10, page 18 | GLP-OPS-C4100 Rev 10, page 18-20 References to be provided to applicants during exam: None. | ||
-20 | Learning Objective: (12) Describe the indications of SLC injection into the reactor. | ||
None. Learning Objective: | |||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(6) 55.43 | ||
Last NRC Exam No | |||
Memory/Fundamental Comprehensive/Analysis X | |||
55.41(b)(6) 55.43 | |||
Examination Outline Cross | Examination Outline Cross-Reference Level RO 212000 RPS Tier # 2 Group # 1 Knowledge of the effect that a loss or K/A # 212000 K3.01 malfunction of the REACTOR PROTECTION Rating 3.0 SYSTEM will have on following: Process radiation monitoring Question 35 The reactor is at 5% power during a startup when EPA-S003A trips on undervoltage. With respect to the process radiation monitors, this event would result in; A. closure of Inboard Reactor Sample Valve, B33-F019. | ||
-Reference Level RO 212000 RPS | B. closure of Outboard Reactor Sample Valve, B33-F020. | ||
Process radiation monitoring | |||
-S003A trips on undervoltage. With respect to the process radiation monitors, this event would result in; A. closure of Inboard Reactor Sample Valve, B33 | |||
-F019. B. closure of Outboard Reactor Sample Valve, B33 | |||
-F020. | |||
C. generation of a mechanical vacuum pump trip signal. | C. generation of a mechanical vacuum pump trip signal. | ||
D. no automatic trip signals or isolations. | D. no automatic trip signals or isolations. | ||
D. | D. | ||
Explanation: | |||
On the loss of RPS A, the power would be automatically switched to inverter 1Y87. | On the loss of RPS A, the power would be automatically switched to inverter 1Y87. | ||
Therefore, none of the RPS components would be affected making | Therefore, none of the RPS components would be affected making D correct. No process monitors will lose power in this event. | ||
Technical | Technical | ||
==References:== | ==References:== | ||
GLP-OPS-D1721 GG UFSAR, 15.8.1 GG UFSAR, 15.2.2.5 References to be provided to applicants during exam: None. Learning Objective Question Source: | GLP-OPS-D1721 GG UFSAR, 15.8.1 GG UFSAR, 15.2.2.5 References to be provided to applicants during exam: None. | ||
Bank # | Learning Objective Question Source: Bank # | ||
Modified Bank # | (note changes; attach parent) Modified Bank # | ||
New X | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental | ||
Last NRC Exam No | |||
Memory/Fundamental | |||
Comprehensive/Analysis X | Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
55.41(b)(7) 55.43 | |||
Examination Outline Cross-Reference Level RO 215003 IRM Tier # 2 Group # 1 Knowledge of the effect that a loss or K/A # 215003 - K6.04 malfunction of the following will have on the Rating 3.0 INTERMEDIATE RANGE MONITOR (IRM) SYSTEM: Detectors Question 36 The plant is starting up following an outage. SRM/IRM overlap has been verified and all IRMs are indicating normally on range 5 when IRM F and IRM H fail high. | |||
What is the expected system/plant response? | What is the expected system/plant response? | ||
A. A full RPS scram. | A. A full RPS scram. | ||
B. A half scram on RPS Division A | B. A half scram on RPS Division A AND a rod block. | ||
C. A half scram on RPS Division B AND a rod block. | C. A half scram on RPS Division B AND a rod block. | ||
D. A rod withdrawal block ONLY. Answer: C | D. A rod withdrawal block ONLY. | ||
A is wrong because both detectors are on the same division so full scram logic would not be made up. Plausible if an applicant | Answer: C Explanation: | ||
D is wrong because a rod block would be generated an RPS signal would also be generated. Technical | A is wrong because both detectors are on the same division so full scram logic would not be made up. Plausible if an applicant doesnt know which IRMs are on which division B is wrong because this is the wrong division of RPS C is correct this is the correct division of RPS and a rod block is generated. | ||
D is wrong because a rod block would be generated an RPS signal would also be generated. | |||
Technical | |||
==References:== | ==References:== | ||
GLP-OPS-C5102 - p. 20-31 | GLP-OPS-C5102 - p. 20-31 References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: Concerning the major automatic features of the IRM System, state/identify the signals and setpoints associated with an IRM scram signal, including when the signals are bypassed. | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No | ||
New X | |||
Last NRC Exam No Question Cognitive Level: | Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) | ||
Memory/Fundamental X | |||
55.41(b)(7) | Examination Outline Cross-Reference Level RO 215003 IRM Tier # 2 Group # 1 Ability to monitor automatic operations of the K/A # 215003 A3.01 INTERMEDIATE RANGE MONITOR (IRM) Rating 3.3 SYSTEM including: Meters and recorders Question 37 When an Intermediate Range Monitors UP button illuminates, the operator should press the associated channels ________ button. | ||
Examination Outline Cross | A. UP B. DRIVE OUT C. DOWN D. DRIVE IN Answer: A No need for a 2 part question. | ||
-Reference Level RO 215003 IRM Ability to monitor automatic operations of the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM including: Meters and recorders | Explanation: The UP button is backlit when the light signifies that the IRM is at 75% of scale. Pressing the button raises the channel to the next highest scale. This condition is expected during a plant startup. | ||
A. UP | There is nothing intuitive about the meaning of this light. It could mean that the detector needs to be driven in (up), or is up and should be down (driven out). If could also logically mean that the current scaling is too high, which would occur during a plant shutdown. | ||
Explanation: | Technical | ||
The UP button is backlit when the light signifies that the IRM is at 75% of scale. Pressing the button raises the channel to the next highest scale. This condition is expected during a plant startup. | |||
There is nothing intuitive about the meaning of this light. It could mean that the detector needs to be driven in (up), or is up and should be down (driven out). If could also logically mean that the current scaling is too high, which would occur during a plant shutdown | |||
==References:== | ==References:== | ||
GLP-OPS-C5102 | GLP-OPS-C5102 References to be provided to applicants during exam: None Learning Objective: | ||
None | GLP-OPS-C5102 For each of the following IRM System components, state/identify methods of operation, including locations of associated controls and indications: (7) Drive mechanism (7.1) IRM range select pushbuttons (7.2) | ||
GLP-OPS-C5102 For each of the following IRM System components, state/identify methods of operation, including locations of associated controls and indications: (7) Drive mechanism (7.1) | Question Source: Bank # | ||
Question Source: | (note changes; attach parent) Modified Bank # | ||
Bank # | New X Question History: Last NRC Exam No | ||
Modified Bank # | |||
New X | Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Last NRC Exam No Question Cognitive Level: | |||
Memory/Fundamental Comprehensive/Analysis X | |||
55.41(b)(7) 55.43 | |||
A. Control rod block; bypass SRM C B. Control rod block; bypass SRM D C. Full RPS scram; bypass SRM C D. Full RPS scram; bypass SRM D Answer: A | Examination Outline Cross-Reference Level RO 215004 Source Range Monitor Tier # 2 Group # 1 Ability to (a) predict the impacts of the K/A # 215004 - A2.01 following on the SOURCE RANGE Rating 2.7 MONITOR (SRM) SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Power supply degraded Question 38 The reactor is starting up following a refueling outage when output voltage on Inverter 1Y96 indicates 0.0 volts. What is an expected automatic action of this condition and what would be the immediate operator action of Alarm Response 04-1-02-1H13-P680, to mitigate this failure so startup can continue? | ||
A is | A. Control rod block; bypass SRM C B. Control rod block; bypass SRM D C. Full RPS scram; bypass SRM C D. Full RPS scram; bypass SRM D Answer: A Explanation: | ||
A is correct because SRM normally only generate rod blocks unless in special situations. | |||
This inverter feeds the power supply for SRM C. | |||
B is wrong because the first half is correct but Inverter 1Y95 feeds SRM D. | B is wrong because the first half is correct but Inverter 1Y95 feeds SRM D. | ||
C is wrong because there are no scram signals generated from SRMs unless the shorting links are removed. This is normally done during fuel loading and would not be done while starting up. It is plausible if an applicant | C is wrong because there are no scram signals generated from SRMs unless the shorting links are removed. This is normally done during fuel loading and would not be done while starting up. It is plausible if an applicant doesnt understand this. | ||
D is wrong because see answer C Technical | D is wrong because see answer C Technical | ||
==References:== | ==References:== | ||
GLP-OPS-C5101 , SOURCE RANGE MONITORING (SRM) SYSTEM | GLP-OPS-C5101, SOURCE RANGE MONITORING (SRM) SYSTEM - C5101, Rev 3 References to be provided to applicants during exam: None. | ||
- C5101, Rev 3 | Learning Objective: 10.1 Describe the interrelationships of the following systems with the SRM System: 120V AC Uninterruptible Power Supply (UPS) System. | ||
None. Learning Objective: 10.1 Describe the interrelationships of the following systems with the SRM System: 120V AC Uninterruptible Power Supply (UPS) System. 8.2 Concerning the major automatic features of the SRM System, state/identify the signals and setpoints associated with an SRM rod withdrawal block signal, including when the signals are bypassed. | 8.2 Concerning the major automatic features of the SRM System, state/identify the signals and setpoints associated with an SRM rod withdrawal block signal, including when the signals are bypassed. | ||
B. control rod block C. post accident monitoring D. emergency core cooling system Answer: | Question Source: Bank # | ||
(note changes; attach parent) Modified Bank # | |||
New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) | |||
Examination Outline Cross-Reference Level RO 215005 APRM / LPRM Tier # 2 Group # 1 Knowledge of the physical connections and/or K/A # 215005 K1.13 cause-effect relationships between AVERAGE Rating 2.6 POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM and the following: Traversing incore probe system Question 39 The traversing incore probe system is used to ensure that the _______ instrumentation remains operable: | |||
A. reactor protection system B. control rod block C. post accident monitoring D. emergency core cooling system Answer: A Explanation: | |||
TS 3.3.1 function 2b cannot remain operable because SR 3.3.1.1.7 (LPRM calibration) cannot be met. | TS 3.3.1 function 2b cannot remain operable because SR 3.3.1.1.7 (LPRM calibration) cannot be met. | ||
The other answers are incorrect because TIPS is not used in maintaining operability for these systems. | The other answers are incorrect because TIPS is not used in maintaining operability for these systems. | ||
Line 934: | Line 766: | ||
GLP-OPS-C5105, TIP system TS 3.3.1, function 2b, SR 3.3.1.1.7. | GLP-OPS-C5105, TIP system TS 3.3.1, function 2b, SR 3.3.1.1.7. | ||
References to be provided to applicants during exam: None | References to be provided to applicants during exam: None Learning Objective: GLP-OPS-C5105, TIP system Describe the interrelationships of the following systems with the TIP System: (10) | ||
Process Computer (10.1) | Process Computer (10.1) | ||
Local Power Range Monitors (10.4) | Local Power Range Monitors (10.4) | ||
Given plant conditions, identify entry into the Limiting Condition for Operation (LCO) for any Technical Specification related to the TIP System. (12) | Given plant conditions, identify entry into the Limiting Condition for Operation (LCO) for any Technical Specification related to the TIP System. (12) | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No | ||
New X | |||
Last NRC Exam No Question Cognitive Level: | Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Memory/Fundamental Comprehensive/Analysis X | |||
55.41(b)(7) 55.43 Examination Outline Cross | Examination Outline Cross-Reference Level RO 217000 RCIC Tier # 2 Group # 1 Ability to evaluate plant performance and K/A # 217000 - 2.1.7 make operational judgments based on Rating 4.4 operating characteristics, reactor behavior, and instrument interpretation Question 40 The plant is operating at rated power when you receive SUPP POOL LVL HI alarm on P601. | ||
-Reference Level RO 217000 RCIC Ability to evaluate plant performance and | Control room operators should immediately verify: | ||
A is correct because this is the immediate action in ARP | A. RCIC suction is from the suppression pool B. RCIC suction is from the condensate storage tank C. HPCS operability D. FCV MOV-F022, RCIC Inboard Test return, is open Answer: A Explanation: | ||
A is correct because this is the immediate action in ARP 04-1-02-1H13-P601. | |||
B is wrong because this is not listed in the ARP but it could be correct if someone believes that high suppression pool level would result in RCIC inoperability/unavailability. | |||
C is wrong because it is not listed in the ARP but could be correct if someone believes the condition makes RCIC inoperable. | C is wrong because it is not listed in the ARP but could be correct if someone believes the condition makes RCIC inoperable. | ||
D is wrong because it is listed in the immediate actions to verify the valve is closed and not open. Technical | D is wrong because it is listed in the immediate actions to verify the valve is closed and not open. | ||
Technical | |||
==References:== | ==References:== | ||
ARP 04-1-02-1H13-P601 | ARP 04-1-02-1H13-P601 References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: (19) GLP-OPS-E5100. | ||
Bank # | Question Source: Bank # | ||
Modified Bank # | (note changes; attach parent) Modified Bank # | ||
New X Question History: | New X | ||
Last NRC Exam No | |||
Memory/Fundamental X | Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b) 55.43 | ||
55.41(b) | |||
-Reference Level RO 218000 ADS Knowledge of the operational implications of the following concepts as they apply to AUTOMATIC DEPRESSURIZATION SYSTEM | Examination Outline Cross-Reference Level RO 218000 ADS Tier # 2 Group # 1 Knowledge of the operational implications of K/A # 218000 K5.01 the following concepts as they apply to Rating 3.8 AUTOMATIC DEPRESSURIZATION SYSTEM | ||
:ADS logic operation | :ADS logic operation Question 41 The reactor has experienced a transient the following conditions currently exist: | ||
Reactor level has been less than Level 3 for 8 minutes Reactor level has been less than Level 1 for 5 minutes All ECCS equipment has responded as designed Drywell pressure is 0.5 psig and is rising at 0.1 psig per minute. | * Reactor level has been less than Level 3 for 8 minutes | ||
* Reactor level has been less than Level 1 for 5 minutes | |||
* All ECCS equipment has responded as designed | |||
* Drywell pressure is 0.5 psig and is rising at 0.1 psig per minute. | |||
Based on these conditions, the Automatic Depressurization System relief valves: | Based on these conditions, the Automatic Depressurization System relief valves: | ||
A. have opened. | A. have opened. | ||
B. will open when drywell pressure reaches 1.39 psig | B. will open when drywell pressure reaches 1.39 psig C. will open 105 seconds after drywell pressure reaches 1.39 psig. | ||
C. will open 105 seconds after drywell pressure reaches 1.39 psig. | |||
D. will open in 4.2 minutes. | D. will open in 4.2 minutes. | ||
Answer: | Answer: D I like this question better as it is more operationally focused. | ||
Explanation: | Explanation: | ||
Input from the high drywell pressure channel is automatically bypassed if Reactor level stays | |||
< -150.3 for 9.2 minutes. This condition assumes a LOCA outside the Drywell with degraded high pressure injection systems, and thus takes override action to initiate ADS to recover RPV level. | < -150.3 for 9.2 minutes. This condition assumes a LOCA outside the Drywell with degraded high pressure injection systems, and thus takes override action to initiate ADS to recover RPV level. | ||
\ | |||
Technical | |||
==References:== | ==References:== | ||
GLP-OPS-E2202 | GLP-OPS-E2202 References to be provided to applicants during exam: None Learning Objective: GLP-OPS-E2202 Describe the signals and setpoints for the initiation of the ADS System for both automatic and manual initiation. (15.0) | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | |||
New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | |||
Examination Outline Cross-Reference Level RO 223002 PCIS/Nuclear Steam Supply Shutoff Tier # 2 Group # 1 Ability to manually operate and/or monitor K/A # 223002 - A4.01 in the control room: valve closures Rating 3.6 Question 42 What combination of NSSSS manual initiation pushbuttons would result in an isolation of MSIVs ONLY? | |||
A. Division 1 and Division 2 B. Division 1 and Division 4 C. Division 2 and Division 3 D. Division 2 and Division 4 Answer: A Explanation: | |||
-Reference Level RO 223002 PCIS/Nuclear Steam Supply Shutoff Ability to manually operate and/or monitor | |||
A is correct because either 1 and 2 or 3 and 4 will give you a MSIV isolation. | A is correct because either 1 and 2 or 3 and 4 will give you a MSIV isolation. | ||
B is wrong because this would give you a MSIV closure and a Div 1 NSSSS, Containment, Drywell, and Auxiliary building isolation. | B is wrong because this would give you a MSIV closure and a Div 1 NSSSS, Containment, Drywell, and Auxiliary building isolation. | ||
Line 995: | Line 830: | ||
==References:== | ==References:== | ||
GLP-OPS-M701, Containment and Drywell Instrumentation and Control System | GLP-OPS-M701, Containment and Drywell Instrumentation and Control System - M71, Rev 11 p.56 References to be provided to applicants during exam: None. | ||
- M71, Rev 11 p.56 | Learning Objective: State/identify the location(s) from which the Containment & Drywell Instrumentation & Control System isolation signals can be initiated. (8.2) | ||
None. Learning Objective: | |||
Drywell Instrumentation & Control System isolation signals can be initiated. (8.2) | |||
Describe the logic arrangements which actuate the isolation logics listed in Objective 7. (9) | Describe the logic arrangements which actuate the isolation logics listed in Objective 7. (9) | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No | ||
New X | |||
Last NRC Exam No | |||
Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(6) | |||
Examination Outline Cross-Reference Level RO 239002 SRVs Tier # 2 Group # 1 Knowledge of RELIEF/SAFETY VALVES K/A # 239002 K4.01 design feature(s) and/or interlocks which Rating 3.9 provide for the following: Insures that only one or two safety/relief valves reopen following the initial portion of a reactor isolation event (LLS logic): Plant-Specific Question 43 The plant is at rated power when the MSIVs close causing a reactor scrama reactor isolation occurs. Reactor pressure reaches 1120 psig resulting in mMultiple SRVs cycling initially lift, Formatted: Highlight then all SRVs close. | |||
Following the initial transient, the SRVs would be expected to automatically maintain reactor pressure between: When pressure subsequently rises, only ____(1)_____ should lift when pressure reaches (2) . psig. | |||
Formatted: | * (2) Formatted: Indent: Left: 0.63", No bullets or A. 926 and 1033 psig.F051D 1103 numbering B. 936 and 1073 psig.F051D 1033 C. 946 and 1113 psig.F051B 1103 D. 1013 and 1113 psig.F051B 1033 Answer: B Explanation: | ||
Low-Low Set initiates automatically when RPV pressure reaches SRV F051Ds normal lift setpoint of 1103 psig. | |||
Indent: Left: | Once initiated, six SRVs are capable of operating in the Low-Low Set mode with the following adjusted opening and closing setpoints: One SRV, F051D, lifts at 1033 psig and blows down to 926 psig. A second SRV, F051B, lifts at 1073 psig and blows down to 936 psig. | ||
Technical | |||
==References:== | |||
GLP-OPS-E2202 References to be provided to applicants during exam: | |||
Learning Objective: GLP-OPS-E2202 For each mode of operation of the SRVs, state/identify the number of valves which open and the associated opening setpoints. (11.2) | |||
Question Source: Bank # | |||
(note changes; attach parent) Modified Bank # | |||
New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | |||
C. the highest value from the remaining narrow range and upset range channels. | Examination Outline Cross-Reference Level RO 259002 Reactor Water Level Control Tier # 2 Group # 1 Knowledge of the effect that a loss or K/A # 259002 - K6.08 malfunction of the following will have on the Rating 3.5 REACTOR WATER LEVEL CONTROL SYSTEM: Reactor water level input Question 44 If the plant is in single element mode with automatic level channel selection mode, and the controlling level channel fails high the DFCS will de-select the failed channel and select A. the upset range channel irrespective of the magnitude. | ||
D. the lowest value from the remaining narrow range and upset range channels. | B. an intermediate value from the remaining narrow range and upset range channels. | ||
Answer: B | C. the highest value from the remaining narrow range and upset range channels. | ||
D. the lowest value from the remaining narrow range and upset range channels. | |||
Answer: B Explanation: | |||
A is wrong because this will happen only if the upset channel is the intermediate value. | A is wrong because this will happen only if the upset channel is the intermediate value. | ||
B is correct because this is design of the system. | B is correct because this is design of the system. | ||
C is wrong because the system is designed to select the intermediate value. | C is wrong because the system is designed to select the intermediate value. | ||
D is wrong because the system is designed to select the intermediate value. Technical | D is wrong because the system is designed to select the intermediate value. | ||
Technical | |||
==References:== | ==References:== | ||
GLP-OPS-C3400, DIGITAL FEEDWATER CONTROL SYSTEM (DFCS) | GLP-OPS-C3400, DIGITAL FEEDWATER CONTROL SYSTEM (DFCS) - C34, Rev 12 References to be provided to applicants during exam: None. | ||
- C34, Rev 12 | Learning Objective: State/identify the Level Control Subsystems response to failure of one or more Narrow Range level control channels when in the Automatic Level Channel Selection Mode. (3.6). | ||
None. Learning Objective: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X | ||
New X | |||
Last NRC Exam No | |||
C. reduce the efficiency of the charcoal adsorber leading to increased off | 10CFR Part 55 Content: 55.41(b)(7) | ||
-site release rates. | Examination Outline Cross-Reference Level RO 261000 SGTS Tier # 2 Group # 1 Knowledge of the effect that a loss or K/A # 261000 K3.02 malfunction of the STANDBY GAS Rating 3.6 TREATMENT SYSTEM will have on following: | ||
D. render the demister inoperable and subsequent fouling of the charcoal. | Off-site release rate Question 45 Procedure 04-1-01-T48-1, Standby Gas Treatment, contains a caution to prevent an automatic start of SBGT if painting in the Auxiliary Building. This is because paint fumes in the SBGT System can: | ||
Answer: | A. result in a fire due to the electric heater in the system. | ||
B. plug the HEPA filters and reduce system flowrates. | |||
C. reduce the efficiency of the charcoal adsorber leading to increased off-site release rates. | |||
D. render the demister inoperable and subsequent fouling of the charcoal. | |||
Answer: C Explanation: | |||
The presence of a volatile organic substance (e.g. painting) in the SBGT system reduces the efficiency of the adsorber material leading to an increased release rate of radioactive particles to the environment. | The presence of a volatile organic substance (e.g. painting) in the SBGT system reduces the efficiency of the adsorber material leading to an increased release rate of radioactive particles to the environment. | ||
Technical | Technical | ||
Line 1,069: | Line 887: | ||
==References:== | ==References:== | ||
GLP-OPS-T4801 | GLP-OPS-T4801 References to be provided to applicants during exam: None Learning Objective: GLP-OPS-T4801 State/identify the design bases of the Standby Gas Treatment System. (2.0) | ||
None | Question Source: Bank # | ||
GLP-OPS-T4801 State/identify the design bases of the Standby Gas Treatment System. (2.0) | (note changes; attach parent) Modified Bank # | ||
Question Source: | New X Question History: Last NRC No Exam Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X | ||
Bank # | |||
Modified Bank # | 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Last NRC Exam | |||
Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: | Examination Outline Cross-Reference Level RO 262001 AC Electrical Distribution Tier # 2 Group # 1 Ability to predict and/or monitor changes in K/A # 262001 - A1.03 parameters associated with operating the Rating 2.9 A.C. ELECTRICAL DISTRIBUTION controls including: Bus voltage Question 46 A degraded voltage on the DIV 1 and DIV 3 ESF buses results in bus voltages to be at 3600 volts for 7 seconds. Following the transient, the status of the DIV 1 and DIV 3 EDGs would be______. | ||
55.41(b)(7) 55.43 Examination Outline Cross | A. Both EDGs running B. Neither EDG running C. DIV 1 EDG running and DIV 3 EDG NOT running D. DIV 1 EDG NOT running and DIV 3 EDG running Answer: B Explanation: | ||
-Reference Level RO 262001 AC Electrical Distribution Ability to predict and/or monitor changes in parameters associated with operating the A.C. ELECTRICAL DISTRIBUTION controls including: Bus voltage | |||
A is wrong because neither of the diesel would start. | A is wrong because neither of the diesel would start. | ||
For the DIV 1 diesel there is a 9 second time delay between 2912 volts and 3744 volts before the DIV 1 diesel starts. | For the DIV 1 diesel there is a 9 second time delay between 2912 volts and 3744 volts before the DIV 1 diesel starts. | ||
For the DIV 3 diesel there is a 4 second time delay between 3045 and 3660 volts for the diesel to start. This start sequence has to be coincident with a LOCA signal. If there is no LOCA signal present coincident with the 4 second time delay then there is a 5 minute time delay until DIV 3 diesel starts. | For the DIV 3 diesel there is a 4 second time delay between 3045 and 3660 volts for the diesel to start. This start sequence has to be coincident with a LOCA signal. If there is no LOCA signal present coincident with the 4 second time delay then there is a 5 minute time delay until DIV 3 diesel starts. | ||
B is correct because of the explanation in A C is wrong because see above D is wrong because see above Technical | B is correct because of the explanation in A C is wrong because see above D is wrong because see above Technical | ||
==References:== | ==References:== | ||
GLP-OPS-R2100.12 , LOAD SHEDDING & SEQUENCING SYSTEM AND ESF AC POWER DISTRIBUTION SYSTEM | GLP-OPS-R2100.12, LOAD SHEDDING & SEQUENCING SYSTEM AND ESF AC POWER DISTRIBUTION SYSTEM - R21, Rev 12, p.19 GLP-OPS-P8100, HIGH PRESSURE CORE SPRAY (HPCS) DIESEL GENERATOR SYSTEM - P81, Rev 14, p. 40 References to be provided to applicants during exam: None. | ||
- R21, Rev 12, p.19 GLP-OPS-P8100 , HIGH PRESSURE CORE SPRAY (HPCS) DIESEL GENERATOR SYSTEM - P81, Rev 14, p. 40 References to be provided to applicants during exam: | |||
None. | Learning Objective: Discuss the interrelationships of the following systems with the HPCS Diesel Generator System: (18). | ||
Learning Objective: | State/identify the signals and setpoints that will produce a Bus Undervoltage signal to LSS Shed System and the actions associated with each signal. (12) | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) | ||
New X | |||
Last NRC Exam No | Examination Outline Cross-Reference Level RO 262001 AC Electrical Distribution Tier # 2 Group # 1 Knowledge of the effect that a loss or K/A # 262001 K3.02 malfunction of the A.C. ELECTRICAL Rating 3.8 DISTRIBUTION will have on following: | ||
Memory/Fundamental Comprehensive/Analysis X | Emergency generators Question 47 The plant is at rated power when a grid disturbance causes the voltage on buses 15AA and 16AB to drop in a step change to a sustained value of 3700 volts at time T=0. The associated incoming offsite bus feeder breakers open at time T= ____(1)____ and Tthe emergency diesel generator will receives an automatic start signal _____atseconds later. | ||
55.41(b)(7) | time T= ____(2)____. | ||
Examination Outline Cross | (1) (2) | ||
-Reference Level RO 262001 AC Electrical Distribution Knowledge of the effect that a loss or malfunction of the A.C. ELECTRICAL DISTRIBUTION will have on following: Emergency generators | A. 0.5 0.5 B. 0.5 1.0 C. 9.0 9.0 D. 9.0 9.5 Answer: D Explanation: | ||
With bus voltage < 3744 volts, after a 9 second delay, the offsite bus feeder breakers open. | |||
This activates the < 2912 volt timer, which, after 0.5 seconds sends a start signal to the associated diesel generator. | |||
With bus voltage < 3744 volts, after a 9 second delay, the offsite bus feeder breakers open. This activates the < 2912 volt timer, which, after 0.5 seconds sends a start signal to the associated diesel generator. | |||
The 0.5 second opening of incoming breakers is credible because this is the time delay of the 70% timer. The start of the EDG simultaneous with breaker opening is credible, since this is what happens with the 70% timer. | The 0.5 second opening of incoming breakers is credible because this is the time delay of the 70% timer. The start of the EDG simultaneous with breaker opening is credible, since this is what happens with the 70% timer. | ||
Technical | Technical | ||
Line 1,109: | Line 923: | ||
==References:== | ==References:== | ||
GLP-OPS-R2100 GLP-OPS-P7500 | GLP-OPS-R2100 GLP-OPS-P7500 References to be provided to applicants during exam: None Learning Objective: GLP-OPS-P7500 Describe the automatic initiation logic for a Standby Diesel Generator for degraded power conditions and a Loss of Coolant Accident (LOCA). | ||
None | (8.0) | ||
GLP-OPS-R2100 State/identify the signals and setpoints that will produce a bus undervoltage signal to LSS shed system and the actions associated with each signal. (12) | |||
Question Source: | Question Source: Bank # | ||
(note changes; attach parent) Modified Bank # | |||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
New X | |||
Last NRC Exam No | Examination Outline Cross-Reference Level RO 262002 UPS (AC/DC) Tier # 2 Group # 1 Knowledge of the effect that a loss or K/A # 262002 - K6.02 malfunction of the following will have on the Rating 2.8 UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.): D.C. electrical power Question 48 If DC power is lost to an ESF inverter the static switch on the inverter will (a)? When the condition is corrected the static switch for the ESF inverter will automatically/manually be transferred back to the DC source? | ||
Memory/Fundamental Comprehensive/Analysis X | A. only transfer if the IN SYNC light is illuminated automatically B. transfer regardless of IN SYNC light automatically C. only transfer if the IN SYNC light is illuminated manually D. transfer regardless of IN SYNC light manually Answer: D Explanation: | ||
55.41(b)(7) 55.43 Examination Outline Cross | |||
-Reference Level RO 262002 UPS (AC/DC) | |||
Knowledge of the effect that a loss or malfunction of the following will have on the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) | |||
: D.C. electrical power | |||
A. only transfer if the IN SYNC light is illuminated automatically B. transfer regardless of IN SYNC light automatically C. only transfer if the IN SYNC light is illuminated manually | |||
Excerpts from the training material: | Excerpts from the training material: | ||
If the inverter output and the AC source are out of sync the static switch will not transfer. An out of sync transfer would cause major damage to the inverter and potential damage to the loads. | * If the inverter output and the AC source are out of sync the static switch will not transfer. An out of sync transfer would cause major damage to the inverter and potential damage to the loads. | ||
If the DC source has low or no voltage IN SYNC is not required, most of the inverters will auto transfer. | * If the DC source has low or no voltage IN SYNC is not required, most of the inverters will auto transfer. | ||
Upon a return of the normal source the BOP Inverters (except 1Y99) will automatically (-2 seconds of normal power) return to the normal power supply. | * Upon a return of the normal source the BOP Inverters (except 1Y99) will automatically (-2 seconds of normal power) return to the normal power supply. | ||
The ESF Inverters and 1Y99 have had the auto return feature disabled internally on the inverter. (Each inverter has a switch to enable or disable this feature.) | * The ESF Inverters and 1Y99 have had the auto return feature disabled internally on the inverter. (Each inverter has a switch to enable or disable this feature.) If DC power is lost to an ESF Inverter, the DC input circuit breaker trips on undervoltage. | ||
A is wrong because a loss of DC would result in no voltage so the IN SYNC light would not come into play. Also, only the BOP buses will automatically transfer when normal DC power is restored. | A is wrong because a loss of DC would result in no voltage so the IN SYNC light would not come into play. Also, only the BOP buses will automatically transfer when normal DC power | ||
B is wrong because ESF inverters have the automatic return to normal supply | |||
is restored. | |||
B is wrong because ESF inverters have the automatic return to normal supply disabled. | |||
C is wrong because the inverter will transfer regardless of the IN SYNC light since the inverter has zero voltage. | |||
D is correct because the transfer will happen regardless of the IN SYNC light and there is no automatic return to the normal source for ESF inverters. | D is correct because the transfer will happen regardless of the IN SYNC light and there is no automatic return to the normal source for ESF inverters. | ||
Technical | Technical | ||
Line 1,136: | Line 948: | ||
==References:== | ==References:== | ||
GLP-OPS-L6200, Static Inverter System | GLP-OPS-L6200, Static Inverter System - L62, Rev 10 References to be provided to applicants during exam: None. | ||
- L62, Rev 10 References to be provided to applicants during exam: | Learning Objective: Describe the automatic feature of the Static Inverter System that transfers power sources and which inverters have the following features: ( 4) | ||
None. Learning Objective: | |||
Inverter to alternate power source ( 4.1) | Inverter to alternate power source ( 4.1) | ||
Alternate power source to inverter upon return of inverter power (4.2) | Alternate power source to inverter upon return of inverter power (4.2) | ||
Describe the operation of the Static Inverter using: (5) | Describe the operation of the Static Inverter using: (5) | ||
Static Switch | Static Switch- Auto (5.1) | ||
- Auto (5.1) Static Switch | Static Switch- Manual (5.2) | ||
- Manual (5.2) | Question Source: Bank # | ||
Question Source: | (note changes; attach parent) Modified Bank # | ||
Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) | ||
Modified Bank # | |||
New X | Examination Outline Cross-Reference Level RO 263000 DC Electrical Distribution Tier # 2 Group # 1 Ability to (a) predict the impacts of the K/A # 263000 A2.01 following on the D.C. ELECTRICAL Rating 2.8 DISTRIBUTION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Grounds Question 49 It is important to promptly eliminate a ground on a DC bus because: | ||
Last NRC Exam No | |||
Memory/Fundamental Comprehensive/Analysis X | |||
55.41(b)(7) | |||
Examination Outline Cross | |||
-Reference Level RO 263000 DC Electrical Distribution Ability to (a) predict the impacts of the following on the D.C. ELECTRICAL DISTRIBUTION ; and (b) based on those predictions, use procedures to correct, control, | |||
Grounds | |||
A. one ground can cause unpredictable spurious operation of equipment. | A. one ground can cause unpredictable spurious operation of equipment. | ||
B. subsequent grounds will be masked, and multiple grounds can produce unanalyzed results. C. a shock hazard exists at the grounded equipment. | B. subsequent grounds will be masked, and multiple grounds can produce unanalyzed results. | ||
C. a shock hazard exists at the grounded equipment. | |||
D. a fire hazard exists due to excessive current flow at the ground location. | D. a fire hazard exists due to excessive current flow at the ground location. | ||
Answer: | Answer: B Explanation: | ||
Failure to promptly eliminate a single ground could mask subsequent grounds. Multiple grounds could lead to unpredictable spurious operation of equipment, inoperable equipment, unanalyzed loads on batteries, or unanalyzed equipment failure modes that could be expected to occur during harsh environments associated with accident conditions. The first ground does not produce adverse effects because there is no path for current flow with one ground in an ungrounded system. | Failure to promptly eliminate a single ground could mask subsequent grounds. Multiple grounds could lead to unpredictable spurious operation of equipment, inoperable equipment, unanalyzed loads on batteries, or unanalyzed equipment failure modes that could be expected to occur during harsh environments associated with accident conditions. The first ground does not produce adverse effects because there is no path for current flow with one ground in an ungrounded system. | ||
Technical | Technical | ||
Line 1,164: | Line 970: | ||
==References:== | ==References:== | ||
GLP-OPS-L1100 | GLP-OPS-L1100 References to be provided to applicants during exam: | ||
Learning Objective: GLP | Learning Objective: GLP-OPS-L1100 State/identify the purpose/function of Gr ound Detection Systems. (5.3) | ||
-OPS-L1100 | Question Source: Bank # | ||
Question Source: | (note changes; attach parent) Modified Bank # | ||
Bank # | New X | ||
Modified Bank # | |||
New X Question History: | Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Last NRC Exam No | |||
Memory/Fundamental Comprehensive/Analysis X | Examination Outline Cross-Reference Level RO DC Electrical Distribution Tier # 2 Group # 1 Knowledge of electrical power supplies to K/A # 263000 - K2.01 the following: Major D.C. loads Rating 3.1 Question 50 The Diesel Generator 11 __________ is(are) powered from the ESF DC distribution system. | ||
55.41(b)(7) 55.43 Examination Outline Cross | A. generator field flash B. fuel oil booster pump C. lube oil pump D. air compressors Answer: A Comments: The relay panel also receives AC power. This question is ok with changes made. | ||
-Reference Level RO DC Electrical Distribution Knowledge of electrical power supplies to the following: Major D.C. loads | |||
A. generator field flash B. fuel oil booster pump C. lube oil pump D. air compressors Answer: A Comments: | |||
Explanation: | Explanation: | ||
B is wrong because it is powered from a BOP bus C is wrong because it is AC powered D is wrong because it is AC powered Technical | B is wrong because it is powered from a BOP bus C is wrong because it is AC powered D is wrong because it is AC powered Technical | ||
Line 1,181: | Line 985: | ||
==References:== | ==References:== | ||
04-1-01-L11-1_123 and GLP | 04-1-01-L11-1_123 and GLP-OPS-P7500_024-1 References to be provided to applicants during exam: None. | ||
-OPS-P7500_024-1 | Learning Objective: GLP-OPS-L1100. (8) State/identify the major loads of the Plant DC System Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X | ||
New X | |||
Last NRC Exam No | Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Memory/Fundamental X | |||
Comprehensive/Analysis 10CFR Part 55 Content: | Examination Outline Cross-Reference Level RO 264000 EDGs Tier # 2 Group # 1 Knowledge of the effect that a loss or K/A # 264000 K3.02 malfunction of the EMERGENCY Rating 3.9 GENERATORS (DIESEL/JET) will have on following: A.C. electrical distribution Question 51 The voltage regulator on a standby diesel generator has a malfunction that limits its maximum voltage to 3900 VAC. | ||
55.41(b)(7) 55.43 Examination Outline Cross | |||
-Reference Level RO 264000 EDGs Knowledge of the effect that a loss or malfunction of the EMERGENCY GENERATORS (DIESEL/JET) will have on following: A.C. electrical distribution | |||
In this condition, the output breaker can be closed: | In this condition, the output breaker can be closed: | ||
: 1. automatically. | : 1. automatically. | ||
: 2. remotely (P864) when paralleling with an offsite source. | : 2. remotely (P864) when paralleling with an offsite source. | ||
: 3. remotely (P864) when energizing a dead bus. | : 3. remotely (P864) when energizing a dead bus. | ||
A. 1, 2 and 3 B. 2 and 3 only C. 3 only | A. 1, 2 and 3 B. 2 and 3 only C. 3 only D. 1 only Answer: C Explanation: DG at rated voltage is an interlock for closing the breaker automatically or remotely when paralleling. It is not an interlock when all offsite feeder breakers are open Technical | ||
DG at rated voltage is an interlock for closing the breaker automatically or remotely when paralleling. It is not an interlock when all offsite feeder breakers are open | |||
==References:== | ==References:== | ||
Table 4 of GLP | Table 4 of GLP-OPS-P7500 References to be provided to applicants during exam: None Learning Objective: GLP-OPS-P7500 State/identify the start sequence and interlocks involved in starting the Standby Diesel Generator System during the following conditions: (15.0) LOCA signal present (15.1) LOP/BUV signal present (15.2) Local Emergency Start signal present (15.3) Normal operations (15.4) | ||
-OPS-P7500 | Question Source: Bank # | ||
GLP-OPS-P7500 State/identify the start sequence and interlocks involved in starting the Standby Diesel Generator System during the following conditions: (15.0) LOCA signal present (15.1) LOP/BUV signal present (15.2) Local Emergency Start signal present (15.3) Normal operations (15.4) | (note changes; attach parent) Modified Bank # | ||
Question Source: | New X | ||
Bank # | |||
Modified Bank # | Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
New X Question History: | |||
Last NRC Exam No | Examination Outline Cross-Reference Level RO 300000 Instrument Air Tier # 2 Group # 1 Knowledge of the connections and/or cause K/A # 300000 - K1.04 effect relationships between INSTRUMENT Rating 2.8 AIR SYSTEM and the following: Cooling water to compressor Question 52 Normal cooling water for the instrument air compressors is provided by _______: | ||
: Memory/Fundamental Comprehensive/Analysis X | A. Plant Service Water. | ||
55.41(b)(7) 55.43 Examination Outline Cross | B. Standby Service Water. | ||
-Reference Level RO 300000 Instrument Air Knowledge of the connections and/or cause effect relationships between INSTRUMENT AIR SYSTEM and the following: Cooling water to compressor | C. Component Cooling Water. | ||
A. Plant Service Water. | D. Turbine Building Cooling Water. | ||
B. Standby Service Water. | Answer: D Explanation: | ||
C. Component Cooling Water. | A is wrong because it does not provide cooling but is plausible if the applicant believes that since the system is not safety related it would come from a non-safety related source. | ||
D. Turbine Building Cooling Water. | |||
Answer: D | |||
A is wrong because it does not provide cooling but is plausible if the applicant believes that since the system is not safety related it would come from a non | |||
-safety related source. | |||
B is wrong because this is the emergency source of water. | B is wrong because this is the emergency source of water. | ||
C is wrong because it does not provide cooling but is plausible if the applicant | C is wrong because it does not provide cooling but is plausible if the applicant doesnt realize that component cooling water only provides cooling to potentially radioactive sources. | ||
D is correct because it is the normally aligned source of cooling water. | D is correct because it is the normally aligned source of cooling water. | ||
Technical | Technical | ||
Line 1,224: | Line 1,021: | ||
==References:== | ==References:== | ||
Document where the correct answer is found References to be provided to applicants during exam: | Document where the correct answer is found References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: Document learning objective if possible. | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) | ||
New X | |||
Last NRC Exam No | |||
Memory/Fundamental X | |||
55.41(b)(7) | |||
Examination Outline Cross | Examination Outline Cross-Reference Level RO 400000 Component Cooling Water Tier # 2 Group # 1 Knowledge of electrical power supplies to the K/A # 40000 K2.02 following: CCW valves Rating 2.9 Question 53 The power supply to P42-F116, CCW RTN FRM DW is: | ||
-Reference Level RO 400000 Component Cooling Water Knowledge of electrical power supplies to the | A. Bus 11DA B. LCC 16BB3 C. MCC17B01 D. MCC 15B11 Answer: D Explanation: | ||
A is wrong because the DA shows that this is a 125V DC bus, and the valve is powered from 480 VAC. | |||
-F116, CCW RTN FRM DW is: | |||
A. Bus 11DA | |||
A is wrong because the | |||
B is wrong because the valve motor is < 50 hp. It is powered from an MCC (not an LCC). C is the power supply to the B CCW pump. | B is wrong because the valve motor is < 50 hp. It is powered from an MCC (not an LCC). C is the power supply to the B CCW pump. | ||
C is wrong because MCC 17B11 is a division III bus which does not power any CCW components. | C is wrong because MCC 17B11 is a division III bus which does not power any CCW components. | ||
Technical | Technical | ||
Line 1,249: | Line 1,038: | ||
04-1-01-P42-1, CCW SOI GLP OPS-R2700, Normal AC Power Distribution System References to be provided to applicants during exam: | 04-1-01-P42-1, CCW SOI GLP OPS-R2700, Normal AC Power Distribution System References to be provided to applicants during exam: | ||
Learning Objective: GLP OPS-R2700 Identify components using the GGNS numbering system. (16) | Learning Objective: GLP OPS-R2700 Identify components using the GGNS numbering system. (16) | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental | ||
New X | |||
Last NRC Exam No | |||
Memory/Fundamental | |||
Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | |||
A. condensate pumps; CST B. condensate booster pumps; CST C. condensate pumps; demineralized water system D. condensate booster pumps; demineralized water system Answer: A | Examination Outline Cross-Reference Level RO 201001 CRD Hydraulic Tier # 2 Group # 2 Knowledge of the physical connections K/A # 201001 - K1.01 and/or cause-effect relationships between Rating 3.1 CONTROL ROD DRIVE HYDRAULIC SYSTEM and the following: Condensate System Question 54 During normal operation, the suction pressure for the control rod drive pumps is from the | ||
________. On a loss of the condensate system the suction of the control rod drive pumps is from the _________. | |||
A. condensate pumps; CST B. condensate booster pumps; CST C. condensate pumps; demineralized water system D. condensate booster pumps; demineralized water system Answer: A Explanation: | |||
A is correct B is wrong because the suctions from the condensate pumps C is wrong because the service water system does not feed the CRD system but is plausible because the water system is very clean and could be used in the CRD system D is wrong because of B and C Technical | A is correct B is wrong because the suctions from the condensate pumps C is wrong because the service water system does not feed the CRD system but is plausible because the water system is very clean and could be used in the CRD system D is wrong because of B and C Technical | ||
==References:== | ==References:== | ||
GLP-OPS-C111A | GLP-OPS-C111A References to be provided to applicants during exam: None. | ||
Question Source: | Learning Objective: 11.1 Describe the interrelationships between the CRWST and the CRD Hydraulic System. | ||
Bank # | Question Source: Bank # | ||
Modified Bank # | (note changes; attach parent) Modified Bank # | ||
New X | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X | ||
Last NRC Exam No | |||
Memory/Fundamental X | Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(6) | ||
Comprehensive/Analysis 10CFR Part 55 Content: | |||
55.41(b)(6) | Examination Outline Cross-Reference Level RO 201003 Control Rod and Drive Mechanism Tier # 2 Group # 2 Knowledge of the operational implications of K/A # 201003 K5.01 the following concepts as they apply to Rating 2.6 CONTROL ROD AND DRIVE MECHANISM | ||
Examination Outline Cross | :Hydraulics Question 55 In order to continuously withdraw a CRDM, the collet fingers are continuously held: | ||
-Reference Level RO 201003 Control Rod and Drive Mechanism Knowledge of the operational implications of the following concepts as they apply to CONTROL ROD AND DRIVE MECHANISM | A. outward by hydraulic pressure B. outward by mechanical interaction with the index tube C. inward by hydraulic pressure D. inward by mechanical interaction with the index tube Answer: A Explanation: The collet fingers are initially opened by mechanical interaction with the index tube by a slight insertion, but they are subsequently held open by hydraulic pressure applied to a piston. The fingers move outward to unlatch the rod, they move inward to latch the rod and prevent outward movement. | ||
:Hydraulics | |||
The collet fingers are initially opened by mechanical interaction with the index tube by a slight insertion, but they are subsequently held open by hydraulic pressure applied to a piston. The fingers move outward to unlatch the rod, they move inward to latch the rod and prevent outward movement. | |||
Technical | Technical | ||
==References:== | ==References:== | ||
GLP-OPS-C111A_008-1 | GLP-OPS-C111A_008-1 References to be provided to applicants during exam: | ||
Learning Objective:GLP-OPS-C111A Describe in detail the following control rod operations: (10.0) o Control rod insertion (10.1) o Control rod withdrawal (10.2) | Learning Objective:GLP-OPS-C111A Describe in detail the following control rod operations: | ||
(10.0) o Control rod insertion (10.1) o Control rod withdrawal (10.2) | |||
GLP-OPS-C111AB Describe the following CRD Mechanism evolutions and operations: (5) | GLP-OPS-C111AB Describe the following CRD Mechanism evolutions and operations: (5) | ||
Operation of the collet locking mechanism. (5.3) | Operation of the collet locking mechanism. (5.3) | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No | ||
New X | |||
Last NRC Exam No Question Cognitive Level: | Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Memory/Fundamental X | |||
55.41(b)(7) 55.43 Examination Outline Cross | Examination Outline Cross-Reference Level RO 201005 RCIS Tier # 2 Group # 2 Ability to predict and/or monitor changes in K/A # 201005 - A1.01 parameters associated with operating the Rating 3.2 ROD CONTROL AND INFORMATION SYSTEM (RCIS) controls including: First stage shell pressure/turbine load: BWR-6 Question 56 If the plant is at 65% power with 1 bypass valve full open the Rod Control and Information System will allow control rods to be withdrawn a maximum of (a) notch/notches at a time. | ||
-Reference Level RO 201005 RCIS Ability to predict and/or monitor changes in parameters associated with operating the ROD CONTROL AND INFORMATION SYSTEM (RCIS) controls including: | A. 1 B. 2 C. 4 D. 12 Answer: C Explanation: | ||
-6 | Above the High Power Setpoint (62% RTP), rod withdrawal is limited to two notches by the RWL. For instance, if reactor power is 63% with the bypass valves open, RC&lS will interpret the lower first stage turbine pressure as a lower reactor power. If RC&lS sees a first stage turbine pressure equivalent to 60%, it will allow rods to be withdrawn four notches (below the HPSP) instead of the limit of two notches as required above the HPSP. | ||
A. 1 | Technical | ||
==References:== | ==References:== | ||
GLP-OPS-C1102, Rod Control and Information Systems (RC&IS), Revision 6, p. 20 References to be provided to applicants during exam: | GLP-OPS-C1102, Rod Control and Information Systems (RC&IS), Revision 6, p. 20 References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: Describe the reason for restricting Main Steam Bypass Valve operation when at power. (7.2) | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X | ||
New X | |||
Last NRC Exam No | |||
Memory/Fundamental Comprehensive/Analysis X | |||
Opening 1G33 | 10CFR Part 55 Content: 55.41(b)(6) | ||
-F003, RWCU SYS BLWDN FLO CONT valve too far can result in the need to subsequently: | Examination Outline Cross-Reference Level RO 204000 RWCU Tier # 2 Group # 2 Ability to manually operate and/or monitor in K/A # 204000 A4.02 the control room: Valve controllers Rating 2.9 Question 57 Reactor pressure is 150 psig during a plant heatup with RWCU blowdown to the main condenser maintaining RPV level. | ||
Opening 1G33-F003, RWCU SYS BLWDN FLO CONT valve too far can result in the need to subsequently: | |||
A. replace RWCU pump seals. | A. replace RWCU pump seals. | ||
B. re-open 1G33-F004. | B. re-open 1G33-F004. | ||
C. backwash and precoat the F/Ds. | C. backwash and precoat the F/Ds. | ||
D. re-open the primary containment isolation group 8 valves. | D. re-open the primary containment isolation group 8 valves. | ||
Answer: B | Answer: B Explanation: | ||
Opening F033 will cause non | Opening F033 will cause non-regenerative HX outlet temp to rise because of a loss of cooling flow in the regenerative HX. If it reaches 140°F, 1GG33-F004 closes and the RWCU pumps trip. | ||
-regenerative HX outlet temp to rise because of a loss of cooling flow in the regenerative HX. If it reaches 140°F, 1GG33 | A is wrong because at this reactor pressure the RWCU pumps are in the POST-Pump mode. | ||
-F004 closes and the RWCU pumps trip. | RWCU will isolate at 140° which is well within design of RWCU seals. | ||
A is wrong because at this reactor pressure the RWCU pumps are in the POST | |||
-Pump mode. RWCU will isolate at 140° which is well within design of RWCU seals. | |||
C is wrong because the demineralizer hold pump is designed to auto start as flow drops to prevent loss of precoat. | C is wrong because the demineralizer hold pump is designed to auto start as flow drops to prevent loss of precoat. | ||
D is wrong because this activity should not result in any condition that causes the group 8 isolation. | D is wrong because this activity should not result in any condition that causes the group 8 isolation. | ||
Line 1,337: | Line 1,109: | ||
04-1-02-1H13-P680-11A-C6 ARI, RWCU FLTR DMIN INL TEMP HI 140°F. | 04-1-02-1H13-P680-11A-C6 ARI, RWCU FLTR DMIN INL TEMP HI 140°F. | ||
04-1-01-G33-1, Reactor Water Cleanup, caution on top of page 55. | 04-1-01-G33-1, Reactor Water Cleanup, caution on top of page 55. | ||
References to be provided to applicants during exam: | References to be provided to applicants during exam: None Learning Objective: GLP-OPS-G3336 Describe any interlocks, trips, or automatic actions associated with the following Reactor Water Cleanup System components: (8.0) System | ||
None | |||
-OPS-G3336 Describe any interlocks, trips, or automatic actions associated with the following Reactor Water Cleanup System components: (8.0) | Isolation Valves (8.6) | ||
Concerning SOI 04 01-G33-1: (10.0) Identify the reasons for the precautions, limitations, cautions, warnings and notes given in the SOI. (10.2) | Concerning SOI 04-1-01-G33-1: (10.0) | ||
Question Source: | Identify the reasons for the precautions, limitations, cautions, warnings and notes given in the SOI. (10.2) | ||
Bank # | Question Source: Bank # | ||
Modified Bank # | (note changes; attach parent) Modified Bank # | ||
New X | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Last NRC Exam No | |||
Memory/Fundamental Comprehensive/Analysis X | Examination Outline Cross-Reference Level RO 219000 RHR/LPCI: Torus/Pool Cooling Tier # 2 Mode Group # 2 K/A # 219000 - 2.1.28 Knowledge of the purpose and function of Rating 4.1 major system components and controls Question 58 The suppression pool cooling mode of RHR is designed to limit suppression pool temperature to a maximum of (a) during normal conditions to ensure suppression pool temperature does not exceed 185oF under accident conditions. This is accomplished in the suppression pool cooling mode by regulating flow through the A. 95oF; F024A/B, RHR A/B test return to suppression pool B. 95oF; F048A/B, heat exchanger A/B bypass valve C. 110oF; F024A/B, RHR A/B test return to suppression pool D. 110oF; F048A/B, heat exchanger A/B bypass valve Answer: B Explanation: | ||
55.41(b)(7) 55.43 Examination Outline Cross | A is wrong because the valve listed is not throttled in the suppression pool cooling mode B is correct because this is the temperature listed in the training manual and the only valve that should be throttled in SOI 04-1-01-E12, Residual Heat removal System. | ||
-Reference Level RO 219000 RHR/LPCI: Torus/Pool Cooling | C is wrong because this temperature is not listed in the training manual but plausible since it is listed in the EOP (EP-2). Also this is the incorrect valve for regulating temperature D is wrong because see answer C. | ||
A is wrong because the valve listed is not throttled in the suppression pool cooling mode B is correct because this is the temperature listed in the training manual and the only valve that should be throttled in SOI 04 01-E12, Residual Heat removal System. | |||
C is wrong because this temperature is not listed in the training manual but plausible since it is listed in the EOP (EP | |||
-2). Also this is the incorrect valve for regulating temperature D is wrong because see answer C. | |||
Technical | Technical | ||
==References:== | ==References:== | ||
GLP-OPS-E1200, Residual Heat Removal (RHR) System | GLP-OPS-E1200, Residual Heat Removal (RHR) System - E12 SOI 04-1-01-E12, Residual Heat removal System References to be provided to applicants during exam: None. | ||
- E12 SOI 04-1-01-E12, Residual Heat removal System References to be provided to applicants during exam: | Learning Objective: State/identify the purpose/function of the Suppression Pool Cooling mode of RHR (1.4) | ||
None. Learning Objective: | Question Source: Bank # | ||
Question Source: | (note changes; attach parent) Modified Bank # | ||
Bank # | New X Question History: Last NRC Exam No | ||
Modified Bank # | |||
New X | Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) | ||
Last NRC Exam No Question Cognitive Level: | |||
Memory/Fundamental X | Examination Outline Cross-Reference Level RO 219000 RHR/LPCI: Torus/Pool Cooling Tier # 2 Mode Group # 2 K/A # 219000 - 2.1.28 Knowledge of the purpose and function of Rating 4.1 major system components and controls Question 58 The suppression pool cooling mode of RHR is designed to limit suppression pool temperature to a maximum of (a) during normal conditions to ensure suppression pool temperature does not exceed 185oF under accident conditions. This is accomplished in the suppression pool cooling mode by regulating flow through the A. 95oF; F024A/B, RHR A/B test return to suppression pool B. 95oF; F048A/B, heat exchanger A/B bypass valve C. 110oF; F024A/B, RHR A/B test return to suppression pool D. 110oF; F048A/B, heat exchanger A/B bypass valve Answer: B Explanation: | ||
55.41(b)(7) | A is wrong because the valve listed is not throttled in the suppression pool cooling mode B is correct because this is the temperature listed in the training manual and the only valve that should be throttled in SOI 04-1-01-E12, Residual Heat removal System. | ||
Examination Outline Cross | C is wrong because this temperature is not listed in the training manual but plausible since it is listed in the EOP (EP-2). Also this is the incorrect valve for regulating temperature D is wrong because see answer C. | ||
-Reference Level RO 219000 RHR/LPCI: Torus/Pool Cooling | |||
A is wrong because the valve listed is not throttled in the suppression pool cooling mode B is correct because this is the temperature listed in the training manual and the only valve that should be throttled in SOI 04 01-E12, Residual Heat removal System. | |||
C is wrong because this temperature is not listed in the training manual but plausible since it is listed in the EOP (EP | |||
-2). Also this is the incorrect valve for regulating temperature D is wrong because see answer C. | |||
Technical | Technical | ||
==References:== | ==References:== | ||
GLP-OPS-E1200, Residual Heat Removal (RHR) System | GLP-OPS-E1200, Residual Heat Removal (RHR) System - E12 SOI 04-1-01-E12, Residual Heat removal System References to be provided to applicants during exam: None. | ||
- E12 SOI 04-1-01-E12, Residual Heat removal System References to be provided to applicants during exam: | Learning Objective: State/identify the purpose/function of the Suppression Pool Cooling mode of RHR (1.4) | ||
None. Learning Objective: | Question Source: Bank # | ||
(note changes; attach parent) Modified Bank # | |||
Bank # | New X Question History: Last NRC Exam No | ||
Modified Bank # | |||
New X | Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) | ||
Last NRC Exam No Question Cognitive Level: | |||
Memory/Fundamental X | Examination Outline Cross-Reference Level RO 219000 RHR/LPCI: Torus/Pool Cooling Tier # 2 Mode Group # 2 K/A # 219000 - 2.1.28 Knowledge of the purpose and function of Rating 4.1 major system components and controls Question 58 The suppression pool cooling mode of RHR is designed to limit suppression pool temperature to a maximum of (a) during normal conditions to ensure suppression pool temperature does not exceed 185oF under accident conditions. This is accomplished in the suppression pool cooling mode by regulating flow through the A. 95oF; F024A/B, RHR A/B test return to suppression pool B. 95oF; F048A/B, heat exchanger A/B bypass valve C. 110oF; F024A/B, RHR A/B test return to suppression pool D. 110oF; F048A/B, heat exchanger A/B bypass valve Answer: B Explanation: | ||
55.41(b)(7) | A is wrong because the valve listed is not throttled in the suppression pool cooling mode B is correct because this is the temperature listed in the training manual and the only valve that should be throttled in SOI 04-1-01-E12, Residual Heat removal System. | ||
Examination Outline Cross | C is wrong because this temperature is not listed in the training manual but plausible since it is listed in the EOP (EP-2). Also this is the incorrect valve for regulating temperature D is wrong because see answer C. | ||
-Reference Level RO 219000 RHR/LPCI: Torus/Pool Cooling | |||
A is wrong because the valve listed is not throttled in the suppression pool cooling mode B is correct because this is the temperature listed in the training manual and the only valve that should be throttled in SOI 04 01-E12, Residual Heat removal System. | |||
C is wrong because this temperature is not listed in the training manual but plausible since it is listed in the EOP (EP | |||
-2). Also this is the incorrect valve for regulating temperature D is wrong because see answer C. | |||
Technical | Technical | ||
==References:== | ==References:== | ||
GLP-OPS-E1200, Residual Heat Removal (RHR) System | GLP-OPS-E1200, Residual Heat Removal (RHR) System - E12 SOI 04-1-01-E12, Residual Heat removal System References to be provided to applicants during exam: None. | ||
- E12 SOI 04-1-01-E12, Residual Heat removal System References to be provided to applicants during exam: | Learning Objective: State/identify the purpose/function of the Suppression Pool Cooling mode of RHR (1.4) | ||
None. Learning Objective: | Question Source: Bank # | ||
Question Source: | (note changes; attach parent) Modified Bank # | ||
Bank # | New X Question History: Last NRC Exam No | ||
Modified Bank # | |||
New X | Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) | ||
Last NRC Exam No Question Cognitive Level: | |||
Memory/Fundamental X | Examination Outline Cross-Reference Level RO 233000 Fuel Pool Cooling/Cleanup Tier # 2 Group # 2 Knowledge of FUEL POOL COOLING K/A # 233000 - K4.08 AND CLEAN-UP design feature(s) and/or Rating 2.6 interlocks which provide for the following: | ||
55.41(b)(7) | Pool cooling during loss of cooling accident: | ||
Examination Outline Cross | BWR-6 Question 60 Both fuel pool cooling water pumps are running when a LOCA signal is received. Both pumps will trip and A. both will be automatically restarted by the sequencer. | ||
-Reference Level RO 233000 Fuel Pool Cooling/Cleanup Knowledge of FUEL POOL COOLING AND CLEAN-UP design feature(s) and/or interlocks which provide for the following: Pool cooling during loss of cooling accident: BWR-6 | |||
B. neither pump can be restarted until the LOCA signal is reset. | B. neither pump can be restarted until the LOCA signal is reset. | ||
C. either pump can be manually restarted immediately. | C. either pump can be manually restarted immediately. | ||
D. either pump can be manually restarted following load shedding and sequencing. | D. either pump can be manually restarted following load shedding and sequencing. | ||
Answer: D | Answer: D Explanation: | ||
A is wrong because the pumps are not listed as loads that automatically sequence on. | A is wrong because the pumps are not listed as loads that automatically sequence on. | ||
B is wrong because the LOCA signal does not lock out the pumps. | B is wrong because the LOCA signal does not lock out the pumps. | ||
C is wrong because the LSS signal | C is wrong because the LSS signal cant be in or the pump will trip and the signal will be in while loads are sequencing. | ||
D is correct because see A, but they are listed as loads that are not locked out and can be manually started. | D is correct because see A, but they are listed as loads that are not locked out and can be manually started. | ||
Technical | Technical | ||
Line 1,418: | Line 1,178: | ||
==References:== | ==References:== | ||
04-1-01-R21-1, Load Shedding and Sequencing System GLP-OPS-R2100, Load Shedding and Sequencing System and ESF AC Power Distribution System | 04-1-01-R21-1, Load Shedding and Sequencing System GLP-OPS-R2100, Load Shedding and Sequencing System and ESF AC Power Distribution System References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: (17) Describe the sequencing of Loads on a LOCA signal. | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No | ||
New X | |||
Last NRC Exam No | |||
Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7), 55.41(b)(8) | |||
Examination Outline Cross-Reference Level RO 245000 Main Turbine Gen. / Aux Tier # 2 Group # 2 Knowledge of the effect that a loss or K/A # 245000 K6.08 malfunction of the following will have on the Rating 3.0 MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS : Main steam Question 61 One SRV failing open at rated power will result in generator megawatts __(1)____ and feedwater injection temperature __(2)__. | |||
(1) (2) | |||
A. lowering lowering B. lowering remaining constant C. remaining constant lowering D. remaining constant remaining constant Answer: A Explanation: | |||
The SRV operation lowers steam pressure, EHC responds by lowering turbine steam flow. | |||
The lowered turbine steam flow leads to reduced extraction steam flow, which lowers feedwater temperature. | |||
Technical | Technical | ||
==References:== | ==References:== | ||
ARI 04-01-02-1H13-P601-19A-A5, SRV/ADS VLV OPEN/DISCH LINE PRESS HI References to be provided to applicants during exam: | ARI 04-01-02-1H13-P601-19A-A5, SRV/ADS VLV OPEN/DISCH LINE PRESS HI References to be provided to applicants during exam: None Learning Objective: GLP-OPS-E2202 Identify the system interrelationships between each of the following systems and the ADS/SRV System: (19.0) | ||
None | |||
GLP-OPS-E2202 | |||
Nuclear Boiler B13/21 (19.2) | Nuclear Boiler B13/21 (19.2) | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No | ||
New X | |||
Last NRC Exam No | |||
Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | |||
A. Feedflow will increase and the reactor will scram on high water level. | Examination Outline Cross-Reference Level RO Reactor Feedwater Tier # 2 Group # 2 Knowledge of the effect that a loss or K/A # 259001 - K6.07 malfunction of the following will have on the Rating 3.8 REACTOR FEEDWATER SYSTEM: | ||
B. Feedflow will decrease and the reactor will scram on low water level. | Reactor water level control system Question 62 The plant is operating at steady state with reactor power at 90% when steam flow transmitter N34-N030A fails upscale. Following this failure, the following occurs: | ||
C. DFCS will automatically shift to single element control and feedflow remains fairly constant. D. DFCS automatically deselects N34 | * STEAM FLOW FAIL light begins flashing | ||
-N030A, remains in 3 | * DFCS TROUBLE alarm annunciates on H13-P680 Based on this malfunction; A. Feedflow will increase and the reactor will scram on high water level. | ||
-element control, and feedflow remains fairly constant. | B. Feedflow will decrease and the reactor will scram on low water level. | ||
Answer: C | C. DFCS will automatically shift to single element control and feedflow remains fairly constant. | ||
D. DFCS automatically deselects N34-N030A, remains in 3-element control, and feedflow remains fairly constant. | |||
Answer: C Explanation: | |||
A is wrong; feedflow will remain fairly constant because the DFCS shifts to single element control and maintains reactor water level at setpoint. | A is wrong; feedflow will remain fairly constant because the DFCS shifts to single element control and maintains reactor water level at setpoint. | ||
B is wrong; feedflow will remain fairly constant because the DFCS shifts to single element control and maintains reactor water level at setpoint. | B is wrong; feedflow will remain fairly constant because the DFCS shifts to single element control and maintains reactor water level at setpoint. | ||
Line 1,470: | Line 1,220: | ||
GLP-OPS-C3400.12, page 31. | GLP-OPS-C3400.12, page 31. | ||
References to be provided to applicants during exam: | References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: C3400.12 - 5.3 - State/identify the consequences of a steam flow channel failure. | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b).4 55.43.5 | ||
New X | |||
Last NRC Exam No | |||
Memory/Fundamental X | |||
55.41(b).4 55.43.5 | |||
Technical | Examination Outline Cross-Reference Level RO 268000 Radwaste Tier # 2 Group # 2 Knowledge of the effect that a loss or K/A # 268000 K3.04 malfunction of the RADWASTE will have on Rating 2.7 following: Drain sumps Question 63 Isolating the floor drain collection tank and both waste surge tanks will result in not being able to pump down the ______. | ||
A. Turbine Building West Equipment Drain Sump B. HPCS Room Sump C. Auxiliary Building North Equipment Drain Sump D. Turbine Building North Chemical Waste Sump Answer: B Explanation: | |||
Of these sumps, only B pumps to these tanks (dirty RW). A and C discharge to the Equipment collection drain tanks (clean RW). D discharges to the Miscellaneous Chemical Waste Receiver Tank Technical | |||
==References:== | ==References:== | ||
GLP-OPS-G1718.08 | |||
None | GLP-OPS-G1718.08 References to be provided to applicants during exam: None Learning Objective: State/identify the purpose/function and location of the Equipment Drain Collector Tanks, Floor Drain Collector Tank and Waste Surge Tanks. (3.0) Discuss the water quality of the various inputs to the tanks from operating the plant and the importance of segregation of the waste water. (3.3) | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No | ||
New X | |||
Last NRC Exam No Question Cognitive Level: | Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Memory/Fundamental Comprehensive/Analysis X | |||
55.41(b)(7) 55.43 Examination Outline Cross | Examination Outline Cross-Reference Level RO 27100 Offgas Tier # 2 Group # 2 Knowledge of the physical connections K/A # 271000 - K1.07 and/or cause-effect relationships between Rating 2.7 OFFGAS SYSTEM and the following: Plant air systems Question 64 The air used in the Offgas System is supplied by the _______ Air System and on a loss of air F061A/B, Offgas Condenser Drain Valves, fail _______. | ||
-Reference Level RO 27100 Offgas Knowledge of the physical connections and/or cause | A. Instrument; open B. Instrument; close C. Service; open D. Service; close Answer: A Explanation: | ||
-effect relationships between OFFGAS SYSTEM and the following: Plant air systems | A is correct. | ||
A. Instrument; open B. Instrument; close C. Service; open D. Service; close Answer: A | B is wrong because the valves fail open. | ||
A is correct. B is wrong because the valves fail open. | |||
C is wrong because Instrument Air is used. | C is wrong because Instrument Air is used. | ||
D is wrong because Insrument Air is used and the valves fail open. | D is wrong because Insrument Air is used and the valves fail open. | ||
Line 1,506: | Line 1,250: | ||
==References:== | ==References:== | ||
GLP-OPS-N6465, | GLP-OPS-N6465, References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: (8.4) State/identify the location from where the Offgas Condenser Drain Valves, F016A/B, can be operated (14.2) Discuss the interrelationships of the Instrument Air System with the Offgas/Vault Refrigeration System Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis | ||
New X | |||
Last NRC Exam No | |||
Memory/Fundamental Comprehensive/Analysis | |||
10CFR Part 55 Content: | 10CFR Part 55 Content: 55.41(b)(13) | ||
55.41(b)(13) | Examination Outline Cross-Reference Level RO 290003 Control Room HVAC Tier # 2 Group # 2 Ability to monitor automatic operations of the K/A # 290003 A3.02 CONTROL ROOM HVAC including: Rating 3.0 Initiation/failure of fire protection system Question 65 The operating control room air conditioning unit will automatically shut down if: | ||
Examination Outline Cross | |||
-Reference Level RO 290003 Control Room | |||
A. smoke is detected in the return ductwork from the control room. | A. smoke is detected in the return ductwork from the control room. | ||
B. high-high radiation is sensed in the outside air intake duct. | B. high-high radiation is sensed in the outside air intake duct. | ||
C. high-high temperature is sensed on an operating fresh air unit filter train. | C. high-high temperature is sensed on an operating fresh air unit filter train. | ||
D. a Freon leak is detected in the control room air conditioner cooling coils. | D. a Freon leak is detected in the control room air conditioner cooling coils. | ||
Answer: | Answer: A Explanation: | ||
Upon sensing the presence of smoke in the return ductwork from the Control Room or in the fresh air intake duct, the smoke detector causes the following actions to take place: | Upon sensing the presence of smoke in the return ductwork from the Control Room or in the fresh air intake duct, the smoke detector causes the following actions to take place: | ||
The operating air conditioning unit inlet and outlet dampers close. | * The operating air conditioning unit shuts down. | ||
The fire detection system sounds the fire alarm. | * The operating air conditioning unit inlet and outlet dampers close. | ||
B is wrong because this isolates the control room but does not trip the air conditioning unit. C is wrong because this shuts down the running control room standby fresh air units. | * The fire detection system sounds the fire alarm. | ||
B is wrong because this isolates the control room but does not trip the air conditioning unit. | |||
C is wrong because this shuts down the running control room standby fresh air units. | |||
D is wrong because the Freon leak alarm has no automatic actions associated with it.. | D is wrong because the Freon leak alarm has no automatic actions associated with it.. | ||
Technical | Technical | ||
Line 1,533: | Line 1,273: | ||
==References:== | ==References:== | ||
ARI 04-S-02-SH13-P855-1A-B4 , CONT RM HVAC FREON HI GLP-OPS-Z5100 | ARI 04-S-02-SH13-P855-1A-B4, CONT RM HVAC FREON HI GLP-OPS-Z5100 References to be provided to applicants during exam: None Learning Objective: GLP-OPS-Z5100 Discuss the interrelationships of the Plant Fire Protection System with the Control Room HVAC System. (13.6) | ||
None | Question Source: Bank # | ||
Question Source: | (note changes; attach parent) Modified Bank # | ||
Bank # | New X Question History: Last NRC Exam No | ||
Modified Bank # | |||
New X | Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Last NRC Exam No Question Cognitive Level: | |||
Memory/Fundamental Comprehensive/Analysis X | Examination Outline Cross-Reference Level RO Conduct of Operations Tier # 3 Group # | ||
55.41(b)(7) 55.43 Examination Outline Cross | Knowledge of shift turnover practices. K/A # 2.1.3 Rating 3.0 Question 66 What is the MAXIMUM time a shift can be one less than the minimum required by regulations? Can the exception to minimum staffing requirements be invoked during shift change for a crewperson being late or absent? | ||
-Reference Level RO Conduct of Operations Knowledge of shift turnover practices. | A. 1 hour; Yes B. 1 hour; No C. 2 hours; Yes D. 2 hours; No Answer: D Explanation: | ||
A. 1 hour; Yes B. 1 hour; No C. 2 hours; Yes D. 2 hours; No Answer: D | |||
A is wrong because the time is less than the maximum allowed but is a logical time to get an onsite replacement. | A is wrong because the time is less than the maximum allowed but is a logical time to get an onsite replacement. | ||
B is wrong because of answer A. The conduct of operations procedure does not allow for this exception for tardiness or absence. The second part of the question is correct. | B is wrong because of answer A. The conduct of operations procedure does not allow for this exception for tardiness or absence. The second part of the question is correct. | ||
Line 1,552: | Line 1,290: | ||
==References:== | ==References:== | ||
EN-OP-115, Conduct of Operations , Rev. 14, Attachment 9.3 References to be provided to applicants during exam: | EN-OP-115, Conduct of Operations , Rev. 14, Attachment 9.3 References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: N/A Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No | ||
New X | |||
Memory/Fundamental Comprehensive/Analysis X | Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(10) | ||
55.41(b)(10) | |||
Examination Outline Cross | Examination Outline Cross-Reference Level RO Conduct of Operations Tier # 3 Group # | ||
-Reference Level RO Conduct of Operations Knowledge of the refueling process. | Knowledge of the refueling process. K/A # 2.1.41 Rating 2.8 Question 67 When removing the reactor vessel head, reactor vessel level should be maintained using the | ||
________ range. | |||
A. Fuel Zone | A. Fuel Zone B. Wide C. Upset D. Shutdown Answer: D Explanation: | ||
The target is to maintain vessel level approximately one foot below the vessel flange (196 to 200 on shutdown range). Level too high would result in water spilling over the flange. Level too low increases dose in the refueling area. Only the Shutdown Range measures level this high. | |||
Technical | |||
==References:== | ==References:== | ||
03-1-01-5 Refueling, Step 5.15.15 GFIG-OPS-B2101, Figure 2 References to be provided to applicants during exam: | 03-1-01-5 Refueling, Step 5.15.15 GFIG-OPS-B2101, Figure 2 References to be provided to applicants during exam: | ||
Learning Objective: GLP-OPS-B2101 | Learning Objective: GLP-OPS-B2101 State/identify the indicating ranges of the following RPV Water Level Instruments: (5.0) o Reactor Water Level Narrow Range (5.1) o Reactor Water Level Wide Range (5.2) o Reactor Water Level Shutdown Range (5.3) o Reactor Water Level Upset Range (5.4) o Reactor Water Level Fuel Zone Range (5.5) | ||
Question Source: Bank # | |||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X | ||
New X Question History: | |||
Last NRC Exam No | Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Memory/Fundamental Comprehensive/Analysis X | |||
55.41(b)(7) 55.43 Examination Outline Cross | Examination Outline Cross-Reference Level RO Conduct of Operations Tier # 3 Group # | ||
-Reference Level RO Conduct of Operations Knowledge of conduct of operations | Knowledge of conduct of operations K/A # 2.1.1 requirements. Rating 3.8 Question 68 Per ENP-OP-115, Conduct of Operations, which of the following tasks is allowed to be performed without a procedure in hand? | ||
A. Adjusting circulating water blowdown flow. | A. Adjusting circulating water blowdown flow. | ||
B. Initiating SLC during an ATWS. | B. Initiating SLC during an ATWS. | ||
C. Resetting a full scram. | C. Resetting a full scram. | ||
D. Rotating CRD pumps. | D. Rotating CRD pumps. | ||
Answer: A | Answer: A Explanation: | ||
A is correct because the activity is specified in Attachment 9.3 of ENP | A is correct because the activity is specified in Attachment 9.3 of ENP-OP-115, Conduct of Operations B is wrong because it is not listed in the procedure. | ||
-OP-115, Conduct of Operations B is wrong because it is not listed in the procedure. | |||
C is wrong because it is not listed in the procedure but resetting a half scram is. | C is wrong because it is not listed in the procedure but resetting a half scram is. | ||
D is wrong because it is not listed in the procedure. | D is wrong because it is not listed in the procedure. | ||
Line 1,589: | Line 1,327: | ||
==References:== | ==References:== | ||
.3 of ENP-OP-115, Conduct of Operations, Rev 14 References to be provided to applicants during exam: None. | |||
Learning Objective: N/A. | |||
Question Source: Bank # | |||
(note changes; attach parent) Modified Bank # | |||
New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(10) | |||
55.43 Examination Outline Cross-Reference Level RO Conduct of Operations Tier # 3 Group # | |||
Knowledge of the process used to track K/A # 2.1.43 inoperable alarms. Rating 3.0 Question 69 A single length of red tape placed diagonally across an alarm window means the annunciator: | |||
- | |||
A. card has been removed. | A. card has been removed. | ||
B. is not functioning properly due to faulty alarm circuitry. | B. is not functioning properly due to faulty alarm circuitry. | ||
C. inputs have been verified to cause a nuisance alarm. | C. inputs have been verified to cause a nuisance alarm. | ||
D. deficiency affects technical specification operability. | D. deficiency affects technical specification operability. | ||
Answer: | Answer: B Explanation: | ||
A is wrong because a removed card is identified by two lengths of red tape placed to form an | A is wrong because a removed card is identified by two lengths of red tape placed to form an X. | ||
C is wrong because an annunciator with input bypassed due to nuisance alarm is designated with two vertical lengths of red tape. | |||
D is wrong because this condition leads to further documentation but not a window marking Technical | D is wrong because this condition leads to further documentation but not a window marking Technical | ||
Line 1,615: | Line 1,349: | ||
References to be provided to applicants during exam: | References to be provided to applicants during exam: | ||
Learning Objective: | Learning Objective: | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) | ||
New X | |||
Last NRC Exam No | |||
Memory/Fundamental X | |||
55.41(b)(7) | |||
55.43 Examination Outline Cross-Reference Level RO Equipment Control Ability to determine operability and/or | 55.43 Examination Outline Cross-Reference Level RO Equipment Control Tier # 3 Group # | ||
Ability to determine operability and/or K/A # 2.2.37 availability of safety related equipment Rating 3.6 Question 70 Can systems be considered operable if a system fails to meet acceptance criteria between required performances of the surveillance? | |||
Can systems be considered operable when auxiliary equipment required to be operable is inoperable, but the system can still meet its surveillance requirement acceptance criteria? | Can systems be considered operable when auxiliary equipment required to be operable is inoperable, but the system can still meet its surveillance requirement acceptance criteria? | ||
A. Yes/Yes B. Yes/No C. No/Yes D. No/No Answer: D Explanation: | |||
A. Yes/ | |||
A is wrong because SR 3.0.1 clearly defines that failure can to meet a SR can happen anytime and if so the LCO is no longer met. Also, the second question tests the definition of OPERABLE/OPERABILITY and the answer does not meet this definition. | A is wrong because SR 3.0.1 clearly defines that failure can to meet a SR can happen anytime and if so the LCO is no longer met. Also, the second question tests the definition of OPERABLE/OPERABILITY and the answer does not meet this definition. | ||
B is wrong because of the first half of A. | B is wrong because of the first half of A. | ||
Line 1,635: | Line 1,365: | ||
==References:== | ==References:== | ||
Technical Specifications SR 3.0.1 and Technical Specification definition of operability References to be provided to applicants during exam: | Technical Specifications SR 3.0.1 and Technical Specification definition of operability References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: N/A Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No | ||
New X | |||
Last NRC Exam No Question Cognitive Level: | Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(10) | ||
Memory/Fundamental X | |||
55.41(b)(10) | Examination Outline Cross-Reference Level RO Equipment Control Tier # 3 Group # | ||
Examination Outline Cross | Ability to track Technical Specification limiting K/A # 2.2.23 conditions for operations. Rating 3.1 Question 71 A valve is re-positioned to satisfy the requirements of a technical specification required action and is documented on an eSOMS LCOTR. | ||
-Reference Level RO Equipment Control Ability to track Technical Specification limiting | |||
-positioned to satisfy the requirements of a technical specification required action and is documented on an eSOMS LCOTR. | |||
This valve would be identified with a ______ tag. | This valve would be identified with a ______ tag. | ||
A. No | A. No B. Danger C. Test & Maintenance D. Caution Answer: D Explanation: | ||
A no tag identifies components that cannot be tagged but require positioning when hanging and removing a tagout. | A no tag identifies components that cannot be tagged but require positioning when hanging and removing a tagout. | ||
There is no LCOTR tag. | There is no LCOTR tag. | ||
A test & maintenance tag makes the tagout holder accountable for the | A test & maintenance tag makes the tagout holder accountable for the components status. | ||
Technical | Technical | ||
Line 1,658: | Line 1,385: | ||
02-S-01-17, Control of Limiting Conditions for Operation References to be provided to applicants during exam: | 02-S-01-17, Control of Limiting Conditions for Operation References to be provided to applicants during exam: | ||
Learning Objective: | Learning Objective: | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) | ||
New X | |||
Last NRC Exam No | 55.43 Examination Outline Cross-Reference Level RO Radiation Control Tier # 3 Group # | ||
Memory/Fundamental X | Ability to use radiation monitoring systems, K/A # 2.3.5 such as fixed radiation monitors and alarms, Rating 2.9 portable survey instruments, personnel monitoring equipment, etc. | ||
55.41(b)(7) 55.43 Examination Outline Cross | Question 72 Taking the mode switch from Operate to Off on an Area Radiation Monitor causes the FAIL SAFE green light to extinguish and the A. LOCAL red light to illuminate. | ||
-Reference Level RO Radiation Control Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. | |||
B. HIGH ALARM/RESET pushbutton to illuminate. | B. HIGH ALARM/RESET pushbutton to illuminate. | ||
C. AREA RAD PNL P845 TROUBLE annunciator on 1H13 | C. AREA RAD PNL P845 TROUBLE annunciator on 1H13-P601 to annunciate. | ||
-P601 to annunciate. | D. AREA RADIATION MONITORING SYSTEM FAILURE annunciator on 1H13-P845 to annunciate. | ||
D. AREA RADIATION MONITORING SYSTEM FAILURE annunciator on 1H13 | Answer: A Explanation: | ||
-P845 to annunciate. | A is correct because this will come in as specified in training material B is wrong because this will not come in but plausible if an applicant believes turning the monitor off doesnt fully remove power and you need to reset the ARM also. | ||
Answer: A | |||
A is correct because this will come in as specified in training material B is wrong because this will not come in but plausible if an applicant believes turning the monitor off | |||
C is wrong because this is not the correct annunciator or panel but plausible since both are close D is wrong because this is the incorrect annunciator panel Technical | C is wrong because this is not the correct annunciator or panel but plausible since both are close D is wrong because this is the incorrect annunciator panel Technical | ||
==References:== | ==References:== | ||
GLP-OPS-D1721, Radiation Monitoring System, Rev 14, p.21 References to be provided to applicants during exam: | GLP-OPS-D1721, Radiation Monitoring System, Rev 14, p.21 References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: Document learning objective if possible. | ||
Document learning objective if possible. | Question Source: Bank # | ||
Question Source: | (note changes; attach parent) Modified Bank # | ||
Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis | ||
Modified Bank # | |||
New X | |||
Last NRC Exam No | |||
Memory/Fundamental X | |||
10CFR Part 55 Content: | 10CFR Part 55 Content: 55.41(b)(11) | ||
55.41(b)(11) | Examination Outline Cross-Reference Level RO Radiation Control Tier # 3 Group # | ||
Examination Outline Cross | Knowledge of radiation monitoring systems, K/A # 2.3.15 such as fixed radiation monitors and alarms, Rating 2.9 portable survey instruments, personnel monitoring equipment, etc. | ||
-Reference Level RO Radiation Control Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. | Question 73 The Area Radiation monitors utilize _________ detectors. | ||
A. Geiger-Mueller tube B. ion chamber C. scintillation D. solid state alpha and beta scintillation Answer: A Explanation: | |||
A. Geiger-Mueller tube B. ion chamber C. scintillation D. solid state alpha and beta scintillation Answer: A | |||
The main steamline radiation monitoring subsystem uses ion chambers. | The main steamline radiation monitoring subsystem uses ion chambers. | ||
The process liquid monitoring subsystem uses scintillation detectors. | The process liquid monitoring subsystem uses scintillation detectors. | ||
Ventilation release rad monitors use solid state alpha detectors and beta scintillation | Ventilation release rad monitors use solid state alpha detectors and beta scintillation detectors. | ||
Technical | |||
==References:== | ==References:== | ||
GLP-OPS-D1721, p 19 of 68 References to be provided to applicants during exam: | GLP-OPS-D1721, p 19 of 68 References to be provided to applicants during exam: None Learning Objective: GLP-OPS-D1721 State/identify the types of detectors used for the following radiation monitors: (5) Area Radiation Monitors (5.1) | ||
None | Question Source: Bank # | ||
GLP-OPS-D1721 State/identify the types of detectors used for the following radiation monitors: (5) | (note changes; attach parent) Modified Bank # | ||
Question Source: | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X | ||
Bank # | |||
Modified Bank # | Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) 55.43 Examination Outline Cross-Reference Level RO Emergency Procedures/Plan Tier # 3 Group # | ||
New X | Knowledge of EOP entry conditions and K/A # 2.4.1 immediate action steps. Rating 4.6 Question 74 Which of the following is an entry condition to EP-2, RPV Control, and what is the purpose of the immediate action that follows? | ||
Last NRC Exam No | A. Suppression pool temperature above 95oF, maintain a sufficient heat sink B. Drywell pressure above 1.23 psig, ensure reactor is shutdown C. Drywell temperature above 135oF, protect equipment in the containment D. Containment temperature above 95oF, maintain containment integrity Answer: B Explanation: | ||
Memory/Fundamental X | A is wrong because it is not an entry condition for EP-2 B is correct because it is an entry condition and the immediate action is to ensure the reactor has scrammed C is wrong because it is not an entry condition for EP-2 D is correct because it is not an entry condition for EP-2 Technical | ||
Comprehensive/Analysis 10CFR Part 55 Content: | |||
55.41(b)(7) 55.43 | |||
-Reference Level RO Emergency Procedures/Plan Knowledge of EOP entry conditions and | |||
-2, RPV Control, and what is the purpose of the immediate action that follows? | |||
A. Suppression pool temperature above | |||
A is wrong because it is not an entry condition for EP | |||
-2 B is correct because it is an entry condition and the immediate action is to ensure the reactor has scrammed C is wrong because it is not an entry condition for EP | |||
-2 D is correct because it is not an entry condition for EP | |||
-2 | |||
==References:== | ==References:== | ||
EP-2, RPV Control References to be provided to applicants during exam: | EP-2, RPV Control References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: Document learning objective if possible. | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental | ||
New X | |||
Last NRC Exam No | |||
Memory/Fundamental | |||
Comprehensive/Analysis X | Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(10) 55.43 | ||
55.41(b)(10) | |||
-Reference Level RO Emergency Procedures/Plan Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines. | Examination Outline Cross-Reference Level RO Emergency Procedures/Plan Tier # 3 Group # | ||
Knowledge of EOP implementation hierarchy K/A # 2.4.16 and coordination with other support Rating 3.5 procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines. | |||
According to Procedure 02 | Question 75 A reactor scram has been automatically initiated due to high drywell pressure. | ||
-S-01-40, EP Technical Bases, Reactor Scram ONEP, 05 02-I-1 should be executed: | According to Procedure 02-S-01-40, EP Technical Bases, Reactor Scram ONEP, 05-01-02-I-1 should be executed: | ||
A. concurrently with EP | A. concurrently with EP-2. | ||
-2. B. prior to entering EP | B. prior to entering EP-2. | ||
-2. | |||
C. only after drywell pressure is less than 1.23 psig. | C. only after drywell pressure is less than 1.23 psig. | ||
D. only after exiting the emergency procedures. | D. only after exiting the emergency procedures. | ||
Answer: | Answer: A. | ||
According to the referenced procedure, ONEP 05-1-02-1-1should be entered and executed concurrently with EP | Explanation: | ||
-2. Technical | According to the referenced procedure, ONEP 05-1-02-1-1should be entered and executed concurrently with EP-2. | ||
Technical | |||
==References:== | ==References:== | ||
02-S-01-40, EP Technical | 02-S-01-40, EP Technical Bases, Revision 004 References to be provided to applicants during exam: None Learning Objective: | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(10) 55.43 | ||
New X | |||
Last NRC Exam No | |||
55.41(b)(10) | |||
Examination Outline Cross | Examination Outline Cross-Reference Level SRO 295021 Loss of Shutdown Cooling Tier # 1 Group # 1 Ability to determine and/or interpret the K/A # 295021 - AA2.04 following as they apply to LOSS OF Rating 3.6 SHUTDOWN COOLING: Reactor water temperature Question 76 The plant is in Mode 4 and flooding up when a spurious Group 3 isolation occurs due to low reactor water level. Thirty minutes has elapsed and maintenance is unable to reset the isolation. Reactor water temperature has risen to 205°F. Primary and secondary containments are intact. | ||
-Reference Level SRO 295021 Loss of Shutdown Cooling Ability to determine and/or interpret the following as they apply to LOSS OF SHUTDOWN COOLING: | What is the current emergency classification for this event? What is the maximum time to make the initial notification to the NRC? | ||
What is the current emergency classification for this event? | A. Unusual Event; 15 minutes B. Unusual Event; 1 hour C. Alert; 15 minutes D. Alert; 1 hour Answer: B Explanation: | ||
A. Unusual Event; 15 minutes B. Unusual Event; 1 hour C. Alert; 15 minutes D. Alert; 1 hour Answer: B | |||
A is wrong because the classification is correct since this is an unplanned event and RCS temperature is greater than 200°F but the time is incorrect. | A is wrong because the classification is correct since this is an unplanned event and RCS temperature is greater than 200°F but the time is incorrect. | ||
B is correct because of A. C is wrong because an alert would only be necessary if 200°F had been exceeded for greater than 60 minutes. | B is correct because of A. | ||
C is wrong because an alert would only be necessary if 200°F had been exceeded for greater than 60 minutes. | |||
D is wrong because of C. | D is wrong because of C. | ||
Technical | Technical | ||
Line 1,766: | Line 1,470: | ||
==References:== | ==References:== | ||
10-S-01-1, Activation of the Emergency Plan, Rev 122, Attachment I, page 7 10-S-01-6, Notification of Offsite Agencies and Plant On-Call Emergency Personnel, Rev 50, Note under Step 6.1.1.d References to be provided to applicants during exam: 10-S-01-1, Activation of the Emergency Plan, Rev 122 Attachment I (all pages) | |||
-Call Emergency Personnel, Rev 50, Note under Step 6.1.1.d References to be provided to applicants during exam: | Learning Objective: Document learning objective if possible. | ||
10-S-01-1, Activation of the Emergency Plan, Rev 122 Attachment I (all pages) | Question Source: Bank # | ||
Learning Objective: | (note changes; attach parent) Modified Bank # | ||
Question Source: | New X Question History: Last NRC Exam No | ||
Bank # | |||
Modified Bank # | Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b) 55.43(b)(5) | ||
New X | |||
Last NRC Exam No Question Cognitive Level: | Examination Outline Cross-Reference Level SRO 295026 Suppression Pool High Water Temp. Tier # 1 Group # 1 Ability to determine and/or interpret the K/A # 295026 EA1.03 following as they apply to SUPPRESSION Rating 3.9 POOL HIGH WATER TEMPERATURE: | ||
Memory/Fundamental Comprehensive/Analysis X | Temperature Monitoring Question 77 | ||
55.41(b) | * The plant is in MODE 2. | ||
Examination Outline Cross | * RCIC testing is in progress in accordance with SR 3.5.3.3. | ||
-Reference Level | * SR 3.5.3.3 was successfully performed 93 days ago. | ||
Ability to determine and/or interpret the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: | * Suppression pool average temperature is 97°F. | ||
Temperature Monitoring | * No other testing is in progress. | ||
RCIC testing is in progress in accordance with SR 3.5.3.3. | * A risk assessment has not been performed | ||
SR 3.5.3.3 was successfully performed 93 days ago. | * LCOs 3.5.3.1 and 3.6.2.1 are provided. | ||
Suppression pool average temperature is 97°F. | |||
No other testing is in progress. | |||
A risk assessment has not been performed LCOs 3.5.3.1 and 3.6.2.1 are provided. | |||
Technical Specifications will allow the plant to enter MODE 1: | Technical Specifications will allow the plant to enter MODE 1: | ||
A. only after the RCIC testing is completed satisfactorily and suppression pool temperature is lowered to | A. only after the RCIC testing is completed satisfactorily and suppression pool temperature is lowered to < 95°F. | ||
< 95°F. B. only after suppression pool average temperature is lowered to | B. only after suppression pool average temperature is lowered to < 95°F but the RCIC testing can still be in progress. | ||
< 95°F but the RCIC testing can still be in progress. | |||
C. with current suppression pool temperature only if RCIC testing is still in progress during the MODE change. | C. with current suppression pool temperature only if RCIC testing is still in progress during the MODE change. | ||
D. with current suppression pool temperature only if the RCIC testing is completed satisfactorily. | D. with current suppression pool temperature only if the RCIC testing is completed satisfactorily. | ||
Answer: | Answer: C Explanation: | ||
LCO 3.6.2.1 Actions A and B require the plant to reduce THERMAL POWER to < 1%, which will require a MODE change from MODE 1 to MODE 2. Thus, 3.0.4.a will not allow MODE 1 entry with the LCO not met. | |||
C conditions meet LCO 3.6.2. LCO 3.5.3 is met because SR 3.5.3.3 is still within the frequency limits of SR 3.0.2. | C conditions meet LCO 3.6.2. LCO 3.5.3 is met because SR 3.5.3.3 is still within the frequency limits of SR 3.0.2. | ||
A is wrong because the SR 3.5.3.3 is still within the frequency limits of SR 3.0.2. | A is wrong because the SR 3.5.3.3 is still within the frequency limits of SR 3.0.2. | ||
B is wrong. With RCIC testing is in progress, the LCO is met at the current suppression pool | B is wrong. With RCIC testing is in progress, the LCO is met at the current suppression pool temperature. | ||
D is wrong because the LCO is only met at the current suppression pool temperature if the testing is still in progress. | |||
Technical | Technical | ||
==References:== | ==References:== | ||
References to be provided to applicants during exam: | References to be provided to applicants during exam: LCOs 3.5.3.1 and 3.6.2.1 Learning Objective: | ||
LCOs 3.5.3.1 and 3.6.2.1 Learning Objective: | Question Source: Bank # | ||
Question Source: | (note changes; attach parent) Modified Bank # | ||
Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.43(b)(2) | ||
Modified Bank # | |||
New X | Examination Outline Cross-Reference Level SRO 295027 High Containment Temperature Tier # 1 Group # 1 Ability to determine and/or interpret the K/A # 295027 - EA2.04 following as they apply to HIGH Rating 3.7 CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY): Containment radiation levels: Mark-III Question 78 A General Emergency has been declared. | ||
Last NRC Exam No | Current conditions are: | ||
Memory/Fundamental Comprehensive/Analysis X | * Reactor water level is -195 and stable | ||
55. | * Approximately 15% fuel damage | ||
Examination Outline Cross | * Containment temperature is 180°F | ||
-Reference Level SRO 295027 High Containment Temperature Ability to determine and/or interpret the following as they apply to HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY): | * All containment radiation monitors are off scale high | ||
-III | * Large fission product inventory in Containment | ||
Current conditions are | * Radiation levels at the Site Boundary are at 25 mRem/hr TEDE | ||
* Projected radiation levels at 8 miles are 2 mRem/hr TEDE What are the Protective Action Recommendations? | |||
-195 | A. No evacuation of surrounding areas is required. | ||
A. No evacuation of surrounding areas is required. | B. Evacuate a 2-mile radius and shelter 5 miles downwind. | ||
B. Evacuate a 2 | C. Evacuate a 2-mile radius and 5 miles downwind; shelter the rest of the 10-mile EPZ; consider the use of Potassium Iodide. | ||
-mile radius and shelter 5 miles downwind. | D. Evacuate a 2-mile radius and 10 miles downwind; shelter the rest of the 10-mile EPZ; consider the use of Potassium Iodide. | ||
C. Evacuate a 2 | Answer: D Explanation: | ||
-mile radius and 5 miles downwind; shelter the rest of the 10 | |||
-mile EPZ; consider the use of Potassium Iodide. | |||
D. Evacuate a 2-mile radius and 10 miles downwind; shelter the rest of the 10 | |||
-mile EPZ; consider the use of Potassium Iodide. | |||
Answer: D | |||
A is wrong because all GE requires PARs to be recommended. | A is wrong because all GE requires PARs to be recommended. | ||
B is wrong because sheltering is required for the entire EPZ and not just downwind C is wrong because the dose projection at 8 miles requires an extended PAR D is correct because the conditions presented require an extended PAR Technical | B is wrong because sheltering is required for the entire EPZ and not just downwind C is wrong because the dose projection at 8 miles requires an extended PAR D is correct because the conditions presented require an extended PAR Technical | ||
Line 1,830: | Line 1,526: | ||
==References:== | ==References:== | ||
10-S-01-1, Activation of the Emergency Plan, Rev 122, Step 6.1.6k References to be provided to applicants during exam: | 10-S-01-1, Activation of the Emergency Plan, Rev 122, Step 6.1.6k References to be provided to applicants during exam: 10-S-01-1, Activation of the Emergency Plan, Rev 122, Step 6.1.6k only Learning Objective: Document learning objective if possible. | ||
10-S-01-1, Activation of the Emergency Plan, Rev 122, Step 6.1.6k only Learning Objective: | |||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b) 55.43(b)(5) | ||
New X | |||
Last NRC Exam No | Examination Outline Cross-Reference Level SRO 295028 High Drywell Temperature Tier # 1 Group # 1 Ability to determine and/or interpret the K/A # 295028 EA2.03 following as they apply to HIGH DRYWELL Rating 3.9 TEMPERATURE : Reactor water level Question 79 The crew has entered EP-2, RPV Control and EP-3, Containment Control. The following conditions exist: | ||
Memory/Fundamental Comprehensive/Analysis X | * Drywell temperature 300°F. | ||
55.41(b) | * RPV pressure 10 psig. | ||
Examination Outline Cross-Reference Level | * Suppression pool temperature is 190°F. | ||
Reactor water level | * Containment pressure 2 psig. | ||
-2, RPV Control and EP | * Suppression pool 23 ft. | ||
-3, Containment Control. The following conditions exist: | * Containment temperature 230°F | ||
Drywell temperature 300°F. | * All RPV level indications are erratic At this point, the SRO should: | ||
RPV pressure 10 psig. | |||
Suppression pool temperature is 190°F. | |||
Containment pressure 2 psig. | |||
Suppression pool 23 ft. | |||
Containment temperature 230°F All RPV level indications are erratic At this point, the SRO should: | |||
A. Enter Emergency Depressurization. | A. Enter Emergency Depressurization. | ||
B. Enter EP-5, RPV Flooding. | B. Enter EP-5, RPV Flooding. | ||
C. Initiate CTMT sprays. | C. Initiate CTMT sprays. | ||
D. Enter Steam Cooling Answer: | D. Enter Steam Cooling Answer: B Explanation: | ||
Conditions are in the | Conditions are in the possible boiling area of the RPVST. This + unstable level indication makes RPV level unknown, which requires transition to EP-5. | ||
-5. A is wrong because emergency depressurizations conditions are not met. | A is wrong because emergency depressurizations conditions are not met. | ||
C is wrong because the given condition are in the | C is wrong because the given condition are in the unsafe to initiate region of the CSIPL D is wrong because this transition is based on level, which is unavailable. | ||
Technical | Technical | ||
Line 1,863: | Line 1,552: | ||
==References:== | ==References:== | ||
EP-2, EP-1, EP-5 | EP-2, EP-1, EP-5 References to be provided to applicants during exam Learning Objective: | ||
Question Source: Bank # | Question Source: Bank # | ||
Modified Bank # | (note changes; attach parent) Modified Bank # | ||
New X | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Last NRC Exam No | |||
Memory/Fundamental Comprehensive/Analysis X | Examination Outline Cross-Reference Level SRO 295030 Low Suppression Pool Water Level Tier # 1 Group # 1 Knowledge of EOP mitigation strategies K/A # 295030 - 2.4.6 Rating 4.7 Question 80 The plant is operating at rated power when an earthquake occurs resulting in an unisolable suppression pool leak. Suppression pool level is 17.5 feet and lowering with all available methods of making up to the suppression pool in service in accordance with EP-3, Containment Control. | ||
55.41(b)(7) 55.43 Examination Outline Cross | EP-4, Auxiliary Building Control is being implemented and sump pumps are maintaining Auxiliary Building Area water levels below their max safe values. | ||
-Reference Level SRO 295030 Low Suppression Pool Water Level | The CRS should enter EP-2, RPV Control A. and order an Emergency Depressurization using 8 ADS SRVs. | ||
Suppression pool level is 17.5 feet and lowering with | B. and order operators to reduce reactor pressure to the reduced band using the bypass valves. | ||
C. and order an Emergency Depressurization using available EP-2, Table 3, Alternate Depressurization Systems. | |||
The CRS should enter EP-2 , RPV Control | D. when suppression pool level drops below 14.5 feet and order an Emergency Depressurization using available EP-2, Table 3, Alternate Depressurization Systems. | ||
Answer: A Explanation: | |||
A. and order an Emergency Depressurization using 8 ADS SRVs. B. and order operators to reduce reactor pressure to the reduced band using the bypass valves. C. and order an Emergency Depressurization using available EP | |||
-2, Table 3, Alternate Depressurization Systems | |||
-2, Table 3, Alternate Depressurization Systems | |||
A is correct because since all methods of suppression pool makeup are in service and level is still dropping you would have to transition to EP-2 and emergency depressurize. | A is correct because since all methods of suppression pool makeup are in service and level is still dropping you would have to transition to EP-2 and emergency depressurize. | ||
B is wrong because you are unable to maintain suppression pool level SPL | B is wrong because you are unable to maintain suppression pool level SPL-9 directs you to ED. | ||
-9 directs you to ED. C is wrong because step ED | C is wrong because step ED-4 in E-2 requires 8 ADS/SRVs to be open to ED. The only allowance to use Table 3 is contained in ED-5. | ||
-4 in E-2 requires 8 ADS/SRVs to be open to ED. The only allowance to use Table 3 is contained in ED | D is wrong because the procedure step has you transition before reaching 14.5 ft. | ||
-5. D is wrong because the procedure step has you transition before reaching 14.5 ft. Understanding that level is dropping and continuing to drop after exhausting all makeup would meet the definition of before in this case. Also use of Table 3 systems is not allowed unless you meet the conditions in ED | Understanding that level is dropping and continuing to drop after exhausting all makeup would meet the definition of before in this case. Also use of Table 3 systems is not allowed unless you meet the conditions in ED-5 Technical | ||
-5 | |||
==References:== | ==References:== | ||
EP-2, RPV Control EP-3, Containment Control 02-S-01-40, EP Technical Bases, Rev 5 References to be provided to applicants during exam: | EP-2, RPV Control EP-3, Containment Control 02-S-01-40, EP Technical Bases, Rev 5 References to be provided to applicants during exam: None. | ||
None. | |||
C. exit EP-2A, flood the CTMT, and enter SAPs. | Learning Objective: Document learning objective if possible. | ||
D. remain in EP | Question Source: Bank # | ||
-2A and inject boron into the RPV with both SLC pumps. | (note changes; attach parent) Modified Bank # | ||
Answer: D | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b) 55.43(b)(5) | ||
-2A, ATWS RPV Control. | |||
Examination Outline Cross-Reference Level SRO 295037 SCRAM Condition Present Tier # 1 and Reactor Power Above APRM Downscale Group # 1 or Unknown K/A # 295037 EA2.07 Rating 4.2 Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN : Containment conditions/isolations Question 81 The plant was at rated power when an inadvertent closure of all MSIVs occurred. The following conditions exist: | |||
* Multiple rods failed to insert. | |||
* Reactor power is 3% and steady. | |||
* Suppression pool temperature is 109°F and rising. | |||
* RPV level is 40. | |||
* The crew is implementing EP-2A, ATWS RPV control. | |||
At this time, the SRO should: | |||
A. exit level and pressure of EP-2A and enter emergency depressurization. | |||
B. exit EP-2A and enter EP-3, Containment Control C. exit EP-2A, flood the CTMT, and enter SAPs. | |||
D. remain in EP-2A and inject boron into the RPV with both SLC pumps. | |||
Answer: D Explanation: | |||
This action is specified in the POWER leg of EP-2A, ATWS RPV Control. | |||
A would only be done if RPV level were low and cannot be restored. | A would only be done if RPV level were low and cannot be restored. | ||
B In this case, EP | B In this case, EP-2A must be continued until the reactor will remain subcritical in all conditions without boron. | ||
-2A must be continued until the reactor will remain subcritical in all conditions without boron. C would only be done if RPV level were low, cannot be restored, and emergency depressurization has been performed. | C would only be done if RPV level were low, cannot be restored, and emergency depressurization has been performed. | ||
D is continuing with the current procedure. | D is continuing with the current procedure. | ||
Technical | Technical | ||
Line 1,925: | Line 1,599: | ||
==References:== | ==References:== | ||
EP-2A | EP-2A References to be provided to applicants during exam: None | ||
Question Source: | Learning Objective: | ||
Bank # | Question Source: Bank # | ||
Modified Bank # | (note changes; attach parent) Modified Bank # | ||
New X | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Last NRC Exam No | |||
Memory/Fundamental Comprehensive/Analysis X | Examination Outline Cross-Reference Level SRO 700000 Generator Voltage and Electric Grid Tier # 1 Disturbances Group # 1 K/A # 700000 - AA2.04 Ability to determine and/or interpret the Rating 3.6 following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: VARs outside capability curve Question 82 The plant is operating at 900MWe with a power factor of 0.9 when alarm GEN HOT SPOT MONITOR comes in. | ||
-Reference Level SRO 700000 Generator Voltage and Electric Grid Disturbances Ability to determine and/or interpret the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: VARs outside capability curve | * RTD 1N41-TE-N156 reads 130°C | ||
RTD 1N41-TE-N156 reads 130°C | * RTD 1N41-TE-N158 reads 135°C What procedure should be entered by the CRS to combat this transient? | ||
What procedure should be entered by the CRS to combat this transient? | A. 03-1-01-2, Power Operations B. 05-1-02-I-4, Loss of AC Power C. 05-1-02-I-2, Turbine and Generator Trips D. 04-1-01-N40-1, Main Generator and Auxiliaries Answer: C Explanation: | ||
A. 03-1-01-2, Power Operations B. 05-1-02-I-4, Loss of AC Power C. 05-1-02-I-2, Turbine and Generator Trips D. 04-1-01-N40-1, Main Generator and | |||
A is wrong because this procedure is not entered during transients. | A is wrong because this procedure is not entered during transients. | ||
B is wrong because temperature is not indicative of grid instability by itself so there is no need to enter the procedure. If there were also voltage and frequency oscillations then this answer would be correct. | B is wrong because temperature is not indicative of grid instability by itself so there is no need to enter the procedure. If there were also voltage and frequency oscillations then this answer would be correct. | ||
C is correct because according to the alarm response procedure whenever temperature is above 120°C than a generator trip is warranted. | C is correct because according to the alarm response procedure whenever temperature is above 120°C than a generator trip is warranted. | ||
D is wrong because this procedure should be entered if | D is wrong because this procedure should be entered if youre going to reduce MVARs to within the precautions listed in the 04-1-01-N40-1. This shouldnt be the conclusion since temperature is elevated also. | ||
Technical | Technical | ||
==References:== | ==References:== | ||
04-1-02-1H13-P680, Alarm Response Instruction References to be provided to applicants during exam: | 04-1-02-1H13-P680, Alarm Response Instruction References to be provided to applicants during exam: Figure 15 Reactive Capability Curve from GFIG-OPS-N4151, Main Generator and Excitation System Figures, Rev. 5. | ||
Figure 15 Reactive Capability Curve from GFIG | Learning Objective: Document learning objective if possible. | ||
-OPS-N4151, Main Generator and Excitation System Figures, Rev. 5. | Question Source: Bank # | ||
Learning Objective: | |||
Question Source: | (note changes; attach parent) Modified Bank # | ||
Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b) 55.43(b)(5) | ||
(note changes; attach parent) | |||
Modified Bank # | Examination Outline Cross-Reference Level SRO 295002 Loss of Main Condenser Vac Tier # 1 Group # 2 Ability to take actions called for in the facility K/A # 295002 2.4.38 emergency plan, including supporting or acting Rating 4.4 as emergency coordinator if required. | ||
New X | Question 83 The plant was increasing power at 38% RTP when the following alarms occurred: | ||
Last NRC Exam No | * HP CNDSR SHELL PRESS HI | ||
Memory/Fundamental Comprehensive/Analysis X | * IP CNDSR SHELL PRESS HI | ||
55.41(b) | * LP CNDSR SHELL PRESS HI | ||
Examination Outline Cross | * EOC/RPT A TRIP | ||
- | * EOC/RPT B TRIP Reactor power is stable at 25% with turbine bypass valves controlling reactor pressure. | ||
Based on these conditions, the CRS should now: | |||
HP CNDSR SHELL PRESS HI IP CNDSR SHELL PRESS HI LP CNDSR SHELL PRESS HI EOC/RPT A TRIP | |||
A. enter EP-2, RPV Control, and if power is reduced to < 4%, declare an Alert. | A. enter EP-2, RPV Control, and if power is reduced to < 4%, declare an Alert. | ||
B. enter EP-2A, ATWS RPV Control, and if power is reduced to < 4%, declare a Site Area Emergency. | B. enter EP-2A, ATWS RPV Control, and if power is reduced to < 4%, declare a Site Area Emergency. | ||
C. enter 05-1-02-I-2, Turbine and Generator Trips. If power is reduced to <4%, no E | C. enter 05-1-02-I-2, Turbine and Generator Trips. If power is reduced to <4%, no E-Plan declaration is necessary. | ||
-Plan declaration is necessary. | D. enter 05-1-02-V-8, Loss of Condenser Vacuum. No E-Plan declaration is necessary. | ||
D. enter 05-1-02-V-8, Loss of Condenser Vacuum. No E | Answer: A Explanation: the reactor should have scrammed because power was > 35.4% RTP when the turbine tripped. This is described by SA3 in the Classification flowcharts. EP-2 should be implemented because a reactor scram is required and all control rods are not at position 00. | ||
-Plan declaration is necessary. | |||
Answer: A | |||
the reactor should have scrammed because power was > 35.4% RTP when the turbine tripped. This is described by SA3 in the Classification flowcharts. EP | |||
-2 should be implemented because a reactor scram is required and all control rods are not at position 00. | |||
Technical | Technical | ||
Line 1,976: | Line 1,643: | ||
EN-OP-115, Conduct of Operations. | EN-OP-115, Conduct of Operations. | ||
References to be provided to applicants during exam: | References to be provided to applicants during exam: Emergency Classification Flowcharts. | ||
Emergency Classification Flowcharts. | |||
Learning Objective: | Learning Objective: | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | |||
New X | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Last NRC Exam No | |||
Memory/Fundamental Comprehensive/Analysis X | |||
55.41(b)(7) 55.43 | |||
B. EP-2, RPV Control C. 04-S-01-M41-1, Containment Cooling System D. 04-S-01-P64-1, Fire Protection Water System Answer: C | Examination Outline Cross-Reference Level SRO 295011 High Containment Temp Tier # 1 Group # 2 Ability to determine and/or interpret the K/A # 295011 - AA2.03 following as they apply to HIGH Rating 3.2 CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY): Containment humidity: Mark-III Question 84 The plant is operating at full power when containment exhaust filter moisture high alarm is received. | ||
* Containment temperature is 90°F. | |||
* Suppression Pool temperature is 90°F | |||
* Radiation levels are normal for the power level | |||
* Containment sump runtimes are normal The CRS should enter: | |||
A. EP-3, Containment Control B. EP-2, RPV Control C. 04-S-01-M41-1, Containment Cooling System D. 04-S-01-P64-1, Fire Protection Water System Answer: C Explanation: | |||
A is wrong because containment temperature and radiation levels would be elevated if a steam leak were occurring. | A is wrong because containment temperature and radiation levels would be elevated if a steam leak were occurring. | ||
B is wrong because radiation levels would be higher and sump runtimes would be increasing to deal with the higher leakage C is correct because the temperature are slightly elevated but not above any EOP entry conditions. | B is wrong because radiation levels would be higher and sump runtimes would be increasing to deal with the higher leakage C is correct because the temperature are slightly elevated but not above any EOP entry conditions. | ||
D is wrong because fire water is relatively cool water it would probably | D is wrong because fire water is relatively cool water it would probably wouldnt add to the amount of vapor inside containment. | ||
Technical | Technical | ||
==References:== | ==References:== | ||
04-1-02-1H13-P842, Alarm Response Instruction, Rev 22 References to be provided to applicants during exam: | 04-1-02-1H13-P842, Alarm Response Instruction, Rev 22 References to be provided to applicants during exam: None. | ||
Learning Objective: Document learning objective if possible. | |||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | |||
New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b) 55.43(b)(5) | |||
Examination Outline Cross-Reference Level SRO 295014 Inadvertent Reactivity Addition Tier # 1 Group # 2 Ability to recognize system parameters that K/A # 295014 2.2.42 are entry-level conditions for Technical Rating 4.6 Specifications. | |||
Question 85 The plant is performing a plant startup following a refueling outage. At 1230, with the plant at 20% power, the reactor operator reports that a review of plant indications show that one hour previously, | |||
* Jet pumps 5 and 6 indicated a step drop in flow. | |||
* Total core flow indicated a step drop. | |||
Examination Outline Cross | * Recirculation loop drive flow indicated a step increase. | ||
-Reference Level | * Reactor power dropped slightly. | ||
Total core flow indicated a step drop. | |||
Recirculation loop drive flow indicated a step increase. | |||
Reactor power dropped slightly. | |||
At this time, the SRO should: (LCO 3.4.3 is provided) | At this time, the SRO should: (LCO 3.4.3 is provided) | ||
A. declare LCO 3.4.3 action condition A entry at 1230. | A. declare LCO 3.4.3 action condition A entry at 1230. | ||
B. declare LCO 3.4.3 action condition A entry at 1130. | B. declare LCO 3.4.3 action condition A entry at 1130. | ||
C. consider LCO 3.4.3 met because SR 3.4.3.1 does not have to be performed at this power level. | C. consider LCO 3.4.3 met because SR 3.4.3.1 does not have to be performed at this power level. | ||
D. consider LCO 3.4.3 met because the established patterns of jet pump flow have not been established following the refueling. | D. consider LCO 3.4.3 met because the established patterns of jet pump flow have not been established following the refueling. | ||
Answer: | Answer: A Explanation: | ||
These are symptoms of a rams head ejection. The definition of OPERABLE is not met. Two jet pumps are not capable of their specified safety related function. | These are symptoms of a rams head ejection. The definition of OPERABLE is not met. Two jet pumps are not capable of their specified safety related function. | ||
B is wrong because action conditions apply from the time of discovery, not the time of occurrence | B is wrong because action conditions apply from the time of discovery, not the time of occurrence. | ||
C is wrong because the SR has to be met, even though it does not have to be performed. | |||
D is wrong because the TS basis says | D is wrong because the TS basis says During the initial weeks of operation under such conditions, while baselining new "established patterns," engineering judgment of the daily surveillance results is used to detect significant abnormalities which could indicate a jet pump failure. | ||
Technical | |||
==References:== | ==References:== | ||
Line 2,035: | Line 1,694: | ||
Learning Objective: | Learning Objective: | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
New X | |||
Last NRC Exam No | Examination Outline Cross-Reference Level SRO 203000 RHR/LPCI: Injection Mode Tier # 2 Group # 1 Knowledge of EOP entry conditions and K/A # 203000 - 2.4.1 immediate action steps Rating 4.8 Question 86 The plant has scrammed from full power due to high drywell pressure. | ||
Memory/Fundamental Comprehensive/Analysis X | 1 control rod is not indicating full in Drywell Pressure is 4 psig Drywell Temperature is 150 F RPV pressure is 700 psig The CRS should A. enter EP-5, RPV Flooding. | ||
55.41(b)(7) 55.43 Examination Outline Cross | B. remain in EP-2, RPV Control. | ||
-Reference Level SRO 203000 RHR/LPCI: Injection Mode Knowledge of EOP entry conditions and | C. enter EP-3, Containment Control. | ||
1 control rod is not indicating full in Drywell Pressure is 4 psig Drywell Temperature is 150 F RPV pressure is 700 psig The CRS should | D. enter EP-2A, ATWS RPV Control. | ||
B. remain in EP | Answer: A Explanation: | ||
-2, RPV Control. | A is correct because all RPV level instruments, with exception of Fuel Zone, are only calibrated to 135oF. Based on this RPV level would not be able to be determined and the second override in EP-2 would need to be enforced. B and C are plausible if the applicant misses the override condition. | ||
C. enter EP-3, Containment Control. | D is wrong because you wouldnt need to enter EP-2A since the reactor would be shutdown under all conditions without boron with one rod either stuck out or not indicating full in. | ||
D. enter EP-2A, ATWS RPV Control. | |||
Answer: A | |||
-2 would need to be enforced. B and C are plausible if the applicant misses the override condition. | |||
D is wrong because you | |||
-2A since the reactor would be shutdown under all conditions without boron with one rod either stuck out or not indicating full in. | |||
Technical | Technical | ||
==References:== | ==References:== | ||
GLP-OPS-B2101, RPV Level Instrumentation, Rev 7 References to be provided to applicants during exam: | GLP-OPS-B2101, RPV Level Instrumentation, Rev 7 References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: State/identify the calibration conditions for each of the following level instruments: (9.0) o Reactor Water Level Narrow Range (9.1) o Reactor Water Level Wide Range (9.2) o Reactor Water Level Shutdown Range (9.3) o Reactor Water Level Upset Range (9.4) o Reactor Water Level Fuel Zone Range (9.5) | ||
Question Source: | Question Source: Bank # | ||
Bank # | |||
(note changes; attach parent) | (note changes; attach parent) Modified Bank # | ||
Modified Bank | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b) 55.43(b)(5) | ||
Last NRC Exam No | Examination Outline Cross-Reference Level SRO 212000 RPS Tier # 2 Group # 1 Ability to (a) predict the impacts of the K/A # 212000 A2.02 following on the REACTOR PROTECTION Rating 3.9 SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: : RPS bus power supply failure Question 87 The plant is at rated power when P680 annunciator HCU TROUBLE is received. When the operator depresses the HCU FAULT pushbutton on the Operators Control Module, the following control rods have blinking red LEDs on the RC&IS display; | ||
Memory/Fundamental Comprehensive/Analysis X | * 04-21 | ||
55.41(b) | * 04-45 | ||
Examination Outline Cross | * 28-05 | ||
-Reference Level | * 28-61 The CRS also notes the Division I MSIV lights on panels 1H13-P622 and P623 are dark. | ||
-P622 and P623 are dark. | |||
The SRO should direct the crew to: | The SRO should direct the crew to: | ||
A. Re-charge the affected | A. Re-charge the affected HCUs in accordance with SOI 04-1-01-C11-1 Control Rod Drive Hydraulic System. | ||
B. Transfer the A RPS bus to the alternate power source per ONEP 05-1-02-III-2, Loss of One or Both RPS buses. | |||
C. Transfer the | C. Transfer the B RPS bus to the alternate power source per ONEP 05-1-02-III-2, Loss of One or Both RPS buses. | ||
D. Dispatch an operator to the affected | D. Dispatch an operator to the affected HCUs inside containment to determine the fault in accordance with ARI 04-1-02-1 H 13-P680-4A2-D4, HCU TROUBLE. | ||
Answer: | Answer: B Explanation: | ||
These are symptoms of loss of RPS bus | These are symptoms of loss of RPS bus A. | ||
Technical | Technical | ||
==References:== | ==References:== | ||
ONEP 05-1-02-III-2, Loss of One or Both RPS buses References to be provided to applicants during exam: None Learning Objective: | ONEP 05-1-02-III-2, Loss of One or Both RPS buses References to be provided to applicants during exam: None | ||
Question Source: | |||
Bank # | Learning Objective: | ||
Modified Bank # | Question Source: Bank # | ||
New X | (note changes; attach parent) Modified Bank # | ||
Last NRC Exam No | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Memory/Fundamental Comprehensive/Analysis X | |||
55.41(b)(7) 55.43 Examination Outline Cross | Examination Outline Cross-Reference Level SRO 215003 IRM Tier # 2 Group # 1 Ability to (a) predict the impacts of the K/A # 215003 - A2.05 following on the INTERMEDIATE RANGE Rating 3.5 MONITOR (IRM) SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Faulty or erratic operation of detectors/system Question 88 A plant startup is in progress with the reactor Mode Switch in STARTUP. | ||
-Reference Level SRO 215003 IRM Ability to (a) predict the impacts of the following on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Faulty or erratic operation of detectors/system | |||
IRMs and APRMs have been verified to have proper overlap, all APRMs are off the downscale light, and all Mode 1 prerequisites have been met. | IRMs and APRMs have been verified to have proper overlap, all APRMs are off the downscale light, and all Mode 1 prerequisites have been met. | ||
Inverter 1Y87 and its alternate power supply fail. | Inverter 1Y87 and its alternate power supply fail. | ||
(1) Regarding TS 3.3.1.1, what is the required action? | |||
(2) When is the Mode Switch allowed to be placed in RUN? | (2) When is the Mode Switch allowed to be placed in RUN? | ||
A. | A. (1) Place the affected IRM channels in trip within 12 hours. | ||
(2) When directed by the Shift Manager in accordance with 03-1-01-1, Cold Shutdown to Generator Carrying Minimum Load. | |||
B. (1) Be in Mode 3 within 12 hours | B. (1) Be in Mode 3 within 12 hours. | ||
(2) Only after either Inverter 1Y87 or its alternate power supply are returned to OPERABLE status. | |||
C. (1) Place the affected IRM channels in trip within 12 hours. | C. (1) Place the affected IRM channels in trip within 12 hours. | ||
(2) Only after either Inverter 1Y87 or its alternate power supply are returned to OPERABLE status. | |||
D. (1) Be in Mode 3 within 12 hours. | D. (1) Be in Mode 3 within 12 hours. | ||
(2) When directed by the Shift Manager in accordance with 03-1-01-1, Cold Shutdown to Generator Carrying Minimum Load. | |||
Answer: A | Answer: A Explanation: | ||
A is correct because this power supply failure would only require entry into Condition A of TS 3.1.1. The action would already be taken so there would be 12 hours to fix the inverter. The second part of the question tests application of TS 3.0.4. Since IRMs are not required in Mode 1 this would meet TS 3.0.4.a B is wrong because TS 3.3.1.1.H requires this only after you fail to meet the time requirements TS 3.3.1.1.A. Even though the action has been taken for A the time allowance still remains at 12 hours before you need to enter condition H. | A is correct because this power supply failure would only require entry into Condition A of TS 3.1.1. The action would already be taken so there would be 12 hours to fix the inverter. The second part of the question tests application of TS 3.0.4. Since IRMs are not required in Mode 1 this would meet TS 3.0.4.a B is wrong because TS 3.3.1.1.H requires this only after you fail to meet the time requirements TS 3.3.1.1.A. Even though the action has been taken for A the time allowance still remains at 12 hours before you need to enter condition H. | ||
C is wrong because you would not need to wait until the inverter is restored. | C is wrong because you would not need to wait until the inverter is restored. | ||
Line 2,110: | Line 1,761: | ||
==References:== | ==References:== | ||
TS 3.3.1.1 References to be provided to applicants during exam: | TS 3.3.1.1 References to be provided to applicants during exam: TS 3.3.1.1. | ||
TS 3.3.1.1. | Learning Objective: Document learning objective if possible. | ||
Learning Objective: | Question Source: Bank # | ||
Question Source: | (note changes; attach parent) Modified Bank # | ||
Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b) 55.43(b)(2) | ||
Modified Bank # | |||
New X | Examination Outline Cross-Reference Level SRO 259002 Reactor Water Level Control Tier # 2 Group # 1 Ability to (a) predict the impacts of the K/A # 259002 A2.04 following on the REACTOR WATER LEVEL Rating 3.1 CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: RFP runout condition: Plant-Specific Question 89 The plant is at rated thermal power when the following alarms are received: | ||
Last NRC Exam No | RFPT A ACT THR BRG WR HI RFPT A TRIP Shortly thereafter, RX LVL 40/32 HI/LO is received. | ||
Memory/Fundamental Comprehensive/Analysis X | |||
55.41(b) | |||
Examination Outline Cross | |||
-Reference Level | |||
-Specific | |||
RFPT A ACT THR BRG WR HI RFPT A TRIP Shortly thereafter, | |||
The plant stabilizes with the following conditions: | The plant stabilizes with the following conditions: | ||
Reactor power | Reactor power - 80% | ||
- 80% RFPT B speed | RFPT B speed - 5900 rpm The procedure that contains the actions to mitigate these conditions is:: | ||
- 5900 rpm | A. ARI 04-1-02-1H13-P680-3A-A3, RX LVL 40/32 HI/LO, to mitigate the low reactor level. | ||
A. ARI 04-1-02-1H13-P680-3A-A3, RX LVL 40 | |||
B. ONEP 05-1-02-III-3, Reduction in Recirculation System Flow Rate, to mitigate the failure of the recirculation runback. | B. ONEP 05-1-02-III-3, Reduction in Recirculation System Flow Rate, to mitigate the failure of the recirculation runback. | ||
C. ONEP 05-1-02-V-7, Feedwater System Malfunctions, to mitigate RFPT B runout. | C. ONEP 05-1-02-V-7, Feedwater System Malfunctions, to mitigate RFPT B runout. | ||
D. ARI 04-1-02-1H13-P680-2A-A2, RFPT A TRIP, to mitigate the low reactor level. | D. ARI 04-1-02-1H13-P680-2A-A2, RFPT A TRIP, to mitigate the low reactor level. | ||
Answer: | Answer: C Explanation: | ||
RFPT B is at runout conditions | RFPT B is at runout conditions and RX level is low. The mitigating actions are to lower reactor power to below 75% and ensure that RFPT speed is reduced to < 5850 rpm. Of these, only Feedwater System Malfunctions contains these instructions. | ||
< 5850 rpm. Of these, only Feedwater System Malfunctions contains these instructions. | |||
Technical | Technical | ||
==References:== | ==References:== | ||
ARI 04-1-02-1H13-P680-3A-A3, RX LVL 40 | ARI 04-1-02-1H13-P680-3A-A3, RX LVL 40/32 HI/LO ONEP 05-1-02-III-3, Reduction in Recirculation System Flow Rate ONEP 05-1-02-V-7, Feedwater System Malfunctions ARI 04-1-02-1H13-P680-2A-A2, RFPT A TRIP | ||
References to be provided to applicants during exam: None Learning Objective: GLP-OPS-N2100 Describe the interrelationship(s) between the Feedwater System and the following: (28.0) Nuclear Boiler System, B21 (28.10) | |||
Concerning SOI 04-1-01-N21-1: (29.0) Identify precautions, limitations, cautions, warnings and notes that apply to a given situation. (29.1) | |||
List/identify the immediate operator actions for the following Off Normal Event Procedures: | |||
(31.0) Feedwater System Malfunctions ONEP, 05-1-02-V-7 (31.2) | |||
Given a copy of the above listed ONEPs and plant conditions, discuss the subsequent actions to be taken with regard to the Feedwater System. (32.0) | |||
Question Source: Bank # | |||
(note changes; attach parent) Modified Bank # | |||
New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | |||
Examination Outline Cross-Reference Level SRO 261000 SGTS Tier # 2 Group # 1 Ability to (a) predict the impacts of the K/A # 261000 - A2.07 following on the STANDBY GAS Rating 2.7 TREATMENT SYSTEM; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations: A.C. electrical failure Question 90 A seismic event has resulted in the following: | |||
* Small break LOCA in the drywell | |||
* Auto initiation of RCIC and HPCS | |||
* Loss of offsite power with all diesels supplying power to their respective buses | |||
* EP-2 has been entered Drywell pressure is 2.0 psig and stable Drywell temperature is 120°F and stable Reactor water level is stable in the normal band Fuel handling exhaust radiation at 4.2 mr/hr and stable Suppression pool temperature at 90°F and stable RCIC equipment area temperature at 150°F and stable At this point operators are required to transition to A. EP-3, Containment Control, and operate all available suppression pool cooling with RHR pumps not required for adequate core cooling. | |||
B. EP-3, Containment Control, and defeat drywell cooling isolation interlocks using Attachment 10 of EP-1. | |||
C. EP-4, Auxiliary Building Control, and verify standby gas treatment system is in service and all automatic isolations are complete. | |||
D. EP-4, Auxiliary Building Control, and operate RCIC room coolers to lower temperature in the RCIC room. | |||
Answer: C Explanation: | |||
A is wrong because suppression pool temperature is higher than normal but does not exceed the 95°F in EP-3. | |||
B is wrong because drywell temperature has not exceeded the temperature in EP-3. | |||
-Reference Level SRO 261000 SGTS Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations: A.C. electrical failure | C is correct because the setpoint has been exceeded in EP-4 D is wrong because the RCIC room temperature has not exceeded the temperature in EP-5 | ||
Small break LOCA in the drywell Auto initiation of RCIC and HPCS Loss of offsite power with all diesels supplying power to their respective buses EP-2 has been entered | |||
Technical | |||
==References:== | ==References:== | ||
EP-4, Auxiliary Building Control References to be provided to applicants during exam: | EP-4, Auxiliary Building Control References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: Document learning objective if possible. | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b) 55.43(b)(5) | ||
New X | |||
Last NRC Exam No | Examination Outline Cross-Reference Level SRO 239001 Main and Reheat Steam Tier # 2 Group # 2 Knowledge of low power/shutdown K/A # 239001 2.4.9 implications in accident (e.g., loss of coolant Rating 4.2 accident or loss of residual heat removal) mitigation strategies. | ||
Memory/Fundamental Comprehensive/Analysis X | Question 91 After being at rated power for 11 continuous months, the crew is performing a cooldown per 03-1-01-3B, Plant Shutdown to comply with LCO 3.5.1, ECCS - Operating. | ||
55.41(b) | * Required action condition D was entered 3 hours ago due to failure of the B RHR motor. | ||
Examination Outline Cross | * Reactor water cleanup is isolated and not available. | ||
-Reference Level | * Shutdown cooling has been placed in service using A RHR and is supplementing the cooldown from operating the turbine bypass valves. | ||
* Reactor pressure is 110 psig. | |||
- Operating. | |||
Required action condition D was entered 3 hours ago due to failure of the B RHR motor. | |||
Reactor water cleanup is isolated and not available. | |||
Shutdown cooling has been placed in service using A RHR and is supplementing the cooldown from operating the turbine bypass valves | |||
Then, the A RHR pump trips and cannot be restarted. | Then, the A RHR pump trips and cannot be restarted. | ||
If no repairs are made, it will eventually be necessary to declare a(n) ___________ due to | If no repairs are made, it will eventually be necessary to declare a(n) ___________ due to (1) (2) | ||
A. NOUE Inability to reach operating mode within TS limits B. NOUE. Unplanned loss of decay heat removal capability with irradiated fuel in the RPV. | |||
C. Alert. Inability to reach operating mode within TS limits D. Alert Unplanned loss of decay heat removal capability with irradiated fuel in the RPV. | |||
Inability to reach operating mode within TS limits | Answer: A Explanation: ONEP 05-1-02-III-1, Inadequate Decay Heat Removal says (section 3.4) to place redundant loop in shutdown cooling (not available) or place ADHRS in service (cannot be done above 200°F). It will not be possible to place the plant in MODE 4 in this condition. Decay heat removal capability has not been lost because the turbine bypass system is still available. | ||
Answer: A | |||
ONEP 05-1-02-III-1, Inadequate Decay Heat Removal says (section 3.4) to place redundant loop in shutdown cooling (not available) or place ADHRS in service (cannot be done above 200°F). It will not be possible to place the plant in MODE 4 in this condition. Decay heat removal capability has not been lost because the turbine bypass system is still available. | |||
Technical | Technical | ||
Line 2,200: | Line 1,833: | ||
ONEP 05-1-02-III-1 Emergency Classification Flowcharts | ONEP 05-1-02-III-1 Emergency Classification Flowcharts | ||
References to be provided to applicants during exam: | References to be provided to applicants during exam: Emergency Classification Flowcharts and TS 3.5.1. | ||
Emergency Classification Flowcharts and TS | Learning Objective: | ||
Question Source: Bank # | |||
(note changes; attach parent) Modified Bank # | |||
New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | |||
Examination Outline Cross-Reference Level SRO 241000 Reactor/Turbine Pressure Tier # 2 Regulator Group # 2 K/A # 241000 - 2.1.25 Ability to interpret reference materials, Rating 4.2 such as graphs, curves, tables, etc. | |||
Question 92 The plant is operating at full power when alarm TURB IPC CAB FAIL is received. Turbine control and bypass valves are operating normally for this power level. I&C personnel are sent to investigate and determine the internal power supply for IPC cabinet 1H13-P825-JC03 needs to be replaced. | |||
Per EN-WM-100, Work Request (WR) Generation, Screening and Classification, what priority should be assigned to the work request A. Priority 1 B. Priority 2 C. Priority 3 D. Priority 4 Answer: B Explanation: | |||
Since the power supply has failed it falls into corrective maintenance space. Since the component presents a risk to generation but the system is still operable, because turbine and bypass valves controls are less redundant, this work request should be screened as a priority | |||
: 2. All other answers are plausible depending on how the applicant judges the risk of additional failures. | |||
Technical | |||
-Reference Level SRO 241000 Reactor/Turbine Pressure | |||
Tier # 2 Group # 2 K/A # 241000 - 2.1.25 Rating 4.2 | |||
-P825-JC03 needs to be replaced. | |||
==References:== | |||
Per EN-WM-100, Work Request (WR) Generation, Screening and Classification, Rev 9 References to be provided to applicants during exam: Per EN-WM-100, Work Request (WR) Generation, Screening and Classification, p. 1-13 and Attachment 9.1 Learning Objective: Document learning objective if possible. | |||
Question Source: Bank # | |||
(note changes; attach parent) Modified Bank # | |||
New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X | |||
10CFR Part 55 Content: 55.41(b) 55.43(b)(5) | |||
Examination Outline Cross-Reference Level SRO 259001 Reactor Feedwater Tier # 2 Group # 2 Ability to (a) predict the impacts of the K/A # 259001 A2.04 following on the REACTOR FEEDWATER Rating 3.4 SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of extraction steam Question 93 The plant is at rated power when P680 alarm FW HTR 6B LVL HI is received. Motor-operated valve 1N36-F011B, FW HTR 6B EXT STM ISOL, is stroking closed. | |||
Examination Outline Cross | |||
-Reference Level | |||
-operated valve 1N36 | |||
-F011B, FW HTR 6B EXT STM ISOL, is stroking closed. | |||
The FIRST thing the SRO should direct the crew to do is: | The FIRST thing the SRO should direct the crew to do is: | ||
A. re-open 1N36-F011B in accordance with ARI 04 02-1H13-P680-2A-A10, FW HTR 6B LVL HI. B. initiate a reactor scram and enter ONEP 05-1-02-1-1, Reactor Scram. | A. re-open 1N36-F011B in accordance with ARI 04-1-02-1H13-P680-2A-A10, FW HTR 6B LVL HI. | ||
C. reduce core flow at the maximum rate in accordance with ONEP 05 02-V-5, Loss of Feedwater Heating | B. initiate a reactor scram and enter ONEP 05-1-02-1-1, Reactor Scram. | ||
C. reduce core flow at the maximum rate in accordance with ONEP 05-1-02-V-5, Loss of Feedwater Heating. | |||
Answer: | D. reduce core flow using the slow detent of reactor recirculation flow control in accordance with ONEP 05-1-02-V-5, Loss of Feedwater Heating. | ||
Answer: C Explanation: | |||
FW HTR 6B is a high pressure heater, so recirculation flow should be reduced rapidly per the note prior to step 2 of ONOP Loss of Feedwater Heating. | FW HTR 6B is a high pressure heater, so recirculation flow should be reduced rapidly per the note prior to step 2 of ONOP Loss of Feedwater Heating. | ||
The note also says that the action should be taken when the isolation valve begins to close. | The note also says that the action should be taken when the isolation valve begins to close. | ||
Line 2,253: | Line 1,870: | ||
==References:== | ==References:== | ||
ONEP 05-1-02-V-5, Loss of Feedwater Heating References to be provided to applicants during exam: | ONEP 05-1-02-V-5, Loss of Feedwater Heating References to be provided to applicants during exam: | ||
Learning Objective: | Learning Objective: | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
New X | |||
Last NRC Exam No | Examination Outline Cross-Reference Level SRO Conduct of Operations Tier # 3 Group # | ||
Memory/Fundamental Comprehensive/Analysis X | Knowledge of refueling administrative K/A # 2.1.40 requirements Rating 3.9 Question 94 According to procedure 03-1-01-5, Refueling, Loads in excess of _______ pounds shall be prohibited from travel over fuel assemblies in the Spent Fuel OR Upper Containment Fuel Storage Pool Racks. | ||
55.41(b)(7) 55.43 Examination Outline Cross | A. 975 B. 1060 C. 1140 D. 1220 Answer: C Explanation: | ||
-Reference Level SRO Conduct of Operations | Precaution and limitation 2.8 of 03-1-01-5, Refueling, Rev 128 defines the maximum load allowed over fuel assemblies in the spent fuel pool. | ||
2.8 Loads in excess of 1140 pounds Shall be prohibited from travel over Fuel assemblies in the Spent Fuel OR Upper Containment Fuel Storage Pool Racks. | |||
Precaution and limitation 2.8 of 03 01-5, Refueling, Rev 128 defines the maximum load allowed over fuel assemblies in the spent fuel pool. | Technical | ||
==References:== | ==References:== | ||
03-1-01-5, Refueling, Rev 128 References to be provided to applicants during exam: | 03-1-01-5, Refueling, Rev 128 References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: Document learning objective if possible. | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b) 55.43(b)(7) | ||
New X | |||
Last NRC Exam No | |||
Memory/Fundamental X | |||
55.41(b) | |||
alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation. | Examination Outline Cross-Reference Level SRO Conduct of Operations Tier # 3 Group # | ||
Knowledge of RO duties in the control room K/A # 2.1.44 during fuel handling such as responding to Rating 3.8 alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation. | |||
Question 95 The plant is in MODE 5, applying the provisions of LCO 3.10.5, Single CRD Removal - | |||
Refueling, to remove one CRD mechanism in a cell containing three fuel assemblies. CRD mechanism removal is in progress. | |||
Then, alarm CONT ROD WITHDRAWAL BLOCK is received. The RO determines that the cause of the alarm is refueling platform near or over core and grapple loaded. | Then, alarm CONT ROD WITHDRAWAL BLOCK is received. The RO determines that the cause of the alarm is refueling platform near or over core and grapple loaded. | ||
Technical specifications require the operators to immediately: | Technical specifications require the operators to immediately: | ||
Line 2,292: | Line 1,902: | ||
: 3. direct the refueling platform operator to stop core alterations. | : 3. direct the refueling platform operator to stop core alterations. | ||
A. 1 only B. 1 and 2 only C. 2 and 3 only D. 1, 2, and 3. | A. 1 only B. 1 and 2 only C. 2 and 3 only D. 1, 2, and 3. | ||
Answer: | Answer: D Explanation: | ||
In this mode, the alarm signifies that the LCO was not met when the CRD removal began. The control rod withdrawal block was not inserted. 1, 2, and 3 are all immediate actions that are required per TS 3.10.5. While a rod block is now present, action 3 will make the rod block clear, so it will be necessary to insert one. | In this mode, the alarm signifies that the LCO was not met when the CRD removal began. | ||
The control rod withdrawal block was not inserted. 1, 2, and 3 are all immediate actions that are required per TS 3.10.5. While a rod block is now present, action 3 will make the rod block clear, so it will be necessary to insert one. | |||
Technical | Technical | ||
Line 2,299: | Line 1,910: | ||
ARI 04-1-02-1H13-P680-4A2-C5, CONT ROD WITHDRAWAL BLOCK. | ARI 04-1-02-1H13-P680-4A2-C5, CONT ROD WITHDRAWAL BLOCK. | ||
LCO 3.10.5 References to be provided to applicants during exam: None Learning Objective: | LCO 3.10.5 References to be provided to applicants during exam: None | ||
Question Source: | |||
Bank # | Learning Objective: | ||
Modified Bank # | Question Source: Bank # | ||
New X | (note changes; attach parent) Modified Bank # | ||
Last NRC Exam No | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
Memory/Fundamental Comprehensive/Analysis X | |||
55.41(b)(7) 55.43 Examination Outline Cross | Examination Outline Cross-Reference Level SRO Equipment Control Tier # 3 Group # | ||
-Reference Level SRO Equipment | Knowledge of the process for making K/A # 2.2.5 changes to procedures Rating 3.6 Question 96 Which of the following situations would be appropriate for issuing a Temporary Change Notice: | ||
: 2. A change is required to implement a surveillance that is scheduled to be performed in 4 weeks. 3. A directive change is required to support an operability review. | : 1. Equipment is out of service and a change is required to complete the work and return the equipment to service. | ||
A. 1 and 2 ONLY B. 1 and 3 ONLY | : 2. A change is required to implement a surveillance that is scheduled to be performed in 4 weeks. | ||
From 01-S-02-3, | : 3. A directive change is required to support an operability review. | ||
A. 1 and 2 ONLY B. 1 and 3 ONLY C. 2 and 3 ONLY D. 1, 2, and 3 Answer: B Explanation: | |||
From 01-S-02-3, Authors Guide, Rev 121, Note 6.4.1, directive change is required to implement a surveillance and the work is scheduled in the near future (i.e., two weeks). | |||
Since the time frame is 4 weeks in (2) then it should be issued as a direct revision instead of a TCN. This makes any answer containing (2) incorrect. | Since the time frame is 4 weeks in (2) then it should be issued as a direct revision instead of a TCN. This makes any answer containing (2) incorrect. | ||
Technical | Technical | ||
Line 2,316: | Line 1,929: | ||
==References:== | ==References:== | ||
01-S-02-3, | 01-S-02-3, Authors Guide, Rev 121, Note 6.4.1 References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: Document learning objective if possible. | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis | ||
New X | |||
Last NRC Exam No | |||
Memory/Fundamental X | |||
10CFR Part 55 Content: | 10CFR Part 55 Content: 55.41(b) 55.43 | ||
55.41(b) | |||
-Reference Level | Examination Outline Cross-Reference Level SRO Equipment Control Tier # 3 Group # | ||
Knowledge of the process for controlling K/A # 2.2.11 temporary design changes. Rating 3.3 Question 97 When an approved procedure installs electrical jumpers for testing purposes, Temporary Modification Tags should be applied whenever the jumpers: | |||
A. must be independently verified. | A. must be independently verified. | ||
B. are out of line of | B. are out of line of sight. | ||
C. are NOT documented in the Asset Suite (AS). | |||
D. will be in place for greater than one hour. | D. will be in place for greater than one hour. | ||
Answer: | Answer: B Explanation: | ||
P&L 7 of EN | P&L 7 of EN-DC-136, Temporary Modifications, contains this requirement. | ||
-DC-136, Temporary Modifications, contains this requirement. | |||
A is wrong because this process (testing) is excluded from T-MOD requirements when restoration is documented and verified through independent verification and the jumper remains in line of sight. | A is wrong because this process (testing) is excluded from T-MOD requirements when restoration is documented and verified through independent verification and the jumper remains in line of sight. | ||
C is wrong because testing jumpers are not documented in the Asset Suite. | C is wrong because testing jumpers are not documented in the Asset Suite. | ||
D is wrong because there are no time requirements. The jumpers do not need a T | D is wrong because there are no time requirements. The jumpers do not need a T-mod tag unless they are left unattended. | ||
-mod tag unless they are left unattended. | |||
Technical | Technical | ||
Line 2,346: | Line 1,954: | ||
EN-DC-136, Temporary Modifications References to be provided to applicants during exam: | EN-DC-136, Temporary Modifications References to be provided to applicants during exam: | ||
Learning Objective: | Learning Objective: | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis | ||
New X | |||
Last NRC Exam No | |||
Memory/Fundamental X | |||
10CFR Part 55 Content: | 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
55.41(b)(7) 55.43 | |||
B. (1) EN-RP-121, Radioactive Material Control (2) 01-S-08-11, Radioactive Discharge | Examination Outline Cross-Reference Level SRO Radiation Control Tier # 3 Group # | ||
A is correct because 01-S-08-11, control liquid and gaseous releases. Step 6.2.1 of 01 | Ability to control radiation releases. K/A # 2.3.11 Rating 4.3 Question 98 (1) What is the governing procedure to process liquid radioactive waste discharges? | ||
-S-08-11 refers to EN | (2) What is the governing procedure to process solid radioactive waste discharges? | ||
-RP-121 for processing solid waste. | A. (1) 01-S-08-11, Radioactive Discharge Controls (2) EN-RP-121, Radioactive Material Control B. (1) EN-RP-121, Radioactive Material Control (2) 01-S-08-11, Radioactive Discharge Controls C. (1) 01-S-08-11, Radioactive Discharge Controls (2) 01-S-08-11, Radioactive Discharge Controls D. (1) EN-RP-121, Radioactive Material Control (2) EN-RP-121, Radioactive Material Control Answer: A Explanation: | ||
B is wrong of A. C is wrong of A. | A is correct because 01-S-08-11, control liquid and gaseous releases. Step 6.2.1 of 01-S-08-11 refers to EN-RP-121 for processing solid waste. | ||
B is wrong of A. | |||
C is wrong of A. | |||
D is wrong of A. | D is wrong of A. | ||
Technical | Technical | ||
Line 2,370: | Line 1,972: | ||
==References:== | ==References:== | ||
01-S-08-11, Radioactive Discharge Controls EN-RP-121, Radioactive Material Control | 01-S-08-11, Radioactive Discharge Controls EN-RP-121, Radioactive Material Control References to be provided to applicants during exam: None. | ||
None. Learning Objective: | Learning Objective: Document learning objective if possible. | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis | ||
New X | |||
Last NRC Exam No | |||
Memory/Fundamental X | |||
10CFR Part 55 Content: | 10CFR Part 55 Content: 55.41(b)(13) 55.43(b)(5) | ||
55.41(b)(13) | |||
Examination Outline Cross | Examination Outline Cross-Reference Level SRO Emergency Procedures / Plan Tier # 3 Group # | ||
-Reference Level | Ability to recognize abnormal indications for K/A # 2.4.4 system operating parameters that are entry- Rating 4.7 level conditions for emergency and abnormal operating procedures. | ||
-level conditions for emergency and abnormal operating procedures. | Question 99 The plant was at rated power when all four channels of MSL PIPE TNL TEMP HI alarms are received: | ||
Concurrently, | |||
A reactor scram occurs with all control rods fully inserted. | * A main steam line isolation occurs. | ||
Shortly thereafter, alarm RX LVL 3 (+10") | * A reactor scram occurs with all control rods fully inserted. | ||
LO is | Shortly thereafter, alarm RX LVL 3 (+10") LO is received. | ||
* SP temperature is 89°F and rising. | |||
* SP Level is 18.5 ft. and rising. | |||
Then, the CRS should enter: | Then, the CRS should enter: | ||
: 1. EP-2, RPV Control | : 1. EP-2, RPV Control | ||
: 2. EP-3, Containment Control | : 2. EP-3, Containment Control | ||
: 3. EP-4, Auxiliary Building Control A. 1 only B. 1 and 2 only | : 3. EP-4, Auxiliary Building Control A. 1 only B. 1 and 2 only C. 1 and 3 only D. 1, 2, and 3 Answer: C Explanation: | ||
At least one entry conditions is met for EP-2 (RV level < 11.4 In). | |||
C. 1 and 3 only D. 1, 2, and 3 Answer: C | At least one entry condition is met for EP-4 (MSL Pipe Tunnel Temp > 185°F) | ||
At least one entry conditions is met for EP | No entry conditions for EP-3 are met. | ||
-2 (RV level < 11.4 In). | |||
At least one entry condition is met for EP | |||
-4 (MSL Pipe Tunnel Temp > 185°F) | |||
No entry conditions for EP | |||
-3 are met. | |||
Technical | Technical | ||
Line 2,408: | Line 2,004: | ||
References to be provided to applicants during exam: | References to be provided to applicants during exam: | ||
Learning Objective: | Learning Objective: | ||
Question Source: | Question Source: Bank # | ||
Bank # | (note changes; attach parent) Modified Bank # | ||
Modified Bank # | New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43 | ||
New X | |||
Last NRC Exam No | Examination Outline Cross-Reference Level SRO Emergency Procedures/Plan Tier # 3 Group # | ||
Memory/Fundamental Comprehensive/Analysis X | Knowledge of fire protection procedures K/A # 2.4.46 Rating 4.2 Question 100 A fire is reported to the control room at the Independent Spent Fuel Storage Facility (ISFSI) at 12:00 pm. How many fire brigade members are required to be sent? | ||
55.41(b)(7) 55.43 Examination Outline Cross | |||
-Reference Level SRO Emergency Procedures/Plan Knowledge of fire protection procedures | |||
The fire brigade leader reports back at 12:25 pm that the fire is not extinguished. Which Emergency Action Level has been exceeded? | The fire brigade leader reports back at 12:25 pm that the fire is not extinguished. Which Emergency Action Level has been exceeded? | ||
A. 3 Unusual Event B. 3 Alert C. 5 Unusual Event D. 5 Alert Answer: C Explanation: | |||
A is wrong because the 5 man team is responsible for responding to the ISFSI. A UE is required by the emergency plan B is wrong because a 5 man team is required and an Alert would not be C is correct because a 5 man team is required by procedure and an unusual event would be required because the ISFSI is not safety related and there has not been a report of an damage D is wrong because the classification is incorrect Technical | |||
==References:== | |||
10-S-03-2, Response to Fires, Rev 25. Step 6.2.3.f 10-S-01-1, Activation of the Emergency Plan, Rev. 122 References to be provided to applicants during exam: None. | |||
Learning Objective: Document learning objective if possible. | |||
Question Source: Bank # | |||
(note changes; attach parent) Modified Bank # | |||
New X | |||
Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b) 55.43(b)(5)}} | |||
Last NRC Exam No | |||
Memory/Fundamental X | |||
55.41(b) |
Latest revision as of 17:48, 5 February 2020
ML14310A408 | |
Person / Time | |
---|---|
Site: | Grand Gulf ![]() |
Issue date: | 10/24/2014 |
From: | Vincent Gaddy Operations Branch IV |
To: | Entergy Operations |
laura hurley | |
References | |
Download: ML14310A408 (199) | |
Text
Examination Outline Cross-Reference Level RO 295001 Partial or Complete Loss of Forced Tier # 1 Core Flow Circulation Group # 1 K/A # 295001 AK1.04 Knowledge of the operational implications Rating 2.5 of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION :
Limiting cycle oscillation: Plant Specific Question 1 The plant is operating on the 100 percent rod line at rated thermal power. Operation is in accordance with Backup Stability Protections due to the inoperability of OPRMs. Then:
- Both reactor recirc pumps unexpectedly downshift to slow speed
- Reactor power stabilizes at 45 percent of rated thermal power With these conditions, in order to limit thermal hydraulic induced power oscillations ONEP 05-01-02-III-3, Reduction in Recirculation Flow Rate, directs the crew to immediately:
A. begin inserting control rods.
B. place the reactor mode switch in SHUTDOWN.
C. trip the recirculation pump with the lowest flow.
D. maximize reactor recirc pump flows .
Answer: B Explanation:
Since the core is operating in the scram region of the power-flow curve with OPRMS inoperable, step 4.1 requires an immediate scram.
A would be correct if in the controlled entry region of the power-flow curve.
C would be correct for trip of a single Recirc pump.
D would be correct if the pumps are manually downshifted Technical
References:
05-01-02-III-3, , Reduction in Recirculation Flow Rate References to be provided to applicants during exam: Figure 1 from 05-01-02-III-3, Power-flow map.
Learning Objective:
Question Source: Bank #
(note changes; attach parent) Modified Bank #
New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 295003 - Partial or complete loss of AC Tier # 1 Group # 1 Knowledge of abnormal condition K/A # 295003 - 2.4.11 procedures. Rating 4.0 Question 2 According to 05-1-02-I-4, Loss of AC Power, which of the following 2 buses would constitute a station blackout if power was lost?
A. 15AA and 16AB B. 15AA and 17AC C. 16AB and 13AD D. 16AB and 14AE Answer: A Explanation:
A is correct because of the note 05-1-02-I-4, Loss of AC Power, Rev 45.
B is wrong because both buses are ESF buses but 17AC is not the Div 3 bus.
C is wrong because 13AD is not an ESF but does carry a recirc pump MG set which could be plausible if an applicant doesnt understand what safety related means.
D is wrong because 14AE is not an ESF but does carry a recirc pump MG set which could be plausible if an applicant doesnt understand what safety related means.
Technical
References:
05-1-02-I-4, Loss of AC Power, Revision 45, Section 5.0 Automatic Actions References to be provided to applicants during exam: None.
Learning Objective: Document learning objective if possible.
Question Source: Bank #
(note changes; attach parent) Modified Bank #
New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis
10CFR Part 55 Content: 55.41(b)(10)
Examination Outline Cross-Reference Level RO 295004 Partial or Total Loss of DC Power Tier # 1 Group # 1 Ability to recognize abnormal indications K/A # 295004 2.4.4 for system operating parameters that are Rating 4.5 entry-level conditions for emergency and abnormal operating procedures.
Question 3 The plant is operating at rated thermal power when an unplanned automatic actuation of the following ESF systems occurs:
Control Room Standby Fresh Air A initiation Combustible Gas Control System A initiation Containment/Drywell Division I isolation Auxiliary Building Division I isolation Standby Service Water System A initiation Standby Gas Treatment System A initiation Auxiliary Building Division I Ventilation isolation At this time, the crew should:
A. restore AC power and enter 05-1-02-V-11 Loss of Plant Service Water.
B. restore DC power and enter 05-1-02-V-11 Loss of Plant Service Water.
C. restore AC power and enter 05-1-02-III-5, Automatic Isolations.
D. restore DC power and enter 05-1-02-III-5, Automatic Isolations.
Answer: D Explanation:
These actuations could not result from a loss of AC, only DC. The affected systems can only be restored by the actions of ONEP 05-1-02-III-5, which resets the affected signals. Plant service water is affected, but 05-1-02-V-11 contains no instructions that will restore service water in this condition.
This event happened at GGNS as documented in LER 95-005-00 Technical
References:
Grand Gulf Nuclear Station LER 95-005-00.
05-1-02-III-5, Automatic Isolations References to be provided to applicants during exam: None
Learning Objective: GLP-OPS-L1100 Discuss the interrelationships of the following systems with the Plant DC System. (10) ESF Power Distribution System- R21 (10.2)
GLP-OPS-R2100 Describe the interrelationship between the following systems and the ESF Distribution System: (25) 125 Volt DC System - L11 (25.1)
Question Source: New Bank #
(note changes; attach parent) Modified Bank #
New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 295005 Main Turbine Generator Trip Tier # 1 Group # 1 Knowledge of the interrelations between K/A # 295005 - AK2.02 MAIN TURBINE GENERATOR TRIP and Rating 3.8 the following: RPS Question 04 Which of the following RPS signals also generates a turbine trip signal?
A. Reactor high water level B. Reactor low water level C. High reactor pressure D. Main steam isolation valve closure Answer: A Explanation:
A is correct because this signal generates a turbine trip to protect the turbine from carryover.
B is wrong because this signal does not directly generate a turbine trip.
C is wrong because this signal does not directly generate a turbine trip.
D is wrong because this signal does not directly generate a turbine trip.
Technical
References:
05-1-02-I-2, Turbine and Generator Trips, Rev 34 References to be provided to applicants during exam: None.
Learning Objective: Document learning objective if possible.
Question Source: Bank #
(note changes; attach parent) Modified Bank #
New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7)
Examination Outline Cross-Reference Level RO 295016 Control Room Abandonment Tier # 1 Group # 1 Knowledge of surveillance procedures K/A # 295016 2.2.12 Rating 3.7 Question 5 All automatic starts of 1P41-C001A, SSW A Pump will at least be momentarily disabled by performance of surveillance procedure:
A. 06-OP-1P41-Q-004, SSW Loop A Valve and Pump Operability Test.
B. 06-OP-1P41-M-004, SSW Loop A Operability Check.
C. 06-OP-1C61-M-001, Remote Shutdown Panel and Accident Monitoring Instrument Channel Check.
D. 06-OP-1C61-R-0002, Remote Shutdown Panel Control Check.
Answer: D - We will have to check at GG but I am thinking there may be parts of A that will render the SSW pump inoperable. Leave it as is and we will check on it later.
Explanation:
Of these, only the Remote Shutdown Panel Control Check disables auto starts.
A, B, and C are all surveillance procedures which operate or monitor SSW components, but they do not disable any pump features.
Technical
References:
Surveillance Procedure 06-OP-1C61-R-002, Remote Shutdown Panel Control Check, Table 1, p. 11.
References to be provided to applicants during exam: None GLP-OPS-C6100 Learning Objective: GLP-OPS-C6100 Describe the reason for disabling the Control Room controls by activating the Lockout Transfer Relays on H22-P152 and LOCAL/REMOTE switches on Alternate Shutdown Panels during a fire emergency in the Main Control Room.
(11)
Question Source: Bank #
(note changes; attach parent) Modified Bank #
New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 295018 Partial or Total Loss of CCW Tier # 1 Group # 1 Knowledge of the reasons for the following K/A # 295018 - AK3.03 responses as they apply to PARTIAL OR Rating 3.1 COMPLETE LOSS OF COMPONENT COOLING WATER: Securing individual components (prevent equipment damage)
Question 06 The plant has been operating full power for 5 months following a refueling outage. One of the 2 running CCW pumps has tripped and the standby pump will not start. What does ONEP 05-1-02-V-1, Loss of Component Cooling Water, direct you to do? What is the reason this action is taken?
A. Scram the reactor; one CCW pump cannot maintain RRC motor temperatures within specification so manual action is required B. Isolate CCW to FPCCU heat exchangers; maximize cooling to RRC pumps C. Isolate CCW to RWCU heat exchangers; maximize cooling to RRC pumps D. Reduce core flow to 70 mlbm/hr; reduce the heat load on RRC pumps Answer: B Explanation:
A is wrong because this would be the appropriate response if this was a complete loss of CCW. Plausible because if the applicant believes this constitutes a complete instead of a partial loss of CCW this is the correct answer.
B is correct because this is specified in step 3.2.2 of the procedure and the note before step 3.2.2 gives the reason for the step. Also, step 3.2.1 was already accomplished because an attempt to start the standby pump was already attempted.
C is wrong because this is required by step 3.2.3. This is plausible if the applicant believes there has not been enough time since the refueling outage and they are not allowed to isolate CCW to FPCCU so the next step is to isolate CCW to RWCU D is wrong because this is specified in step 3.2.4 as a conditional step if RRC temperatures cannot be maintained within specification Technical
References:
ONEP 05-1-02-V-1, Loss of Component Cooling Water, Rev. 24, p. 3-4 References to be provided to applicants during exam: None.
Learning Objective: N/A
Question Source: Bank #
(note changes; attach parent) Modified Bank #
New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(10)
Examination Outline Cross-Reference Level RO 295019 Partial or Total Loss of Inst. Air Tier # 1 Group # 1 Ability to obtain and interpret station K/A # 295019 2.2.41 electrical and mechanical drawings. Rating 3.5 Question 7 When TBCW is not available to plant air compressors, aligning SSW to supply cooling water to plant air compressors requires opening valve:
A. P41-F155A B. P41-F159A C. P41-F160B D. P41-F042 Answer: A Explanation:
B is wrong because this valve supplies the A drywell purge compressor C is wrong because this is the return from the B drywell purge compressor D is wrong because this is the supply to DRWL CLRS/CCW HXS The valve descriptions are omitted because the purpose of this question is to require use of the P & ID. Giving the valve descriptions makes use of the reference unnecessary.
Technical
References:
Step 3.3 of ONEP 05-1-02-V-9, Loss of Instrument Air Standby Service Water System P & I Diagrams M-1061D (G-2)
References to be provided to applicants during exam:
Standby Service Water System P & I Diagrams M-1061A, B, C, and D Learning Objective:
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X
10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 295021 Loss of Shutdown Cooling Tier # 1 Group # 1 Ability to determine and/or interpret the K/A # 295021 - AA2.01 following as they apply to LOSS OF Rating 3.5 SHUTDOWN COOLING: Reactor water heatup/cooldown rate Question 08 The plant is shut down for 5 days for RF19 with RHR B in service and DIV 1 ESF bus out of service for maintenance. Initial conditions are:
- RPV temperature is 110°F
- Fuel shuffling has not commenced
- Reactor vessel is flooded up to below the flange What is the current maximum heatup rate?
A. 50° B. 80° C. 100° D. 120° Answer: B Explanation:
Since the temperature is 110°F the applicant should use the 120°F curve of Attachment 1, Figure 3, of 05-1-02-III-1, Inadequate Decay Heat Removal, Rev. 39. Using this curve the difference between 200°F and 120°F is 80°F and the time 5 days after shutdown is 1 hr. All other rates are plausible if the applicant chooses the wrong graph.
Technical
References:
05-1-02-III-1, Inadequate Decay Heat Removal, Rev. 39 References to be provided to applicants during exam: All attachments from 05-1-02-III-1, Inadequate Decay Heat Removal, Rev. 39 Learning Objective: Document learning objective if possible.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(5)
Examination Outline Cross-Reference Level RO 295023 Refueling Accident Tier # 1 Group # 1 Ability to determine and/or interpret the K/A # 295023 AA2.01 following as they apply to REFUELING Rating 3.6 ACCIDENTS : Area radiation levels.
Question 9 Refueling activities are in progress. A CONTAINMENT FUEL HDLG AREA RADIATION HIGH alarm is received. No other alarms are received at this time. This condition could be caused by:
A. a fuel assembly being inadvertently raised too high at the refueling platform.
B. drop of a spent fuel assembly from the refueling platform.
C. a fuel assembly being inadvertently raised too high at the fuel handling platform.
D. drop of a spent fuel assembly from the fuel handling platform.
Answer: A Explanation:
Raising an irradiated fuel assembly too high could result in reduced shielding with a subsequent rise in area radiation levels.
B and D are wrong because if release of gaseous activity from a damaged fuel assembly is the cause of the area radiation alarm, this would be accompanied by gaseous process radiation alarms.
C and D are wrong because the fuel handling platform is not in the containment building.
Technical
References:
ARI 04-1-02-1H13-P844-1A-A3, CONTAINMENT FUEL HDLG AREA RADIATION HIGH.
Lesson plan GLP-RF-F1101, Fuel handling/Refueling Platform References to be provided to applicants during exam:
None Learning Objective: GLP-OPS-D1721 Given applicable Alarm Response Instructions (ARIs) and plant conditions, state/identify the probable causes for any alarm listed in the System Alarm Index of SOI 04-1-01-D17-1 and SOI 04-1-01-D21-1 (NLOs responsible for LOCAL Panels only). (19)
Question Source: Bank #
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New X
Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 295024 High Drywell Pressure Tier # 1 Group # 1 Ability to operate and/or monitor the K/A # 295024 - EA1.04 following as they apply to HIGH Rating 4.1 DRYWELL PRESSURE: RHR/LPCI Question 10 The plant has scrammed after receiving a high drywell pressure signal. The amber light above the RHR A pump is lit indicating the A RHR pump breaker has A. tripped on a load shed.
B. tripped on no minimum flow path.
C. received a close signal and is tripped.
D. received a close signal and is running.
Answer: C Explanation:
A is wrong because there would not be a reason for the pump to trip on a load shed. The applicant should assume all equipment was in a normal position, so the pump wouldnt trip.
The pump should load after LSS is complete.
B is wrong because there is no trip on no minimum flow path, but plausible since this should be an immediate action for operators. Applicants may confuse the immediate action with preventing an automatic action from occurring.
C is correct because this is the meaning of the light per Table 1 of GFIG-OPS-E1200.
D is wrong because of C.
Technical
References:
GFIG-OPS-E1200, Residual Heat Removal (RHR) System - Figures, Rev 1 References to be provided to applicants during exam: None.
Learning Objective: Document learning objective if possible.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental
Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7)
Examination Outline Cross-Reference Level RO 295025 High Reactor Pressure Tier # 1 Group # 1 Ability to determine and/or interpret the K/A # 295025 EA2.01 following as they apply to HIGH REACTOR Rating 4.3 PRESSURE: Reactor pressure.
Question 11 A reactor vessel steam dome high pressure scram signal should be the signal that first generates a reactor scram on a:
A. single MSIV closure with reactor power at 75%.
B. closure of all MSIVs at full power.
C. turbine trip at full power.
D. pressure controller failing closed with reactor power at 75%.
Answer: D Explanation:
Interpreting reactor pressure involves determining if it is responding as expected.
A is wrong because this should not result in a scram.
B is wrong because the reactor will scram on the main steam isolation valve closure.
C is wrong because the reactor will scram on Turbine stop valve closure or low trip oil pressure.
At less than RTP, the high pressure signal should precede the high power signal.
Technical
References:
Mitigating of Core Damage (EPTS-2) Pressure Increase Events, GLP-OPS-MCD12 References to be provided to applicants during exam: None.
Learning Objective: GLP-OPS-MCD12 Given a pressure increase event and associated plant parameter curves, explain the behavior of the plant parameters.(2)
Question Source: Bank #
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 295026 Suppression Pool High Water Temp Tier # 1 Group # 1 Knowledge of the reasons for the following K/A # 295026 - EK3.05 responses as they apply to SUPPRESSION Rating 3.9 POOL HIGH WATER TEMPERATURE:
Reactor SCRAM Question 12 The reason for transitioning out of EP-3, Containment Control, before suppression pool temperature reaches 110oF is to ensure:
A. There is an adequate NPSH for all pumps taking suction off of the suppression pool.
B. All pumps taking suction from the suppression pool will not become gas bound.
C. Containment pressure remains below 10 psig during a design basis accident.
D. EP-2, RPV Control, is initiated before reaching maximum boron injection initiation temperature.
Answer: D Explanation:
A is wrong because NPSH is only referenced for level and not temperature. This is plausible since NPSH is a combination of both.
B is wrong because gas binding of pumps is not mentioned for high suppression pool temperatures.
C is wrong because the design containment pressure is 15 psig.
D is correct because in the PSTG this is referenced as the reason for transitioning.
Technical
References:
05-S-01-PSTG, Plant Specific Technical Guidelines, Rev 05 References to be provided to applicants during exam: None.
Learning Objective: Document learning objective if possible.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis
10CFR Part 55 Content: 55.41(b)(7);(8)
Examination Outline Cross-Reference Level RO 295027 High Containment Temperature Tier # 1 Group # 1 Knowledge of the reasons for the following K/A # 295027 EK3.02 responses as they apply to HIGH Rating 3.2 CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) : Containment spray:
Plant specific.
Question 13 The reason containment sprays are used to mitigate high containment temperature ONLY when containment pressure is relatively high is this:
A. ensures the steam formation will not over-pressurize containment.
B. prevents an excessive rate of depressurization.
C. ensures RHR pump discharge pressure is adequate to prevent runout.
D. prevents excessive flow through the RHR heat exchanger.
Answer: B Explanation:
The CSIPL does not allow spray to be initiated when temperature is high and pressure is low.
Spray with high temperature and low pressure results in a rapid cooldown/depressurization which may lead to forming a negative pressure in containment with subsequent loss of containment integrity.
A is credible because steam may be produced by spray flow, but the concern is overcooling, not overpressurization.
C is credible because high pressure would limit centrifugal pump flow but this is not the basis for the CSIPL.
D is credible because low pressure would result in more HX flow but this is not the basis for the CSIPL.
Technical
References:
BWROG EP Guidelines section 17.9.
References to be provided to applicants during exam:
Learning Objective: GLP-OPS-EP3
- 7. State/identify the basis associated with each individual step in EP-3.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 295028 High Drywell Temperature Tier # 1 Group # 1 Knowledge of EOP entry conditions and K/A # 295028 - 2.4.1 immediate action steps. Rating 4.3 Question 14 Which of the following would require an entry into 05-S-01-EP-3, Containment Control?
If you were required to enter 05-S-01-EP-2, RPV Control, based on not being able to control a parameter in EP-3, what would your immediate action be upon entry into EP-2?
A. Suppression Pool temperature at 85oF Maximize Suppression Pool cooling B. Drywell pressure at 1.15 psig Prevent ECCS injection C. Drywell temperature at 145oF Verify the Reactor Mode Switch in Shutdown D. Suppression Pool level at 18.45 ft Inhibit ADS Answer: C Explanation:
A wrong because this temperature would not require entry into the EOP. The immediate action is not an action required when entering EP-2, but is reasonable for a high temperature.
B is wrong because the pressure would not require entry into the EOP. The immediate action is a step in EP-2 for high drywell pressure but pressure has to be above 1.39 psig.
C is correct because this temperature is above the entry criteria of 135oF. The immediate action is correct upon entry into EP-2.
D is wrong because the level would not require entry into an EOP. The immediate action is a step in the EP-2 procedure that should be second nature to an applicant so they could believe it is an immediate action.
Technical
References:
05-S-01-EP-3, Containment Control 05-S-01-EP-2, RPV Control References to be provided to applicants during exam: None.
Learning Objective:
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(10)
Examination Outline Cross-Reference Level RO 295030 Low Suppression Pool Wtr Lvl Tier # 1 Group # 1 Knowledge of the reasons for the following K/A # 295030 EK3.06 responses as they apply to LOW Rating 3.6 SUPPRESSION POOL WATER LEVEL:
Reactor SCRAM Question 15 The reason a reactor scram is required on a low suppression pool level is:
A. the drywell to containment suppression pool vents will become uncovered.
B. the SRV sparger will become uncovered C. the ECCS pumps may fail due to vortexing.
D. a LOCA may result in a loss of containment..
Answer: D Explanation:
The EP technical basis states that the reason is to preserve containment integrity because the SP may not adequately condense steam on a primary system break..
Technical
References:
EP-2, RPV Control EP-3, Containment control EP Technical Basis, Step References to be provided to applicants during exam: None Learning Objective: GLP-OPS-EP3
- 7. State/identify the basis associated with each individual step in EP-3.
Question Source: Bank #
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 295031 Reactor Low Water Level Tier # 1 Group # 1 Knowledge of the reasons for the following K/A # 295031 - EK3.01 responses as they apply to REACTOR LOW Rating 3.9 WATER LEVEL: Automatic depressurization system actuation Question 16 The reason for the 105 second time delay before ADS initiation is to allow enough time A. To inhibit ADS if not desired.
B. To ensure systems are aligned for an emergency depressurization.
C. For RCIC to recover RPV level.
D. For HPCS to recover RPV level.
Answer: D Explanation:
A is wrong because it is not the reason for the timer exists but plausible if an applicant believes the system initiation is based on the emergency procedure.
B is wrong because emergency depressurization does use the ADS valves and proper alignment is needed but an emergency depressurization occurs much later in the emergency procedure and it is not the basis for the timer.
C is wrong because it is the incorrect high pressure system but plausible if an applicant confuses RCIC for an ECCS system.
D is correct because the reason is specified in the training manaual.
Technical
References:
GLP-OPS-E2202, Automatic Depressurization System (ADS)
References to be provided to applicants during exam: None.
Learning Objective: Describe the signals and setpoints for the initiation of the ADS System for both automatic and manual initiation.
Question Source: Bank #
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(8),(10)
Examination Outline Cross-Reference Level RO 295037 SCRAM Condition Present Tier # 1 and Reactor Power Above APRM Downscale Group # 1 or Unknown K/A # 295037 2.4.6 Rating 3.7 Knowledge of EOP mitigation strategies Question 17 The plant was at rated thermal power when a turbine trip occurred. Multiple control rods remained at the fully withdrawn position. Currently;
- Reactor power is 10%
- RPV level is 18
- Reactor pressure is 935 psig being controlled by the turbine bypass valves.
According to EP-2A, ATWS RPV Control, the crew should lower RPV level:
A. to -70 and maintain it as close to -70 as possible.
B. until power is below 5% or level drops to -167.
C. to between -191 and -167 D. to between -191 and -70.
Answer: D Explanation:
A is wrong because, while level is initially lowered to -70 in step 7.1, step 9 subsequently directs a level band of -191 and -70 B and C are correct only if SRVs are open.
Technical
References:
EP-2A, Revision Date 5/15/12 References to be provided to applicants during exam: None Learning Objective:
Question Source: Bank #
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New X
Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(10) 55.43
Examination Outline Cross-Reference Level RO 295038 High Off-site Release Rate Tier # 1 Group # 1 Knowledge of the interrelations between K/A # 295038 - EK2.02 HIGH OFF-SITE RELEASE RATE and the Rating 3.6 following: Offgas System Question 18 To prevent an off-site release greater than allowable limits, the Offgas system isolates when (a) __________ Upscale HI-HI-HI trip channel is(are) received. The Upscale HI-HI-HI alarm setpoint is ____________ throughout an operating cycle by Chemistry.
A. single; fixed B. single; varied C. both; fixed D. both; varied Answer: D Explanation:
A is wrong because it takes both Upscale HI-HI-HI alarms to isolate Offgas but it takes a single alarm to take the system out of bypass which makes this answer plausible. This value can be varied throughout an operating cycle at management discretion according to procedure 08-S-03-22, INSTALLED RADIATION MONITORING SYSTEM ALARM SETPOINT DETERMINATION AND CONTROL, Rev 114.
B is wrong because the first answer is false but the second is true C is wrong because it takes both channels to generate a trip but the setpoint can be varied at any time throughout the cycle.
D is correct because it takes both channels to isolate and the setpoint can be varied.
Technical
References:
Procedure 08-S-03-22, INSTALLED RADIATION MONITORING SYSTEM ALARM SETPOINT DETERMINATION AND CONTROL, Revision 114 References to be provided to applicants during exam: None.
Learning Objective: Discuss the types of alarms received on the Radiation Monitoring Systems. (8)
Describe the automatic actions initiated by the Process Radiation Monitoring. (15)
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(11)
Examination Outline Cross-Reference Level RO 600000 Plant Fire On Site Tier # 1 Group # 1 Ability to operate and / or monitor the following K/A # 600000 AA1.06 as they apply to PLANT FIRE ON SITE: Fire Rating 3.0 Alarm Question 19 A rate-of-rise heat detector in the B RPS MG room triggers a local fire alarm. The expected fire system response is a:
A. CO2 discharge occurs immediately.
B. CO2 discharge occurs after a 30 second delay.
C. halon discharge occurs immediately.
D. halon discharge occurs after a 30 second delay.
Answer: B Explanation:
C and D are wrong because this room is not protected by Halon.
A is wrong because the discharge is delayed to allow for evacuation.
Technical
References:
GFIG-OPS-P6400 Figure 11, Typical CO2 Control Station.
References to be provided to applicants during exam:
Learning Objective: GLP-OPS-P6400 Describe the automatic actions/features associated with each of the following Fire Protection System components, including setpoints and bypasses (if applicable): (6.0) Fire Protection C02 System, including automatic and manual start (6.6)
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis
10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 700000 Generator Voltage and Electric Grid Tier # 1 Disturbances Group # 1 K/A # 700000 - AA1.03 Ability to operate and/or monitor the Rating 3.8 following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Voltage regulator controls Question 20 What is the maximum allowable reactive load allowed during normal and emergency conditions?
Which pushbuttons are used to change reactive load?
A. +253 MVARS; TVR raise/lower B. +253 MVARS; Load Demand raise/lower C. +297.5 MVARS; TVR raise/lower D. +297.5 MVARS; Load Demand raise/lower Answer: C Explanation:
A is wrong because the maximum reactive load is listed in 04-1-01-N40-1 as +297.5 in P&L 3.8. A -253 corresponds to the minimum reactive load allowed by procedure. This is plausible if the applicant reverses the signs on maximum load.
B is wrong because this does not meet the maximum specified in procedure. Also, changing the load with the load demand pushbuttons changes actual load and not reactive load. This is plausible if an applicant doesnt understand the difference in grid/turbine load.
C is correct because this is the correct value and the correct button D is wrong because the incorrect pushbutton is listed.
Technical
References:
04-1-01-N40-1, Main Generator and Auxiliaries, Rev 37, p.4, P&L 3.8 Describe how the output voltage of the Main Generator is varied, including any limitations.
(8)
References to be provided to applicants during exam: None.
Learning Objective: Identify precautions, limitations, cautions, warnings and notes which apply to a given situation and are related to the Main Generator. (14.1).
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(10)
Examination Outline Cross-Reference Level RO 295002 Loss of Main Condenser Vac Tier # 1 Group # 2 Knowledge of the interrelations between LOSS K/A # 295002 AK2.07 OF MAIN CONDENSER VACUUM and the Rating 3.1 following: Offgas system Question 21 With the plant at rated power, for which of the following alarms would a slow, gradual loss of condenser vacuum be expected?
A. OG POST-TREAT RAD HI-HI-HI/INOP.
B. OG RADWST VENT RAD HI.
C. OG CHAR VAULT RAD HI.
D. MSL B/MSL C RAD HI-HI/INOP.
Answer: A Explanation:
OG POST-TREAT RAD HI-HI-HI/INOP isolates condenser off-gas, which, according to 05 02-V-8 Loss of Condenser Vacuum should lead to a slow, gradual reduction in condenser vacuum.
OG RADWST VENT RAD HI has no automatic actions.
OG CHAR VAULT RAD HI has no automatic actions.
MSL B/MSL C RAD HI-HI/INOP only results in a half-trip.
Technical
References:
05-1-02-V-8, Loss of Condenser Vacuum 05-1-02-II-2, Off-Gas Activity High References to be provided to applicants during exam:
Learning Objective: GLP-OPS-N6200
- 13. Discuss the interrelationships of the following systems with the Condenser Air Removal System. h. Process Radiation Monitoring System, D17 i. Offgas System, N64 Question Source: Bank #
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO Low Reactor Water Level Tier # 1 Group # 2 Knowledge of the interrelations between K/A # 295009 - AK2.04 LOW REACTOR WATER LEVEL and the Rating 2.6 following: Reactor water cleanup Question 22 Which of the following would result in the isolation of Reactor Water Cleanup?
A. Reactor vessel water level at -50.
B. Main steam line tunnel temperature at 165oF.
C. RWCU heat exchanger room at 110oF.
D. RWCU differential flow at 70 gpm for 30 seconds.
Answer: A Explanation:
A is correct because it is less than the setpoint of -41.6 B is wrong because the setpoint is at 185oF C is wrong because the setpoint is 120oF D is wrong because the setpoint is 79 gpm for 45 seconds Technical
References:
GLP-OPS-G3336, Rev 16, Reactor Water Cleanup System References to be provided to applicants during exam: None.
Learning Objective: 8.6 Describe automatic actions associated with system isolation valves.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b) 55.43
Examination Outline Cross-Reference Level RO 295010 High Drywell Pressure Tier # 1 Group # 2 Ability to operate and/or monitor the following K/A # 295010 AA1.01 as they apply to HIGH DRYWELL Rating 3.4 PRESSURE: Drywell ventilation/cooling Question 23 An energized white light above the associated drywell chiller hand switch in the control room indicates the chiller:
A. is in standby.
B. is in local control.
C. has tripped.
D. has auto started.
Answer: A Explanation:
B, C, and D are wrong because A is correct.
Technical
References:
04-1-02-1H13-P601-16A-B4, ARI for DRWL PRESS HI GLP-OPS-M5100, Drywell Cooling and Drywell Chilled Water Systems References to be provided to applicants during exam: None Learning Objective: GLP-OPS-M5100. 04 State/identify the locations from which the following components of the Drywell Cooling and Drywell Chilled Water Systems can be found. Drywell Coolers Drywell Chillers Obj 6, Describe the automatic actions . . . Drywell Chillers Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis
10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 295011 High Containment Temp Tier # 1 Group # 2 Knowledge of the interrelations between K/A # 295011 - AK2.01 HIGH CONTAINMENT TEMPERATURE Rating 3.7 (MARK III CONTAINMENT ONLY) and the following: Containment ventilation/cooling: Mark-III.
Question 24 What is/are the MINIMUM number of fan coolers required to be in service per SOI 04-1 M41, Containment Cooling System? Will containment fan coolers receive an auto start signal if a high containment temperature alarm is received?
A. 1/Yes B. 2/No C. 1/No D. 2/Yes Answer: B Explanation:
A is wrong because the minimum number required is 2 and there is no auto start on high containment temperature.
B is correct because the minimum required is 2 and the only auto start for the fan coolers is on low flow across a fan.
C is wrong because see A D is wrong because the minimum number is correct there is no auto start on high containment temperature.
Technical
References:
GLP-OPS-M4100, Containment Cooling System M41, Rev 5 Note from 04-1-01-M41, Containment Cooling System:
The following operations are performed at 1H13-P842, Unless otherwise noted. Two OR three Containment coolers Should be in service during normal operations.
References to be provided to applicants during exam: None.
Learning Objective: 10.1 State/identify the interlocks associated with starting and stopping of fans.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(10)
Examination Outline Cross-Reference Level RO 295012 High Drywell Temperature Tier # 1 Group # 2 Knowledge of the operational implications of K/A # 295010 AK1.01 the following concepts as they apply to HIGH Rating 3.3 DRYWELL TEMPERATURE :
Pressure/temperature relationship Question 25 The purpose of the RPV Saturation Temperature (RPVST) curve is to evaluate the effect of drywell temperature on:
A. reactor vessel integrity.
B. containment integrity.
C. RPV level instrumentation accuracy.
D. RPV pressure instrumentation accuracy.
Answer: C Explanation:
The RPV Saturation Temperature is a plot of the saturation temperature of water as a function of pressure. If the temperature of the water in an RPV water level instrument run exceeds this temperature, the water may start to boil, resulting in unreliable level indication.
Technical
References:
02-S-01-40, p. 42 of 45.
References to be provided to applicants during exam: none Learning Objective: GLP-OPS- Describe the system interrelationship between the Drywell Cooling and Drywell Chilled Water Systems and the following: (10) Containment and Drywell Instrumentation and Control System (10.6)
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X
10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 295013 High Suppression Pool Temperature Tier # 1 Group # 2 Ability to operate and/or monitor the K/A # 295013 - AA1.01 following as they apply to HIGH Rating 3.9 SUPPRESSION POOL TEMPERATURE:
Suppression pool cooling Question 26 RHR B is in service in suppression pool cooling mode due to high temperature in the suppression pool from RCIC operability testing. According to procedure 04-1-01-E12-1, Residual Heat Removal System, the RHR system flow must be maintained greater than
_________. At what minimum temperature should suppression pool cooling be secured?
A. 7300 gpm; 65oF B. 7300 gpm; 70oF C. 7450 gpm; 65oF D. 7450 gpm; 70oF Answer: A Explanation:
A is correct because as referenced in the procedure this is the minimum flow and a caution in the procedure has you secure suppression pool cooling before you go below 65oF.
B is wrong because it is the correct flow but temperature is incorrect. This is plausible because the note references 70oF but it doesnt explicitly have you shutdown suppression pool cooling until below 65oF.
C is wrong because the flow requirements are incorrect but plausible since this is the tech spec value for flow. The temperature is correct D is wrong because both flow and temperature are incorrect but plausible.
Technical
References:
04-1-01-E12-1, Residual Heat Removal System, Rev. 143, p.26 References to be provided to applicants during exam: None.
Learning Objective: Document learning objective if possible.
Question Source: Bank #
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(8)
Examination Outline Cross-Reference Level RO 295015 Incomplete SCRAM Tier # 1 Group # 2 Knowledge of the operational implications of K/A # 295015 AK1.01 the following concepts as they apply to Rating 3.6 INCOMPLETE SCRAM : Shutdown margin Question 27 Select the statement(s) that correctly complete(s) this sentence.
Following a reactor scram with two control rods at the fully withdrawn position, the crew may make a transition from EP-2A, ATWS, to EP-2, RPV control relying on the negative reactivity from:
- 1. inserted control rods.
- 2. injected boron.
- 3. current xenon concentration.
A. 1, 2 and 3 B. 1 and 2 only C. 1 and 3 only D. 1 only Answer: D Explanation:
BWROG EPGs/SAGs, Appendix B Revision 2 says Note that the instruction requires a positive determination, not only that the reactor is shutdown, but that it will remain shutdown, without reliance upon boron, under worst-case cold shutdown conditions. The phrase without boron does not imply that the condition cannot be met if boron has been injected, but that credit cannot be taken for the negative reactivity contributed by the boron. Control rod insertion alone must provide the necessary shutdown margin.
Technical
References:
BWROG EPGs/SAGs, Appendix B Revision 2 References to be provided to applicants during exam:
Learning Objective: GLP-OPS-EP02A 7. State/identify the basis associated with each
individual step in EP-2A.
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 203000 RHR/LPCI: Injection Mode Tier # 2 Group # 1 Knowledge of RHR/LPCI: INJECTION K/A # 203000 - K4.14 MODE (PLANT SPECIFIC) design feature(s) Rating 3.6 and/or interlocks which provide for the following: Operation from remote shutdown panel Question 28 If the RHR A INJ DISABLE handswitch is placed in the ENABLE position at the Remote Shutdown Panel, F042A, RHR A Injection Shutoff Valve, will not automatically ______:
A. Open on a LOCA signal concurrent with low reactor pressure AND no containment spray initiation signal.
B. Close on containment spray initiation signal.
C. Open on LOCA signal concurrent with low reactor pressure OR no containment spray initiation signal.
D. Open on LOCA signal.
Answer: A Explanation:
A is correct because it is listed as a caution in 05-1-02-II-1 B is wrong because it is not defeated. The valve can still be opened manually with the signal present but it will auto close C is wrong because this does not meet the caution in 05-1-02-II-1 D is wrong because the valve does not get an open signal solely on initiation. Plausible if an applicant believes it does Technical
References:
05-1-02-II-1, Shutdown from the Remote Shutdown Panel, Attachment XIV References to be provided to applicants during exam: None.
Learning Objective:
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(8)
Examination Outline Cross-Reference Level RO 205000 Shutdown Cooling Tier # 2 Group # 1 Knowledge of the operational implications of K/A # 295000 K5.02 the following concepts as they apply to Rating 2.8 SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) :Valve operation Question 29 Shutdown cooling is being established using RHR loop A per SOI-04-1 E12-2, Shutdown Cooling and Alternate Decay heat Removal Operations.
After starting RHR pump A, the operator is procedurally directed to open a valve and immediately establish a minimum flow in order to prevent:
A. cavitation in RHR pump A.
B. discharging reactor vessel coolant to the suppression pool.
C. reactor pressure vessel thermal stratification.
D. lifting the RHR pump A discharge relief valve.
Answer: B Explanation:
According to the note prior to the pump start, Failure to establish greater than 1154 gpm within 8 seconds of pump start automatically opens F064A, establishing flow from Reactor to Suppression Pool.
A is wrong because, while inadequate pump flow could eventually lead to pump cavitation, F064A operation will prevent this.
C is wrong because, while stratification is a concern when flow is inadequate, F064A operation will prevent this.
D is wrong, because the RHR pump is centrifugal, and its discharge pressure at shutoff head is well below the lift setpoint of system safety valves.
Technical
References:
Shutdown Cooling and Alternate Decay Heat Removal Operation, SOI 04-1-01-E12-2, Revision 116. Caution prior to step 4.1.2c(17)
References to be provided to applicants during exam: None
Learning Objective:
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 205000 Shutdown Cooling Tier # 2 Group # 1 Knowledge of SHUTDOWN COOLING K/A # 205000 - K4.02 SYSTEM (RHR SHUTDOWN COOLING Rating 2.6 MODE) design feature(s) and/or interlocks which provide for the following: High pressure isolation Question 30 Which NSSSS group isolation provides protection against high reactor pressure for the RHR system in the Shutdown Cooling Mode of Operation?
A. 2 B. 3 C. 4 D. 5 Answer: B Explanation:
A is wrong because Group 2 isolations protect for RHR to Radwaste B is correct because Group 3 isolations protect the RHR in shutdown cooling C is wrong because Group 4 isolations were part of steam condensing mode of RHR D is wrong because Group 5 isolations protect RHR test lines Technical
References:
Table 2 of GFIG-OPS-E1200; GLP-OPS-M701 p.36 References to be provided to applicants during exam: None.
Learning Objective: Describe the signals, setpoints and valves actuated by the RHR Shutdown Cooling Isolation Logic. (7.3)
Question Source: Bank #
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 209001 LPCS Tier # 2 Group # 1 Knowledge of the effect that a loss or K/A # 209001 K6.01 malfunction of the following will have on the Rating 3.4 LOW PRESSURE CORE SPRAY SYSTEM : A.C. power Question 31 Following a loss of MCC 15B11, an ECCS initiation signal would result in the LPCS pump:
A. failing to start.
B. starting and running at shutoff head (zero flow) regardless of RCS pressure.
C. starting, and running on mini-flow only regardless of RCS pressure.
D. starting and running without mini-flow protection, but will inject into the core when RCS pressure drops low enough.
Answer: C Explanation:
MCC 15B11 powers all system MOVs but not the pump. The pump will start, but no MOV can be repositioned.
A is wrong because the pump has not lost power.
B is wrong because the mini-flow valve has no power but it is normally open.
D is wrong because the injection flowpath is normally isolated with an MOV that has no power.
Technical
References:
GLP-OPS-E2100 References to be provided to applicants during exam: None Learning Objective: GLP-OPS-E2100 Rev. 10, Obj. 7.1 State/identify the power supplies for the following LPCS system components: Motor Operated Valves Obj 16 Upon recognition of the following abnormal plant indications, predict system response and potential consequences - AC power disturbances Question Source: Bank #
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 209001 LPCS Tier # 2 Group # 1 Ability to determine operability and/or K/A # 209001 - 2.2.37 availability of safety related equipment Rating 3.6 Question 32 The plant is in Mode 4 with Electrical Bus 16AB OOS for planned maintenance. Youve been asked to perform 06-OP-1E21-M-01, LPCS Monthly Functional Test, and the LPCS valves are in the following position:
LPCS Injection valve - Closed LPCS Suction Valve - Open LPCS Minimum flow to suppression Pool - Open LPCS Testable Check Valve - Closed Is the LPCS system operable? Are the minimum required systems for TS 3.5.2 met?
A. Yes/Yes B. No/Yes C. Yes/No D. No/No Answer: A Explanation:
A is correct because this lineup meets the requirements of LPCS Monthly Functional Test, and since LPCS, RHR A and HPCS are all operable and only 2 are required this meets the LCO for 3.5.2.
B is wrong because the system is not operable but plausible since it is counterintuitive to have the min flow valve should be in the open position for the system to be operable.
C is wrong because the system is operable and the minimum systems are met.
D is wrong because the system is operable and the minimum systems are met.
Technical
References:
06-OP-1E21-M-01, LPCS Monthly Functional Test, Revision 106 TS SR 3.5.2 References to be provided to applicants during exam: None.
Learning Objective: Document learning objective if possible.
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7);(8)
Examination Outline Cross-Reference Level RO 209002 HPCS Tier # 2 Group # 1 Ability to predict and/or monitor changes in K/A # 209002 A1.09 parameters associated with operating the Rating 2.6 HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) controls including: Condensate storage tank level: BWR-5,6 Question 33 The reactor is shutdown with RHR A in shutdown cooling. A full flow test (CST to CST) of HPCS is in progress when E22-FIS-N656, HPCS Pump Discharge Flow fails downscale.
Following the instrument failure, CST level will:
A. drop and RPV level will rise.
B. drop and suppression pool level will rise.
C. rise and suppression pool level will drop.
D. remain steady.
Answer: B Explanation: The full flow test is recirculating the CST. Transmitter FT-N056 feeds FIS-N656. With measured flow < 1206 gpm, F012, HPCS recirc. opens, moving water from the CST to the suppression pool.
A would be correct if the recirc valve discharged to the RCS.
C would be correct if the full flow test was recirculating the suppression pool and the recirc discharged to the CST.
D would be correct if equalizing a flow transmitter caused indicated flow to fail high.
Technical
References:
GFIG-OPS-E2201, HPCS figures, Figure 2, HPCS System Overview References to be provided to applicants during exam: None Learning Objective: The HPCS lesson plan was not provided Question Source: Bank #
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New X
Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 211000 SLC Tier # 2 Group # 1 Knowledge of the operational implications K/A # 211000 - K5.05 of the following concepts as they apply to Rating 2.5 STANDBY LIQUID CONTROL SYSTEM:
Explosive valve operation Question 34 Following an initiation of SLC A, which of the following sets of indications would be observed if the A squib valve fails to open?
A. SLC storage tank level decreasing, SLC pump discharge pressure higher than reactor pressure, and reactor power decreasing.
B. SLC storage tank level decreasing, SLC pump discharge pressure lower than reactor pressure, and reactor power constant.
C. SLC storage tank level constant, SLC pump discharge pressure higher than reactor pressure, and reactor power decreasing.
D. SLC storage tank level constant, SLC pump discharge pressure higher than reactor pressure, and reactor power constant.
Answer: D Comments: An applicant could reasonably argue B and D are correct.
Explanation:
A is wrong because it describes a good start of the SLC system B is wrong because if SLC pump discharge pressure is less than reactor pressure SLC would not be able to inject, therefore it is not indicative of a failure of the squib to fire but of the system not developing pressure C is wrong because SLC storage tank level would not remain constant if SLC was initiated.
The indication describe a failed instrument D is correct because tank level would remain constant and discharge pressure would be higher than reactor pressure because the pump would be recircing due to the relief valve lifting.
Technical
References:
GLP-OPS-C4100 Rev 10, page 18-20 References to be provided to applicants during exam: None.
Learning Objective: (12) Describe the indications of SLC injection into the reactor.
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(6) 55.43
Examination Outline Cross-Reference Level RO 212000 RPS Tier # 2 Group # 1 Knowledge of the effect that a loss or K/A # 212000 K3.01 malfunction of the REACTOR PROTECTION Rating 3.0 SYSTEM will have on following: Process radiation monitoring Question 35 The reactor is at 5% power during a startup when EPA-S003A trips on undervoltage. With respect to the process radiation monitors, this event would result in; A. closure of Inboard Reactor Sample Valve, B33-F019.
B. closure of Outboard Reactor Sample Valve, B33-F020.
C. generation of a mechanical vacuum pump trip signal.
D. no automatic trip signals or isolations.
D.
Explanation:
On the loss of RPS A, the power would be automatically switched to inverter 1Y87.
Therefore, none of the RPS components would be affected making D correct. No process monitors will lose power in this event.
Technical
References:
GLP-OPS-D1721 GG UFSAR, 15.8.1 GG UFSAR, 15.2.2.5 References to be provided to applicants during exam: None.
Learning Objective Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental
Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 215003 IRM Tier # 2 Group # 1 Knowledge of the effect that a loss or K/A # 215003 - K6.04 malfunction of the following will have on the Rating 3.0 INTERMEDIATE RANGE MONITOR (IRM) SYSTEM: Detectors Question 36 The plant is starting up following an outage. SRM/IRM overlap has been verified and all IRMs are indicating normally on range 5 when IRM F and IRM H fail high.
What is the expected system/plant response?
B. A half scram on RPS Division A AND a rod block.
C. A half scram on RPS Division B AND a rod block.
D. A rod withdrawal block ONLY.
Answer: C Explanation:
A is wrong because both detectors are on the same division so full scram logic would not be made up. Plausible if an applicant doesnt know which IRMs are on which division B is wrong because this is the wrong division of RPS C is correct this is the correct division of RPS and a rod block is generated.
D is wrong because a rod block would be generated an RPS signal would also be generated.
Technical
References:
GLP-OPS-C5102 - p. 20-31 References to be provided to applicants during exam: None.
Learning Objective: Concerning the major automatic features of the IRM System, state/identify the signals and setpoints associated with an IRM scram signal, including when the signals are bypassed.
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7)
Examination Outline Cross-Reference Level RO 215003 IRM Tier # 2 Group # 1 Ability to monitor automatic operations of the K/A # 215003 A3.01 INTERMEDIATE RANGE MONITOR (IRM) Rating 3.3 SYSTEM including: Meters and recorders Question 37 When an Intermediate Range Monitors UP button illuminates, the operator should press the associated channels ________ button.
A. UP B. DRIVE OUT C. DOWN D. DRIVE IN Answer: A No need for a 2 part question.
Explanation: The UP button is backlit when the light signifies that the IRM is at 75% of scale. Pressing the button raises the channel to the next highest scale. This condition is expected during a plant startup.
There is nothing intuitive about the meaning of this light. It could mean that the detector needs to be driven in (up), or is up and should be down (driven out). If could also logically mean that the current scaling is too high, which would occur during a plant shutdown.
Technical
References:
GLP-OPS-C5102 References to be provided to applicants during exam: None Learning Objective:
GLP-OPS-C5102 For each of the following IRM System components, state/identify methods of operation, including locations of associated controls and indications: (7) Drive mechanism (7.1) IRM range select pushbuttons (7.2)
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 215004 Source Range Monitor Tier # 2 Group # 1 Ability to (a) predict the impacts of the K/A # 215004 - A2.01 following on the SOURCE RANGE Rating 2.7 MONITOR (SRM) SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Power supply degraded Question 38 The reactor is starting up following a refueling outage when output voltage on Inverter 1Y96 indicates 0.0 volts. What is an expected automatic action of this condition and what would be the immediate operator action of Alarm Response 04-1-02-1H13-P680, to mitigate this failure so startup can continue?
A. Control rod block; bypass SRM C B. Control rod block; bypass SRM D C. Full RPS scram; bypass SRM C D. Full RPS scram; bypass SRM D Answer: A Explanation:
A is correct because SRM normally only generate rod blocks unless in special situations.
This inverter feeds the power supply for SRM C.
B is wrong because the first half is correct but Inverter 1Y95 feeds SRM D.
C is wrong because there are no scram signals generated from SRMs unless the shorting links are removed. This is normally done during fuel loading and would not be done while starting up. It is plausible if an applicant doesnt understand this.
D is wrong because see answer C Technical
References:
GLP-OPS-C5101, SOURCE RANGE MONITORING (SRM) SYSTEM - C5101, Rev 3 References to be provided to applicants during exam: None.
Learning Objective: 10.1 Describe the interrelationships of the following systems with the SRM System: 120V AC Uninterruptible Power Supply (UPS) System.
8.2 Concerning the major automatic features of the SRM System, state/identify the signals and setpoints associated with an SRM rod withdrawal block signal, including when the signals are bypassed.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7)
Examination Outline Cross-Reference Level RO 215005 APRM / LPRM Tier # 2 Group # 1 Knowledge of the physical connections and/or K/A # 215005 K1.13 cause-effect relationships between AVERAGE Rating 2.6 POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM and the following: Traversing incore probe system Question 39 The traversing incore probe system is used to ensure that the _______ instrumentation remains operable:
A. reactor protection system B. control rod block C. post accident monitoring D. emergency core cooling system Answer: A Explanation:
TS 3.3.1 function 2b cannot remain operable because SR 3.3.1.1.7 (LPRM calibration) cannot be met.
The other answers are incorrect because TIPS is not used in maintaining operability for these systems.
This is RO level because the RO is required to recognize conditions that require TS entry.
Technical
References:
GLP-OPS-C5105, TIP system TS 3.3.1, function 2b, SR 3.3.1.1.7.
References to be provided to applicants during exam: None Learning Objective: GLP-OPS-C5105, TIP system Describe the interrelationships of the following systems with the TIP System: (10)
Process Computer (10.1)
Local Power Range Monitors (10.4)
Given plant conditions, identify entry into the Limiting Condition for Operation (LCO) for any Technical Specification related to the TIP System. (12)
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 217000 RCIC Tier # 2 Group # 1 Ability to evaluate plant performance and K/A # 217000 - 2.1.7 make operational judgments based on Rating 4.4 operating characteristics, reactor behavior, and instrument interpretation Question 40 The plant is operating at rated power when you receive SUPP POOL LVL HI alarm on P601.
Control room operators should immediately verify:
A. RCIC suction is from the suppression pool B. RCIC suction is from the condensate storage tank C. HPCS operability D. FCV MOV-F022, RCIC Inboard Test return, is open Answer: A Explanation:
A is correct because this is the immediate action in ARP 04-1-02-1H13-P601.
B is wrong because this is not listed in the ARP but it could be correct if someone believes that high suppression pool level would result in RCIC inoperability/unavailability.
C is wrong because it is not listed in the ARP but could be correct if someone believes the condition makes RCIC inoperable.
D is wrong because it is listed in the immediate actions to verify the valve is closed and not open.
Technical
References:
ARP 04-1-02-1H13-P601 References to be provided to applicants during exam: None.
Learning Objective: (19) GLP-OPS-E5100.
Question Source: Bank #
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New X
Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b) 55.43
Examination Outline Cross-Reference Level RO 218000 ADS Tier # 2 Group # 1 Knowledge of the operational implications of K/A # 218000 K5.01 the following concepts as they apply to Rating 3.8 AUTOMATIC DEPRESSURIZATION SYSTEM
- ADS logic operation Question 41 The reactor has experienced a transient the following conditions currently exist:
- Reactor level has been less than Level 3 for 8 minutes
- Reactor level has been less than Level 1 for 5 minutes
- All ECCS equipment has responded as designed
- Drywell pressure is 0.5 psig and is rising at 0.1 psig per minute.
Based on these conditions, the Automatic Depressurization System relief valves:
A. have opened.
B. will open when drywell pressure reaches 1.39 psig C. will open 105 seconds after drywell pressure reaches 1.39 psig.
D. will open in 4.2 minutes.
Answer: D I like this question better as it is more operationally focused.
Explanation:
Input from the high drywell pressure channel is automatically bypassed if Reactor level stays
< -150.3 for 9.2 minutes. This condition assumes a LOCA outside the Drywell with degraded high pressure injection systems, and thus takes override action to initiate ADS to recover RPV level.
\
Technical
References:
GLP-OPS-E2202 References to be provided to applicants during exam: None Learning Objective: GLP-OPS-E2202 Describe the signals and setpoints for the initiation of the ADS System for both automatic and manual initiation. (15.0)
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 223002 PCIS/Nuclear Steam Supply Shutoff Tier # 2 Group # 1 Ability to manually operate and/or monitor K/A # 223002 - A4.01 in the control room: valve closures Rating 3.6 Question 42 What combination of NSSSS manual initiation pushbuttons would result in an isolation of MSIVs ONLY?
A. Division 1 and Division 2 B. Division 1 and Division 4 C. Division 2 and Division 3 D. Division 2 and Division 4 Answer: A Explanation:
A is correct because either 1 and 2 or 3 and 4 will give you a MSIV isolation.
B is wrong because this would give you a MSIV closure and a Div 1 NSSSS, Containment, Drywell, and Auxiliary building isolation.
C is wrong because this would give you a MSIV closure and a Div 2 NSSSS, Containment, Drywell, and Auxiliary building isolation.
D is wrong because should create a half isolation signal.
Technical
References:
GLP-OPS-M701, Containment and Drywell Instrumentation and Control System - M71, Rev 11 p.56 References to be provided to applicants during exam: None.
Learning Objective: State/identify the location(s) from which the Containment & Drywell Instrumentation & Control System isolation signals can be initiated. (8.2)
Describe the logic arrangements which actuate the isolation logics listed in Objective 7. (9)
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(6)
Examination Outline Cross-Reference Level RO 239002 SRVs Tier # 2 Group # 1 Knowledge of RELIEF/SAFETY VALVES K/A # 239002 K4.01 design feature(s) and/or interlocks which Rating 3.9 provide for the following: Insures that only one or two safety/relief valves reopen following the initial portion of a reactor isolation event (LLS logic): Plant-Specific Question 43 The plant is at rated power when the MSIVs close causing a reactor scrama reactor isolation occurs. Reactor pressure reaches 1120 psig resulting in mMultiple SRVs cycling initially lift, Formatted: Highlight then all SRVs close.
Following the initial transient, the SRVs would be expected to automatically maintain reactor pressure between: When pressure subsequently rises, only ____(1)_____ should lift when pressure reaches (2) . psig.
- (2) Formatted: Indent: Left: 0.63", No bullets or A. 926 and 1033 psig.F051D 1103 numbering B. 936 and 1073 psig.F051D 1033 C. 946 and 1113 psig.F051B 1103 D. 1013 and 1113 psig.F051B 1033 Answer: B Explanation:
Low-Low Set initiates automatically when RPV pressure reaches SRV F051Ds normal lift setpoint of 1103 psig.
Once initiated, six SRVs are capable of operating in the Low-Low Set mode with the following adjusted opening and closing setpoints: One SRV, F051D, lifts at 1033 psig and blows down to 926 psig. A second SRV, F051B, lifts at 1073 psig and blows down to 936 psig.
Technical
References:
GLP-OPS-E2202 References to be provided to applicants during exam:
Learning Objective: GLP-OPS-E2202 For each mode of operation of the SRVs, state/identify the number of valves which open and the associated opening setpoints. (11.2)
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 259002 Reactor Water Level Control Tier # 2 Group # 1 Knowledge of the effect that a loss or K/A # 259002 - K6.08 malfunction of the following will have on the Rating 3.5 REACTOR WATER LEVEL CONTROL SYSTEM: Reactor water level input Question 44 If the plant is in single element mode with automatic level channel selection mode, and the controlling level channel fails high the DFCS will de-select the failed channel and select A. the upset range channel irrespective of the magnitude.
B. an intermediate value from the remaining narrow range and upset range channels.
C. the highest value from the remaining narrow range and upset range channels.
D. the lowest value from the remaining narrow range and upset range channels.
Answer: B Explanation:
A is wrong because this will happen only if the upset channel is the intermediate value.
B is correct because this is design of the system.
C is wrong because the system is designed to select the intermediate value.
D is wrong because the system is designed to select the intermediate value.
Technical
References:
GLP-OPS-C3400, DIGITAL FEEDWATER CONTROL SYSTEM (DFCS) - C34, Rev 12 References to be provided to applicants during exam: None.
Learning Objective: State/identify the Level Control Subsystems response to failure of one or more Narrow Range level control channels when in the Automatic Level Channel Selection Mode. (3.6).
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X
10CFR Part 55 Content: 55.41(b)(7)
Examination Outline Cross-Reference Level RO 261000 SGTS Tier # 2 Group # 1 Knowledge of the effect that a loss or K/A # 261000 K3.02 malfunction of the STANDBY GAS Rating 3.6 TREATMENT SYSTEM will have on following:
Off-site release rate Question 45 Procedure 04-1-01-T48-1, Standby Gas Treatment, contains a caution to prevent an automatic start of SBGT if painting in the Auxiliary Building. This is because paint fumes in the SBGT System can:
A. result in a fire due to the electric heater in the system.
B. plug the HEPA filters and reduce system flowrates.
C. reduce the efficiency of the charcoal adsorber leading to increased off-site release rates.
D. render the demister inoperable and subsequent fouling of the charcoal.
Answer: C Explanation:
The presence of a volatile organic substance (e.g. painting) in the SBGT system reduces the efficiency of the adsorber material leading to an increased release rate of radioactive particles to the environment.
Technical
References:
GLP-OPS-T4801 References to be provided to applicants during exam: None Learning Objective: GLP-OPS-T4801 State/identify the design bases of the Standby Gas Treatment System. (2.0)
Question Source: Bank #
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New X Question History: Last NRC No Exam Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X
10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 262001 AC Electrical Distribution Tier # 2 Group # 1 Ability to predict and/or monitor changes in K/A # 262001 - A1.03 parameters associated with operating the Rating 2.9 A.C. ELECTRICAL DISTRIBUTION controls including: Bus voltage Question 46 A degraded voltage on the DIV 1 and DIV 3 ESF buses results in bus voltages to be at 3600 volts for 7 seconds. Following the transient, the status of the DIV 1 and DIV 3 EDGs would be______.
A. Both EDGs running B. Neither EDG running C. DIV 1 EDG running and DIV 3 EDG NOT running D. DIV 1 EDG NOT running and DIV 3 EDG running Answer: B Explanation:
A is wrong because neither of the diesel would start.
For the DIV 1 diesel there is a 9 second time delay between 2912 volts and 3744 volts before the DIV 1 diesel starts.
For the DIV 3 diesel there is a 4 second time delay between 3045 and 3660 volts for the diesel to start. This start sequence has to be coincident with a LOCA signal. If there is no LOCA signal present coincident with the 4 second time delay then there is a 5 minute time delay until DIV 3 diesel starts.
B is correct because of the explanation in A C is wrong because see above D is wrong because see above Technical
References:
GLP-OPS-R2100.12, LOAD SHEDDING & SEQUENCING SYSTEM AND ESF AC POWER DISTRIBUTION SYSTEM - R21, Rev 12, p.19 GLP-OPS-P8100, HIGH PRESSURE CORE SPRAY (HPCS) DIESEL GENERATOR SYSTEM - P81, Rev 14, p. 40 References to be provided to applicants during exam: None.
Learning Objective: Discuss the interrelationships of the following systems with the HPCS Diesel Generator System: (18).
State/identify the signals and setpoints that will produce a Bus Undervoltage signal to LSS Shed System and the actions associated with each signal. (12)
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7)
Examination Outline Cross-Reference Level RO 262001 AC Electrical Distribution Tier # 2 Group # 1 Knowledge of the effect that a loss or K/A # 262001 K3.02 malfunction of the A.C. ELECTRICAL Rating 3.8 DISTRIBUTION will have on following:
Emergency generators Question 47 The plant is at rated power when a grid disturbance causes the voltage on buses 15AA and 16AB to drop in a step change to a sustained value of 3700 volts at time T=0. The associated incoming offsite bus feeder breakers open at time T= ____(1)____ and Tthe emergency diesel generator will receives an automatic start signal _____atseconds later.
time T= ____(2)____.
(1) (2)
A. 0.5 0.5 B. 0.5 1.0 C. 9.0 9.0 D. 9.0 9.5 Answer: D Explanation:
With bus voltage < 3744 volts, after a 9 second delay, the offsite bus feeder breakers open.
This activates the < 2912 volt timer, which, after 0.5 seconds sends a start signal to the associated diesel generator.
The 0.5 second opening of incoming breakers is credible because this is the time delay of the 70% timer. The start of the EDG simultaneous with breaker opening is credible, since this is what happens with the 70% timer.
Technical
References:
GLP-OPS-R2100 GLP-OPS-P7500 References to be provided to applicants during exam: None Learning Objective: GLP-OPS-P7500 Describe the automatic initiation logic for a Standby Diesel Generator for degraded power conditions and a Loss of Coolant Accident (LOCA).
(8.0)
GLP-OPS-R2100 State/identify the signals and setpoints that will produce a bus undervoltage signal to LSS shed system and the actions associated with each signal. (12)
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 262002 UPS (AC/DC) Tier # 2 Group # 1 Knowledge of the effect that a loss or K/A # 262002 - K6.02 malfunction of the following will have on the Rating 2.8 UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.): D.C. electrical power Question 48 If DC power is lost to an ESF inverter the static switch on the inverter will (a)? When the condition is corrected the static switch for the ESF inverter will automatically/manually be transferred back to the DC source?
A. only transfer if the IN SYNC light is illuminated automatically B. transfer regardless of IN SYNC light automatically C. only transfer if the IN SYNC light is illuminated manually D. transfer regardless of IN SYNC light manually Answer: D Explanation:
Excerpts from the training material:
- If the inverter output and the AC source are out of sync the static switch will not transfer. An out of sync transfer would cause major damage to the inverter and potential damage to the loads.
- If the DC source has low or no voltage IN SYNC is not required, most of the inverters will auto transfer.
- Upon a return of the normal source the BOP Inverters (except 1Y99) will automatically (-2 seconds of normal power) return to the normal power supply.
- The ESF Inverters and 1Y99 have had the auto return feature disabled internally on the inverter. (Each inverter has a switch to enable or disable this feature.) If DC power is lost to an ESF Inverter, the DC input circuit breaker trips on undervoltage.
A is wrong because a loss of DC would result in no voltage so the IN SYNC light would not come into play. Also, only the BOP buses will automatically transfer when normal DC power
is restored.
B is wrong because ESF inverters have the automatic return to normal supply disabled.
C is wrong because the inverter will transfer regardless of the IN SYNC light since the inverter has zero voltage.
D is correct because the transfer will happen regardless of the IN SYNC light and there is no automatic return to the normal source for ESF inverters.
Technical
References:
GLP-OPS-L6200, Static Inverter System - L62, Rev 10 References to be provided to applicants during exam: None.
Learning Objective: Describe the automatic feature of the Static Inverter System that transfers power sources and which inverters have the following features: ( 4)
Inverter to alternate power source ( 4.1)
Alternate power source to inverter upon return of inverter power (4.2)
Describe the operation of the Static Inverter using: (5)
Static Switch- Auto (5.1)
Static Switch- Manual (5.2)
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7)
Examination Outline Cross-Reference Level RO 263000 DC Electrical Distribution Tier # 2 Group # 1 Ability to (a) predict the impacts of the K/A # 263000 A2.01 following on the D.C. ELECTRICAL Rating 2.8 DISTRIBUTION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Grounds Question 49 It is important to promptly eliminate a ground on a DC bus because:
A. one ground can cause unpredictable spurious operation of equipment.
B. subsequent grounds will be masked, and multiple grounds can produce unanalyzed results.
C. a shock hazard exists at the grounded equipment.
D. a fire hazard exists due to excessive current flow at the ground location.
Answer: B Explanation:
Failure to promptly eliminate a single ground could mask subsequent grounds. Multiple grounds could lead to unpredictable spurious operation of equipment, inoperable equipment, unanalyzed loads on batteries, or unanalyzed equipment failure modes that could be expected to occur during harsh environments associated with accident conditions. The first ground does not produce adverse effects because there is no path for current flow with one ground in an ungrounded system.
Technical
References:
GLP-OPS-L1100 References to be provided to applicants during exam:
Learning Objective: GLP-OPS-L1100 State/identify the purpose/function of Gr ound Detection Systems. (5.3)
Question Source: Bank #
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New X
Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO DC Electrical Distribution Tier # 2 Group # 1 Knowledge of electrical power supplies to K/A # 263000 - K2.01 the following: Major D.C. loads Rating 3.1 Question 50 The Diesel Generator 11 __________ is(are) powered from the ESF DC distribution system.
A. generator field flash B. fuel oil booster pump C. lube oil pump D. air compressors Answer: A Comments: The relay panel also receives AC power. This question is ok with changes made.
Explanation:
B is wrong because it is powered from a BOP bus C is wrong because it is AC powered D is wrong because it is AC powered Technical
References:
04-1-01-L11-1_123 and GLP-OPS-P7500_024-1 References to be provided to applicants during exam: None.
Learning Objective: GLP-OPS-L1100. (8) State/identify the major loads of the Plant DC System Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X
Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 264000 EDGs Tier # 2 Group # 1 Knowledge of the effect that a loss or K/A # 264000 K3.02 malfunction of the EMERGENCY Rating 3.9 GENERATORS (DIESEL/JET) will have on following: A.C. electrical distribution Question 51 The voltage regulator on a standby diesel generator has a malfunction that limits its maximum voltage to 3900 VAC.
In this condition, the output breaker can be closed:
- 1. automatically.
- 2. remotely (P864) when paralleling with an offsite source.
- 3. remotely (P864) when energizing a dead bus.
A. 1, 2 and 3 B. 2 and 3 only C. 3 only D. 1 only Answer: C Explanation: DG at rated voltage is an interlock for closing the breaker automatically or remotely when paralleling. It is not an interlock when all offsite feeder breakers are open Technical
References:
Table 4 of GLP-OPS-P7500 References to be provided to applicants during exam: None Learning Objective: GLP-OPS-P7500 State/identify the start sequence and interlocks involved in starting the Standby Diesel Generator System during the following conditions: (15.0) LOCA signal present (15.1) LOP/BUV signal present (15.2) Local Emergency Start signal present (15.3) Normal operations (15.4)
Question Source: Bank #
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New X
Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 300000 Instrument Air Tier # 2 Group # 1 Knowledge of the connections and/or cause K/A # 300000 - K1.04 effect relationships between INSTRUMENT Rating 2.8 AIR SYSTEM and the following: Cooling water to compressor Question 52 Normal cooling water for the instrument air compressors is provided by _______:
A. Plant Service Water.
B. Standby Service Water.
C. Component Cooling Water.
D. Turbine Building Cooling Water.
Answer: D Explanation:
A is wrong because it does not provide cooling but is plausible if the applicant believes that since the system is not safety related it would come from a non-safety related source.
B is wrong because this is the emergency source of water.
C is wrong because it does not provide cooling but is plausible if the applicant doesnt realize that component cooling water only provides cooling to potentially radioactive sources.
D is correct because it is the normally aligned source of cooling water.
Technical
References:
Document where the correct answer is found References to be provided to applicants during exam: None.
Learning Objective: Document learning objective if possible.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7)
Examination Outline Cross-Reference Level RO 400000 Component Cooling Water Tier # 2 Group # 1 Knowledge of electrical power supplies to the K/A # 40000 K2.02 following: CCW valves Rating 2.9 Question 53 The power supply to P42-F116, CCW RTN FRM DW is:
A. Bus 11DA B. LCC 16BB3 C. MCC17B01 D. MCC 15B11 Answer: D Explanation:
A is wrong because the DA shows that this is a 125V DC bus, and the valve is powered from 480 VAC.
B is wrong because the valve motor is < 50 hp. It is powered from an MCC (not an LCC). C is the power supply to the B CCW pump.
C is wrong because MCC 17B11 is a division III bus which does not power any CCW components.
Technical
References:
04-1-01-P42-1, CCW SOI GLP OPS-R2700, Normal AC Power Distribution System References to be provided to applicants during exam:
Learning Objective: GLP OPS-R2700 Identify components using the GGNS numbering system. (16)
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental
Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 201001 CRD Hydraulic Tier # 2 Group # 2 Knowledge of the physical connections K/A # 201001 - K1.01 and/or cause-effect relationships between Rating 3.1 CONTROL ROD DRIVE HYDRAULIC SYSTEM and the following: Condensate System Question 54 During normal operation, the suction pressure for the control rod drive pumps is from the
________. On a loss of the condensate system the suction of the control rod drive pumps is from the _________.
A. condensate pumps; CST B. condensate booster pumps; CST C. condensate pumps; demineralized water system D. condensate booster pumps; demineralized water system Answer: A Explanation:
A is correct B is wrong because the suctions from the condensate pumps C is wrong because the service water system does not feed the CRD system but is plausible because the water system is very clean and could be used in the CRD system D is wrong because of B and C Technical
References:
GLP-OPS-C111A References to be provided to applicants during exam: None.
Learning Objective: 11.1 Describe the interrelationships between the CRWST and the CRD Hydraulic System.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X
Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(6)
Examination Outline Cross-Reference Level RO 201003 Control Rod and Drive Mechanism Tier # 2 Group # 2 Knowledge of the operational implications of K/A # 201003 K5.01 the following concepts as they apply to Rating 2.6 CONTROL ROD AND DRIVE MECHANISM
- Hydraulics Question 55 In order to continuously withdraw a CRDM, the collet fingers are continuously held:
A. outward by hydraulic pressure B. outward by mechanical interaction with the index tube C. inward by hydraulic pressure D. inward by mechanical interaction with the index tube Answer: A Explanation: The collet fingers are initially opened by mechanical interaction with the index tube by a slight insertion, but they are subsequently held open by hydraulic pressure applied to a piston. The fingers move outward to unlatch the rod, they move inward to latch the rod and prevent outward movement.
Technical
References:
GLP-OPS-C111A_008-1 References to be provided to applicants during exam:
Learning Objective:GLP-OPS-C111A Describe in detail the following control rod operations:
(10.0) o Control rod insertion (10.1) o Control rod withdrawal (10.2)
GLP-OPS-C111AB Describe the following CRD Mechanism evolutions and operations: (5)
Operation of the collet locking mechanism. (5.3)
Question Source: Bank #
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 201005 RCIS Tier # 2 Group # 2 Ability to predict and/or monitor changes in K/A # 201005 - A1.01 parameters associated with operating the Rating 3.2 ROD CONTROL AND INFORMATION SYSTEM (RCIS) controls including: First stage shell pressure/turbine load: BWR-6 Question 56 If the plant is at 65% power with 1 bypass valve full open the Rod Control and Information System will allow control rods to be withdrawn a maximum of (a) notch/notches at a time.
A. 1 B. 2 C. 4 D. 12 Answer: C Explanation:
Above the High Power Setpoint (62% RTP), rod withdrawal is limited to two notches by the RWL. For instance, if reactor power is 63% with the bypass valves open, RC&lS will interpret the lower first stage turbine pressure as a lower reactor power. If RC&lS sees a first stage turbine pressure equivalent to 60%, it will allow rods to be withdrawn four notches (below the HPSP) instead of the limit of two notches as required above the HPSP.
Technical
References:
GLP-OPS-C1102, Rod Control and Information Systems (RC&IS), Revision 6, p. 20 References to be provided to applicants during exam: None.
Learning Objective: Describe the reason for restricting Main Steam Bypass Valve operation when at power. (7.2)
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X
10CFR Part 55 Content: 55.41(b)(6)
Examination Outline Cross-Reference Level RO 204000 RWCU Tier # 2 Group # 2 Ability to manually operate and/or monitor in K/A # 204000 A4.02 the control room: Valve controllers Rating 2.9 Question 57 Reactor pressure is 150 psig during a plant heatup with RWCU blowdown to the main condenser maintaining RPV level.
Opening 1G33-F003, RWCU SYS BLWDN FLO CONT valve too far can result in the need to subsequently:
A. replace RWCU pump seals.
B. re-open 1G33-F004.
C. backwash and precoat the F/Ds.
D. re-open the primary containment isolation group 8 valves.
Answer: B Explanation:
Opening F033 will cause non-regenerative HX outlet temp to rise because of a loss of cooling flow in the regenerative HX. If it reaches 140°F, 1GG33-F004 closes and the RWCU pumps trip.
A is wrong because at this reactor pressure the RWCU pumps are in the POST-Pump mode.
RWCU will isolate at 140° which is well within design of RWCU seals.
C is wrong because the demineralizer hold pump is designed to auto start as flow drops to prevent loss of precoat.
D is wrong because this activity should not result in any condition that causes the group 8 isolation.
Technical
References:
04-1-02-1H13-P680-11A-C6 ARI, RWCU FLTR DMIN INL TEMP HI 140°F.
04-1-01-G33-1, Reactor Water Cleanup, caution on top of page 55.
References to be provided to applicants during exam: None Learning Objective: GLP-OPS-G3336 Describe any interlocks, trips, or automatic actions associated with the following Reactor Water Cleanup System components: (8.0) System
Isolation Valves (8.6)
Concerning SOI 04-1-01-G33-1: (10.0)
Identify the reasons for the precautions, limitations, cautions, warnings and notes given in the SOI. (10.2)
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 219000 RHR/LPCI: Torus/Pool Cooling Tier # 2 Mode Group # 2 K/A # 219000 - 2.1.28 Knowledge of the purpose and function of Rating 4.1 major system components and controls Question 58 The suppression pool cooling mode of RHR is designed to limit suppression pool temperature to a maximum of (a) during normal conditions to ensure suppression pool temperature does not exceed 185oF under accident conditions. This is accomplished in the suppression pool cooling mode by regulating flow through the A. 95oF; F024A/B, RHR A/B test return to suppression pool B. 95oF; F048A/B, heat exchanger A/B bypass valve C. 110oF; F024A/B, RHR A/B test return to suppression pool D. 110oF; F048A/B, heat exchanger A/B bypass valve Answer: B Explanation:
A is wrong because the valve listed is not throttled in the suppression pool cooling mode B is correct because this is the temperature listed in the training manual and the only valve that should be throttled in SOI 04-1-01-E12, Residual Heat removal System.
C is wrong because this temperature is not listed in the training manual but plausible since it is listed in the EOP (EP-2). Also this is the incorrect valve for regulating temperature D is wrong because see answer C.
Technical
References:
GLP-OPS-E1200, Residual Heat Removal (RHR) System - E12 SOI 04-1-01-E12, Residual Heat removal System References to be provided to applicants during exam: None.
Learning Objective: State/identify the purpose/function of the Suppression Pool Cooling mode of RHR (1.4)
Question Source: Bank #
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7)
Examination Outline Cross-Reference Level RO 219000 RHR/LPCI: Torus/Pool Cooling Tier # 2 Mode Group # 2 K/A # 219000 - 2.1.28 Knowledge of the purpose and function of Rating 4.1 major system components and controls Question 58 The suppression pool cooling mode of RHR is designed to limit suppression pool temperature to a maximum of (a) during normal conditions to ensure suppression pool temperature does not exceed 185oF under accident conditions. This is accomplished in the suppression pool cooling mode by regulating flow through the A. 95oF; F024A/B, RHR A/B test return to suppression pool B. 95oF; F048A/B, heat exchanger A/B bypass valve C. 110oF; F024A/B, RHR A/B test return to suppression pool D. 110oF; F048A/B, heat exchanger A/B bypass valve Answer: B Explanation:
A is wrong because the valve listed is not throttled in the suppression pool cooling mode B is correct because this is the temperature listed in the training manual and the only valve that should be throttled in SOI 04-1-01-E12, Residual Heat removal System.
C is wrong because this temperature is not listed in the training manual but plausible since it is listed in the EOP (EP-2). Also this is the incorrect valve for regulating temperature D is wrong because see answer C.
Technical
References:
GLP-OPS-E1200, Residual Heat Removal (RHR) System - E12 SOI 04-1-01-E12, Residual Heat removal System References to be provided to applicants during exam: None.
Learning Objective: State/identify the purpose/function of the Suppression Pool Cooling mode of RHR (1.4)
Question Source: Bank #
(note changes; attach parent) Modified Bank #
New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7)
Examination Outline Cross-Reference Level RO 219000 RHR/LPCI: Torus/Pool Cooling Tier # 2 Mode Group # 2 K/A # 219000 - 2.1.28 Knowledge of the purpose and function of Rating 4.1 major system components and controls Question 58 The suppression pool cooling mode of RHR is designed to limit suppression pool temperature to a maximum of (a) during normal conditions to ensure suppression pool temperature does not exceed 185oF under accident conditions. This is accomplished in the suppression pool cooling mode by regulating flow through the A. 95oF; F024A/B, RHR A/B test return to suppression pool B. 95oF; F048A/B, heat exchanger A/B bypass valve C. 110oF; F024A/B, RHR A/B test return to suppression pool D. 110oF; F048A/B, heat exchanger A/B bypass valve Answer: B Explanation:
A is wrong because the valve listed is not throttled in the suppression pool cooling mode B is correct because this is the temperature listed in the training manual and the only valve that should be throttled in SOI 04-1-01-E12, Residual Heat removal System.
C is wrong because this temperature is not listed in the training manual but plausible since it is listed in the EOP (EP-2). Also this is the incorrect valve for regulating temperature D is wrong because see answer C.
Technical
References:
GLP-OPS-E1200, Residual Heat Removal (RHR) System - E12 SOI 04-1-01-E12, Residual Heat removal System References to be provided to applicants during exam: None.
Learning Objective: State/identify the purpose/function of the Suppression Pool Cooling mode of RHR (1.4)
Question Source: Bank #
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7)
Examination Outline Cross-Reference Level RO 233000 Fuel Pool Cooling/Cleanup Tier # 2 Group # 2 Knowledge of FUEL POOL COOLING K/A # 233000 - K4.08 AND CLEAN-UP design feature(s) and/or Rating 2.6 interlocks which provide for the following:
Pool cooling during loss of cooling accident:
BWR-6 Question 60 Both fuel pool cooling water pumps are running when a LOCA signal is received. Both pumps will trip and A. both will be automatically restarted by the sequencer.
B. neither pump can be restarted until the LOCA signal is reset.
C. either pump can be manually restarted immediately.
D. either pump can be manually restarted following load shedding and sequencing.
Answer: D Explanation:
A is wrong because the pumps are not listed as loads that automatically sequence on.
B is wrong because the LOCA signal does not lock out the pumps.
C is wrong because the LSS signal cant be in or the pump will trip and the signal will be in while loads are sequencing.
D is correct because see A, but they are listed as loads that are not locked out and can be manually started.
Technical
References:
04-1-01-R21-1, Load Shedding and Sequencing System GLP-OPS-R2100, Load Shedding and Sequencing System and ESF AC Power Distribution System References to be provided to applicants during exam: None.
Learning Objective: (17) Describe the sequencing of Loads on a LOCA signal.
Question Source: Bank #
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7), 55.41(b)(8)
Examination Outline Cross-Reference Level RO 245000 Main Turbine Gen. / Aux Tier # 2 Group # 2 Knowledge of the effect that a loss or K/A # 245000 K6.08 malfunction of the following will have on the Rating 3.0 MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS : Main steam Question 61 One SRV failing open at rated power will result in generator megawatts __(1)____ and feedwater injection temperature __(2)__.
(1) (2)
A. lowering lowering B. lowering remaining constant C. remaining constant lowering D. remaining constant remaining constant Answer: A Explanation:
The SRV operation lowers steam pressure, EHC responds by lowering turbine steam flow.
The lowered turbine steam flow leads to reduced extraction steam flow, which lowers feedwater temperature.
Technical
References:
ARI 04-01-02-1H13-P601-19A-A5, SRV/ADS VLV OPEN/DISCH LINE PRESS HI References to be provided to applicants during exam: None Learning Objective: GLP-OPS-E2202 Identify the system interrelationships between each of the following systems and the ADS/SRV System: (19.0)
Nuclear Boiler B13/21 (19.2)
Question Source: Bank #
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO Reactor Feedwater Tier # 2 Group # 2 Knowledge of the effect that a loss or K/A # 259001 - K6.07 malfunction of the following will have on the Rating 3.8 REACTOR FEEDWATER SYSTEM:
Reactor water level control system Question 62 The plant is operating at steady state with reactor power at 90% when steam flow transmitter N34-N030A fails upscale. Following this failure, the following occurs:
- STEAM FLOW FAIL light begins flashing
- DFCS TROUBLE alarm annunciates on H13-P680 Based on this malfunction; A. Feedflow will increase and the reactor will scram on high water level.
B. Feedflow will decrease and the reactor will scram on low water level.
C. DFCS will automatically shift to single element control and feedflow remains fairly constant.
D. DFCS automatically deselects N34-N030A, remains in 3-element control, and feedflow remains fairly constant.
Answer: C Explanation:
A is wrong; feedflow will remain fairly constant because the DFCS shifts to single element control and maintains reactor water level at setpoint.
B is wrong; feedflow will remain fairly constant because the DFCS shifts to single element control and maintains reactor water level at setpoint.
C is correct; feedflow will remain fairly constant because the DFCS shifts to single element control and maintains reactor water level at setpoint.
D is wrong because DFCS automatically shifts to single element control.
Technical
References:
GLP-OPS-C3400.12, page 31.
References to be provided to applicants during exam: None.
Learning Objective: C3400.12 - 5.3 - State/identify the consequences of a steam flow channel failure.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b).4 55.43.5
Examination Outline Cross-Reference Level RO 268000 Radwaste Tier # 2 Group # 2 Knowledge of the effect that a loss or K/A # 268000 K3.04 malfunction of the RADWASTE will have on Rating 2.7 following: Drain sumps Question 63 Isolating the floor drain collection tank and both waste surge tanks will result in not being able to pump down the ______.
A. Turbine Building West Equipment Drain Sump B. HPCS Room Sump C. Auxiliary Building North Equipment Drain Sump D. Turbine Building North Chemical Waste Sump Answer: B Explanation:
Of these sumps, only B pumps to these tanks (dirty RW). A and C discharge to the Equipment collection drain tanks (clean RW). D discharges to the Miscellaneous Chemical Waste Receiver Tank Technical
References:
GLP-OPS-G1718.08 References to be provided to applicants during exam: None Learning Objective: State/identify the purpose/function and location of the Equipment Drain Collector Tanks, Floor Drain Collector Tank and Waste Surge Tanks. (3.0) Discuss the water quality of the various inputs to the tanks from operating the plant and the importance of segregation of the waste water. (3.3)
Question Source: Bank #
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO 27100 Offgas Tier # 2 Group # 2 Knowledge of the physical connections K/A # 271000 - K1.07 and/or cause-effect relationships between Rating 2.7 OFFGAS SYSTEM and the following: Plant air systems Question 64 The air used in the Offgas System is supplied by the _______ Air System and on a loss of air F061A/B, Offgas Condenser Drain Valves, fail _______.
A. Instrument; open B. Instrument; close C. Service; open D. Service; close Answer: A Explanation:
A is correct.
B is wrong because the valves fail open.
C is wrong because Instrument Air is used.
D is wrong because Insrument Air is used and the valves fail open.
Technical
References:
GLP-OPS-N6465, References to be provided to applicants during exam: None.
Learning Objective: (8.4) State/identify the location from where the Offgas Condenser Drain Valves, F016A/B, can be operated (14.2) Discuss the interrelationships of the Instrument Air System with the Offgas/Vault Refrigeration System Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis
10CFR Part 55 Content: 55.41(b)(13)
Examination Outline Cross-Reference Level RO 290003 Control Room HVAC Tier # 2 Group # 2 Ability to monitor automatic operations of the K/A # 290003 A3.02 CONTROL ROOM HVAC including: Rating 3.0 Initiation/failure of fire protection system Question 65 The operating control room air conditioning unit will automatically shut down if:
A. smoke is detected in the return ductwork from the control room.
B. high-high radiation is sensed in the outside air intake duct.
C. high-high temperature is sensed on an operating fresh air unit filter train.
D. a Freon leak is detected in the control room air conditioner cooling coils.
Answer: A Explanation:
Upon sensing the presence of smoke in the return ductwork from the Control Room or in the fresh air intake duct, the smoke detector causes the following actions to take place:
- The operating air conditioning unit shuts down.
- The operating air conditioning unit inlet and outlet dampers close.
- The fire detection system sounds the fire alarm.
B is wrong because this isolates the control room but does not trip the air conditioning unit.
C is wrong because this shuts down the running control room standby fresh air units.
D is wrong because the Freon leak alarm has no automatic actions associated with it..
Technical
References:
ARI 04-S-02-SH13-P855-1A-B4, CONT RM HVAC FREON HI GLP-OPS-Z5100 References to be provided to applicants during exam: None Learning Objective: GLP-OPS-Z5100 Discuss the interrelationships of the Plant Fire Protection System with the Control Room HVAC System. (13.6)
Question Source: Bank #
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO Conduct of Operations Tier # 3 Group #
Knowledge of shift turnover practices. K/A # 2.1.3 Rating 3.0 Question 66 What is the MAXIMUM time a shift can be one less than the minimum required by regulations? Can the exception to minimum staffing requirements be invoked during shift change for a crewperson being late or absent?
A. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; Yes B. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; No C. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; Yes D. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; No Answer: D Explanation:
A is wrong because the time is less than the maximum allowed but is a logical time to get an onsite replacement.
B is wrong because of answer A. The conduct of operations procedure does not allow for this exception for tardiness or absence. The second part of the question is correct.
C is wrong because this is the correct time, but the conduct of operations procedure does not all for this exception D is correct because this is the maximum time allowed and the correct interpretation of the conduct of operations procedure.
Technical
References:
EN-OP-115, Conduct of Operations , Rev. 14, Attachment 9.3 References to be provided to applicants during exam: None.
Learning Objective: N/A Question Source: Bank #
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(10)
Examination Outline Cross-Reference Level RO Conduct of Operations Tier # 3 Group #
Knowledge of the refueling process. K/A # 2.1.41 Rating 2.8 Question 67 When removing the reactor vessel head, reactor vessel level should be maintained using the
________ range.
A. Fuel Zone B. Wide C. Upset D. Shutdown Answer: D Explanation:
The target is to maintain vessel level approximately one foot below the vessel flange (196 to 200 on shutdown range). Level too high would result in water spilling over the flange. Level too low increases dose in the refueling area. Only the Shutdown Range measures level this high.
Technical
References:
03-1-01-5 Refueling, Step 5.15.15 GFIG-OPS-B2101, Figure 2 References to be provided to applicants during exam:
Learning Objective: GLP-OPS-B2101 State/identify the indicating ranges of the following RPV Water Level Instruments: (5.0) o Reactor Water Level Narrow Range (5.1) o Reactor Water Level Wide Range (5.2) o Reactor Water Level Shutdown Range (5.3) o Reactor Water Level Upset Range (5.4) o Reactor Water Level Fuel Zone Range (5.5)
Question Source: Bank #
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New X
Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level RO Conduct of Operations Tier # 3 Group #
Knowledge of conduct of operations K/A # 2.1.1 requirements. Rating 3.8 Question 68 Per ENP-OP-115, Conduct of Operations, which of the following tasks is allowed to be performed without a procedure in hand?
A. Adjusting circulating water blowdown flow.
B. Initiating SLC during an ATWS.
C. Resetting a full scram.
D. Rotating CRD pumps.
Answer: A Explanation:
A is correct because the activity is specified in Attachment 9.3 of ENP-OP-115, Conduct of Operations B is wrong because it is not listed in the procedure.
C is wrong because it is not listed in the procedure but resetting a half scram is.
D is wrong because it is not listed in the procedure.
Technical
References:
.3 of ENP-OP-115, Conduct of Operations, Rev 14 References to be provided to applicants during exam: None.
Learning Objective: N/A.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(10)
55.43 Examination Outline Cross-Reference Level RO Conduct of Operations Tier # 3 Group #
Knowledge of the process used to track K/A # 2.1.43 inoperable alarms. Rating 3.0 Question 69 A single length of red tape placed diagonally across an alarm window means the annunciator:
A. card has been removed.
B. is not functioning properly due to faulty alarm circuitry.
C. inputs have been verified to cause a nuisance alarm.
D. deficiency affects technical specification operability.
Answer: B Explanation:
A is wrong because a removed card is identified by two lengths of red tape placed to form an X.
C is wrong because an annunciator with input bypassed due to nuisance alarm is designated with two vertical lengths of red tape.
D is wrong because this condition leads to further documentation but not a window marking Technical
References:
02-S-01-25 Deficient Equipment Identification, sections 6.2 and 6.3.
References to be provided to applicants during exam:
Learning Objective:
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7)
55.43 Examination Outline Cross-Reference Level RO Equipment Control Tier # 3 Group #
Ability to determine operability and/or K/A # 2.2.37 availability of safety related equipment Rating 3.6 Question 70 Can systems be considered operable if a system fails to meet acceptance criteria between required performances of the surveillance?
Can systems be considered operable when auxiliary equipment required to be operable is inoperable, but the system can still meet its surveillance requirement acceptance criteria?
A. Yes/Yes B. Yes/No C. No/Yes D. No/No Answer: D Explanation:
A is wrong because SR 3.0.1 clearly defines that failure can to meet a SR can happen anytime and if so the LCO is no longer met. Also, the second question tests the definition of OPERABLE/OPERABILITY and the answer does not meet this definition.
B is wrong because of the first half of A.
C is wrong because of the second half A.
D is correct because it meets SR 3.0.1 and the definition of operability.
Technical
References:
Technical Specifications SR 3.0.1 and Technical Specification definition of operability References to be provided to applicants during exam: None.
Learning Objective: N/A Question Source: Bank #
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(10)
Examination Outline Cross-Reference Level RO Equipment Control Tier # 3 Group #
Ability to track Technical Specification limiting K/A # 2.2.23 conditions for operations. Rating 3.1 Question 71 A valve is re-positioned to satisfy the requirements of a technical specification required action and is documented on an eSOMS LCOTR.
This valve would be identified with a ______ tag.
A. No B. Danger C. Test & Maintenance D. Caution Answer: D Explanation:
A no tag identifies components that cannot be tagged but require positioning when hanging and removing a tagout.
There is no LCOTR tag.
A test & maintenance tag makes the tagout holder accountable for the components status.
Technical
References:
02-S-01-17, Control of Limiting Conditions for Operation References to be provided to applicants during exam:
Learning Objective:
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7)
55.43 Examination Outline Cross-Reference Level RO Radiation Control Tier # 3 Group #
Ability to use radiation monitoring systems, K/A # 2.3.5 such as fixed radiation monitors and alarms, Rating 2.9 portable survey instruments, personnel monitoring equipment, etc.
Question 72 Taking the mode switch from Operate to Off on an Area Radiation Monitor causes the FAIL SAFE green light to extinguish and the A. LOCAL red light to illuminate.
B. HIGH ALARM/RESET pushbutton to illuminate.
C. AREA RAD PNL P845 TROUBLE annunciator on 1H13-P601 to annunciate.
D. AREA RADIATION MONITORING SYSTEM FAILURE annunciator on 1H13-P845 to annunciate.
Answer: A Explanation:
A is correct because this will come in as specified in training material B is wrong because this will not come in but plausible if an applicant believes turning the monitor off doesnt fully remove power and you need to reset the ARM also.
C is wrong because this is not the correct annunciator or panel but plausible since both are close D is wrong because this is the incorrect annunciator panel Technical
References:
GLP-OPS-D1721, Radiation Monitoring System, Rev 14, p.21 References to be provided to applicants during exam: None.
Learning Objective: Document learning objective if possible.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis
10CFR Part 55 Content: 55.41(b)(11)
Examination Outline Cross-Reference Level RO Radiation Control Tier # 3 Group #
Knowledge of radiation monitoring systems, K/A # 2.3.15 such as fixed radiation monitors and alarms, Rating 2.9 portable survey instruments, personnel monitoring equipment, etc.
Question 73 The Area Radiation monitors utilize _________ detectors.
A. Geiger-Mueller tube B. ion chamber C. scintillation D. solid state alpha and beta scintillation Answer: A Explanation:
The main steamline radiation monitoring subsystem uses ion chambers.
The process liquid monitoring subsystem uses scintillation detectors.
Ventilation release rad monitors use solid state alpha detectors and beta scintillation detectors.
Technical
References:
GLP-OPS-D1721, p 19 of 68 References to be provided to applicants during exam: None Learning Objective: GLP-OPS-D1721 State/identify the types of detectors used for the following radiation monitors: (5) Area Radiation Monitors (5.1)
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X
Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(7) 55.43 Examination Outline Cross-Reference Level RO Emergency Procedures/Plan Tier # 3 Group #
Knowledge of EOP entry conditions and K/A # 2.4.1 immediate action steps. Rating 4.6 Question 74 Which of the following is an entry condition to EP-2, RPV Control, and what is the purpose of the immediate action that follows?
A. Suppression pool temperature above 95oF, maintain a sufficient heat sink B. Drywell pressure above 1.23 psig, ensure reactor is shutdown C. Drywell temperature above 135oF, protect equipment in the containment D. Containment temperature above 95oF, maintain containment integrity Answer: B Explanation:
A is wrong because it is not an entry condition for EP-2 B is correct because it is an entry condition and the immediate action is to ensure the reactor has scrammed C is wrong because it is not an entry condition for EP-2 D is correct because it is not an entry condition for EP-2 Technical
References:
EP-2, RPV Control References to be provided to applicants during exam: None.
Learning Objective: Document learning objective if possible.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental
Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(10) 55.43
Examination Outline Cross-Reference Level RO Emergency Procedures/Plan Tier # 3 Group #
Knowledge of EOP implementation hierarchy K/A # 2.4.16 and coordination with other support Rating 3.5 procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines.
Question 75 A reactor scram has been automatically initiated due to high drywell pressure.
According to Procedure 02-S-01-40, EP Technical Bases, Reactor Scram ONEP, 05-01-02-I-1 should be executed:
A. concurrently with EP-2.
B. prior to entering EP-2.
C. only after drywell pressure is less than 1.23 psig.
D. only after exiting the emergency procedures.
Answer: A.
Explanation:
According to the referenced procedure, ONEP 05-1-02-1-1should be entered and executed concurrently with EP-2.
Technical
References:
02-S-01-40, EP Technical Bases, Revision 004 References to be provided to applicants during exam: None Learning Objective:
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b)(10) 55.43
Examination Outline Cross-Reference Level SRO 295021 Loss of Shutdown Cooling Tier # 1 Group # 1 Ability to determine and/or interpret the K/A # 295021 - AA2.04 following as they apply to LOSS OF Rating 3.6 SHUTDOWN COOLING: Reactor water temperature Question 76 The plant is in Mode 4 and flooding up when a spurious Group 3 isolation occurs due to low reactor water level. Thirty minutes has elapsed and maintenance is unable to reset the isolation. Reactor water temperature has risen to 205°F. Primary and secondary containments are intact.
What is the current emergency classification for this event? What is the maximum time to make the initial notification to the NRC?
A. Unusual Event; 15 minutes B. Unusual Event; 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. Alert; 15 minutes D. Alert; 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Answer: B Explanation:
A is wrong because the classification is correct since this is an unplanned event and RCS temperature is greater than 200°F but the time is incorrect.
B is correct because of A.
C is wrong because an alert would only be necessary if 200°F had been exceeded for greater than 60 minutes.
D is wrong because of C.
Technical
References:
10-S-01-1, Activation of the Emergency Plan, Rev 122, Attachment I, page 7 10-S-01-6, Notification of Offsite Agencies and Plant On-Call Emergency Personnel, Rev 50, Note under Step 6.1.1.d References to be provided to applicants during exam: 10-S-01-1, Activation of the Emergency Plan, Rev 122 Attachment I (all pages)
Learning Objective: Document learning objective if possible.
Question Source: Bank #
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New X Question History: Last NRC Exam No
Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b) 55.43(b)(5)
Examination Outline Cross-Reference Level SRO 295026 Suppression Pool High Water Temp. Tier # 1 Group # 1 Ability to determine and/or interpret the K/A # 295026 EA1.03 following as they apply to SUPPRESSION Rating 3.9 POOL HIGH WATER TEMPERATURE:
Temperature Monitoring Question 77
- The plant is in MODE 2.
- RCIC testing is in progress in accordance with SR 3.5.3.3.
- SR 3.5.3.3 was successfully performed 93 days ago.
- Suppression pool average temperature is 97°F.
- No other testing is in progress.
- A risk assessment has not been performed
- LCOs 3.5.3.1 and 3.6.2.1 are provided.
Technical Specifications will allow the plant to enter MODE 1:
A. only after the RCIC testing is completed satisfactorily and suppression pool temperature is lowered to < 95°F.
B. only after suppression pool average temperature is lowered to < 95°F but the RCIC testing can still be in progress.
C. with current suppression pool temperature only if RCIC testing is still in progress during the MODE change.
D. with current suppression pool temperature only if the RCIC testing is completed satisfactorily.
Answer: C Explanation:
LCO 3.6.2.1 Actions A and B require the plant to reduce THERMAL POWER to < 1%, which will require a MODE change from MODE 1 to MODE 2. Thus, 3.0.4.a will not allow MODE 1 entry with the LCO not met.
C conditions meet LCO 3.6.2. LCO 3.5.3 is met because SR 3.5.3.3 is still within the frequency limits of SR 3.0.2.
A is wrong because the SR 3.5.3.3 is still within the frequency limits of SR 3.0.2.
B is wrong. With RCIC testing is in progress, the LCO is met at the current suppression pool temperature.
D is wrong because the LCO is only met at the current suppression pool temperature if the testing is still in progress.
Technical
References:
References to be provided to applicants during exam: LCOs 3.5.3.1 and 3.6.2.1 Learning Objective:
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.43(b)(2)
Examination Outline Cross-Reference Level SRO 295027 High Containment Temperature Tier # 1 Group # 1 Ability to determine and/or interpret the K/A # 295027 - EA2.04 following as they apply to HIGH Rating 3.7 CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY): Containment radiation levels: Mark-III Question 78 A General Emergency has been declared.
Current conditions are:
- Reactor water level is -195 and stable
- Approximately 15% fuel damage
- Containment temperature is 180°F
- All containment radiation monitors are off scale high
- Large fission product inventory in Containment
- Radiation levels at the Site Boundary are at 25 mRem/hr TEDE
- Projected radiation levels at 8 miles are 2 mRem/hr TEDE What are the Protective Action Recommendations?
A. No evacuation of surrounding areas is required.
B. Evacuate a 2-mile radius and shelter 5 miles downwind.
C. Evacuate a 2-mile radius and 5 miles downwind; shelter the rest of the 10-mile EPZ; consider the use of Potassium Iodide.
D. Evacuate a 2-mile radius and 10 miles downwind; shelter the rest of the 10-mile EPZ; consider the use of Potassium Iodide.
Answer: D Explanation:
A is wrong because all GE requires PARs to be recommended.
B is wrong because sheltering is required for the entire EPZ and not just downwind C is wrong because the dose projection at 8 miles requires an extended PAR D is correct because the conditions presented require an extended PAR Technical
References:
10-S-01-1, Activation of the Emergency Plan, Rev 122, Step 6.1.6k References to be provided to applicants during exam: 10-S-01-1, Activation of the Emergency Plan, Rev 122, Step 6.1.6k only Learning Objective: Document learning objective if possible.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b) 55.43(b)(5)
Examination Outline Cross-Reference Level SRO 295028 High Drywell Temperature Tier # 1 Group # 1 Ability to determine and/or interpret the K/A # 295028 EA2.03 following as they apply to HIGH DRYWELL Rating 3.9 TEMPERATURE : Reactor water level Question 79 The crew has entered EP-2, RPV Control and EP-3, Containment Control. The following conditions exist:
- Drywell temperature 300°F.
- RPV pressure 10 psig.
- Suppression pool temperature is 190°F.
- Containment pressure 2 psig.
- Suppression pool 23 ft.
- Containment temperature 230°F
A. Enter Emergency Depressurization.
C. Initiate CTMT sprays.
D. Enter Steam Cooling Answer: B Explanation:
Conditions are in the possible boiling area of the RPVST. This + unstable level indication makes RPV level unknown, which requires transition to EP-5.
A is wrong because emergency depressurizations conditions are not met.
C is wrong because the given condition are in the unsafe to initiate region of the CSIPL D is wrong because this transition is based on level, which is unavailable.
Technical
References:
EP-2, EP-1, EP-5 References to be provided to applicants during exam Learning Objective:
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level SRO 295030 Low Suppression Pool Water Level Tier # 1 Group # 1 Knowledge of EOP mitigation strategies K/A # 295030 - 2.4.6 Rating 4.7 Question 80 The plant is operating at rated power when an earthquake occurs resulting in an unisolable suppression pool leak. Suppression pool level is 17.5 feet and lowering with all available methods of making up to the suppression pool in service in accordance with EP-3, Containment Control.
EP-4, Auxiliary Building Control is being implemented and sump pumps are maintaining Auxiliary Building Area water levels below their max safe values.
The CRS should enter EP-2, RPV Control A. and order an Emergency Depressurization using 8 ADS SRVs.
B. and order operators to reduce reactor pressure to the reduced band using the bypass valves.
C. and order an Emergency Depressurization using available EP-2, Table 3, Alternate Depressurization Systems.
D. when suppression pool level drops below 14.5 feet and order an Emergency Depressurization using available EP-2, Table 3, Alternate Depressurization Systems.
Answer: A Explanation:
A is correct because since all methods of suppression pool makeup are in service and level is still dropping you would have to transition to EP-2 and emergency depressurize.
B is wrong because you are unable to maintain suppression pool level SPL-9 directs you to ED.
C is wrong because step ED-4 in E-2 requires 8 ADS/SRVs to be open to ED. The only allowance to use Table 3 is contained in ED-5.
D is wrong because the procedure step has you transition before reaching 14.5 ft.
Understanding that level is dropping and continuing to drop after exhausting all makeup would meet the definition of before in this case. Also use of Table 3 systems is not allowed unless you meet the conditions in ED-5 Technical
References:
EP-2, RPV Control EP-3, Containment Control 02-S-01-40, EP Technical Bases, Rev 5 References to be provided to applicants during exam: None.
Learning Objective: Document learning objective if possible.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b) 55.43(b)(5)
Examination Outline Cross-Reference Level SRO 295037 SCRAM Condition Present Tier # 1 and Reactor Power Above APRM Downscale Group # 1 or Unknown K/A # 295037 EA2.07 Rating 4.2 Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN : Containment conditions/isolations Question 81 The plant was at rated power when an inadvertent closure of all MSIVs occurred. The following conditions exist:
- Multiple rods failed to insert.
- Reactor power is 3% and steady.
- Suppression pool temperature is 109°F and rising.
- RPV level is 40.
At this time, the SRO should:
A. exit level and pressure of EP-2A and enter emergency depressurization.
B. exit EP-2A and enter EP-3, Containment Control C. exit EP-2A, flood the CTMT, and enter SAPs.
D. remain in EP-2A and inject boron into the RPV with both SLC pumps.
Answer: D Explanation:
This action is specified in the POWER leg of EP-2A, ATWS RPV Control.
A would only be done if RPV level were low and cannot be restored.
B In this case, EP-2A must be continued until the reactor will remain subcritical in all conditions without boron.
C would only be done if RPV level were low, cannot be restored, and emergency depressurization has been performed.
D is continuing with the current procedure.
Technical
References:
EP-2A References to be provided to applicants during exam: None
Learning Objective:
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level SRO 700000 Generator Voltage and Electric Grid Tier # 1 Disturbances Group # 1 K/A # 700000 - AA2.04 Ability to determine and/or interpret the Rating 3.6 following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: VARs outside capability curve Question 82 The plant is operating at 900MWe with a power factor of 0.9 when alarm GEN HOT SPOT MONITOR comes in.
- RTD 1N41-TE-N156 reads 130°C
- RTD 1N41-TE-N158 reads 135°C What procedure should be entered by the CRS to combat this transient?
A. 03-1-01-2, Power Operations B. 05-1-02-I-4, Loss of AC Power C. 05-1-02-I-2, Turbine and Generator Trips D. 04-1-01-N40-1, Main Generator and Auxiliaries Answer: C Explanation:
A is wrong because this procedure is not entered during transients.
B is wrong because temperature is not indicative of grid instability by itself so there is no need to enter the procedure. If there were also voltage and frequency oscillations then this answer would be correct.
C is correct because according to the alarm response procedure whenever temperature is above 120°C than a generator trip is warranted.
D is wrong because this procedure should be entered if youre going to reduce MVARs to within the precautions listed in the 04-1-01-N40-1. This shouldnt be the conclusion since temperature is elevated also.
Technical
References:
04-1-02-1H13-P680, Alarm Response Instruction References to be provided to applicants during exam: Figure 15 Reactive Capability Curve from GFIG-OPS-N4151, Main Generator and Excitation System Figures, Rev. 5.
Learning Objective: Document learning objective if possible.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b) 55.43(b)(5)
Examination Outline Cross-Reference Level SRO 295002 Loss of Main Condenser Vac Tier # 1 Group # 2 Ability to take actions called for in the facility K/A # 295002 2.4.38 emergency plan, including supporting or acting Rating 4.4 as emergency coordinator if required.
Question 83 The plant was increasing power at 38% RTP when the following alarms occurred:
- HP CNDSR SHELL PRESS HI
- IP CNDSR SHELL PRESS HI
- LP CNDSR SHELL PRESS HI
- EOC/RPT A TRIP
- EOC/RPT B TRIP Reactor power is stable at 25% with turbine bypass valves controlling reactor pressure.
Based on these conditions, the CRS should now:
A. enter EP-2, RPV Control, and if power is reduced to < 4%, declare an Alert.
B. enter EP-2A, ATWS RPV Control, and if power is reduced to < 4%, declare a Site Area Emergency.
C. enter 05-1-02-I-2, Turbine and Generator Trips. If power is reduced to <4%, no E-Plan declaration is necessary.
D. enter 05-1-02-V-8, Loss of Condenser Vacuum. No E-Plan declaration is necessary.
Answer: A Explanation: the reactor should have scrammed because power was > 35.4% RTP when the turbine tripped. This is described by SA3 in the Classification flowcharts. EP-2 should be implemented because a reactor scram is required and all control rods are not at position 00.
Technical
References:
EN-OP-115, Conduct of Operations.
References to be provided to applicants during exam: Emergency Classification Flowcharts.
Learning Objective:
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level SRO 295011 High Containment Temp Tier # 1 Group # 2 Ability to determine and/or interpret the K/A # 295011 - AA2.03 following as they apply to HIGH Rating 3.2 CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY): Containment humidity: Mark-III Question 84 The plant is operating at full power when containment exhaust filter moisture high alarm is received.
- Containment temperature is 90°F.
- Suppression Pool temperature is 90°F
- Radiation levels are normal for the power level
A. EP-3, Containment Control B. EP-2, RPV Control C. 04-S-01-M41-1, Containment Cooling System D. 04-S-01-P64-1, Fire Protection Water System Answer: C Explanation:
A is wrong because containment temperature and radiation levels would be elevated if a steam leak were occurring.
B is wrong because radiation levels would be higher and sump runtimes would be increasing to deal with the higher leakage C is correct because the temperature are slightly elevated but not above any EOP entry conditions.
D is wrong because fire water is relatively cool water it would probably wouldnt add to the amount of vapor inside containment.
Technical
References:
04-1-02-1H13-P842, Alarm Response Instruction, Rev 22 References to be provided to applicants during exam: None.
Learning Objective: Document learning objective if possible.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b) 55.43(b)(5)
Examination Outline Cross-Reference Level SRO 295014 Inadvertent Reactivity Addition Tier # 1 Group # 2 Ability to recognize system parameters that K/A # 295014 2.2.42 are entry-level conditions for Technical Rating 4.6 Specifications.
Question 85 The plant is performing a plant startup following a refueling outage. At 1230, with the plant at 20% power, the reactor operator reports that a review of plant indications show that one hour previously,
- Jet pumps 5 and 6 indicated a step drop in flow.
- Total core flow indicated a step drop.
- Recirculation loop drive flow indicated a step increase.
- Reactor power dropped slightly.
At this time, the SRO should: (LCO 3.4.3 is provided)
A. declare LCO 3.4.3 action condition A entry at 1230.
B. declare LCO 3.4.3 action condition A entry at 1130.
C. consider LCO 3.4.3 met because SR 3.4.3.1 does not have to be performed at this power level.
D. consider LCO 3.4.3 met because the established patterns of jet pump flow have not been established following the refueling.
Answer: A Explanation:
These are symptoms of a rams head ejection. The definition of OPERABLE is not met. Two jet pumps are not capable of their specified safety related function.
B is wrong because action conditions apply from the time of discovery, not the time of occurrence.
C is wrong because the SR has to be met, even though it does not have to be performed.
D is wrong because the TS basis says During the initial weeks of operation under such conditions, while baselining new "established patterns," engineering judgment of the daily surveillance results is used to detect significant abnormalities which could indicate a jet pump failure.
Technical
References:
Technical Specifications 3.4.3, 3.4.3 bases, SR 3.0.1.
References to be provided to applicants during exam: LCO 3.4.3.
Learning Objective:
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level SRO 203000 RHR/LPCI: Injection Mode Tier # 2 Group # 1 Knowledge of EOP entry conditions and K/A # 203000 - 2.4.1 immediate action steps Rating 4.8 Question 86 The plant has scrammed from full power due to high drywell pressure.
1 control rod is not indicating full in Drywell Pressure is 4 psig Drywell Temperature is 150 F RPV pressure is 700 psig The CRS should A. enter EP-5, RPV Flooding.
B. remain in EP-2, RPV Control.
C. enter EP-3, Containment Control.
D. enter EP-2A, ATWS RPV Control.
Answer: A Explanation:
A is correct because all RPV level instruments, with exception of Fuel Zone, are only calibrated to 135oF. Based on this RPV level would not be able to be determined and the second override in EP-2 would need to be enforced. B and C are plausible if the applicant misses the override condition.
D is wrong because you wouldnt need to enter EP-2A since the reactor would be shutdown under all conditions without boron with one rod either stuck out or not indicating full in.
Technical
References:
GLP-OPS-B2101, RPV Level Instrumentation, Rev 7 References to be provided to applicants during exam: None.
Learning Objective: State/identify the calibration conditions for each of the following level instruments: (9.0) o Reactor Water Level Narrow Range (9.1) o Reactor Water Level Wide Range (9.2) o Reactor Water Level Shutdown Range (9.3) o Reactor Water Level Upset Range (9.4) o Reactor Water Level Fuel Zone Range (9.5)
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b) 55.43(b)(5)
Examination Outline Cross-Reference Level SRO 212000 RPS Tier # 2 Group # 1 Ability to (a) predict the impacts of the K/A # 212000 A2.02 following on the REACTOR PROTECTION Rating 3.9 SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: : RPS bus power supply failure Question 87 The plant is at rated power when P680 annunciator HCU TROUBLE is received. When the operator depresses the HCU FAULT pushbutton on the Operators Control Module, the following control rods have blinking red LEDs on the RC&IS display;
- 04-21
- 04-45
- 28-05
The SRO should direct the crew to:
A. Re-charge the affected HCUs in accordance with SOI 04-1-01-C11-1 Control Rod Drive Hydraulic System.
B. Transfer the A RPS bus to the alternate power source per ONEP 05-1-02-III-2, Loss of One or Both RPS buses.
C. Transfer the B RPS bus to the alternate power source per ONEP 05-1-02-III-2, Loss of One or Both RPS buses.
D. Dispatch an operator to the affected HCUs inside containment to determine the fault in accordance with ARI 04-1-02-1 H 13-P680-4A2-D4, HCU TROUBLE.
Answer: B Explanation:
These are symptoms of loss of RPS bus A.
Technical
References:
ONEP 05-1-02-III-2, Loss of One or Both RPS buses References to be provided to applicants during exam: None
Learning Objective:
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level SRO 215003 IRM Tier # 2 Group # 1 Ability to (a) predict the impacts of the K/A # 215003 - A2.05 following on the INTERMEDIATE RANGE Rating 3.5 MONITOR (IRM) SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Faulty or erratic operation of detectors/system Question 88 A plant startup is in progress with the reactor Mode Switch in STARTUP.
IRMs and APRMs have been verified to have proper overlap, all APRMs are off the downscale light, and all Mode 1 prerequisites have been met.
Inverter 1Y87 and its alternate power supply fail.
(1) Regarding TS 3.3.1.1, what is the required action?
(2) When is the Mode Switch allowed to be placed in RUN?
A. (1) Place the affected IRM channels in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(2) When directed by the Shift Manager in accordance with 03-1-01-1, Cold Shutdown to Generator Carrying Minimum Load.
B. (1) Be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(2) Only after either Inverter 1Y87 or its alternate power supply are returned to OPERABLE status.
C. (1) Place the affected IRM channels in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(2) Only after either Inverter 1Y87 or its alternate power supply are returned to OPERABLE status.
D. (1) Be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(2) When directed by the Shift Manager in accordance with 03-1-01-1, Cold Shutdown to Generator Carrying Minimum Load.
Answer: A Explanation:
A is correct because this power supply failure would only require entry into Condition A of TS 3.1.1. The action would already be taken so there would be 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to fix the inverter. The second part of the question tests application of TS 3.0.4. Since IRMs are not required in Mode 1 this would meet TS 3.0.4.a B is wrong because TS 3.3.1.1.H requires this only after you fail to meet the time requirements TS 3.3.1.1.A. Even though the action has been taken for A the time allowance still remains at 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> before you need to enter condition H.
C is wrong because you would not need to wait until the inverter is restored.
D is wrong because of the TS discussion in B.
Technical
References:
TS 3.3.1.1 References to be provided to applicants during exam: TS 3.3.1.1.
Learning Objective: Document learning objective if possible.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b) 55.43(b)(2)
Examination Outline Cross-Reference Level SRO 259002 Reactor Water Level Control Tier # 2 Group # 1 Ability to (a) predict the impacts of the K/A # 259002 A2.04 following on the REACTOR WATER LEVEL Rating 3.1 CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: RFP runout condition: Plant-Specific Question 89 The plant is at rated thermal power when the following alarms are received:
RFPT A ACT THR BRG WR HI RFPT A TRIP Shortly thereafter, RX LVL 40/32 HI/LO is received.
The plant stabilizes with the following conditions:
Reactor power - 80%
RFPT B speed - 5900 rpm The procedure that contains the actions to mitigate these conditions is::
A. ARI 04-1-02-1H13-P680-3A-A3, RX LVL 40/32 HI/LO, to mitigate the low reactor level.
B. ONEP 05-1-02-III-3, Reduction in Recirculation System Flow Rate, to mitigate the failure of the recirculation runback.
C. ONEP 05-1-02-V-7, Feedwater System Malfunctions, to mitigate RFPT B runout.
D. ARI 04-1-02-1H13-P680-2A-A2, RFPT A TRIP, to mitigate the low reactor level.
Answer: C Explanation:
RFPT B is at runout conditions and RX level is low. The mitigating actions are to lower reactor power to below 75% and ensure that RFPT speed is reduced to < 5850 rpm. Of these, only Feedwater System Malfunctions contains these instructions.
Technical
References:
ARI 04-1-02-1H13-P680-3A-A3, RX LVL 40/32 HI/LO ONEP 05-1-02-III-3, Reduction in Recirculation System Flow Rate ONEP 05-1-02-V-7, Feedwater System Malfunctions ARI 04-1-02-1H13-P680-2A-A2, RFPT A TRIP
References to be provided to applicants during exam: None Learning Objective: GLP-OPS-N2100 Describe the interrelationship(s) between the Feedwater System and the following: (28.0) Nuclear Boiler System, B21 (28.10)
Concerning SOI 04-1-01-N21-1: (29.0) Identify precautions, limitations, cautions, warnings and notes that apply to a given situation. (29.1)
List/identify the immediate operator actions for the following Off Normal Event Procedures:
(31.0) Feedwater System Malfunctions ONEP, 05-1-02-V-7 (31.2)
Given a copy of the above listed ONEPs and plant conditions, discuss the subsequent actions to be taken with regard to the Feedwater System. (32.0)
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level SRO 261000 SGTS Tier # 2 Group # 1 Ability to (a) predict the impacts of the K/A # 261000 - A2.07 following on the STANDBY GAS Rating 2.7 TREATMENT SYSTEM; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations: A.C. electrical failure Question 90 A seismic event has resulted in the following:
- Small break LOCA in the drywell
- Loss of offsite power with all diesels supplying power to their respective buses
- EP-2 has been entered Drywell pressure is 2.0 psig and stable Drywell temperature is 120°F and stable Reactor water level is stable in the normal band Fuel handling exhaust radiation at 4.2 mr/hr and stable Suppression pool temperature at 90°F and stable RCIC equipment area temperature at 150°F and stable At this point operators are required to transition to A. EP-3, Containment Control, and operate all available suppression pool cooling with RHR pumps not required for adequate core cooling.
B. EP-3, Containment Control, and defeat drywell cooling isolation interlocks using Attachment 10 of EP-1.
C. EP-4, Auxiliary Building Control, and verify standby gas treatment system is in service and all automatic isolations are complete.
D. EP-4, Auxiliary Building Control, and operate RCIC room coolers to lower temperature in the RCIC room.
Answer: C Explanation:
A is wrong because suppression pool temperature is higher than normal but does not exceed the 95°F in EP-3.
B is wrong because drywell temperature has not exceeded the temperature in EP-3.
C is correct because the setpoint has been exceeded in EP-4 D is wrong because the RCIC room temperature has not exceeded the temperature in EP-5
Technical
References:
EP-4, Auxiliary Building Control References to be provided to applicants during exam: None.
Learning Objective: Document learning objective if possible.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b) 55.43(b)(5)
Examination Outline Cross-Reference Level SRO 239001 Main and Reheat Steam Tier # 2 Group # 2 Knowledge of low power/shutdown K/A # 239001 2.4.9 implications in accident (e.g., loss of coolant Rating 4.2 accident or loss of residual heat removal) mitigation strategies.
Question 91 After being at rated power for 11 continuous months, the crew is performing a cooldown per 03-1-01-3B, Plant Shutdown to comply with LCO 3.5.1, ECCS - Operating.
- Required action condition D was entered 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago due to failure of the B RHR motor.
- Reactor water cleanup is isolated and not available.
- Shutdown cooling has been placed in service using A RHR and is supplementing the cooldown from operating the turbine bypass valves.
- Reactor pressure is 110 psig.
Then, the A RHR pump trips and cannot be restarted.
If no repairs are made, it will eventually be necessary to declare a(n) ___________ due to (1) (2)
A. NOUE Inability to reach operating mode within TS limits B. NOUE. Unplanned loss of decay heat removal capability with irradiated fuel in the RPV.
C. Alert. Inability to reach operating mode within TS limits D. Alert Unplanned loss of decay heat removal capability with irradiated fuel in the RPV.
Answer: A Explanation: ONEP 05-1-02-III-1, Inadequate Decay Heat Removal says (section 3.4) to place redundant loop in shutdown cooling (not available) or place ADHRS in service (cannot be done above 200°F). It will not be possible to place the plant in MODE 4 in this condition. Decay heat removal capability has not been lost because the turbine bypass system is still available.
Technical
References:
ONEP 05-1-02-III-1 Emergency Classification Flowcharts
References to be provided to applicants during exam: Emergency Classification Flowcharts and TS 3.5.1.
Learning Objective:
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level SRO 241000 Reactor/Turbine Pressure Tier # 2 Regulator Group # 2 K/A # 241000 - 2.1.25 Ability to interpret reference materials, Rating 4.2 such as graphs, curves, tables, etc.
Question 92 The plant is operating at full power when alarm TURB IPC CAB FAIL is received. Turbine control and bypass valves are operating normally for this power level. I&C personnel are sent to investigate and determine the internal power supply for IPC cabinet 1H13-P825-JC03 needs to be replaced.
Per EN-WM-100, Work Request (WR) Generation, Screening and Classification, what priority should be assigned to the work request A. Priority 1 B. Priority 2 C. Priority 3 D. Priority 4 Answer: B Explanation:
Since the power supply has failed it falls into corrective maintenance space. Since the component presents a risk to generation but the system is still operable, because turbine and bypass valves controls are less redundant, this work request should be screened as a priority
- 2. All other answers are plausible depending on how the applicant judges the risk of additional failures.
Technical
References:
Per EN-WM-100, Work Request (WR) Generation, Screening and Classification, Rev 9 References to be provided to applicants during exam: Per EN-WM-100, Work Request (WR) Generation, Screening and Classification, p. 1-13 and Attachment 9.1 Learning Objective: Document learning objective if possible.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X
10CFR Part 55 Content: 55.41(b) 55.43(b)(5)
Examination Outline Cross-Reference Level SRO 259001 Reactor Feedwater Tier # 2 Group # 2 Ability to (a) predict the impacts of the K/A # 259001 A2.04 following on the REACTOR FEEDWATER Rating 3.4 SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of extraction steam Question 93 The plant is at rated power when P680 alarm FW HTR 6B LVL HI is received. Motor-operated valve 1N36-F011B, FW HTR 6B EXT STM ISOL, is stroking closed.
The FIRST thing the SRO should direct the crew to do is:
A. re-open 1N36-F011B in accordance with ARI 04-1-02-1H13-P680-2A-A10, FW HTR 6B LVL HI.
B. initiate a reactor scram and enter ONEP 05-1-02-1-1, Reactor Scram.
C. reduce core flow at the maximum rate in accordance with ONEP 05-1-02-V-5, Loss of Feedwater Heating.
D. reduce core flow using the slow detent of reactor recirculation flow control in accordance with ONEP 05-1-02-V-5, Loss of Feedwater Heating.
Answer: C Explanation:
FW HTR 6B is a high pressure heater, so recirculation flow should be reduced rapidly per the note prior to step 2 of ONOP Loss of Feedwater Heating.
The note also says that the action should be taken when the isolation valve begins to close.
Control rods would only be inserted if the reduction in recirc flow resulted in being above the MEOD boundary line.
It may be possible to avoid a scram on this occurrence, so the procedures direct a power reduction.
Technical
References:
ONEP 05-1-02-V-5, Loss of Feedwater Heating References to be provided to applicants during exam:
Learning Objective:
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level SRO Conduct of Operations Tier # 3 Group #
Knowledge of refueling administrative K/A # 2.1.40 requirements Rating 3.9 Question 94 According to procedure 03-1-01-5, Refueling, Loads in excess of _______ pounds shall be prohibited from travel over fuel assemblies in the Spent Fuel OR Upper Containment Fuel Storage Pool Racks.
A. 975 B. 1060 C. 1140 D. 1220 Answer: C Explanation:
Precaution and limitation 2.8 of 03-1-01-5, Refueling, Rev 128 defines the maximum load allowed over fuel assemblies in the spent fuel pool.
2.8 Loads in excess of 1140 pounds Shall be prohibited from travel over Fuel assemblies in the Spent Fuel OR Upper Containment Fuel Storage Pool Racks.
Technical
References:
03-1-01-5, Refueling, Rev 128 References to be provided to applicants during exam: None.
Learning Objective: Document learning objective if possible.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b) 55.43(b)(7)
Examination Outline Cross-Reference Level SRO Conduct of Operations Tier # 3 Group #
Knowledge of RO duties in the control room K/A # 2.1.44 during fuel handling such as responding to Rating 3.8 alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.
Question 95 The plant is in MODE 5, applying the provisions of LCO 3.10.5, Single CRD Removal -
Refueling, to remove one CRD mechanism in a cell containing three fuel assemblies. CRD mechanism removal is in progress.
Then, alarm CONT ROD WITHDRAWAL BLOCK is received. The RO determines that the cause of the alarm is refueling platform near or over core and grapple loaded.
Technical specifications require the operators to immediately:
- 1. direct the maintenance crew to suspend the removal of the CRD mechanism.
- 2. insert a control rod withdrawal block.
- 3. direct the refueling platform operator to stop core alterations.
A. 1 only B. 1 and 2 only C. 2 and 3 only D. 1, 2, and 3.
Answer: D Explanation:
In this mode, the alarm signifies that the LCO was not met when the CRD removal began.
The control rod withdrawal block was not inserted. 1, 2, and 3 are all immediate actions that are required per TS 3.10.5. While a rod block is now present, action 3 will make the rod block clear, so it will be necessary to insert one.
Technical
References:
ARI 04-1-02-1H13-P680-4A2-C5, CONT ROD WITHDRAWAL BLOCK.
LCO 3.10.5 References to be provided to applicants during exam: None
Learning Objective:
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level SRO Equipment Control Tier # 3 Group #
Knowledge of the process for making K/A # 2.2.5 changes to procedures Rating 3.6 Question 96 Which of the following situations would be appropriate for issuing a Temporary Change Notice:
- 1. Equipment is out of service and a change is required to complete the work and return the equipment to service.
- 2. A change is required to implement a surveillance that is scheduled to be performed in 4 weeks.
- 3. A directive change is required to support an operability review.
A. 1 and 2 ONLY B. 1 and 3 ONLY C. 2 and 3 ONLY D. 1, 2, and 3 Answer: B Explanation:
From 01-S-02-3, Authors Guide, Rev 121, Note 6.4.1, directive change is required to implement a surveillance and the work is scheduled in the near future (i.e., two weeks).
Since the time frame is 4 weeks in (2) then it should be issued as a direct revision instead of a TCN. This makes any answer containing (2) incorrect.
Technical
References:
01-S-02-3, Authors Guide, Rev 121, Note 6.4.1 References to be provided to applicants during exam: None.
Learning Objective: Document learning objective if possible.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis
10CFR Part 55 Content: 55.41(b) 55.43
Examination Outline Cross-Reference Level SRO Equipment Control Tier # 3 Group #
Knowledge of the process for controlling K/A # 2.2.11 temporary design changes. Rating 3.3 Question 97 When an approved procedure installs electrical jumpers for testing purposes, Temporary Modification Tags should be applied whenever the jumpers:
A. must be independently verified.
B. are out of line of sight.
C. are NOT documented in the Asset Suite (AS).
D. will be in place for greater than one hour.
Answer: B Explanation:
P&L 7 of EN-DC-136, Temporary Modifications, contains this requirement.
A is wrong because this process (testing) is excluded from T-MOD requirements when restoration is documented and verified through independent verification and the jumper remains in line of sight.
C is wrong because testing jumpers are not documented in the Asset Suite.
D is wrong because there are no time requirements. The jumpers do not need a T-mod tag unless they are left unattended.
Technical
References:
EN-DC-136, Temporary Modifications References to be provided to applicants during exam:
Learning Objective:
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis
10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level SRO Radiation Control Tier # 3 Group #
Ability to control radiation releases. K/A # 2.3.11 Rating 4.3 Question 98 (1) What is the governing procedure to process liquid radioactive waste discharges?
(2) What is the governing procedure to process solid radioactive waste discharges?
A. (1) 01-S-08-11, Radioactive Discharge Controls (2) EN-RP-121, Radioactive Material Control B. (1) EN-RP-121, Radioactive Material Control (2) 01-S-08-11, Radioactive Discharge Controls C. (1) 01-S-08-11, Radioactive Discharge Controls (2) 01-S-08-11, Radioactive Discharge Controls D. (1) EN-RP-121, Radioactive Material Control (2) EN-RP-121, Radioactive Material Control Answer: A Explanation:
A is correct because 01-S-08-11, control liquid and gaseous releases. Step 6.2.1 of 01-S-08-11 refers to EN-RP-121 for processing solid waste.
B is wrong of A.
C is wrong of A.
D is wrong of A.
Technical
References:
01-S-08-11, Radioactive Discharge Controls EN-RP-121, Radioactive Material Control References to be provided to applicants during exam: None.
Learning Objective: Document learning objective if possible.
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis
10CFR Part 55 Content: 55.41(b)(13) 55.43(b)(5)
Examination Outline Cross-Reference Level SRO Emergency Procedures / Plan Tier # 3 Group #
Ability to recognize abnormal indications for K/A # 2.4.4 system operating parameters that are entry- Rating 4.7 level conditions for emergency and abnormal operating procedures.
Question 99 The plant was at rated power when all four channels of MSL PIPE TNL TEMP HI alarms are received:
Concurrently,
- A main steam line isolation occurs.
- A reactor scram occurs with all control rods fully inserted.
Shortly thereafter, alarm RX LVL 3 (+10") LO is received.
- SP temperature is 89°F and rising.
- SP Level is 18.5 ft. and rising.
Then, the CRS should enter:
- 2. EP-3, Containment Control
- 3. EP-4, Auxiliary Building Control A. 1 only B. 1 and 2 only C. 1 and 3 only D. 1, 2, and 3 Answer: C Explanation:
At least one entry conditions is met for EP-2 (RV level < 11.4 In).
At least one entry condition is met for EP-4 (MSL Pipe Tunnel Temp > 185°F)
No entry conditions for EP-3 are met.
Technical
References:
EP-2, 3, and 4
References to be provided to applicants during exam:
Learning Objective:
Question Source: Bank #
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New X Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental Comprehensive/Analysis X 10CFR Part 55 Content: 55.41(b)(7) 55.43
Examination Outline Cross-Reference Level SRO Emergency Procedures/Plan Tier # 3 Group #
Knowledge of fire protection procedures K/A # 2.4.46 Rating 4.2 Question 100 A fire is reported to the control room at the Independent Spent Fuel Storage Facility (ISFSI) at 12:00 pm. How many fire brigade members are required to be sent?
The fire brigade leader reports back at 12:25 pm that the fire is not extinguished. Which Emergency Action Level has been exceeded?
A. 3 Unusual Event B. 3 Alert C. 5 Unusual Event D. 5 Alert Answer: C Explanation:
A is wrong because the 5 man team is responsible for responding to the ISFSI. A UE is required by the emergency plan B is wrong because a 5 man team is required and an Alert would not be C is correct because a 5 man team is required by procedure and an unusual event would be required because the ISFSI is not safety related and there has not been a report of an damage D is wrong because the classification is incorrect Technical
References:
10-S-03-2, Response to Fires, Rev 25. Step 6.2.3.f 10-S-01-1, Activation of the Emergency Plan, Rev. 122 References to be provided to applicants during exam: None.
Learning Objective: Document learning objective if possible.
Question Source: Bank #
(note changes; attach parent) Modified Bank #
New X
Question History: Last NRC Exam No Question Cognitive Level: Memory/Fundamental X Comprehensive/Analysis 10CFR Part 55 Content: 55.41(b) 55.43(b)(5)