ML20149K697
| ML20149K697 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 04/10/2020 |
| From: | Exelon Generation Co |
| To: | NRC/RGN-III/DRS/OLB |
| Roach G | |
| Shared Package | |
| ML19121A187 | List: |
| References | |
| Download: ML20149K697 (112) | |
Text
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 76 ID: 2122925 Points: 1.00 Unit 1 is at 100% power.
Unit 2 is in Mode 5.
The Unit 2 125Vdc Battery Discharge Test and fuel moves are in progress.
The Unit 2 125Vdc Alternate Battery has been on-line for 6 days to support the Battery Discharge Test.
The Test Director has just informed the shift that the Unit 2 125Vdc Battery has failed to meet the Performance Acceptance Criteria of the Battery Discharge Test. Electrical Maintenance has estimated a 10-day repair time to replace cells and retest the battery.
What effect does this have on the operating and shutdown Units?
Reference provided.
A. Unit 1 will enter a 7-day LCO.
Unit 2 may continue Fuel Moves.
B. Unit 1 has NO operational concerns.
Unit 2 must stop Fuel Moves immediately.
C. Unit 1 will enter a 7-day LCO.
Unit 2 must stop Fuel Moves immediately.
D. Unit 1 has no operational concerns.
Unit 2 may continue Fuel Moves.
Answer: A QC-OPS-EXAM-ILT Page: 1 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation Answer Explanation: For Unit 1, TS 3.8.4 Condition E applies as 125Vdc Division 2 is inoperable. The Alternate Battery is already on line satisfying Required Action C.1. Entering a 7 day LCO satisfies C.2 For Unit 2, TS LCO 3.8.5 is satisfied as only one 125 VDC electrical power subsystem is required for a shutdown Unit. Therefore, fuel moves can continue.
Distractor 1: Plausible because a shutdown Unit requires only one 125Vdc subsystem operable. Incorrect because an operating Unit requires both 125Vdc subsystems and fuel moves may continue as a shutdown Unit only requires one operable 125 VDC electrical power subsystem.
Distractor 2: Plausible because Unit 1 is required to enter a 7 day LCO.
Incorrect because Unit 2 may continue fuel moves.
Distractor 3: Plausible because Unit 2 can continue fuel moves. Incorrect because Unit 1 must enter a 7 day LCO.
Reference:
Quad Cities Technical Specifications sections 3.8.4 and 3.8.5 Reference provided during examination: Technical Specification sections 3.8.4 and 3.8.5 Cognitive level (High/Memory): Higher Level (RO/SRO): SRO Tier: 1 Group: 1 Question Source: New Question History: n/a 10 CFR Part 55 Content: 41.10/43.2/45.13 SRO Justification: Can the question be answered solely by knowing the following?
1-hour TS/TRM Actions: No The LCO/TRM information listed above the line: No The TS safety limits: No KA: 295004 Partial or Total Loss of DC Power, Generic K/A 2.2.36; Ability to analize the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations. (SRO= 4.2)
Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 3 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 77 ID: 2125026 Points: 1.00 Unit 1 was at 100% power when supply breaker 125 Vdc Bus 1A-2 trips and a spurious Main Turbine trip occurs.
What action will the Unit Supervisor direct FIRST?
A. Transfer control power for Bus 11 to the reserve feed.
B. Transfer control power for Bus 15 to the reserve feed.
C. Locally trip the Main Generator and Exciter field breakers.
D. Transfer annunciator power to the reserve feed.
Answer: C QC-OPS-EXAM-ILT Page: 4 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation QC-OPS-EXAM-ILT Page: 5 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 With a loss of 1A-2, the Main Gen Field Breaker control power is lost. Remote control of the field breaker at the 901-8 panel would be ineffective and the breaker must be opened locally. Opening of the Man Gen Field Breaker after a generator trip is required to prevent damage to generator components from overcurrent. As the generator speed drops, AVR will increase the current to the field to try to maintain voltage resulting in an excessive current draw to the generator field.
Distractor 1: Plausible because the transferring Bus 11 control power is an action in QOA 6900-02. Incorrect because Bus 11 and any loads can be tripped locally if necessary. No impending equipment damage will occur as a result of the loss of control power.
Distractor 2: Plausible because the transferring Bus 15 control power is an action in QOA 6900-02. Incorrect because Bus 15 loads can be tripped locally if necessary. No impending equipment damage will occur as a result of the loss of control power.
Distractor 3: Plausible because the transferring annunciator control power is an action in QOA 6900-02. Incorrect because a failure to promptly trip the main generator and exciter field breakers may damage the Turbine-Generator system.
Reference:
QOA 6900-02 Rev. 25 Reference provided during examination: None Cognitive level (High/Memory): Higher Level (RO/SRO): SRO Tier: 1 Group: 1 Question Source: New Question History: n/a 10 CFR Part 55 Content: 41.10/43.5/45.13 SRO Justification: Can the question be answered solely by knowing the following?
Systems knowledge (i.e., how the system works, flowpath, logic, component location): No Immediate operator actions: No Entry conditions for AOPs or plant parameters that require direct entry into major EOPs: No The purpose, overall sequence of events, or overall mitigative strategy of a procedure: No QC-OPS-EXAM-ILT Page: 6 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 KA: 295005 Main Turbine Generator Trip, Generic K/A 2.4.35; Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects. (SRO= 4.0)
Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 8 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 78 ID: 2122948 Points: 1.00 Unit 1 was operating at 100% power when a rupture occurred in the TBCCW system.
- Reactor Mode Switch in SHUTDOWN
- Reactor pressure is 900 psig and steady
- Several control rods did NOT insert due to a hydraulic ATWS
- Reactor power is 5% and lowering at 0.25% per minute
- Annunciator 912-1 E-2, TURB BLDG COOLING WATER HIGH TEMP, is in alarm
- Annunciator 912-1 D-2, TURB BLDG COOLING WATER LOW PRESS, is in alarm The Unit Supervisor is directing the ANSO to remove equipment cooled by TBCCW from operation per QCOA 3800-03, TOTAL FAILURE OF THE TBCCW SYSTEM.
Which of the following TBCCW system loads WILL be removed LAST?
A. Circulating Water Pumps B. CRD Pump C. EHC Pumps D. Reactor Feed Pumps Answer: B QC-OPS-EXAM-ILT Page: 9 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation QC-OPS-EXAM-ILT Page: 10 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 The question poses plant conditions where the only equipment the procedure allows to remain in service are the CRD pumps. QCOA 3800-03, Loss of TBCCW, directs all loads cooled by TBCCW to be tripped. The CRD pump cannot be secured since all control rods are NOT inserted to position 00.
Distractor 1: Plausible because the examinee may determine the Main Condenser is needed as a heat sink and delay removing the Circ Water Pumps from service. Incorrect because RPV pressure can be controlled by relief valves, HPCI, RCIC, etc.
Distractor 2: Plausible because the examinee may determine the Main Turbine and BPVs are needed as a heat sink and delay removing the EHC Pumps from service. Incorrect because RPV pressure can be controlled by relief valves, HPCI, RCIC, etc.
Distractor 3: Plausible because the examinee may determine RFPs are essential for RPV level control and delay removing them from service.
Incorrect because HPCI, RCIC, and SSMP can provide adequate RPV makeup for the given plant conditions.
Reference:
QCOA 3800-03 Rev.4 Reference provided during examination: None Cognitive level (High/Memory): Higher Level (RO/SRO): SRO Tier: 1 Group: 1 Question Source: Quad Cities Exam Bank (QDC.ILT.1244454)
Question History: ILT 14-1 Cert Exam 10 CFR Part 55 Content: 41.10/43.5/45.13 SRO Justification: Can the question be answered solely by knowing systems knowledge, i.e., how the system works, flowpath, logic, component location?
No Can the question be answered solely by knowing immediate operator actions?
No Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs? No Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure? No KA: 295018 Partial or Complete Loss of CCW, AA2.03; Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS QC-OPS-EXAM-ILT Page: 11 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 OF COMPONENT COOLING WATER: Cause for partial or complete loss.
(SRO= 3.5)
Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 79 ID: 2132387 Points: 1.00 Unit 1 is operating at 100% rated power.
The U1NSO reports that the following Scram Discharge Instrument Volume valves have just changed to CLOSED indication.
An EO reports that there is an Instrument Air leak on the air operators and both valves are fully closed and will NOT open.
Per LCO 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves, how many Scram Discharge Volume lines must be isolated?
A. One line ONLY must be isolated within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.(Condition B)
B. Two lines must be isolated within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.(Condition B)
C. One line ONLY must be isolated within 7 days.(Condition A)
D. Two lines must be isolated within 7 days.(Condition A)
Answer: D QC-OPS-EXAM-ILT Page: 14 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation QC-OPS-EXAM-ILT Page: 15 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 When one SDV vent or drain valve is inoperable in one or more lines, the line must be isolated to contain the reactor coolant during a scram.
The ACTIONS Table is modified by a Note indicating that a separate Condition entry is allowed for each SDV vent and drain line. This is acceptable, since the Required Actions for each Condition provide appropriate compensatory actions for each inoperable SDV line. Complying with the Required Actions may allow for continued operation, and subsequent inoperable SDV lines are governed by subsequent Condition entry and application of associated Required Actions.
Since each of the inoperable valves are in separate lines, each line must be isolated within 7 days in accordance with LCO 3.1.8 Condition A.
Distractor 1 is incorrect: The two valves that are inoperable are in separate lines. Plausible if the note indicating separate condition entry for each line is not recalled. Or if assumed that both valves are in the same line, or if the entire pathway is one line.
Distractor 2 is incorrect: The required time to isolate both lines is 7 days.
Plausible if assumed that both valves are in the same line, or if the entire pathway is one line.
Distractor 3 is incorrect: The two valves that are inoperable are in separate lines. Plausible if a separate condition entry for each line is not recalled.
Reference:
T.S. 3.1.8 Amendment 199/195, P&ID M-41 Sh 3 Reference provided during examination: Embedded clip of TS LCO 3.1.8 Conditions 'A' and 'B'.
Cognitive level: Higher Level (RO/SRO): SRO Tier: 1 Group: 1 SRO Justification: 10 CFR 55.43(b)(2)
Facility operating limitations in the TS.
Can question be answered solely by knowing ? 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TS/TRM Action? NO Can question be answered solely by knowing the LCO/TRM information listed above-the-line? NO Can question be answered solely by knowing the TS Safety Limits? NO Question Source: Quad Cities Exam Bank (78)
Question History: 2014 Quad Cities ILT NRC Exam QC-OPS-EXAM-ILT Page: 16 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 KA: 295019 Partial or Complete loss of Instrument Air, AA2.02; Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LISS OF INSTRUMENT AIR: Status of safety-related instrument air system loads (see AK2.1 - AK2.19). (SRO= 3.7)
Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 80 ID: 2121302 Points: 1.00 A failure results in a high RPV pressure transient.
Per the Technical Specification Bases for LCO 3.3.1.1. Reactor Protection System (RPS) Instrumentation, which scram signal is conservatively assumed to maintain RPV pressure within the RPV Pressure Safety Limit?
A. APRM Fixed Neutron Flux-High scram setpoint.
B. MSIV Closure scram setpoint.
C. RPV Low Level scram setpoint.
D. Turbine Control Valve Closure scram setpoint.
Answer: A QC-OPS-EXAM-ILT Page: 19 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation QC-OPS-EXAM-ILT Page: 20 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Per Technical Specification B3.3.1.1, Reactor Vessel Steam Dome Pressure-High it is assumed in the Reactor overpressurization analysis, the reactor scram occurs on Average Power Range Monitor Fixed Neutron Flux-High signal and not the Reactor Vessel Steam Dome Pressure-High or the Main Steam Line Isolation Valve-Closure signals.
Distractor 1: Plausible because Main Steam Isolation Valve closure would cause a major pressure transient and the setpoint is listed in the Tech Spec bases discussion but incorrect because APRM High Flux is stated as the function that initiates a scram for transients that result in a pressure increase.
Distractor 2: Plausible because RPV water level will drop when voids collapse but incorrect because Reactor Vessel Steam Dome Pressure High is stated as the function that initiates a scram for transients that result in a pressure increase.
Distractor 3: Plausible because turbine control valves will close to control pressure and also could fast close on low oil pressure(assuming an oil leak is the failure), but incorrect because Reactor Vessel Steam Dome Pressure High is stated as the function that initiates a scram for transients that result in a pressure increase.
Reference:
Quad Cities Technical Specifications Bases B3.3.1.1 Revision 4.
Reference provided during examination: None.
Cognitive level (High/Memory): Memory Level (RO/SRO): SRO Tier: 1 Group: 1 Question Source: New Question History: n/a 10 CFR Part 55 Content: (41.10 / 43.2 / 45.13)
SRO Justification: Can the question be answered solely by knowing the following?
1-hour TS/TRM Actions: No The LCO/TRM information listed above the line: No The TS safety limits: No KA: 295025 High Reactor Pressure, EA2.02; Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE: Reactor power. (SRO= 4.2)
Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 22 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 23 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 81 ID: 2122984 Points: 1.00 The reactor was at 15% power when a manual scram was inserted.
- Reactor power is 12% and lowering
- Manual ARI failed to actuate
- RPV water level is +25 inches and slowly lowering
- RPV pressure is 900 psig
- SBLC Tank level is 82% and lowering What is the HIGHEST PRIORITY action to be directed in QGA 101, RPV CONTROL (ATWS)?
A. Bypass Low RPV water level MSIV isolations per QCOP 0250-02, BYPASSING MSIV GROUP I ISOLATION SIGNAL FROM LOW LOW REACTOR WATER LEVEL.
B. Terminate and Prevent Injection and lower RPV water level to at least -35 inches.
C. Pull the scram solenoid fuses per QCOP 0300-28, ALTERNATE CONTROL ROD INSERTION.
D. Start an RPV cooldown at < 100 °F/hr Answer: C QC-OPS-EXAM-ILT Page: 24 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation QC-OPS-EXAM-ILT Page: 25 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Per OP-QC-103-102-1002, Quad Cities Strategies for Successful Transient Mitigation:
Both procedures (QCOP 0300-28 and QCOP 0250-02) can be ordered at the same time with a priority based on which procedure is likely to have greater effect on controlling the plant. The US will make this decision based on plant conditions such as type of ATWS and status of the Main Condenser. In this case, the Main Condenser is available and RPV pressure is being controlled by DEHC preventing heat input into the containment. There is ample time to remove ARI fuses and terminate the transient.
Distractor 1: Plausible because bypassing the Low RPV water level MSIV isolation is a QGA 101 level leg action. Incorrect because the indications are showing an Electric ATWS and all control rods can be rapidly inserted by de-energizing the scram solenoids.
Distractor 2: Plausible because lowering RPV water level lowers reactor power and is a QGA 101 action. Incorrect because the indications are showing an Electric ATWS and all control rods can be rapidly inserted by de-energizing the scram solenoids.
Distractor 3: Plausible because an RPV cooldown is a QGA 101 action.
Incorrect because the Cold Shutdown Weight of Boron must be injected before a cooldown can be started and the transient is terminated more quickly by de-energizing scram solenoids.
Reference:
Per OP-QC-103-102-1002, Quad Cities Strategies for Successful Transient Mitigation, QGA 101, RPV CONTROL(ATWS)
Reference provided during examination: None.
Cognitive level (High/Memory): Higher Level (RO/SRO): SRO Tier: 1 Group: 1 Question Source: New question developed for ILT 18-1 NRC Exam Question History: None.
10 CFR Part 55 Content: 41.10/43.5/45.2/45.6 SRO Justification: Can the question be answered solely by knowing the following?
Systems knowledge (i.e., how the system works, flowpath, logic, component location): No Immediate operator actions: No Entry conditions for AOPs or plant parameters that require direct entry into major EOPs: No QC-OPS-EXAM-ILT Page: 26 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 The purpose, overall sequence of events, or overall mitigative strategy of a procedure: No KA: 295037 Scram condition present and reactor power above APRM downscale or unknown, Generic K/A 2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation. (SRO= 4.4)
Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 28 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 82 ID: 2123043 Points: 1.00 Unit 1 is at full power and Unit 2 is in a refueling outage when the following events occur:
1300 Outside EO reports a fire in the ISFSI Protected Area. Several of the High Integrity Casks (HIC) appear to be on fire.
1315 Fire Brigade Leader contacts the control room and reports fire fighting efforts are initiated.
1335 Fire Brigade Leader requests off-site assistance from the Cordova Fire Department.
1345 Cordova Fire Department arrives and assists in fire fighting efforts.
1355 Fire Brigade Leader reports the fire is OUT.
What reporting requirements, if any, are required?
Reference provided.
A. State and NRC notifications B. None C. State notification ONLY D. NRC notification ONLY Answer: A QC-OPS-EXAM-ILT Page: 29 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation The conditions for EAL HU3 are met requiring a NARS notification to Iowa and Illinois within 15 minutes. In addition, an NRC notification within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is required per 10CFR50.72(a)(1)(i) due to the declaration of an Emergency Classification.
Distractor 1: Plausible because the fire is extinguished in < 60 minutes.
Incorrect because offsite fire fighting assistance was required.
Distractor 2: Plausible because a State notification is required. Incorrect because an NRC notification is also required.
Distractor 3: Plausible because a NRC notification is required. Incorrect because an State notification is also required.
Reference:
EP-AA-1006 Addendum 3, Rev.5 Reference provided during examination: EAL pages: QC 2-9, 2-11, 2-13 Cognitive level (High/Memory): Higher Level (RO/SRO): SRO Tier: 1 Group: 1 Question Source: New question developed for ILT 18-1 NRC Exam Question History: None.
10 CFR Part 55 Content: 41.10/43.5/45.11 SRO Justification: Can the question be answered solely by knowing the following?
Systems knowledge (i.e., how the system works, flowpath, logic, component location): No Immediate operator actions: No Entry conditions for AOPs or plant parameters that require direct entry into major EOPs: No The purpose, overall sequence of events, or overall mitigative strategy of a procedure: No KA: 295038 High offsite radioactivity release rate, Generic K/A 2.4.30 -
Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (SRO= 4.1)
Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 31 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 83 ID: 2123047 Points: 1.00 Unit 2 was operating at 100% power when a large LOCA occurred. QGA 100 and QGA 200 actions are in progress. All systems responded as designed.
- RPV water level -30 inches and rising
- Drywell temperature 330°F and rising
- Torus temperature 110°F and rising
- Torus level -5 inches and stable
- Drywell pressure 20 psig and rising
- Torus pressure 15 psig and rising
- Low Pressure ECCS pumps are injecting
- Torus sprays are ON Which of the following actions has the HIGHEST PRIORITY?
Reference provided.
A. Start Torus Cooling B. Enter QGA 500-1, RPV Blowdown C. Raise Torus level D. Start Drywell Sprays Answer: D QC-OPS-EXAM-ILT Page: 32 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation QC-OPS-EXAM-ILT Page: 33 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Containment sprays, ie. Drywell and Torus Sprays, are required to be established prior to entering QGA 500-1 to prevent exceeding PSP or Drywell high temperature limits if they are available. Raising Torus level or starting Torus Cooling are required actions but NOT the priority since the containment design temperature is being approached. Therefore, establishing Drywell Sprays is the next required action.
Distractor 1: Plausible because it is a required action in QGA 200. Incorrect because Drywell temperature has exceeded the Containment design limit (280°F) and is approaching the ADS operability limit (338°F) and requires a higher priority.
Distractor 2: Plausible because the conditions for entering QGA 500-1 are met.
Incorrect because all mitigation systems, ie. Drywell sprays are to be used and assessed even if a blowdown parameter is exceeded.
Distractor 3: Plausible because it is a required action in QGA 200. Incorrect because Drywell temperature has exceeded the Containment design limit (280°F) and is approaching the ADS operability limit (338°F) and requires a higher priority.
Reference:
OP-QC-103-102-1002, Rev.25 Reference provided during examination: QGA 200 with entry conditions and required from memory numbers redacted.
Cognitive level (High/Memory): Higher Level (RO/SRO): SRO Tier: 1 Group: 2 Question Source: New question developed for ILT 18-1 NRC Exam Question History: None.
10 CFR Part 55 Content: 41.10/43.5/45.13 SRO Justification: Can the question be answered solely by knowing the following?
Systems knowledge (i.e., how the system works, flowpath, logic, component location): No Immediate operator actions: No Entry conditions for AOPs or plant parameters that require direct entry into major EOPs: No The purpose, overall sequence of events, or overall mitigative strategy of a procedure: No QC-OPS-EXAM-ILT Page: 34 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 KA: 295012 High Drywell temperature, 2.4.6 - Knowledge of EOP mitigation strategies. (SRO= 4.7)
Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 36 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 84 ID: 2123049 Points: 1.00 Which of the following unisolable leaks, with offsite radiation release rates approaching the General Emergency level, would require you to select QGA 500-01 as the appropriate procedure to protect the general public?
A. Fuel Pool cooling discharging into Radwaste Valve-Alley B. RWCU piping discharging into the RWCU Demin room C. HPCI steam inlet piping discharging into the Torus area D. The Main Turbine Bypass Valves discharging into the Turbine Building Answer: D QC-OPS-EXAM-ILT Page: 37 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation Answer Explanation: The answer is the only choice in which the SOURCE of the leak meets the criteria for RPV blowdown in QGA 400. Main Steam leaking in the Turbine Building is a PRIMARY system discharging outside the primary AND secondary containment.
Distractor 1: Plausible because the Radwaste Valve-Alley is outside secondary containment. Incorrect because Fuel Pool cooling is not a primary system.
Distractor 2: Plausible because the RWCU is a primary system. Incorrect because the RWCU Demin room is not outside secondary containment.
Distractor 3: Plausible because the HPCI steam inlet supply is a primary system. Incorrect because the Torus area is not outside secondary containment.
Reference:
P&IDs, M-3 and M-4A Sh.1 Reference provided during examination: QGA 400 (embedded clip)
Cognitive level (High/Memory): Higher Level (RO/SRO): SRO Tier: 1 Group: 2 Question Source: Quad Cities Exam Bank (QDC.03-01 NRC SRO 85)
Question History: ILT 03-1 NRC Exam 10 CFR Part 55 Content: 55.43(b) (5)
SRO Justification: Can the question be answered solely by knowing systems knowledge, i.e., how the system works, flowpath, logic, component location?
No Can the question be answered solely by knowing immediate operator actions?
No Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs?
No Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure?
No KA: 295017 Abnormal offsite release rate, AA2.03 - Ability to determine and/or interpret the following as they apply to HIGH OFF SITE RELEASE RATE:
Radiation levels: Plant-Specific. (SRO= 3.1)
Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 40 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 85 ID: 2123050 Points: 1.00 The SAMGs have been entered and the TSC is providing SAMG decision-making.
- Drywell Hydrogen: 7%
- Drywell Oxygen: 6%
- Torus Hydrogen: 5%
- Torus Oxygen: 5%
WHICH BLOCKS of SAMG-2 should be followed to control Hydrogen and Oxygen?
A. 12 and 15 B. 12 and 16 C. 13 and 15 QC-OPS-EXAM-ILT Page: 41 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 D. 13 and 16 Answer: D QC-OPS-EXAM-ILT Page: 42 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation Answer Explanation: The correct Drywell Block Action is derived by intersecting a horizontal line drawn from Drywell H2 ( > 6% or unknown) with a vertical line from Torus H2 (< 6%). The Torus Block Action is derived by intersecting a horizontal line from Torus H2 (< 6%) with a vertical line from Drywell H2 ( > 6% or unknown).
Distractor 1: Plausible because Drywell and Torus H2 levels are close to the limits for blocks 13 and 16. Incorrect because the H2 levels have exceeded the Block 12 and 15 limits.
Distractor 2: Plausible because the Torus block actions are correct. Incorrect because the Drywell block actions are wrong.
Distractor 3: Plausible because the Drywell block actions are correct. Incorrect because the Torus block are wrong.
Reference:
Technical Support Guidelines (TSG) Reference Manual, Rev.5 Reference provided during examination: SAMG-2 Drywell and Torus H2/O2 charts. (embedded clip)
Cognitive level (High/Memory): Higher Level (RO/SRO): SRO Tier: 1 Group: 2 Question Source: Bank Question History:
10 CFR Part 55 Content: (41.10 / 43.5 / 45.13)
SRO Justification: Can the question be answered solely by knowing systems knowledge, i.e., how the system works, flowpath, logic, component location?
No Can the question be answered solely by knowing immediate operator actions?
No Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs? No Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure? No KA: 500000 EA2.03 Ability to determine and/or interpret the following as they apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS:
Combustible limits for drywell. (SRO=3.8)
Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 44 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 45 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 86 ID: 2123066 Points: 1.00 A large LOCA with a Group I isolation has occurred. QGA 100 and QGA 200 have been entered.
- Reactor pressure is 750 psig and lowering
- RPV water level is -130 inches and lowering
- Drywell pressure is 8 psig and steady
- Torus pressure is 6 psig and steady
- Torus Cooling is running on both RHR loops
- Drywell and Torus Sprays are operating on RHR Loop A
All 5 ADS valves are opened and RPV pressure is 500 psig and lowering.
What is the next action the Unit Supervisor will direct?
Reference provided.
A. Split RHR Loops and maintain Torus Cooling and Containment sprays on A RHR Loop ONLY.
B. Split RHR Loops and secure Containment Sprays only.
C. Secure ALL Containment Cooling and Sprays.
D. Continue operating Containment Cooling and Sprays.
Answer: C QC-OPS-EXAM-ILT Page: 46 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation QC-OPS-EXAM-ILT Page: 47 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation: Per QCAP 0200-10, the four viable mechanisms of core cooling in order of preference are core submergence, spray cooling, steam cooling with injection, and steam cooling without injection. When a blowdown is initiated at TAF, core submergence is lost. The direction to NOT divert RHR flow to torus cooling or containment sprays is to insure all RHR injection is into the RPV and therefore to restore core submergence as quickly as possible to prevent core damage. Also per QCOP 1000-30, Limitations and Actions step E.6, An RHR Pump can be used for Containment Cooling only if it is NOT required to assure adequate core cooling by continuous operation in the LPCI mode, unless directed by QGA or SAMG procedures.
Distractor 1: Plausible because establishing Torus Cooling and Containment sprays are required actions in QGA 200. Incorrect because QGA 500-1 was entered at TAF and all flow is to be directed to the reactor to maintain core cooling via submergence.
Distractor 2: Plausible because establishing Torus Cooling is a required action in QGA 200. Incorrect because QGA 500-1 was entered at TAF and all flow is to be directed to the reactor to maintain core cooling via submergence.
Distractor 3: Plausible because establishing Torus Cooling and Containment sprays are required actions in QGA 200. Incorrect because QGA 500-1 was entered at TAF and all flow is to be directed to the reactor to maintain core cooling via submergence.
Reference:
QGA 500-1 Rev.16, Reference provided during examination: Redacted QGA 200, redacted QGA 500-1.
Cognitive level (High/Memory): Higher Level (RO/SRO): SRO Tier: 2 Group: 1 Question Source: Bank Question History:
10 CFR Part 55 Content: (41.10 / 43.5 / 45.12)
SRO Justification: Can the question be answered solely by knowing systems knowledge, i.e., how the system works, flowpath, logic, component location?
No Can the question be answered solely by knowing immediate operator actions?
No QC-OPS-EXAM-ILT Page: 48 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs? No Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure? No KA: 203000 G2.1.20 RHR/LPCI: Injection Mode Ability to interpret and execute procedure steps. (SRO=4.6)
Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 50 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 87 ID: 2123095 Points: 1.00 Unit 1 is in Mode 4.
- RPV Head Vents are open
- RPV water level is +30 inches
- RPV water temperature band is 140°F to 160°F
- RPV water temperature is 150°F and rising at 10°F/hr
- Shutdown Cooling lined up for a subsequent restart on 'A' Loop
- Both Recirc Pumps are off
What actions will the Unit Supervisor direct in order to maintain RPV water temperature in band?
A. Establish a Feed and Bleed per QCOA 1000-05, LOSS OF SHUTDOWN COOLING.
B. Restart the 1B Recirc Pump per QCOP 0202-43, REACTOR RECIRCULATION SYSTEM STARTUP.
C. Realign and restart Shutdown Cooling on B RHR Loop per QCOP 1000-05, SHUTDOWN COOLING OPERATION.
D. Restart Shutdown Cooling on A RHR Loop per QCOP 1000-05, SHUTDOWN COOLING OPERATION.
Answer: A QC-OPS-EXAM-ILT Page: 51 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation QC-OPS-EXAM-ILT Page: 52 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation: The loss of MCC 18/19-5 prevents operation of Shutdown Cooling (SDC) on either loop as it is the power supply to both loops injection valves. Since there is no indication of stratification, starting a Recirc pump will only add heat as it does work on the system. Since the RWCU system is available, a feed and bleed with CRD or Condensate can be readily established to control RPV water temperature.
Distractor 1: Plausible because a Recirc pump provides forced circulation and a more accurate assessment of bulk temperature. Incorrect because the pump will add heat.
Distractor 2: Plausible because RHR Shutdown Cooling is designed to control RPV water temperature. Incorrect because the RHR injection valves on both RHR Loops are unavailable due to the loss of MCC 18/19-5.
Distractor 3: Plausible because RHR Shutdown Cooling is designed to control RPV water temperature. Incorrect because the RHR injection valves on both RHR Loops are unavailable due to the loss of MCC 18/19-5.
Reference:
QCOA 1000-02, Rev.21 Reference provided during examination: None Cognitive level (High/Memory): Higher Level (RO/SRO): SRO Tier: 2 Group: 1 Question Source: New Question History: N/A 10 CFR Part 55 Content: (41.5 / 45.6)
SRO Justification: Can the question be answered solely by knowing systems knowledge, i.e., how the system works, flowpath, logic, component location?
No Can the question be answered solely by knowing immediate operator actions?
No Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs? No Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure? No KA: 205000 A2.03 Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE); and (b) based on those predictions, use procedures to correct, control, or mitigate QC-OPS-EXAM-ILT Page: 53 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 the consequences of those abnormal conditions or operations: A.C. failure.
(SRO=3.2)
Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 55 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 88 ID: 2123109 Points: 1.00 A LOCA has occurred on Unit 2.
The 2B Core Spray pump and the RHR system are injecting and maintaining RPV water level.
The 2A Core Spray pump is in PTL for RPV water level control.
- 2B Core Spray pump flow, discharge pressure, and current are lowering.
- All other Low Pressure ECCS pumps are operating normally.
- An EO reports that the 2B Core Spray pump sounds as if it were cavitating and the casing is hot.
What action will the Unit Supervisor direct next?
A. Start the 2A Core Spray pump and secure the 2B Core Spray pump.
B. Throttle OPEN the 2B Core Spray pump discharge valve fully to maintain rated flow.
C. Swap the 2B Core Spray pump suction to the CCSTs.
D. Throttle CLOSED the 2B Core Spray pump discharge valve to stabilize discharge pressure and flow.
Answer: A QC-OPS-EXAM-ILT Page: 56 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation QC-OPS-EXAM-ILT Page: 57 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation: Since all other ECCS pumps are operating normally, Suction Strainer clogging is not the cause of the 2B Core Spray pump degraded flow. Therefore, swapping the pump suction to the CCSTs is not a correct action. Throttling the pump discharge valve may stabilize flow, but based on the EO report, pump damage is inevitable. Securing an ECCS pump must be directed by the Unit Supervisor.
Distractor 1: Plausible because throttling a discharge valve open increases flow.
Incorrect because the pump is cavitating and flow becomes more unstable.
Distractor 2: Plausible because the symptoms of cavitation are similar to suction strainer clogging for which the corrective action is to swap suction to the CCSTs. Incorrect because all other running ECCS pumps are operating normally. Suction strainer clogging would have affected all of the ECCS pumps.
Distractor 3: Plausible because throttling the discharge valve closed will stabilize pressure and flow. Incorrect because pump flow will be reduced and RPV water level will not be maintained.
Reference:
QCOP 1000-30 Rev.32 Reference provided during examination: None Cognitive level (High/Memory): Higher Level (RO/SRO): SRO Tier: 2 Group: 1 Question Source: New Question History: N/A 10 CFR Part 55 Content: 41.5 / 43.5 / 45.6 SRO Justification: Can the question be answered solely by knowing the following?
Systems knowledge, i.e., how the system works, flowpath, logic, component location: No Can the question be answered solely by knowing immediate operator actions:
No Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs: No Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure: No QC-OPS-EXAM-ILT Page: 58 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 KA: 209001 A2.06 Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Inadequate system flow. (SRO=3.2)
Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 89 ID: 2123126 Points: 1.00 Unit 1 is in Mode 1 when annunciator 901-4 F-18, TARGET ROCK VALVE 3A BELLOWS FAILURE, alarms.
Target Rock Valve indications:
- Acoustic Monitor CLOSED green light is LIT
- Amber MEMORY light is OFF
- Tailpipe temperature is steady The Target Rock Valve bellows is confirmed to be leaking.
What action, if any, will the Unit Supervisor direct?
Reference provided.
A. Enter Tech Spec 3.4.3 Condition 'A' ONLY.
B. Enter Tech Spec 3.4.3 Condition 'C' ONLY.
C. Enter Tech Spec 3.4.3 Condition 'A' and 'C'.
D. No action required.
Answer: B QC-OPS-EXAM-ILT Page: 61 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation Answer Explanation: The 203-3A is considered a Relief valve and a Safety valve. The Safety valve portion is the most limiting in Tech Specs. The question states that the 3A Target Rock Valve bellows is leaking. This would prevent the Safety Valve Mode from actuating on high reactor pressure. Tech Spec 3.4.3 Condition C is applicable for "one or more safety valves inop".
There is no 14 days of operation allowed.
Distractor 1: Plausible because the valve is inoperable. Incorrect because it is the Safety valve function that is inoperable, not the Relief valve function.
Distractor 2: Plausible because the Safety valve is inop but incorrect because the relief valve function in still operable.
Distractor 3: Plausible because if the valve is determined to be operable then both functions could be considered operable but incorrect because only the Relief valve function is still operable.
Reference:
Technical Specification 3.4.3 Safety and Relief Valves Reference provided during examination: TS 3.4.3 Cognitive level (High/Memory): Higher Level (RO/SRO): SRO Tier: 2 Group: 1 Question Source: New Question History: N/A 10 CFR Part 55 Content: (41.7 / 43.2 / 45.12)
SRO Justification: Can the question be answered solely by knowing the following?
1-hour TS/TRM Actions: No The LCO/TRM information listed above the line: No The TS safety limits: No KA: 239002 G2.2.37 Safety Relief Valves: Ability to determine operability and/or availability of safety related equipment. (SRO=4.6)
Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 63 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 90 ID: 2123127 Points: 1.00 Unit 1 is at 100% power when the following annunciators alarm:
- 901-8 C-2, RESERVE AUX TRANS 12 TROUBLE
- 901-8 E-2, RESERVE TRANS 12 TRIP
- Transformer 12 has tripped
- The reserve feed breakers for Bus 12 and Bus 13 from Transformer 11 have auto closed
- Reactor power, pressure, and water level are stable.
What action will the Unit Supervisor direct?
A. Reduce power to 2511 Mwth per QCGP 3-1 ONLY.
B. Enter TS LCO 3.8.1 AC Sources-Operating, Condition C, Two required offsite circuits inoperable.
C. Enter TS LCO 3.8.1 AC Sources Operating, Condition A, One required off-site circuit inoperable ONLY.
D. Enter TS LCO 3.8.1 AC Sources Operating, Condition A, One required off-site circuit inoperable, AND Reduce power to 2511 Mwth per QCGP 3-1 REACTOR POWER OPERATIONS.
Answer: D QC-OPS-EXAM-ILT Page: 64 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation QC-OPS-EXAM-ILT Page: 65 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation: QOA 6100-01, Loss of Reserve Auxiliary Transformer 12(22) During Power Operation, step 7.a.(2) requires reactor power reduced to
< 2511 MWth within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after the loss of RAT 12 due to the reduced operating margins for UAT 11 windings.
Distractor 1: Plausible because one offsite circuit is inoperable. Incorrect because a tech spec will have to be entered.
Distractor 2: Plausible because one offsite circuit is inoperable. Incorrect because two operable offsite circuits are available through the crossties from Unit 2.
Distractor 3: Plausible because reactor power, pressure, and level are stable and Aux power auto-transferred as designed. Incorrect because reactor power must be lowered due to the reduced operating margins for UAT 11 windings.
Reference:
QOA 6100-01, Rev.35 Reference provided during examination: None Cognitive level (High/Memory): Higher Level (RO/SRO): SRO Tier: 2 Group: 1 Question Source: New Question History: N/A 10 CFR Part 55 Content: (41.5 / 43.5 / 45.6)
SRO Justification: 10 CFR 55.43 topic involves both (1) assessing plant conditions (normal, abnormal, or emergency) and then (2) selecting a procedure or section of a procedure to mitigate or recover, or with which to proceed. One area of SRO-level knowledge (with respect to selecting a procedure) is knowledge of the content of the procedure versus knowledge of the procedures overall mitigative strategy or purpose.
Can the question be answered solely by knowing systems knowledge, i.e.,
how the system works, flowpath, logic, component location? No Can the question be answered solely by knowing immediate operator actions?
No Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs? No Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure? No QC-OPS-EXAM-ILT Page: 66 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 KA: 262001 A2.04 Ability to (a) predict the impacts of the following on the A.C.
ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Types of loads that, if deenergized, would degrade or hinder plant operation. (SRO=4.2)
Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 68 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 91 ID: 2132388 Points: 1.00 Unit 1 is at 27% power with both Reactor Recirculation pumps at 38% speed when the 1A Reactor Recirculation pump TRIPS.
NO operator action has been taken.
If annunciator 901-4 G-8, RECIRC LOOP B LO FLOW LIMIT, alarms, the 1B Reactor Recirculation pump speed will __(1)__.
Per LCO 3.4.1 (Recirculation Loops Operating) Technical Specification bases, APLHGR limits are required to be adjusted for continued single loop operation to account for
__(2)__.
A. (1) remain at 38%
(2) heat balance uncertainties that impact APLHGR calculations in the core B. (1) remain at 38%
(2) the change in predicted core flow coastdown during a LOCA from single loop operation C. (1) runback to 32%
(2) heat balance uncertainties that impact APLHGR calculations in the core D. (1) runback to 32%
(2) the change in predicted core flow coastdown during a LOCA from single loop operation Answer: D QC-OPS-EXAM-ILT Page: 69 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation 901-4 panel G-8 indicates that feedwater flow is <20% of rated. Therefore RRCS will runback the operating recirc pump to 32% due to the anti-cavitation interlock.
Should a LOCA occur with one recirculation loop not in operation, the core flow coastdown and resultant core response may not be bounded by the LOCA analysis. Therefore, thermal limits must be adjusted to compensate for the different core response.
Distractor 1: Combination of distractors 2 and 3.
Distractor 2: Plausible if candidate does not recognize that RRCS will runback the operating recirc pump to minimum speed with this alarm in.
Distractor 3: Plausible because various equipment malfunctions will cause a error in the heat balance calculation.
Reference:
QCAN 901(2)-4 G-8 Rev 16, TS B3.4.1 Rev 43 Reference provided during examination: None Cognitive level: Memory Level (RO/SRO): SRO Tier: 2 Group: 2 Question Source: Quad ILT Exam Bank (QDC.ILT.816126)
Question History: 2012 Quad ILT NRC Exam 10 CFR Part 55 Content: 55.43 (2)
SRO Justification: The questions requires the candidate to have knowledge of technical specification bases.
202001, G 2.1.7 - Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (CFR41.5/43.5/45.12/45.13) (SRO = 4.7)
Comments: None.
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 71 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 92 ID: 2123161 Points: 1.00 Unit 1 is at 50% power with a startup in progress.
When control rod D-8 is withdrawn to position 48, the following annunciators alarm:
- 901-5 A-3, ROD DRIFT
- 901-5 B-3, ROD WORTH MIN BLOCK Indication for position 48 was lost on the Full Core, 4-Rod, and RWM Display screen.
Control rod coupling was verified, and stall flow was obtained.
When control rod D-8 is inserted to position 46, position indication returns and annunciators 901-5 A-3 and 901-5 B-3 reset.
Per QCOP 0207-01, ROD WORTH MINIMIZER OPERATION To continue control rod withdrawal, the Unit Supervisor will direct the NSO to ...
A. notch out control rod D-8 to position 48 and enter a SUBSTITUTE POSITION.
B. leave control rod D-8 at position 46 and insert an ALTERNATE LIMIT.
C. leave control rod D-8 at position 46 and BYPASS the RWM.
D. insert control rod D-8 to position 00 and declare it INOPERABLE.
Answer: B QC-OPS-EXAM-ILT Page: 72 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation QC-OPS-EXAM-ILT Page: 73 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Inserting an ALTERNATE LIMIT will satisfy the sequence requirements on the RWM and allow control rod withdrawal to continue. Substitute positions are NOT allowed for a control rod whose position can NOT be determined from RPIS. The control rod is NOT inoperable solely due to a failed reed switch at position 48. Per QCGP 4-1, the RWM should only be bypassed if it has failed or for control rod testing, sequence changes, and special maneuvers.
Distractor 1: Plausible because coupling and stall flow checks were successful and the control rod can be determined to be at position 48. Incorrect because per QCOP 9950-07, substitute positions cannot be used for a rod whose position can NOT be determined from RPIS. The substitute position is used only if the RWM cannot process the information from RPIS.
Distractor 2: Plausible because bypassing the RWM would clear the RWM block and allow further control rod movement. Incorrect because per QCGP 4-1, the RWM should only be bypassed if it has failed or for control rod testing, sequence changes, and special maneuvers.
Distractor 3: Plausible because taking the control rod OOS mechanically and on the RWM will allow control rod movement to continue. Incorrect because removing the control rod from service is not required and would require a sequence change.
Reference:
QCGP 4-1, Rev.50 Reference provided during examination: None Cognitive level (High/Memory): Higher Level (RO/SRO): SRO Tier: 2 Group: 2 Question Source: New Question History: N/A 10 CFR Part 55 Content: (41.5 / 45.6)
SRO Justification: Can the question be answered solely by knowing systems knowledge, i.e., how the system works, flowpath, logic, component location?
No Can the question be answered solely by knowing immediate operator actions?
No Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs? No Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure? No QC-OPS-EXAM-ILT Page: 74 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 KA: 214000 A2.01 Ability to (a) predict the impacts of the following on the ROD POSITION INFORMATION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failed reed switches. (SRO=3.3)
Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 76 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 93 ID: 2123198 Points: 1.00 A leak in the B Main Steam Line resulted in a reactor scram from 100% power.
QGA 100, RPV CONTROL and QGA 200, PRIMARY CONTAINMENT CONTROL have been entered.
RPV pressure is 800 psig Drywell temperature is 265°F Drywell pressure is 10 psig Torus pressure is 8 psig Torus water temperature is 98°F All automatic actuations and isolations have been verified.
The NSO attempts to initiate Torus Sprays then reports the following:
The breaker for MO 1-1001-34B, TORUS TEST OR SPRAY VLV, has tripped.
MO 1-1001-34A, TORUS TEST OR SPRAY VLV, will NOT open.
What action will the Unit Supervisor direct next?
A. Place CNMT CLG 2/3 LVL AND ECC INIT BYP SWITCH 18 to MANUAL OVERRD.
B. Dispatch EOs to manually open valves to establish Torus Sprays on RHR Loop A.
C. Vent the Torus through the SBGTS.
D. Restart RBCCW and Drywell Coolers.
Answer: B QC-OPS-EXAM-ILT Page: 77 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation QC-OPS-EXAM-ILT Page: 78 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation: The containment spray and cooling valves are interlocked closed on a LOCA signal, ie. 2.5 psig Drywell pressure or -59 in.
RPV water level. Placing the S-17 switch to ON will bypass the interlock and allow opening of the valves, however, the valves can be manually opened if the logic has failed. The Torus cannot be vented through SBGT per QCOP 1600-02 as the procedure does not allow bypassing the Group II isolation. RBCCW should not be restarted as Drywell temperature is > 260°F. The S-18 switch bypass 2/3 core height (-191 inches) RPV water level interlock ONLY for containment spray and cooling valves.
Distractor 1: Plausible because Switch 18 overrides close interlocks on the containment spray and cooling valves. Incorrect because switch 18 bypasses the interlock associated with low-low reactor water level (-191 inches) which is not present.
Distractor 2: Plausible because containment venting is a QGA 200 action to reduce pressure. Incorrect because a Group II isolation signal is present and the procedures delineated in QGA 200 to vent the containment do not allow bypassing a Group II isolation signal.
Distractor 3: Plausible because restarting RBCCW and Drywell Coolers would reduce containment pressure. Incorrect because QCOP 5750-19 prohibits starting RBCCW if a LOCA has occurred and Drywell temperature is > 260°F.
Reference:
QGA 200 Rev.12, QCOP 5750-19 Rev.11, QCOP 1600-02 Rev.16 Reference provided during examination: None Cognitive level (High/Memory): Higher Level (RO/SRO): SRO Tier: 2 Group: 2 Question Source: New Question History: N/A 10 CFR Part 55 Content: (41.5 / 45.6)
SRO Justification: Can the question be answered solely by knowing systems knowledge, i.e., how the system works, flowpath, logic, component location?
No Can the question be answered solely by knowing immediate operator actions?
No Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs? No Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure? No QC-OPS-EXAM-ILT Page: 79 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 KA: 230000 A2.12 Ability to (a) predict the impacts of the following on the RHR/LPCI: TORUS/SUPPRESSION POOL SPRAY MODE; and (b) based on those predictions, use procedures to correct, or mitigate the consequences of those abnormal conditions or operations: Valve logic failure. (SRO=3.3)
Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 81 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 94 ID: 2131847 Points: 1.00 You are the SRO assigned to supervise fuel moves on the refuel floor for the outage.
Which of the following activities is required every shift, before fuel moves can begin?
A. Sign on as a holder of the Tag Out that is placed to prevent cavity draining.
B. Notify the Drywell control point Radiation Technician that fuel moves are about to begin.
C. Verify both Fuel Pool Cooling Pumps and associated heat exchangers are functional on both Units.
D. Verify from the QNE that Shutdown Margin requirements of Technical Specification 3.1.1 are met for all fuel movements.
Answer: B QC-OPS-EXAM-ILT Page: 82 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation QC-OPS-EXAM-ILT Page: 83 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Prerequisite C.8 of QCFHP 0100-01 states:
Prior to the start of moving fuel within the confines of the Reactor vessel or cavity, the SRO (L) / SRO Licensed Supervisor shall contact the drywell point Radiation Technician (or RP Supervisor).
Distractor 1 is incorrect: Plausible because it is a QCFHP 0100-01 prerequisite, but NOT a once a shift requirement. The clearance order is placed and held by the Operations department. There is no requirement for individuals moving fuel to sign on.
Distractor 2 is incorrect: Plausible because it is a requirement for a full core off load and it is NOT a once a shift requirement.
Distractor 3 is incorrect: Plausible because it is a QCFHP 0100-01 prerequisite, however, this is NOT a once per shift requirement.
Reference:
QCFHP 0100-01 Rev. 36 Reference provided during examination: None Cognitive level: Memory Level (RO/SRO): SRO Tier: 3 K/A: Generic 2.1.35 Knowledge of the fuel handling responsibilities of SROs (CFR: 41.10 / 43.7 )
IMPORTANCE RO 2.2 SRO 3.9 SRO Justification: 10 CFR 55.43(b)(7)
Fuel handling facilities and procedures.
- Refuel floor SRO responsibilities
- Assessment of fuel handling equipment surveillance requirement acceptance criteria
- Prerequisites for vessel disassembly and reassembly
- Decay heat assessment
- Assessment of surveillance requirements for the refueling mode
- Reporting requirements
- Emergency classifications Question Source: Bank Question History: 2004 Quad Cities ILT NRC Exam QC-OPS-EXAM-ILT Page: 84 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Comments: None QC-OPS-EXAM-ILT Page: 85 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 86 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 95 ID: 2123362 Points: 1.00 Unit 1 is in a refueling outage with fuel offloading scheduled to begin this shift.
SRM 21 is INOPERABLE and bypassed with its joystick.
Which of the following describes the administrative requirements for fuel moves?
A. Fuel can be offloaded from all quadrants EXCEPT the UPPER LEFT.
B. Fuel can be offloaded from the LOWER RIGHT quadrant ONLY.
C. Fuel can be offloaded from ALL quadrants.
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 D. Fuel can NOT be offloaded from ANY quadrant.
Answer: A QC-OPS-EXAM-ILT Page: 88 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation QC-OPS-EXAM-ILT Page: 89 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation: QCFHP 0100-01, Step E.5.d, states that while you must have 2 operable SRMs, they must be in the quadrant you are performing the core alterations in and in a quadrant adjacent to where core alterations are being performed.
Distractor 1: Plausible because the LOWER RIGHT quadrant meets the requirements for fuel moves. Incorrect because two other quadrants also meet the requirements.
Distractor 2: Plausible because three quadrants meet the requirements for fuel moves. Incorrect because the UPPER LEFT quadrant does not have an operable SRM.
Distractor 3: Plausible because one quadrant does not have an operable SRM.
Incorrect because the requirement is: an operable SRM in the quadrant fuel moves are being performed and an adjacent quadrant. Fuel can be moved in all quadrants except the UPPER LEFT.
Reference:
QCFHP 0100-01 Rev 37 Reference provided during examination: Graphic of core map embedded in exam question.
Cognitive level: Higher Level (RO/SRO): SRO Tier: 3 Group: N/A Question Source: Quad Cities ILT Exam Bank (QDC.ILT.15608)
Question History: ILT 10-1 NRC Exam 10 CFR Part 55 Content: 41.2 / 41.10 / 43.6 / 45.13 SRO Justification: Can the question be answered solely by knowing the following?
Systems knowledge (i.e., how the system works, flowpath, logic, component location): No Immediate operator actions: No Entry conditions for AOPs or plant parameters that require direct entry into major EOPs: No The purpose, overall sequence of events, or overall mitigative strategy of a procedure: No KA: G2.1.41: Knowledge of refueling process. (SRO=3.7)
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 92 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 96 ID: 2123424 Points: 1.00 Which of the following Temporary Configuration Changes can be authorized prior to the completion of the Temporary Configuration Change Package documentation?
A. Installation of jumpers to allow Rod Exercising.
B. Installation of a patch on a pipe that has wall thinning.
C. Installation of a jumper on a faulty ground overcurrent relay on an RHR pump needed for core cooling.
D. Installation of a Blocking Device to maintain Div I Diesel Generator Ventilation Exhaust Damper open.
Answer: C QC-OPS-EXAM-ILT Page: 93 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation QC-OPS-EXAM-ILT Page: 94 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation: Per CC-AA-112, section 4.6, an Urgent Temporary Modification may be authorized prior to completion of the documentation. An Urgent Temporary Modification is one that must be needed immediately to eliminate a threat to the safety of personnel or facilities. Shift Manager approval and Site Engineering Director concurrence are required as well as a 50.59 review, by a qualified individual per LS-AA-104, prior to installation.
Distractor 1: Plausible because the jumper installation is an alteration of plant equipment. Incorrect because control rod exercising is not urgent, and the authorization is incorporated into the procedure.
Distractor 2: Plausible because the pipe patch requires Temporary Modification paperwork. Incorrect because it does not meet the definition of "urgent" as described in CC-AA-112.
Distractor 3: Plausible because installation of a blocking device on the EDG Exhaust Damper is a TCC. Incorrect because it does not meet the definition of "urgent" as described in CC-AA-112.
Reference:
CC-AA-112 Rev.27 Reference provided during examination: None Cognitive level (High/Memory): Higher Level (RO/SRO): SRO Tier: 3 Question Source: New Question History: N/A 10 CFR Part 55 Content: 41.10 / 43.3 / 45.13 SRO Justification: This is the administrative process for temporary modifications.
Can the question be answered solely by knowing the following?
Systems knowledge (i.e., how the system works, flowpath, logic, component location): No Immediate operator actions: No Entry conditions for AOPs or plant parameters that require direct entry into major EOPs: No The purpose, overall sequence of events, or overall mitigative strategy of a procedure: No KA: G2.2.11 Knowledge of the process for controlling temporary design changes. (SRO=3.3)
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 97 ID: 2123438 Points: 1.00 Which of the following personnel could be assigned as a "Designated Operator" for a task inside the Protected Area as defined by WC-AA-101, ON-LINE WORK CONTROL PROCESS?
Reference provided.
A. An Equipment Operator assigned attendant duties for a Permit Required Confined Space per SA-AA-114, CONFINED SPACE ENTRY.
B. The Outside Equipment Operator at the H2 farm receiving a truck per QCOP 2700-11, HYDROGEN STORAGE FACILITY LIQUID HANDLING.
C. The Unit Equipment Operator performing QOS 0005-01, OPERATIONS DAILY SURVEILLANCES.
D. A Dedicated Equipment Operator supporting QCOS 1100-07, SBLC PUMP FLOW RATE TEST.
Answer: C QC-OPS-EXAM-ILT Page: 98 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation QC-OPS-EXAM-ILT Page: 99 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Per WC-AA-101, On-Line Work Control Process, section 2.12: "The dispatching supervisor must ensure that collateral duties do not interfere with the designated operator response.
If, as described in the Stations licensing basis, the allowed time to complete the action is greater than 30 minutes, a designated operator may be assigned to perform the action."
Distractor 1: Plausible because the EO is inside the Protected Area. Incorrect because per SA-AA-114, the Confined Space Attendant must remain outside of the Permit Required Confined Space at all times.
Distractor 2: Plausible because the EO can leave the H2 farm if relieved.
Incorrect because the EO is outside of Protected Area and the response time is excessive due to turnover and distance.
Distractor 3: Plausible because the EO is inside the Protected Area. Incorrect because the EO is already a "Dedicated Operator" assigned to the surveillance test.
Reference:
WC-AA-101 Rev.28 Reference provided during examination: WC-AA-101, pages 1-3.
Cognitive level (High/Memory): Higher Level (RO/SRO): SRO Tier: 3 Question Source: New Question History: N/A 10 CFR Part 55 Content: (41.10 / 43.5 / 45.13)
SRO Justification: Can the question be answered solely by knowing systems knowledge, i.e., how the system works, flowpath, logic, component location?
No Can the question be answered solely by knowing immediate operator actions?
No Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs? No Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure? No KA: G2.2.17 Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator. (SRO=3.8)
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 102 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 98 ID: 2123441 Points: 1.00 Both Units are operating at 100% power.
Which of the following conditions can the Shift Manager WAIVE the requirement for Verification in accordance with HU-AA-101, HUMAN PERFORMANCE TOOLS AND VERIFICATION PRACTICES?
A Danger Tag is to be hung on a...
A. Stator Cooling Water valve when Stator Cooling Water is posted as Protected Equipment.
B. LP Heater Drain valve located in LP Heater Bay.
C. 1/2 Diesel Generator 'A' Starting Air Compressor control switch for the air start motor that will be replaced.
D. Service Air isolation valve located 8 feet off the floor in the Turbine Building Mezzanine level.
Answer: B QC-OPS-EXAM-ILT Page: 103 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation QC-OPS-EXAM-ILT Page: 104 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation: Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions.
The Shift Manager may waive verification requirements for ALARA concerns in accordance with HU-AA-101 section 4.3.2.1. With the unit at power (and Hydrogen injection taking place), a valve in the Heater Bay would be of a dose concern.
Distractor 1 is incorrect: With a system protected, ensuring the right equipment is taken out of service is key to sustained operation and would be verified.
Plausible because work is not normally allowed on protected equipment per OP-AA-108-117, Protected Equipment Program.
Distractor 2 is incorrect: A component (safety related) in the EDG room also does not meet the criteria for waiving IV.
Distractor 3 is incorrect: The valve located above 7' [where RP would not normally survey for contamination] is not a valid reason to waive IV. As part of the original hanging, RP would have surveyed the area.
Reference:
HU-AA-101 Rev 10 Reference provided during examination: None Cognitive level: Memory Level (RO/SRO): SRO Tier: 3 Question Source: Quad Cities ILT Exam Bank Question History: N/A 10 CFR Part 55 Content: 41.10/43.5/45.11 SRO Justification: Can the question be answered solely by knowing the following?
Systems knowledge (i.e., how the system works, flowpath, logic, component location): No Immediate operator actions: No Entry conditions for AOPs or plant parameters that require direct entry into major EOPs: No The purpose, overall sequence of events, or overall mitigative strategy of a procedure: No KA: G2.3.14 - Knowledge of radiation or contamination hazards that may arise QC-OPS-EXAM-ILT Page: 105 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 during normal, abnormal, or emergency conditions or activities. (SRO= 3.8)
Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 99 ID: 2123458 Points: 1.00 Unit 1 has experienced a reactor scram and a loss of off-site power.
A fire is reported at the Hydrogen Seal Oil Panel 2251-7.
The Unit Supervisor has determined that normal and emergency plant procedures are insufficient to control the event.
Which Safe Shutdown Procedure, in accordance with QCOA 0010-12, Attachment D, should be DIRECTED by the Unit Supervisor?
A. QCARP 0030-01 B. QCARP 0030-02 C. QCARP 0060-01 D. NO QCARP actions.
Answer: A QC-OPS-EXAM-ILT Page: 108 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation Answer Explanation: From QCOA 0010-12 attachment D, the Unit 1 H2 Seal Oil panel is on the Mezzanine floor. QCARP 0030-01 addresses a fire in TB-III.
Distractor 1: Plausible because it would be correct for Unit 2. Incorrect because the answer choice is for the opposite unit.
Distractor 2: Plausible because area CT-1 is within Turbine Building area TB-III on Attachment D. Incorrect because a fire in area CT-1 directs a separate procedure QCARP 0060-01.
Distractor 3: Plausible because the Main Generator is on the Turbine deck and uses H2 Seal Oil and General firefighting actions would be used, incorrect because the H2 seal oil panel is on the Mezzanine.
Reference:
QCOA 0010-12 Revision 51 Reference provided during examination: QCOA 0010-12 Revision 51, Attachment D.
Cognitive level (High/Memory): Higher Level (RO/SRO): SRO Tier: 3 Question Source: New Question History: n/a 10 CFR Part 55 Content: (41.10 / 43.5 / 43.13)
SRO Justification: Can the question be answered solely by knowing systems knowledge, i.e., how the system works, flowpath, logic, component location?
No Can the question be answered solely by knowing immediate operator actions?
No Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs? No Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure? No KA: G2.4.27 Knowledge of "fire in the plant" procedures. (SRO=3.9)
Comments:
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Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 QC-OPS-EXAM-ILT Page: 110 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 100 ID: 2123466 Points: 1.00 At 12:00 the threshold value for an UNUSUAL EVENT was exceeded, with indications available in the control room.
At 12:08 the Shift Emergency Director classified an UNUSUAL EVENT based on the associated control room indications.
Which of the following is the LATEST time at which COMPLETE notification of the UNUSUAL EVENT can be made to the State/Local agencies per EP-AA-114, NOTIFICATIONS?
A. 12:15 B. 12:23 C. 13:00 D. 13:08 Answer: B QC-OPS-EXAM-ILT Page: 111 of 112 05 March 2020
Test Answer Key 2020 QDC NRC Exam SRO Section Test ID: 330949 Answer Explanation The Nuclear Accident Reporting System (NARS) is a telecommunication network and form used to transmit information to appropriate state and local agencies. This notification must be initiated within 15 minutes of the DECLARATION of an emergency.
Distractor 1: Plausible because the event must be classified within 15 minutes but incorrect because the time is 15 minutes from threshold value being exceeded.
Distractor 2: Combination of distractor 1 and 2.
Distractor 3: Plausible because this is when the NRC must be notified (ENS) but incorrect because state and local agencies must be notified within 15 minutes.
Reference:
EP-AA-114 Rev 15 Reference provided during examination: None Cognitive level: Higher Level (RO/SRO): SRO Tier: 3 Question Source: Quad Cities Exam Bank (QDC.ILT.16406)
Question History: LaSalle 2008 ILT NRC Exam 10 CFR Part 55 Content: 41.10/43.5/45.11 SRO Justification: Can the question be answered solely by knowing the following?
Systems knowledge (i.e., how the system works, flowpath, logic, component location): No Immediate operator actions: No Entry conditions for AOPs or plant parameters that require direct entry into major EOPs: No The purpose, overall sequence of events, or overall mitigative strategy of a procedure: No KA: G2.4.29: Knowledge of the emergency plan. (SRO= 4.4)
Comments:
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