ML20246G740
| ML20246G740 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/27/2020 |
| From: | Gary Callaway Nuclear Management Co, Xcel Energy |
| To: | NRC/RGN-III/DRS/OLB |
| Callaway G | |
| Shared Package | |
| ML19127A306 | List: |
| References | |
| Download: ML20246G740 (209) | |
Text
QF-1 030-03, Revision 5 (FP-T-SAT-30) Page 1 of 1 WRITTEN/ORAL EXAMI NATION KEY AXrelErnrgy- COVERSHEET Examination Number: Pl-tLT-NRC-200sE
Title:
2O2O ILT NRC REACTOR OPERATOR WRITTEN EXAM Training Program: FL-ILT Lesson Plan Number(s): P8100 Exam Total Points Possible: 75 Pass Criteria: > 80%
Time:
6.0 HRS EXAMINATION REVIEW AND APPROVAL: ..nfi Submitted by lnstructor: Justin Hasner tLrfil Date: 1lz-l I W Reviewed by SME: Fredrick Collins lt ,lH Date: z /zA/2, zo Approved by Training Supervisor: ShawnSarrasiffi Date: ?/tt /toz, Writtenr.r*=ffi Attach tkey to this pase.
Key should contain the followi tr Lea rn ing e Number tr Test I o tion or o e ans r) Answer ln o Value Refe if applicable)
ArN GUTDANcE spEctFtc ro NRC ExAMS.
lndicate in the followi if any changes are made to the exam after approval:
DESCRIPTION OF CHTNGE REASON FOR CHANGE Retention. Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.
- 1. P8176L-003 088/062 2.1.7/4.4/7B//P8100/ECA-0.0/C35 AOP1/2020 ILT NRC R01
- A Loss of All Offsite Power has occurred.
- Unit 1 Safety Injection is ACTUATED.
The crew will start the...
Y A. 11 Motor Driven Cooling Water pump.
B. 12 Diesel Driven Cooling water pump.
C. 21 Motor Driven Cooling Water pump.
3-PEO KE D. 22 Diesel Driven Cooling Water pump.
Justifications:
- a. Incorrect. Plausible if examinee incorrectly believes 11 CL pump has power, is a safeguards pump, and can be aligned to the 'B' header.
- b. Incorrect. Plausible if examinee incorrectly believes the 12 CL pump supplies the 'B' header.
- c. Incorrect. Plausible if examinee incorrectly believes the 21 CL pump (Unit 2) has power.
- d. Correct. The CL system consists of 2 loops which are common to both Units. Each loop supplies components for both units. 11 & 12 CL pumps supply the 'A' header. 21 & 22 CL pumps supply the 'B' header. In the event of a Loss of offsite power, CL pumps 11 & 21 will not be available. 121 CL pump will start when header pressure drops below 80#. 12 & 22 CL pumps will start and 121 will trip if header pressure does not increase above 75# in 15 seconds. If an SI signal is received, the same actions occur with the addition of 121 CL pump, which will auto align to the SI unit. The headers will be "split" to provide 2 redundant CL headers for vital equipment. In the stem, the 22 DDCLG pump did not start as expected and will need to be started in order to provide cooling to unit 1 loads.
1
2020 ILT NRC EXAM RO EXAM K/A Number:
062 2.1.7 Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation.
K/A Value: 4.4 Technical Reference(s): B35 pgs 23-24 ; C35 AOP1 pg. 5, 1ECA-0.0 pg. 5 Proposed references to be provided to applicants during examination: None Learning Objective: P8176L-003 Obj. 7b Predict the response of the system to a component failure.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Y Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
X KE Comments:
55.41 4 55.43 2
- 2. P8170L-003 107/008 AK1.01/3.2/7B//P8100/B4A/1C4 AOP1/2020 ILT NRC R02
- Unit 1 is at 100% power.
- 47012-0109, PRZR SAFETY/RELIEF VALVE FLOW, is LIT.
- No operator action has been taken.
- ERCS indications are as follows:
Indication before alarm Indication upon alarm Y
KE 10 Minutes after alarm Question continued on next page.
3
- 2. P8170L-003 107/008 AK1.01/3.2/7B//P8100/B4A/1C4 AOP1/2020 ILT NRC R02 Question continued on next page.
Question continued from previous page.
Based on the above conditions, a Pressurizer __________________________.
A. PORV is CLOSED and LEAKING by B. PORV is FULL open C. Safety is CLOSED and LEAKING by D. Safety is FULL open 3-PEO Y
The photos from the plant computer system (ERCS) show initial and 10 minute later conditions demonstrating the expected temperature changes for a leaking Safety. To successfully answer the question the candidate must recognize the temperature differential present at the beginning of a leaking safety/porv will be equalized based on location of temperature measurement and piping configuration.
Also the examinee must recognize that the leak rate from a fully open PORV and/or Safety would result in KE a reactor trip and the 10 minute later ERCS display clearly shows a non trip condition.
Justification:
- a. Incorrect. Plausible if examinee assumes the PORV would be more likely cause of leakage due to the lower setpoint and does not recognize the temperature differential from the initial ERCS condition and the leakage portion of the answer is correct.
- b. Incorrect. Plausible if examinee assumes the PORV would be more likely cause of leakage due to the lower setpoint and believes the leakage indication is that of a fully open PORV.
- c. Correct, see EXPLANATION above.
- d. Incorrect. Plausible if the applicant correctly diagnosiss the safety as the source of leakage, but does not recognize that PZR conditions in the 10 minute later ERCS display do not support a trip.
4
2020 ILT NRC EXAM RO EXAM K/A Number:
008 Pressurizer Vapor Space Accident AK1.01:
Knowledge of the operational implications of the following concepts as they apply to Pressurizer Vapor Space Accident:
Thermodynamics and flow characteristics of open or leaking valves.
K/A Value: 3.2 Technical Reference(s): B4A pg 18 Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-003 Obj. 7B For the Reactor Coolant System, predict the response of the system to a component failure..
Question Source: Bank # X Modified Bank #
New Question History: Last NRC Exam Question Cognitive Level: Y 2017 Biennial Exam Memory or Fundamental Knowledge KE Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 3 55.43 X
5
- 3. P8140L-224 006/009 2.4.21/4.0/8//P8100/1E-0/SWI 0-10/2020 ILT NRC R03 will be read from (the)
A. (1) ADVERSE (2) .
Y Based ONLY on containment pressure, containment is (1) and subcooling KE (2) ICCM B. (1) ADVERSE (2) ERCS C. (1) NOT ADVERSE (2) ICCM D. (1) NOT ADVERSE (2) ERCS 3-SPK Justifications:
- a. Correct. Picture created from small break LOCA. Containment is adverse when pressure is greater than 5 lbs. Per SWI O-10, subcooling must be read from ICCM due to large instrument uncertainties with RCS wide range pressure.
- b. Incorrect. Plausible if the examinee incorrectly believes that ICCM RCS pressure instruments are affected by containment pressure.
- c. Incorrect. Plausible if the examinee incorrectly believes that containment is not adverse until 23 psig.
- d. Incorrect. Plausible if the examinee incorrectly believes that containment is not adverse until 23 psig and ICCM does not out until containment is adverse.
6
2020 ILT NRC EXAM RO EXAM K/A Number:
009 Small Break LOCA 2.4.21:
Knowledge of the parameters and logc used to assess the status of safety functions, such as reacticity control, core cooling, and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
K/A Value: 4.0 Technical Reference(s): E-0 Information Page, SWI O-10 pg 12 Proposed references to be provided to applicants during examination: None Learning Objective: P8140L-224 Obj. 8 Explain all notes and cautions as to their purpose and operational implications.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y Memory or Fundamental Knowledge N/A KE Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 10 55.43 X
7
- 4. P8197L-012 220/011 EA1.11/4.2/15//P8100/1ES-1.2//2020 ILT NRC R04
- The crew is on step 15 of 1ES-1.2, Transfer to Recirculation.
- RWST level is 5% and LOWERING.
- The ECCS System is aligned per picture below:
Y KE Question continued on next page.
8
- 4. P8197L-012 220/011 EA1.11/4.2/15//P8100/1ES-1.2//2020 ILT NRC R04 Question continued from previous page.
The Reactor Operator will stop ____________ pumps.
A. 11 RHR and 11 SI B. 11 RHR and 12 SI C. 12 RHR and 11 SI D. 12 RHR and 12 SI 3-SPR Justifications:
Y
- a. Incorrect. Plausible if examinee confuses light indication and thinks green lights means the valve is open and the red light means the valve is closed.
- b. Incorrect. Plausible as the 12 SI pump will be secured; however, 12 RHR pump will be secured instead of 11 RHR pump.
- c. Incorrect. Plausible as 12 RHR pump will be secured; however, 12 SI pump will be secured instead of KE 11 SI pump.
- d. Correct. The picture shows that 11 RHR pump is aligned to Sump B, 12 RHR pump is aligned to the RWST, 11 SI pump is aligned to 11 RHR pump for High Head Recirc, and 12 SI pump is aligned to the RWST. Therefore, 12 RHR and 12 SI pumps would be secured.
9
2020 ILT NRC EXAM RO EXAM K/A Number:
011 Large Break LOCA EA1.11 Ability to operate and monitor the following as they apply to a Large Break LOCA:
Long term core cooling.
K/A Value: 4.2 Technical Reference(s): 1ES-1.2 pages 3-5 Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-220 Obj. 15 For ES-1.2 Explain the purpose for any step or step sequence for associated E series EOP.
Question Source: Bank # X Modified Bank #
New Question History: Last NRC Exam Question Cognitive Level:
Y 2019 Biennial Memory or Fundamental Knowledge Comprehension or Analysis X KE 10 CFR Part 55 Content:
Comments:
55.41 7 55.43 10
- 5. P8170L-002 017/015 AA1.10/2.7/3H//P8100/C47012-0101//2020 ILT NRC R05
- 47012-0101, 11 RCP Locked Out, ALARMS.
- 11 RCP is NOT running.
- Unit 1 is at 100% power.
The crew will...
A. start 11 RCP.
B. trip Unit 1 reactor.
C. block AMSAC/DSS.
D. start 11 RCP lift oil pump.
1-I Justifications:
Y
- a. Incorrect. Plausible if the examinee incorrectly believes that forced flow must be restored in A reactor coolant loop to prevent exceeding a core thermal limit.
- b. Correct. Plausible if the examinee incorrectly believes that the EAL is met if ANY of the communciation system sare out of service.
- c. Incorrect. Plausible if the examinee incorrectly believes that AMSAC/DSS has malfunctioned and it needs to be blocked.
KE
- d. Incorrect. Plausible if the examinee incorrectly believes that this action will prevent damage to the RCP.
11
2020 ILT NRC EXAM RO EXAM K/A Number:
015 RCP Malfunctions AA1.10 Ability to operate and / or monitor the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow):
RCP ammeter and trip alarm.
K/A Value: 2.7 Technical Reference(s): ARP C47012-0101 Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-002 Obj. 3h For each of the major system cmponents describe the: control room controls and indications for RCPs Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y N/A KE Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 7 55.43 X
12
- 6. P8172L-001A 162/022 AA2.02/3.2/7B//P8100/B12A//2020 ILT NRC R06
- Unit 1 is at 100% power.
- 11 Charging pump is RUNNING in AUTO.
- 12 Charging pump is RUNNING in MANUAL at MINIMUM speed.
- 13 Charging pump is in STANDBY.
Prior to the transient: After the transient:
Y KE The crew determines that...
A. CV-31328, REGEN HX CHG LINE OUTL, failed CLOSED.
B. CV-31328, REGEN HX CHG LINE OUTL, failed OPEN.
C. CV-31198, CHG LINE FLOW CONT, failed CLOSED.
D. 11 Charging Pump has failed to MINIMUM speed.
2-RI Justifications:
- a. Incorrect. Plausible if the examinee incorrectly believes that Regen HX CHG Line Outl failing closed will reduce flow to the RCP seals and increase charging flow and reduce charging header pressure.
- b. Incorrect. Plausible if the examinee incorrectly believes the Regen HX CHG Line Outl is normally throttled AND that the valve opening starves the RCP seals.
- c. Incorrect. Plausible if the examinee incorrectly believes that Chg Line Flow Cont valve failing closed will reduce seal water flow to the RCP seals and reduce charging header pressure.
- d. Correct.
13
2020 ILT NRC EXAM RO EXAM K/A Number:
022 Loss of Reactor Coolant Makeup.
AA2.02 Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant Makeup:
Charging pump problems.
K/A Value: 3.2 Technical Reference(s): B12A Pg 24 Proposed references to be provided to applicants during examination: None Learning Objective: P8172L-001A Obj. 7b Predict response of the system to a component failure.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level: Y N/A Memory or Fundamental Knowledge KE Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 3 55.43 X
14
- 7. P8180L-003 080/025 AK1.01/3.9/7B//P8100/B15//2020 ILT NRC R07
- Unit 1 is in Mode 6.
- Train A RHR is aligned for SHUTDOWN COOLING.
- Train B RHR is in STANDBY.
- 11 RHR PUMP TRIPS.
RCS average temperature will (1) and 12 RHR pump (2) start AUTOMATICALLY.
A. (1) RISE (2) WILL B. (1) RISE (2) WILL NOT C. (1) LOWER (2) WILL D. (1) LOWER 2-RI (2) WILL NOT Y KE Justifications:
- a. Incorrect. Plausible if the examinee incorrectly believes that RHR will auto start on high RCS temp.
- b. Correct.
- c. Incorrect. Plausible if examinee incorrectly believes that RHR purpose is to maintain temperature to prevent inadvertant reactivity addition by lowering temperature.
- d. Incorrect. Plausible if examinee incorrectly believes that in mode 6 the RHR pump is maintained running as an RCS heat load.
15
2020 ILT NRC EXAM RO EXAM K/A Number:
025 Loss of RHR System AK1.01:
Knowledge of the operational implications of the following concepts as they apply to Loss of Residual Heat Removal System:
Loss of RHRS during all modes of operation Technical Reference(s): B15 pg 7 and 8 Proposed references to be provided to applicants during examination: NONE.
Learning Objective: P8180L-003 Obj. 7B Predict the response of the system to a component failure.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam NA Question Cognitive Level:
Comprehension or Analysis 10 CFR Part 55 Content:
Y Memory or Fundamental Knowledge X
KE Comments:
55.41 2 55.43 16
- 8. P8172L-002 205/026 AK3.03/4.0/5.A.//P8100/1ES-1.2//2020 ILT NRC R08
- A large break LOCA has occurred.
RECIRCULATION mode because Y
Based on the above indications ONLY, train (1) of RHR will be placed in (2) .
KE A. (1) A (2) train B can NOT remove decay heat B. (1) A (2) train B is providing cooling to 12 RCP C. (1) B (2) train A can NOT remove decay heat D. (1) B (2) train A is providing cooling to 11 RCP 3-SPK Justifications:
- a. Correct.
- b. Incorrect. Plausible if the examinee incorrectly believes that RHR and not charging provides seal cooling to RCPs.
- c. Incorrect. Plausible if the examinee incorrectly believes that RHR is cooled by cooling water and that, when travel stops are removed, the load CC puts on the system chokes RHR.
- d. Incorrect. Plausible if the examinee incorrectly believes that one train of CC must be available to provide cooling to the RCP thermal barrier.
17
2020 ILT NRC EXAM RO EXAM K/A Number:
026 Loss of Component Cooling Water AK3.03:
Knowledge of the reasons for the following responses as they apply to the Loss of Component Cooling Water:
Guidance actions contained in EOP for Loss of CCW.
K/A Value: 4.0 Technical Reference(s): 1ES1.2 pg 4 and bases pg 3 Proposed references to be provided to applicants during examination: None Learning Objective: P8172L-002 Obj. 5A State the functional interrelationship between the Component Cooling System and the following systems, also predict the effect of a loss of Component Cooling on each system: RHR.
Question Source: Bank # X Modified Bank #
New Y
Question History: Last NRC Exam 2018 ILT / 2019 Biennial Question Cognitive Level:
Memory or Fundamental Knowledge KE Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 8 55.43 X
18
- 9. P8170L-005 082/027 AK2.03/2.6/7B//P8100/1C51.3//2020 ILT NRC R09
- Unit 1 is at 100% power.
- 47012-0408, PRZR Hi/Lo Press, ALARMS.
- 47012-0608, PRZR Control Hi Press or Backup Heaters On, ALARMS.
Y KE The crew observe...
A. PRZR PORV PCV-430 OPEN.
B. PRZR PORV PCV-431 OPEN.
C. PRZR SPRAY VALVES OPEN.
D. PRZR BACKUP HEATERS ENERGIZE.
1-I Justifications:
- a. Incorrect. Plausible if the examinee incorrectly believes that the BLUE channel is the interlock channel vice the controlling channel and is the only input needed to open PRZR PORV PCV-430.
- b. Plausible if the examinee incorrectly believes that controlling BLUE channel is the only input needed to open PRZR PORV PCV-431.
- c. Correct.
- d. Incorrect. Plausible if the examinee incorrectly believes the failure will energize based on the fact that that 47012-0608 PRZR Control HI Press or Backup Heaters on has alarmed.
19
2020 ILT NRC EXAM RO EXAM K/A Number:
027 Pressurizer Pressure Control System Malfunction.
AK2.03:
Knowledge of the interrelations between the Pressurizer Pressure Control Malfunctions and the following:
Controllers and positioners.
K/A Value: 2.6 Technical Reference(s): 1C51.3 Pressurizer Pressure 1P-431 - HIGH Page 1 Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-005 Obj. 7b Predict the response of the system to a component failure.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level: Y N/A Memory or Fundamental Knowledge KE Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 7 55.43 X
20
- 10. P8197L-014 071/029 EK3.10/4.1/7//P8100/FR-S.1//2020 ILT NRC R10
- Unit 2 is at 100% power.
- Both Unit 2 main feedwater pumps LOCKOUT.
- Unit 2 reactor FAILS to trip automatically and manually.
- The crew has entered 2FR-S.1 Response to Nuclear Power Generation/ATWS.
The crew will manually insert control rods to...
A. lower reactor power.
B. displace boron from the reactor.
C. meet a technical specification action.
D. activate the reactor protection system.
1-B Justifications:
A. Correct. Y B. Incorrect. Plausible if the examinee incorrectly believes that displacing boron would add negative KE reactivity to the core..
C. Incorrect. Plausible if the examinee incorrectly believes control rod insertion is required to meet a technical specification requirement.
D. Incorrect. Plausible if the examinee incorrectly believes control rod insertion would or could cause the reactor protection system to trip the reactor after it has already failed to do so.
21
2020 ILT NRC EXAM RO EXAM K/A Number:
029 ATWS EK3.10:
Knowledge of the reasons for the following responses as they apply to the ATWS:
Manual rod insertion.
K/A Value: 4.1 Technical Reference(s): 2FR-S.1 Background info page 1 Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-014 Obj. 7 For FR-S.1: Explain the purpose for any step[ or step sequence for associated E or FR series EOP.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y N/A Memory or Fundamental Knowledge Comprehension or Analysis X
KE 10 CFR Part 55 Content:
Comments:
55.41 10 55.43 22
- 11. P8197L-013 120/038 EK3.01/4.1/6//P8100/2E-3//2020 ILT NRC R11
- A SGTR has occurred in 21 Steam Generator.
- The crew is on step 29 of 2E-3, Steam Generator Tube Rupture.
The crew will equilize RCS pressure and 21 Steam Generator pressure to ...
A. obtain adequate subcooling.
B. minimize RCS to secondary leakage.
C. maintain 21 Steam Generator chemistry.
D. minimize thermal stress on 21 Steam Generator.
1-B Justifications:
B. Correct.
Y A. Incorrect. Plausible if the examinee incorrectly believes that equilizing pressure vice cooling down is the action needed to obtain adequate subcooling in E-3.
C. Incorrect. Plausible if the examinee incorrectly believes that stopping leakage into the the ruptured SG is for chemitry concerns in the ruptured SG.
D. Incorrect. Plausible if the examinee incorrectly believes that equlizing pressures will is to minimize KE thermal strees in the ruptured SG.
23
2020 ILT NRC EXAM RO EXAM K/A Number:
038 Steam Generator Tube Rupture EK3.01:
Knowledge of the reasons for the following responses as they apply to the SGTR:
Equalizing pressure on primary and secondary sides of ruptured S/G.
K/A Value: 4.1 Technical Reference(s): 2E-3 Background Information pg 17 Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-013 Obj. 6 For E-3: Explain the purpose for any step or step sequence for associated E series EOP.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y N/A Memory or Fundamental Knowledge Comprehension or Analysis X
KE 10 CFR Part 55 Content:
Comments:
55.41 10 55.43 24
- 12. P8197L-012 258/E12 EK2.1/3.4/44//P8100/1ECA-2.1//2020 ILT NRC R12
- The crew is on Step 1 of 1ECA-2.1, Uncontrolled Depressurization of Both Steam Generators.
Y KE CV-31084, 11 SG PWR OPER RLF, CV-31127, A MAIN FW, (2)
(1) in the CORRECT POSITION.
in the CORRECT POSITION.
A. (1) IS (2) IS B. (1) IS (2) IS NOT C. (1) IS NOT (2) IS D. (1) IS NOT (2) IS NOT 25
2020 ILT NRC EXAM RO EXAM 3-SPR Justifications:
- a. Incorrect. 11 PORV is OPEN and should be CLOSED. Plausible if the examinee incorrectly believes that since the deviation matches the output, the valve is in the correct. position.
- b. Incorrect. 11 PORC is OPEN should should be CLOSED. A MFRV is correctly positioned. Plausible if the examinee incorrectly believes that a secondary "feed and bleed" should be established on A steam generator.
- c. Correct.
- d. Incorrect. A MFRV is in the correct (closed) position. Plausible if the examinee incorrectly believes that .
K/A Number:
E12 EK2.1 Knowledge of the interrelations between the Uncontrolled Depressurization of all Steam Generators and the following:
Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
K/A Value: 3.4 Y
Technical Reference(s): 1ECA-2.1 pg. 3 Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-012 Obj. 44 KE Identify any steps tha must be performed in ECA-2.1 and what indications are available in the control room for verification of those steps.
Question Source: Bank # X Modified Bank #
New Question History: Last NRC Exam Question Cognitive Level:
2019 LOR NRC Exam Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content:
55.41 7 55.43 Comments:
26
- 13. P8180L-007 131/054 2.4.20/3.8/6//P8100/1E-2//2020 ILT NRC R13
- 13 Condensate Pump is OOS.
- 11 & 12 Condensate Pumps are locked out.
- 11 Steam Generator is FAULTED inside Containment.
- 12 Steam Generator is RUPTURED.
Y KE Question continued on next page.
27
- 13. P8180L-007 131/054 2.4.20/3.8/6//P8100/1E-2//2020 ILT NRC R13 Question continued from previous page.
Which of the following steam supply valve configurations is CORRECT when step 4 of 1E-2, Steam Generator Isolation, is complete?
A.
Y B.
C.
KE D.
3-SPR Justifications:
- a. Incorrect. Plausible if examinee incorrectly believes that BOTH steam supplies must remain open; however, in this case only the 11SG is faulted and the crew will close the A SG supply to the 11 TD AFWP.
- b. Incorrect. Plausible if examinee incorrectly confuses which steam supply comes from which SG.
- c. Correct. Step 4 tells the crew to isolate the steam supply from the faulted SG. The 'caution' preceeding this step requires that a steam supply to the TD AFWP must be maintained if the TD AFWP is the only available source. Since there are no condensate pumps available, the MFPs are also not available, leaving the TD AFWP as the only source.
- d. Incorrect. Plausible if examinee incorrectly believes the MFPs are still available.
28
2020 ILT NRC EXAM RO EXAM K/A Number:
054 2.4.20 Knowledge of operational implications of EOP warnings, cautions, and notes.
K/A Value: 3.8 Technical Reference(s): 1E-2, step 4; pg. 4 Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-007 Obj. 6 Recall precautions, limitations, and hazards associated with system operation, their bases, and required safety equipment.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y N/A Memory or Fundamental Knowledge Comprehension or Analysis X KE 10 CFR Part 55 Content:
Comments:
55.41 10 55.43 29
- 14. P8197L-011 240/056 AA1.33/3.3/F//P8100/ECA-0.0//2020 ILT NRC R14
- The crew is performing 1ECA-0.0, Loss of All Safeguards Power.
- RCS pressure is 2150 psig and LOWERING.
Y KE The crew will...
A. CLOSE pressurizer PORV 1PCV-430 only.
B. OPEN pressurizer PORV 1PCV-431C only.
C. OPEN BOTH pressurizer PORV Block valves.
D. CLOSE BOTH pressurizer PORV Block valves.
30
2020 ILT NRC EXAM RO EXAM 1-P Justifications:
- a. Correct. Per step 1 of ECA-0.0, the crew will verify both PRZR PORVs are closed and if they are not, will manually close PRZR PORVs. The block valves were open before the loss of power and are therefore assumed by the crew to still be open and will not be closed in this step. Also, the block valves are required to be maintained open in the event a bleed path is needed.
- b. Incorrect. Plausible if examinee incorrectly believes PORVs should be opened in this step.
- c. Incorrect. Plausible if examinee incorrectly believes the PORV block valves are closed.
- d. Incorrect. Plausible is examinee incorrectly believes the PORV block valves should be closed.
K/A Number:
056 AA1.33 Ability to operateand/or monitor the following as they apply to the LOOP:
PORV block valve control switch.
K/A Value: 3.3 Technical Reference(s): ECA-0.0 Proposed references to be provided to applicants during examination: None Y
Learning Objective: P8197L-011 Obj. F Given a procedural step or series of steps, state the purpose/basis for the step: ECA-0.0 Question Source: Bank #
KE Question Cognitive Level:
Modified Bank #
New X Question History: Last NRC Exam Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
N/A X
55.41 10 55.43 Comments:
31
- 15. P8186L-015 032/057 AA2.04/3.7/7A//P8100/B20.8//2020 ILT NRC R15 Panel ___________________ is DE-ENERGIZED.
A. 111 Instrument Bus II B. 112 Instrument Bus I C. 113 Instrument Bus III Y
2-RI KE D. 114 Instrument Bus IV Justifications:
- a. Incorrect. Plausible if examinee incorrectly believes the RED channel is Panel 111 Instrument Bus II.
- b. Correct. RED channel Panel 112 instrument Bus I is conventionally listed first on panels (red, white, blue, yellow) and procedures but is out of order WRT numbering (112-1, 111-2, 113-3, 114-4).
- c. Incorrect. Plausible if examinee incorrectly believes red channel is Bus III.
- d. Incorrect. Plausible if examinee incorrectly believes red channel is Bus IV.
32
2020 ILT NRC EXAM RO EXAM K/A Number:
057 AA2.04 Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus:
ESF system panel alarm annunciators and channel status indicators.
K/A Value: 3.7 Technical Reference(s): B20.8; pg. 5 Proposed references to be provided to applicants during examination: None Learning Objective: P8186L-015 Obj. 7a Predict the response of the system to a loss of power.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y Memory or Fundamental Knowledge Comprehension or Analysis N/A X
KE 10 CFR Part 55 Content:
Comments:
55.41 7 55.43 33
- 16. PI-OPS-GFE-192008 005/007 EK1.05/3.3/4.3//P8100/PI-OPS-GFE-192008//2020 ILT NRC R16
- Unit 1 has been operating at 100% power for several weeks.
- Unit 1 reactor spuriously TRIPS.
- No operator actions occur.
After FIVE MINUTES, Start Up Rate (SUR) is...
A. NEGATIVE 5 DPM.
B. NEGATIVE 1/3 DPM.
C. POSITIVE 1/3 DPM.
D. POSITIVE 5 DPM.
1-I Justifications:
Y
- a. Incorrect. Plausible if the examinee incorrectly believes that the observed SUR is due to power coming down from 100% to below 5%.
KE
- b. Correct.
- c. Incorrect. Plausible if the examinee incorrectly believes that SUR reads the absolute value of actual power change.
- d. Incorrect. Plausible if the examinee incorrectly believes that the turbine has not tripped and power will attempt to maintain tavg at tref.
34
2020 ILT NRC EXAM RO EXAM K/A Number:
007 Reactor Trip - Stabilization - Recovery / 1 EK1.05 Knowledge of the operational implications of the following concepts as they apply to the reactor trip:
Decay power as a function of time.
K/A Value: 3.3 Technical Reference(s): PI-OPS-GFE-192008 Reactor Operational Physics - Student Guide page 43 Proposed references to be provided to applicants during examination: None Learning Objective: PI-OPS-GFE-192008 Obj. 4.3 Describe the realtionship between heat generation, power history, and time after reactor shutdown.
Question Source: Bank #
New X Question History: Last NRC Exam Y
Modified Bank #
N/A KE Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 1 55.43 X
35
- 17. P8178L-005 012/065 AA2.08/2.9*/7B//P8100/C34 AOP1//2020 ILT NRC R17
- Unit 1 is at 100% power.
- CV-31740, Unit 1 CNTMT INSTR AIR, fails CLOSED.
Which of the following is(are) still AVAILABLE?
NORMAL LETDOWN EXCESS LETDOWN A. Available Available B. Available NOT Available C. NOT Available Available D. NOT Available NOT Available 1-I Justifications:
Y
- a. Incorrect. Plausible if examinee incorrectly believes normal and excess L/D would still be available.
- b. Incorrect. Plausible as excess L/D isolates and if examinee incorrectly believes that normal L/D is still available; however, in this case normal L/D will also isolate.
- c. Incorrect. Plausible as normal L/D isolates and if examinee incorrectly believes that excess L/D is still available; however, in this case excess L/D will also isolate.
KE
- d. Correct. Normal and Excess L/D will isolate and cannot be re-established without IA.
36
2020 ILT NRC EXAM RO EXAM K/A Number:
065 Loss of Instrument Air AA2.08:
Ability to determine and interpret the following as they apply to the Loss of Instrument Air:
Failure modes of air operated equipment.
Technical Reference(s): C34 AOP1 Att. A, pg. 30; Att. C, pg. 39 Proposed references to be provided to applicants during examination: None Learning Objective: P8178L-005 Obj. 7b Predict the response of the system to a component failure.
Question Source: Bank # ____
Modified Bank #
New X Question History: Last NRC Exam NA Question Cognitive Level:
Comprehension or Analysis 10 CFR Part 55 Content:
Y Memory or Fundamental Knowledge 55.41 4 X
KE Comments:
55.43 37
- 18. P8197L-014 226/E05 EK2.2/3.9/23//P8100/1FR-H.1//2020 ILT NRC R18
- The crew is establishing RCS bleed and feed per 1FR-H.1, Response to Loss of Secondary Heat Sink.
To establish the BLEED path, the crew will OPEN the...
A. Pressurizer PORVs.
B. Steam Generator PORVs.
C. Main Steam Isolation Valves (MSIVs).
D. Letdown Line CTMT Isolation control valve.
1-P Justifications:
- a. Correct.
Y
- b. Incorrect. Plausible as SG PORVs can be used for decay heat removal; however, in this case the SGs are not available because B&F is being established and SGs cannot be used for a bleed path.
- c. Incorrect. Plausible as MSIVs and steam dumps can be used for DHR; however, in this case the SGs are not available because B&F is being established and SGs cannot be used for a bleed path.
- d. Incorrect. Plausible if examinee incorrectly believes letdown ccan be used for B&F.
KE 38
2020 ILT NRC EXAM RO EXAM K/A Number:
E05 Loss of Secondary Heat Sink EK2.2:
Knowledge of the interrelations between the (Loss of Secondary Heat Sink) and the following:
Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
K/A Value: 3.9 Technical Reference(s): 1FR-H.1 pg. 10 Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-014 Obj. 23 For FR-H.1, describe the major action categories.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y N/A KE Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 8 55.43 X
39
- 19. P8184L-005 146/003 2.4.18/3.3/6//P8100/1C5 AOP4//2020 ILT NRC R19 During performance of 1C5 AOP4, Dropped RCCA, diverse indication is used to CONFIRM a DROPPED ROD to ensure a has not been misdiagnosed.
A. RPI FAILURE B. REACTOR TRIP C. SAFETY INJECTION D. CONTROL ROD EJECTION 1-P Justifications:
- a. Correct.
Y
- b. Incorrect. Plausible if the examinee incorrectly believes that 47013-0407, ROD AT BOTTOM, would only be lit during a reactor trip.
- c. Incorrect. Plausible if examinee incorrectly believes that the Tavg and NIS changes used as diverse indication would be caused by an SI and a single rod would not produce noticable changes.
- d. Incorrect. Plausible if examinee incorrectly believes the purpose of checking tavg and NIS is not to observe a change but to observe the direction of the change to determine whether a rod has suddenly KE been inserted or removed.
40
2020 ILT NRC EXAM RO EXAM K/A Number:
003 Dropped Control Rod 2.4.18 Knowldege of the specific bases for EOPs.
Technical Reference(s): 1C5 AOP4, pg 3 Proposed references to be provided to applicants during examination: None Learning Objective: P8184L-005 Obj. 6 Recall precautions, limitations, and hazards associated with system operation, their bases and required safety equipment.
Question Source: Bank # _______
Modified Bank # _______
New ___X____
Question History: Last NRC Exam ___N/A_________
Question Cognitive Level:
Y Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
55.41 _10___
__X__
KE Comments:
55.43 _____
41
- 20. P8184L-005 149/005 AA1.03/3.4/7//P8100/LCO 3.1.6/COLR/2020 ILT NRC R20
- Unit 1 is at 50% power.
- Control Rod Bank D is at 200 steps.
- Rod G11 is STUCK and INOPERABLE.
- 1) Per the Core Operating Limits Report, what are Rod Control Bank D ROD INSERTION LIMITS?
- 2) Is LCO 3.1.6, Control Bank Insertion Limits, MET?
A. 1) 175
- 2) YES B. 1) 175
- 2) NO C. 1) 224
- 2) YES D. 1) 224 Y
3-SPR KE
- 2) NO Justifications:
- a. Correct.
- b. Incorrect. Plausible if the examinee incorrectly believes that rods are inserted from the bottom similar to BWR.
- c. Incorrect. Plausible if the examinee incorrectly believes that rods are insreted from the bottom of the core similar to a BWR AND incorrectly believes that rods should be fully inserted to compensate for the stuck rod.
- d. Incorrect. Plausible if the examinee incorrectly believes that rods should be fully withdrawn to compensate for a rod that can not drop.
42
2020 ILT NRC EXAM RO EXAM K/A Number:
005 Inoperable/Stuck Control Rod AA1.03:
Ability to operate and/or montor the following as they apply to the Inoperable/Stuck Rod:
Metroscope K/A Value: 3.4 Technical Reference(s): COLR Page 24, LCO 3.1.6.
Proposed references to be provided to applicants during examination: Page 24 COLR Learning Objective: P8182L-005 Obj. 7 Predict the response of the system to a component failure.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y N/A Memory or Fundamental Knowledge Comprehension or Analysis X
KE 10 CFR Part 55 Content:
Comments:
55.41 10 55.43 43
- 21. P8184L-002 120/033 AA2.04/3.2/3//P8100/B9A//2020 ILT NRC R21
- Unit 1 is performing a Startup.
Y Intermediate Range Nuclear Instrument, (1) , is FAILED.
KE P-10, Nuclear At Power Permissive, A. (1) N35 (2) IS B. (1) N35 (2) IS NOT (2) MET.
C. (1) N36 (2) IS D. (1) N36 (2) IS NOT 1-I Justifications:
- a. Incorrect. Plausible if the examinee incorrectly believes that P-10 permissive is MET below 10% power.
- b. Correct.
- c. Incorrect. Plausible if the examinee incorrectly believes that Intermediate range should NOT be on scale at this power level and the P-10 is met below 10% power
- d. Incorrect. Plausible if the examinee incorrectly believes that Intermediate range should not be on scale at this power level.
44
2020 ILT NRC EXAM RO EXAM K/A Number:
033 Loss of Intermediate Range AA2.04:
Ability to determine and interpret the following as they apply ot the Loss of Intermediate Range Nuclear Instrumentation:
Satisfactory overlap between source range, intermediate range, and power range instrumentation.
K/A Value: 3.2 Technical Reference(s): B9A-1 Proposed references to be provided to applicants during examination: None Learning Objective: P8184L-002 Obj. 3 For Nuclear Instrumentation ranges describe the normal values of significant indications and relationship between values.
Question Source: Bank #
New X Question History: Last NRC Exam Y
Modified Bank #
N/A KE Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 2 55.43 X
45
- 22. P8182L-003 105/036 AK3.02/2.9/5//P8100/C17 AOP1//2020 ILT NRC R22
- The crew is performing checkerboarding in the Spent Fuel Pool.
- While lifting a fuel module, the OVERLOAD light illuminates on the pendant.
- The crew is performing C17 AOP1, New and Spent Fuel Bridge Crane Malfunction.
- The Fuel Handling Supervisor and the Nuclear Engineer have determined that the overload indication is VALID.
The crew will...
A. RESET the overload condition.
B. RAISE Spent Fuel Pool Level for shielding.
C. RAISE the hoist to relieve the overload condition.
Y D. SUSPEND crane operations and investigate further.
1-I KE Justifications:
- a. Incorrect. Plausible if the examinee incorrectly believes that reset of the overload condition is performed to validate the FHS determination.
- b. Incorrect. Plausible if the examinee incorrectly believes that the fuel is out of the water and if allowed to dry out would create a high airborn alarm.
- c. Incorrect. Plausible if the examinee incorrectly believes that the overload light is illuminated until a load is placed on the hook.
- d. Correct.
46
2020 ILT NRC EXAM RO EXAM K/A Number:
036 Fuel Handling Incidents AK3.02:
Knowledge of the reasons for the following responses as they apply to the Fuel Handling Incidents:
Interlocks assoicated with fuel handling equipment.
K/A Value: 2.9 Technical Reference(s): C17 AOP 1 pg 4 Proposed references to be provided to applicants during examination: None Learning Objective: P8182L-003 Obj. 5 Recall precautions limitations and hazards associated with system operation, their bases, and required safety equipment.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y N/A KE Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 10 55.43 X
47
- 23. P8140L-242 123/037 AK1.01/2.9/A.5.//P8100/STEAM TABLES//2020 ILT NRC R23
- ERCS is OOS.
- RCS pressure is 965 psig.
- RCS Core Exit Temperature is 560 °F.
- Containment is NOT adverse.
The RCS is...
A. SUPERHEATED.
B. SATURATED.
C. SUBCOOLED BETWEEN 0 and 21 °F.
D. SUBCOOLED BETWEEN 21 and 41 °F.
3-SPR Justifications:
- a. Correct.
Y
- b. Incorrect. Plausible if the examinee incorrectly believes that a liquid is saturated if there is any liquid still in the RCS.
- c. Incorrect. Plausible if the examinee incorrectly believes that subcooling is determined by dividing KE pressure by temperature.
- d. Incorrect. Plausible if the examinee incorrectly believes that subcooling is determined by subtracting current RCS temperature from saturated liquid enthalpy at the given pressure.
48
2020 ILT NRC EXAM RO EXAM K/A Number:
038 Steam Generator Tube Leak AK1.01:
Knowledge of the operation implications of the following concepts as they apply to the SGTL:
Use of steam tables.
K/A Value: 2.9 Technical Reference(s): Steam Tables Proposed references to be provided to applicants during examination: Steam Tables Learning Objective: P8197L-013 Obj. A.5.
For 1C4 AOP2, SGTL, explain the purpose and sequence for major steps.
Question Source: Bank #
Modified Bank # P8197L-013 121 New Question History: Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X KE 10 CFR Part 55 Content:
Comments:
55.41 5 55.43 49
- 24. P8174L-005 051/51 AA2.02/3.9/6//P8100/FIG C1-20//2020 ILT NRC R24
- Unit 1 is at 100% power.
Condenser the reactor.
(1)
Y is the most limiting, and the Reactor Operator (2) TRIP KE A. (1) 1A (2) WILL B. (1) 1A (2) WILL NOT C. (1) 1B (2) WILL D. (1) 1B (2) WILL NOT 3-PEO Justifications:
- a. incorrect. plausible if the examinee incorrectly believes the differential pressure warrants a reactor trip.
- b. Correct.
- c. incorrect. Plausible if the examinee incorrectly believes that the highest vacuum is actually the highest pressure and most limiting AND that the examinee incorrectly believes that the differential pressure warrants a reactor trip.
- d. incorrect. plausible if the examinee incorrectly believes that the highest vacuum is actually the highest pressure and thus most limiting.
50
2020 ILT NRC EXAM RO EXAM K/A Number:
051 Loss of Condenser Vacuum AA2.02:
Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum:
Conditions requiring reactor and/or turbine trip.
K/A Value: 3.9 Technical Reference(s): FIG C1-20, C47008-0108 Proposed references to be provided to applicants during examination: None Learning Objective: P8174L-005 Obj. 6 For the Main Turbine, recall precautions limitations and hazards associated with system operation their bases and required safety equipment.
Question Source: Bank #
Modified Bank # P8174L-005 029 New Question History: Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge KE Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 5 55.43 X
51
- 25. P8182L-001A 072/059 AK1.01/2.7/3.1/3J//P8100/B21B/B21B-2/2020 ILT NRC R25
- 1R-30, Unit 1 Aux Building Vent Radiation Monitor, is alarming at 1000 CPM.
- The HP Technicians have determined the cause to be dissolved fission gases from an accidental liquid release.
The source of the alarm is from _________(1)_________ radiation in the
_________(2)_________ .
A. (1) Neutron & Alpha (2) Waste Holdup Tank B. (1) Neutron & Alpha (2) Volume Control Tank C. (1) Beta-Gamma (2) Reactor Makeup Tank D. (1) Beta-Gamma 1-S (2) Non-Aerated Sump Tank Justification:
Y KE
- a. Incorrect. The WHT recieves water from floor drains and would not have any delayed neutrons or alpha radiation.
- b. Incorrect. VCT would not have any delayed neutron radiation.
- c. Incorrect. RMU tank is processed water and has no radiation concerns.
- d. Correct. The Non-Aerated Sump Tank would not have nuclear fuel leakoff therefore no neutron or alpha radiation; however, since it does accept water from the following drains: CVCS HUT, seal water return filter, letdown filter, low level waste gas decay tank, VCT, RC filter, etc., B-g radiation in the NAST is the only plausible source.
52
2020 ILT NRC EXAM RO EXAM 059 AK1.01:
Knowledge of the operational implications of the following concepts as they apply to Accidental Liquid Radwaste Release:
Types of radiation, their units of intensity and the location of the sources of radiation in a nuclear power plant Technical Reference(s): B21B , B21B-2 Proposed references to be provided to applicants during examination: None Learning Objective: P8182L-001A 3j For the WHT, VCT, RMU, and NAST describe the normal values of significant indications and relationships between values.
Question Source: Bank # _______
Modified Bank # __P8182L-001A 071____
New _______
Question History: Last NRC Exam ___________
Question Cognitive Level:
Comprehension or Analysis 10 CFR Part 55 Content:
Y Memory or Fundamental Knowledge 55.41 _12_
__X__
KE Comments:
55.43 _____
53
- 26. P8176L-003 090/W/E15 EA1.1/2.9/7//P8100/47016-0304//2020 ILT NRC R26
- 47016-0304, CONTAINMENT SUMP A HI LVL, is ALARMING.
Y KE The operator will secure cooling water to CFCU.
A. 11 B. 12 C. 13 D. 14 54
2020 ILT NRC EXAM RO EXAM 3-SPK Justifications:
- a. Incorrect. Plausible if the examinee incorrectly believes that 11 is not already secured.
- b. Correct.
- c. Incorrect. Plausible if the examinee incorrectly believes that 13 is overpowering 14 (similar to CC pumps).
- d. Incorrect. Plausible if the examinee incorrectly believes that the low flow is indication of a plugged line.
K/A Number:
W/E15 Containment Flooding EA1.1:
Ability to operate and/or monitor the following as they apply to the (containment flooding):
Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
K/A Value: 2.9 Technical Reference(s): C47016-0304 Proposed references to be provided to applicants during examination: None Learning Objective: P8176L-003 Obj 7 Y
For Cooling Water, predict the response of the system to a component failure.
Question Source: Bank #
KE Question Cognitive Level:
Modified Bank #
New X Question History: Last NRC Exam Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
N/A X
55.41 4 55.43 Comments:
55
- 27. P8197L-012 007/003 EK2.2/3.7/16//P8100/ES-1.1//2020 ILT NRC R27
- 1ES-1.1, Post LOCA Cooldown and Depressurization, is in progress.
- RCS pressure is 1500 psig and STABLE.
- Pressurizer Level is 78% and STABLE.
- Two SI Pumps are RUNNING.
- A Safety Injection Pump is STOPPED.
RCS SUBCOOLING will (1) and pressurizer LEVEL will (2) .
A. (1) RISE (2) RISE B. (1) RISE (2) LOWER C. (1) LOWER (2) RISE D. (1) LOWER (2) LOWER 3 - PEO Y
KE
- a. Incorrect. Plausible as the purpose of most EOPs is to raise RCS subcooling and pressurizer level; however, not in this case.
- b. Incorrect. Plausible as pressurizer level will lower; however, RCS subcooling would lower due to pressure lowering when stopping the SI pump.
- c. Incorrect. Plausible as RCS subcooling would lower; however, pressurizer level would lower due to pressure lowering when stopping the SI pump.
- d. Correct.
56
2020 ILT NRC EXAM RO EXAM K/A Number:
W/E03 LOCA Cooldown - Depressurization EAK2.2:
Knowledge of the interrelations between the (LOCA Cooldown and Depressurization) and the following:
Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
K/A Value: 3.7 Technical Reference(s): 1ES-1.1 info page Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-012 Obj. 16 Explain all notes or cautions as to their purpose and operational implications for associated E series EOP.
Question Source:
Y Bank # P8197L-012 007 Modified Bank #
New Question History: Last NRC Exam 2017 LOR KE Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 10 55.43 X
57
- 28. P8140L-209 013/003 2.1.32/3.8/4.0/4//98100/C3/1C1.2-M5/2020 ILT NRC R28
- Unit 1 is in MODE 5, Cold Shutdown.
- The crew is performing section 5.6 of 1C1.2-M5, STARTUP TO MODE 5.
- RCS pressure is 300 psig.
- 12413, 11 SG SKIN TI, is 175 °F.
- 12414, 12 SG SKIN TI, is 157 °F.
- 1T0406A, RCS A TCOLD 450B, is 150 °F.
- 1T0426A, RCS B TCOLD 451B, is 150 °F.
RCPs can NOT be started because...
A. Steam Generator Skin temps are BOTH too LOW.
B. Steam Generator Skin temps are BOTH too HIGH.
Y C. limiting RCS to SG temperature difference is too LOW.
D. limiting RCS to SG temperature difference is too HIGH.
3-SPK KE Justifications:
- a. Incorrect. Plausible if examinee incorrectly believes the only requirement is for SG skin temp to be
>88°F per step 5.6.4.
- b. Incorrect. Plausible as 12 RCP is not allowed to be started and if examinee incorrectly believes that there must be MINIMUM 15 degrees of difference to ensure that heat transfer occurs.
- c. Incorrect. Plausible as 11 RCP is not allowed to be started and if examinee incorrectly believes that 12 RCP can be started because 12 skin temp is within 15 degrees of the associated RCP.
- d. Correct. Per C3 Limitation 4.4, SG skin temp and RCS temp must be within 15°F before starting ANY RCP in order to minimize pressure transients.
58
2020 ILT NRC EXAM RO EXAM K/A Number:
003 Reactor Coolant Pump 2.1.32:
Ability to explain and apply all system limits and precautions.
K/A Value: 3.8/4.0 Technical Reference(s): C3 pg.6; 1C1.2-M5 pgs. 32-33 Proposed references to be provided to applicants during examination: C3 page 6 Learning Objective: P8140L-209 Obj. 4 For 1C1.2-M5 and C3, explain any limitations.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam _________
Question Cognitive Level:
Comprehension or Analysis 10 CFR Part 55 Content:
Y Memory or Fundamental Knowledge X
KE Comments:
55.41 10 55.43 59
- 29. P8172L-001A 161/004 A1.12/2.8/3.2/4A//P8100/2C12.5//2020 ILT NRC R29
- Unit 2 is at end of core life.
- The crew is placing the 21 Deborating IX in service.
- The previous dilution was 200 gallons.
Y KE In accordance with 2C12.5, Unit 2 Boron Concentration Control, the crew will place the 21 Deborating IX in service for approximately __________ minutes.
A. 0.73 B. 1.7 C. 5 D. 12.5 2-DR Justifications:
- a. Incorrect. Plausible if examinee incorrectly confuses letdown pressure with letdown flow.
- b. Incorrect. Plausible if examinee incorrectly beleives that the normal boration rate should be used rather than the last boration volume.
- c. Correct.
- d. Incorrect. Plausible if examinee incorrectly believes letdown flow solely consists of CVCS make up to RCS through RCP seals and that the letdown flow matches makeup.
60
2020 ILT NRC EXAM RO EXAM K/A Number:
004 Chemical and Volume Control System A1.12:
Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls including:
Rate of boron concentration reduction in RCS as a function of letdown flow while deborating demineralizer is in service.
K/A Value: 2.8 Technical Reference(s): 2C12.5 pg. 32 Proposed references to be provided to applicants during examination: 2C12.5 pg 32 Learning Objective: P8172L-001A Obj. 4A Describe the system flowpath and major components for normal operations.
Question Source: Bank #
New X Question History: Last NRC ExamY Modified Bank #
N/A KE Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 6 55.43 X
61
- 30. PI-OPS-GFE-192004L 004/004 K5.15/3.3/5//P8100/B12A//2020 ILT NRC R30
- BOTH Units are at 100% power and stable.
- Unit 1 is at the BEGINNING of core life.
- Unit 2 is at the END of core life.
- An uncontrolled BORATION occurs on BOTH units.
Tavg will change MORE on (1) due to the (2) temperature coefficient.
A. (1) Unit 1 (2) MODERATOR B. (1) Unit 1 (2) FUEL C. (1) Unit 2 (2) MODERATOR D. (1) Unit 2 Y
2-DR KE (2) FUEL Justifications:
- a. Correct.
- b. Incorrect. Plausible if the examinee incorrectly believes that ITC over core life is driven by the change in FTC.
- c. Incorrect. Plausible if the examinee incorrectly believes that MTC approaches 0 as the core ages.
- d. Incorrect. Plausible if the examinee incorrectly believes that MTC approaches 0 as the core ages and the change in ITC over core life is driven by the change in FTC.
62
2020 ILT NRC EXAM RO EXAM K/A Number:
005 Chemical and Volume Control K5.15:
Knowledge of the operational implications of the following concepts as they apply to the CVCS:
Boron and control rod reactivity effects as they relate to MTC.
K/A Value: 3.3 Technical Reference(s): PI-OPS-GFE-192004L; Proposed references to be provided to applicants during examination: None Learning Objective: PI-OPS-GFE-192004L Obj. 1 Describe the moderator reactivity coefficient and how it is effected by changing reactor conditions.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y Memory or Fundamental Knowledge N/A KE Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 1 55.43 X
63
- 31. P8197L-006 029/005 K5.05/2.7*/3.1*/4//P8100/DOE FUND HB V 1/B15/2020 ILT NRC R31
- Unit 1 is in MODE 5.
- The PRZR is water solid.
- RHR Train A is aligned for shutdown cooling.
A small rise in RCS TEMPERATURE will cause a (1) rise in PRESSURE due to the relative(ly) (2) of water.
A. (1) SMALL (2) incompressability B. (1) SMALL (2) SMALL specific heat constant C. (1) LARGE (2) incompressability D. (1) LARGE (2) SMALL specific heat constant 3-PEO Y
KE Justifications:
- a. Incorrect. Pressure change will be large. Plausible if examinee incorrectly believes that water solid operations are similar to at power operations where water is still imcompressible but the system acts differently.
- b. Incorrect. Pressure change will be large and water has a large specific heat constant. Plausible if the examinee incorrectly believes that the change will be small because so little energy is required to raise temperature that it can not have a large impact on pressure.
c.Correct. Due to the incompressability of water, any small addition of energy to the system in the form of temperature will cause a correspondingly large increase in pressure.
- d. Incorrect. Water has a large specifc heat constant. Plausible if the examinee incorrectly believes that the system is unstable in this configuration due to the small amount of energy required to throw it out of balance.
64
2020 ILT NRC EXAM RO EXAM K/A Number:
005 RHR K5.05:
Knowledge of the operational implications of the following concepts as they apply to the RHRS:
Plant response during solid plant pressure change due to the relative incompressibility of water.
K/A Value: 2.7*/3.1*
Technical Reference(s): B15 pg 22; DOE Fundamentals - Thermodynamics Vol. 1 pg. 101 Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-006 Obj. 4 Using C1.3 series, explain the basis for the major steps in the procedure, and discuss the consequences of not performing the steps as delineated.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y N/A Memory or Fundamental Knowledge KE Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 14 55.43 X
65
- 32. P8180L-006 081/006 K4.30/3.6/4//P8100/1E-0 ATT L//2020 ILT NRC R32
- Small Break LOCA is in progress.
- Safety Injection is ACTUATED.
- Containment Isolation is ACTUATED.
- MSIVs are OPEN.
- Containment pressure is 11 psig.
Y KE The operator will...
A. NOT isolate Instrument Air to Containment.
B. close CV-31741, UNIT 1 CNTMT INSTR AIR, ONLY.
C. close CV-31740, UNIT 1 CNTMT INSTR AIR, ONLY.
D. close BOTH CV-31740, UNIT 1 CNTMT INSTR AIR, and CV-31741, UNIT 1 CNTMT INSTR AIR.
66
2020 ILT NRC EXAM RO EXAM 1-I Justifications:
- a. Correct.
- b. Incorrect. Plausible if the examinee incorrectly believes that only the valve inside the building must be closed for a successful containment isolation.
- c. Incorrect. Plausible if the examinee incorrectly believes that the CV-31740 is closed to prevent instrument air loss during containment integrity failure.
- d. Incorrect. Plausible if the examinee incorrectly belieives that instrument air is isolated any time containment is adverse.
K/A Number:
006 Emergency Core Cooling K4.30:
Knowledge of the ECCS design feature(s) and/or interlock(s) which provide for the following:
Containment Isolation.
K/A Value: 3.6 Technical Reference(s): 1E-0 Att L pg 3 Y
Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-006 Obj. 4 For the ESFAS, describe the system flowpath and major componets for emergency operations.
KE Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis N/A X
10 CFR Part 55 Content:
55.41 7 55.43 Comments:
67
- 33. P8170L-003 128/007 A2.03/2.6/3.2/4A//P8100/47012-0406/1C4/2020 ILT NRC R33 Y
KE The crew is required to (1)
(2) in the Pressurizer Relief Tank per A. (1) RAISE level (2) 1C4, Reactor Coolant System B. (1) RAISE level (2) 1C15, Residual Heat Removal System, Unit 1 C. (1) LOWER pressure (2) 1C4, Reactor Coolant System D. (1) LOWER pressure (2) 1C15, Residual Heat Removal System, Unit 1 68
2020 ILT NRC EXAM RO EXAM 3-PEO Justifications:
- a. Incorrect. Plausible if examinee incorrectly believes PRT level is low and should be raised for quench volume; however, in this case level is at the high end of the band (71.5% -76%)
- b. Incorrect. Plausible if examinee incorrectly believes PRT level is below the normal operating level and can be filled from the RWST.
- c. Correct.
- d. Incorrect. Plausible if examinee incorrectly believes that the PRT can be pumped down to containment sump B via RHR.
K/A Number:
007 Pressurizer Relief Tank System A2.02:
Ability to (a) predict the impacts of the following malfunctions or operations on the P S; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Abnormal pressure in the PRT Technical Reference(s): 1C4 pg. 7; C47012-0406 Question Source: Bank # X Y
Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-003 Obj. 4A Modified Bank #
KE New Question History: Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
55.41 3 2014 ILT NRC X
55.43 Comments:
69
- 34. P8170L-003 227/007 A3.01/2.7/4//P8100/47012-0506//2020 ILT NRC R34
- Instrument Air to Unit 1 Containment is ISOLATED and can not be restored.
- Pressure in the PRT is RISING.
- No operator actions occur.
The PRT...
A. heaters will energize.
B. will relieve to the RCS.
C. RUPTURE DISK will rupture.
D. will AUTOMATICALLY drain to the RCDT.
1-I Justifications:
Y
- a. Incorrect. The PRT does not have heaters. Plausible if the examinee incorrectly believes that pressurizer heaters are used to lower pressure and that the PRT is similarly equipped.
- b. Incorrect. The RCS is maintained at over 2K psi pressure and the PRT is maintained at low pressure.
Plausible if the examinee incorrectly believes that since the RCS can transfer volume to the PRT, the KE opposite must also be true.
- c. Correct. Site OE. With instrument air to containment isolated, the CVCS system will relieve to the PRT and the rupture disk will rupture.
Plausible if the examinee incorrectly believes that there is an automatic drain function to lower pressure in the PRT.
70
2020 ILT NRC EXAM RO EXAM K/A Number:
007 Pressurizer Relief/Quench Tank A3.01:
Ability to monitor automatic operation of the PRTS, including:
Components which discharge to the PRT.
K/A Value: 2.7 Technical Reference(s): C47012-0506 Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-003 Obj. 4 For the reactor coolant system, describe the system flowpach and major components for normal, abnormal, and emergency operations.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y N/A Memory or Fundamental Knowledge KE Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 3 55.43 X
71
- 35. P8172L-002 109/008 K3.03/4.1/6//P8100/C14 AOP1//2020 ILT NRC R35
- Unit 1 is at 100% power.
- Safety Injection is INADVERTANTLY ACTUATED.
RCP SEAL temperatures will (1) .
The Operator (2) TRIP the RCP.
A. (1) RISE (2) WILL B. (1) RISE (2) WILL NOT C. (1) REMAIN CONSTANT (2) WILL D. (1) REMAIN CONSTANT 1-I (2) WILL NOT Y
KE Justifications:
- a. Incorrect. CC will continue to be supplied to RCPs. Plausible if the examinee incorrectly believes that CC is isolated to RCPs on SI because RCPs are not safety related and that temperatues will rise .
- b. Incorrect. RCPs will still have cooling. Plausible if the examinee incorrectly believes that CC will be isolated but seal cooling from charging will maintain temperatures to prevent RCPs from needing to be tripped.
- c. Incorrect. RCPs will not need to be tripped in this scenario. Plausible if the examinee incorrectly believes that the RCPs are tripped whenever SI is actuated rather than only on some LOCAs.
- d. Correct.
72
2020 ILT NRC EXAM RO EXAM K/A Number:
008 Component Cooling Water K3.03:
Knowledge of the effect that a loss or malfunction of the CCWS will have on the following:
RCP.
K/A Value: 4.1 Technical Reference(s): 1C14 AOP1 pg 5 Proposed references to be provided to applicants during examination: None Learning Objective: P8172L-002 Obj. 6 Recall precautions, limitations, and hazards associated with system operation, their bases and required safety equipment.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y N/A Memory or Fundamental Knowledge X KE Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 10 55.43 73
- 36. P8170L-005 084/010 A4.02/3.6/3.4/3H//P8100/C7//2020 ILT NRC R36
- Pressurizer Backup Heaters are in AUTOMATIC.
- Pressurizer Spray Valves are in AUTOMATIC.
- 1HC-431K, Pressurizer Master Controller, is aligned as follows:
Y KE To energize Pressurizer Backup HEATERS, the operator will rotating the manual knob A. (1) RAISE (2) CLOCKWISE (2) .
(1) output by B. (1) RAISE (2) COUNTERCLOCKWISE C. (1) LOWER (2) CLOCKWISE D. (1) LOWER (2) COUNTERCLOCKWISE 74
2020 ILT NRC EXAM RO EXAM 2-RI Justifications:
- a. Incorrect. Plausible if examinee incorrectly believes that heaters will be energized by high output from the controller.
- b. Incorrect. Plausible if the examinee incorrectly believes that turning the manual knob will impact the deviation and incorrectly believes that heaters will be energized by high output from the master controller.
- c. Incorrect. Plausible if examinee incorrectly believes that turning the manualt dial will lower output on the controller.
- d. Correct.
K/A Number:
010 Pressurizer Pressure Control A4.02:
Ability to manually operate and/or monitor in the control room, including:
PZR heaters K/A Value 3.6 Technical Reference(s): C7 pg 33 Y
Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-005 Obj. 3H For each of the major system components, describe the control room controls and indications.
KE Question Source: Bank #
Modified Bank #
New Question History: Last NRC Exam Question Cognitive Level:
X Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content:
55.41 7 55.43 Comments:
75
- 37. P8170L-006 074/012 K6.02/2.9/7//P8100/B7//2020 ILT NRC R37
- BLUE channel Pressurizer LEVEL FAILED LOW.
- Bistables have been TRIPPED by I&C.
The reactor will AUTOMATICALLY TRIP if Pressurizer LEVEL (1) channel fails (2) .
A. (1) RED (2) LOW B. (1) RED (2) HIGH C. (1) YELLOW (2) LOW D. (1) YELLOW (2) HIGH 3-PEO Justifications:
Y
- a. Incorrect. Plausible if the examinee incorrectly believes that PRZR LVL has a low level trip setpoint KE similar to PRZR pressure.
- b. Correct. With bistables tripped, one channel is already in alert. Another failure in the direction of the trip setpoint would cause an automatic trip.
- c. Incorrect. Plausible if the examinee incorrectly believes that Yellow channel has a low level trip setpoint.
and that yellow and blue must both have channel in alert to cause a trip, similar to PORV operation.
- d. Incorrect. Plausible if the examinee incorrectly believes that yellow channel has a high level trip setpoint and that yellow and blue must both have channel in alert to cause a trip, similar to PORV operaiton.
76
2020 ILT NRC EXAM RO EXAM K/A Number:
012 Reactor Protection K6.02:
Knowledge of the effect of a loss or malfunction of the following will have on the RPS:
Redundant Channels.
K/A Value: 2.9 Technical Reference(s): B7 pg 74 Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-006 Obj. 7 For the pressurizer level control system, predict the response of the system to a component failure.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y Memory or Fundamental Knowledge N/A KE Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 5 55.43 X
77
- 38. P8186L-009 013/013 K2.01/3.6/RHR/SI LP//P8100/B15/B18A/2020 ILT NRC R38 What is the power supply to 11 SI Pump?
A. Bus 11 B. Bus 12 C. Bus 15 D. Bus 16 1-F Justifications:
- a. Incorrect. Plausible if the examinee incorrectly believes that the "11" signifies the bus.
- b. Incorrect. Plausible if the examinee incorrectly believes that bus 12 is the emergency pump bus.
- c. Correct.
- d. Incorrect. Plausible if the examinee incorrectly believes that 11 SI pump is powered from B train, similar to charging pumps.
Y KE 78
2020 ILT NRC EXAM RO EXAM K/A Number:
013 Engineered Safety Features Actuation K2.01:
Knowledge of bus power supplies to the following:
ESFAS / Safeguards Equipment Control K/A Value: 3.6 Technical Reference(s): B15 pg 6, B18A pg 5 Proposed references to be provided to applicants during examination: None Learning Objective: P8186L-003 Obj. 10a Predict the response of the system to a loss of power Question Source: Bank # P8186L-009 11 Modified Bank #
New Question History: Last NRC Exam Question Cognitive Level: Y 2017 LOR, 2018 NRC Memory or Fundamental Knowledge Comprehension or Analysis X KE 10 CFR Part 55 Content:
Comments:
55.41 7 55.43 79
- 39. P8180L-006 044/013 K5.02/2.9/3//P8100/B18C//2020 ILT NRC R39
- A reactor trip occurred on Unit 1.
- Pressurizer pressures are as follows:
Y KE
- No operator actions occur.
11 Safety Injection Pump is 12 Safety Injection Pump is (1)
(2) .
and A. (1) RUNNING (2) RUNNING B. (1) RUNNING (2) NOT RUNNING C. (1) NOT RUNNING (2) RUNNING D. (1) NOT RUNNING (2) NOT RUNNING 80
2020 ILT NRC EXAM RO EXAM 2-RI Justifications:
- a. Correct. An SI will actuate if 2 of 3 pressurizer pressures fall below 1830 psig. Only red, white, and blue channels are used. Yellow channel is not used.
- b. Incorrect. Plausible if examinee incorrectly believes the red and blue channel pressurizer pressure falling below 1830 will start 11 SI Pump and 12 SI Pump does not start because the white and yellow channel pressurizer pressures are above 1830 psig.
- c. Incorrect. Plausible if examinee incorrectly believes the red and blue channel pressurizer pressure falling below 1830 will start 12 SI Pump and 11 SI Pump does not start because the white and yellow channel pressurizer pressures are above 1830 psig.
- d. Incorrect. Plausible because there are two channels (white and yellow) that are NOT below 1830; however, the yellow channel is NOT used for pressurizer low pressure SI actuation.
K/A Number:
013 Engineered Safety Features Actuation K5.02:
Knowledge of the operational implications fo the following concepts as they apply to the ESFAS:
Safety System logic and reliability.
K/A Value: 2.9 Technical Reference(s): B18C pg 9 Y
Proposed references to be provided to applicants during examination: None KE Learning Objective: P8180L-006 Obj. 3 For the Engineered Safeguards system, describe the automatic functions incluing starts, trips, and interlocks and their set points.
Question Source: Bank #
New Question History: Last NRC Exam X
Modified Bank #
2019 LOR Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content:
55.41 7 55.43 Comments:
81
- 40. P8180L-009H 057/022 A3.01/4.1/4.3/4//P8100/1E-0 ATT L//2020 ILT NRC R40
- Unit 1 Safety Injection is actuated.
A. 11 and 13 B. 11 and 14 Y
Which Containment Fan Coil Units will the Reactor Operator reposition?
3-SPK KE C. 12 and 13 D. 12 and 14 Justification:
- a. Incorrect. Plausible if the examinee incorrectly beleives that the A train must be running in fast for a unit 1 SI.CFCUs must be in FAST during SI to provide maximum cooling during a LCOA.
- b. Incorrect. Plausible if the examinee incorrectly beleives that all CFCUs must be in FAST for an SI.
- c. Correct.
- d. Incorrect. Plausible if the examinee incorrectly beleives that train A must be in SLOW for a unit 1 SI.
82
2020 ILT NRC EXAM RO EXAM K/A Number:
022 Containment Cooling A3.01:
Ability to monitor automatic operation of the CCS, including: Initiation of safeguards mode of operations.
K/A Value: 4.1 Technical Reference(s): 1E-0 Att L pg 6 Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-009H Obj. 3 For Containment Air Handling, describe the system flowpath and major components for:
Emergency Operations Question Source: Bank # X Modified Bank #
New Question History: Last NRC Exam Question Cognitive Level:
Y Memory or Fundamental Knowledge N/A KE Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 9 55.43 X
83
- 41. P8180L-002 049/026 K3.02/3.9/10A//P8100/TS 3.6.5//2020 ILT NRC R41
- Unit 1 is at 100% power.
- 11 Containment Spray pump is out of service.
- Unit 2 is in Hot Standby.
- 21 and 23 Containment Fan Coil Units are out of service.
What is the status of TS LCO 3.6.5, Containment Spray and Cooling Systems for Unit 1 and Unit 2?
Unit 1 Unit 2 TS 3.6.5 TS 3.6.5 A. MET MET B. MET NOT MET C. NOT MET MET D.
3-SPR NOT MET NOT MET Y
KE Justifications:
- a. Incorrect. Plausible if examinee incorrectly believes more than one pump or fan per train per unit must be OOS for the TS to be not met.
- b. Incorrect. Plausible as TS LCO 3.6.5 is not met on U2; also if examinee incorrectly believes two CS pumps must be OOS for the TS to be not met.
- c. Incorrect. Plausible as TS LCO 3.6.5 is not met for U1; also if examinee incorrectly believes two CFCU must be OOS on one train for the TS to be not met.
- d. Correct.
84
2020 ILT NRC EXAM RO EXAM K/A Number:
026 Containment Spray K1.02:
Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems:
Cooling Water.
K/A Value: 4.1 Technical Reference(s): TS LCO 3.6.5 Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-002 Obj. 10A Recall if Technical Specifications exist for the system.
Question Source: Bank # X Modified Bank #
New Question History: Last NRC Exam Question Cognitive Level:
Y Memory or Fundamental Knowledge N/A KEComprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 8 55.43 X
85
- 42. P8180L-002 052/026 K2.02/2.7/2.9/7//P8100/NF-40036/NF-40022-1/2020 ILT NRC R42
- Bus 121 is LOCKED OUT.
During an accident, will remain CLOSED.
A. CV-31938, 12 CS PMP SUCT FROM CA STANDPIPE CV B. CV-31939, 21 CS PMP SUCT FROM CA STANDPIPE CV C. MV-32105, 12 CNTMT SPRAY PUMP DISCH D. MV-32114, 21 CNTMT SPRAY PUMP DISCH 1-I Justifications:
A. Incorrect. Plausible if the examinee incorrectly believes that caustic addition valves is powered from 1KA2.
Y B. Incorrect, Plausible if the examinee incorrectly believes that Bus 121 is a Unit 2 bus and that causitc addition is powered from bus 121 since a bus 25 failure would make 21 CS inoperable.
C. Correct, normally valve closed breaker closed, powered from 1KA2 MCC.
D. Incorrect. Plausible if the examinee incorrectly believes that Bus 121 is a Unit 2 bus.
KE 86
2020 ILT NRC EXAM RO EXAM K/A Number:
026 Containment Spray K2.02 Knowledge of bus power supplies to the following:
MOVs K/A Value: 2.7 Technical Reference(s): NF-40036 and NF-40022-1 Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-002 Obj. 7 For the Containment Spray system, predict the system response to a loss of power.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level: Y N/A Memory or Fundamental Knowledge Comprehension or Analysis X
KE 10 CFR Part 55 Content:
Comments:
55.41 8 55.43 87
- 43. P8174L-001 043/039 2.2.22/4.0/5//P8100/1C1.2 BOP//2020 ILT NRC R43
- Unit 1 Startup is IN PROGRESS.
The main steam line HEAT UP RATE shall NOT exceed per hour.
A. 100°F B. 230°F C. 300°F D. 547°F 1-P Justification:
- a. Correct.
- b. Incorrect. Plausible if the examinee incorrectly believes that the exhaust temperature of the turbine is the heat up rate for the steam line.
Y
- c. Incorrect. Plausible if the examinee incorrectly believes that the low pressure turbine metal temperature is an indication of the heat up rate of the steam lines.
- d. Incorrect. Plausible if the examinee incorrectly believes Tref is an indication of the heat up rate of the steam lines.
KE 88
2020 ILT NRC EXAM RO EXAM K/A Number:
039 Main and Reheat Steam System (MRSS) 2.1.22:
Knowledge of limiting conditions for operations and safety limits.
K/A Value: 4.0 Technical Reference(s): 1C1.2-BOP pg 3 Proposed references to be provided to applicants during examination: None Learning Objective: P8174L-001 Obj. 5 Recall precautions, limitations, and hazards associated with system operation, their bases and required safety equipment.
Question Source: Bank # P8174L-001 043 Modified Bank #
New Question History: Last NRC Exam Question Cognitive Level: Y Memory or Fundamental Knowledge Comprehension or Analysis 2018 ILT NRC X
KE 10 CFR Part 55 Content:
Comments:
55.41 4 55.43 89
- 44. P8174L-001 012/039 K4.07/3.4/3//P8100/1E-0 ATT L//2020 ILT NRC R44
- The crew is performing F9, High Energy Line Break/Leak.
Y KE
- Containment pressure is 0.1 psig
- Safety Injection is ACTUATED.
- BOTH MSIVs are OPEN.
Question Continued on Next Page 90
- 44. P8174L-001 012/039 K4.07/3.4/3//P8100/1E-0 ATT L//2020 ILT NRC R44 Question Continued From Previous Page The operator will...
A. maintain MSIVs OPEN.
B. CLOSE 11 MSIV ONLY.
C. CLOSE 12 MSIV ONLY.
D. CLOSE BOTH 11 and 12 MSIV.
3 - PEO Y
Steam line isolation is Hi-Hi stm flow (4.44 E6) and SI signal or Hi stm flow (.505 E6) with Lo Lo Tave (2/4
<540) and SI signal or Containment pressure HI (2/3 >16#)
Justifications:
- a. Incorrect. Plausible if the examinee incorrectly believes that MSIVs are allowing the SGs to cool the KE core and must be maintained open.
- b. Incorrect. Plausible if the examinee incorrectly believes that A MSIV flow is lower because flow out of the break is not measured.
- c. Incorrect. Plausible if the examinee incorrectly believes that B MSIV flow is above the set point for MSIV isolation, but A is not.
- d. Correct.
91
2020 ILT NRC EXAM RO EXAM K/A Number:
039 Main and Reheat Steam K4.017:
Knowledge of the MRSS design feature(s) and/or interlock(s) which provide for the following:
Reactor building isolation.
K/A Value: 3.4 Technical Reference(s): 1E-0 Attachment L pg 4 Proposed references to be provided to applicants during examination: None Learning Objective: P8174L-001 Obj. 3 For the Main Steam Isolation Valves, describe the automatic actions including starts, trips, and interlocks and their set points.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y N/A Memory or Fundamental Knowledge KE Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 4 55.43 X
92
- 45. P8174L-003 084/3/3.5/7//P8100/B28A//2020 ILT NRC R45
- Unit 2 is at 100% power.
- 21 Main Feedwater Pump LOCKS OUT.
- No operator actions occur.
Level in 22 Steam Generator will...
A. OSCILLATE.
B. remain ON PROGRAM.
C. RISE until REACTOR TRIP.
D. LOWER until REACTOR TRIP.
3-PEO Justifications:
Y
- a. Incorrect. Level will lower until the reactor trips. Plausible if the examinee incorrectly believes that the pump lockout will put the fw control system through a transient that it will not be able to recover from KE without intervention.
- b. Incorrect. Level will lower until the reactor trips. Plausible if the examinee incorrectly believes that 21 MFP will have no impact on 22 SG
- c. Incorrect. Level will lower until the reactor trips. Plausible if the examinee incorrectly believes that 21 MFP LO will cause SWELL in 22 SG.
- d. Correct.
93
2020 ILT NRC EXAM RO EXAM K/A Number:
059 Main Feedwater K3.03:
Knowledge of the effect that a loss or malfunction of the MFW will have on the following:
S/Gs.
K/A Value: 3.5 Technical Reference(s): B28A pg 9 Proposed references to be provided to applicants during examination: None Learning Objective: P8174L-003 Obj. 7 For the Main Fee, describe the automatic actions including starts, trips, and interlocks and their set points.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y Memory or Fundamental Knowledge N/A KEComprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 11 55.43 X
94
- 46. P8180L-007 223/061 A2.05/3.1/3//P8100/1E-0//2020 ILT NRC R46
- SAFETY INJECTION is ACTUATED.
- A SI to AFW relay failed to actuate.
The Reactor Operator will (1) an Auxiliary Feedwater Pump per (2) .
A. (1) STOP Y
(2) 1ES-0.1, Reactor Trip Recovery B. (1) STOP (2) 1E-0, Reactor Trip or Safety Injection KE C. (1) START (2) 1ES-0.1, Reactor Trip Recovery D. (1) START (2) 1E-0, Reactor Trip or Safety Injection 3-SPK Justifications:
- a. Incorrect. Plausible if examinee incorrectly believes that AFW should not be running when SI has been actuated due to feedwater isolation and incorrectly believes that the crew will transtiion to ES-0.1 in the RNO of step 4 because SI is actuated.
- b. Incorrect. Plausible if examinee incorrectly believes that AFW should not be running when SI has been actuated due to feedwater isolation.
- c. Incorrect. Plausible if the examinee incorrectly believes that the crew will transition to ES-0.1 in the RNO of step 4 because SI is actuated.
- d. Correct.
95
2020 ILT NRC EXAM RO EXAM K/A Number:
061 Auxiliary/Emergency Feedwater A2.05:
Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Automatic control malfunction.
K/A Value: 3.1 Technical Reference(s): 1E-0 Attachment L pg 1 Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-007 Obj. 3 For Aux Feedwater Pumps, describe the automatic functions including starts, trips, interlocks, and their setpoints.
Question Source: Bank #
New X Question History: Last NRC Exam Y
Modified Bank #
N/A KE Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 55.43 4
X 96
- 47. P8180L-007 128/061 K6.01/2.5/7//P8100/47010-0105//2020 ILT NRC R47
- Unit 1 is at 100% power.
- 47010-0105, 11 TD AFWP ACCUMULATOR LO AIR PRESS, is ALARMING.
- Accumulator air pressure is 70 psig and slowly lowering.
The operator will...
A. START 11 TDAFW.
B. place 11 TDAFW in MANUAL.
C. OPEN both steam supply valves to 11 TDAFW.
D. CLOSE both steam supply valves to 11 TDAFW.
1-P Justifications:
Y
- a. Incorrect. Plausible if the examinee incorrectly believes that the pump can be started to maintain operability because it will be fufulling its safety function.
- b. Incorrect. Plausible if the examinee incorrectly believes that this will prevent the pump from autostarting due to lo air pressure.
KE
- c. Incorrect. Plausible if the examinee incorrectly believes that lo air pressure will cause these valves to not be able to be opened and that they must be opened prior to air pressure getting too low.
- d. Correct. The ARP requires the steam supply valves to be closed to prevent an inadvertant start.
97
2020 ILT NRC EXAM RO EXAM K/A Number:
061 Auxiliary/Emergency Feedwater K6.01:
Knowledge of the effect of a loss or malfunction of the following will have on the AFE components:
Controllers and positioners.
K/A Value: 2.5 Technical Reference(s): 47010-0105 Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-007 Obj. 7 Predict the response of the system to a failed component.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y N/A Memory or Fundamental Knowledge KE Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 4 55.43 X
98
- 48. P8186L-008 068/062 A1.03/2.5/3//P8100/SP1093//2020 ILT NRC R48
- D1 Emergency Diesel Generator is being paralled with the grid.
Per 1C20.7, D1\D2 Diesel Generators, when the operator closes the output breaker:
- The synchroscope will be rotating in the (1) direction.
- The synchroscope indicator will be (2) the 12 o'clock position.
A. (1) CLOCKWISE (2) DEPARTING B. (1) CLOCKWISE (2) APPROACHING C. (1) COUNTERCLOCKWISE (2) DEPARTING D. (1) COUNTERCLOCKWISE 1-P (2) APPROACHING Y KE Justifications:
- a. Incorrect. The procedure requires the indicator to be approaching the 12 o'clock position. Incorrect if the examinee incorrectly believes closing the breaker before 12 o'clock will motor the generator.
- b. Correct.
- c. Incorrect. The procedure requires the indicator to be approaching the 12:00 position and rotating in the fast (clockwise) direction. Plausible if the examinee incorrectly believes fast is the counter clockwise direction but knows that the needle should be to the left of 12:00 when the breaker is closed.
- d. Incorrect. The procedure requires the indicator to be rotating in the fast (clockwise) direction. Plausible if the examinee incorrectly believes that the fast direction is counterclockwise.
99
2020 ILT NRC EXAM RO EXAM K/A Number:
062 AC Electrical Distribution A1.03:
Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) assoicated with operating the AC distribution system controls including:
Effect on instrumentation and controls of switching power supplies.
K/A Value: 2.5 Technical Reference(s): SP1093 pg 21 Proposed references to be provided to applicants during examination: None Learning Objective: P8186L-008 Obj. 3 For the AC distribution system, describe the automatic actions including starts, trips, and interlocks and their set points.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y N/A KEMemory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 4 55.43 X
100
- 49. P8186L-005 112/E16 2.4.3/3.7/3.G.8//P8100/H3//2020 ILT NRC R49 Which instrument(s) below is(are) intended for use under accident conditions?
Y A.
KE B.
C. D.
101
2020 ILT NRC EXAM RO EXAM 1-F Justifications:
- a. Incorrect. Plausible if examinee incorrectly believes this instrument is only available post-accident because CTMT Pressure NR instruments provide input for safeguards actuation.
- b. Incorrect. Plausible if examinee incorrectly believes this instrument is only available post-accident because CTMT Pressure WR instruments provide input for safeguards actuation.
- c. Incorrect. Plausible because CTMT humidity and pressure are used for normal conditions and post-accident, but they are not designated as such.
- d. Correct. The white "star" specifically designates this recorder instrument as post-accident use.
K/A Number:
063 DC Electrical Distribution 2.4.3:
Ability to identify post-accident instrumentation K/A Value: 3.7 Technical Reference(s): H3 pg 71 Proposed references to be provided to applicants during examination: None Y
Learning Objective: P8186L-005 Obj 3.g.8 For major system components (Safeguards DC Distribution panels), describe the control room indications.
KE Question Source: Bank #
Modified Bank #
New Question History: Last NRC Exam Question Cognitive Level:
X Memory or Fundamental Knowledge Comprehension or Analysis N/A X
10 CFR Part 55 Content:
55.41 7 55.43 Comments:
102
- 50. P8186L-005 107/063 K4.04/2.6/7//P8100/C20.9 AOP1//2020 ILT NRC R50
- Unit 1 is at 100% power.
- 47018-0501, SAFEGUARD LOGIC TRAIN A DC FAILURE, alarms.
- 47024-1003, D1 EMERG GEN LOSS OF CONTROL VOLTAGE, alarms.
- 47024-1102, 11 DC SYSTEM TROUBLE, alarms.
- 47024-1201, 11 DC PANEL UNDERVOLTAGE, alarms.
SHUTDOWN Bank Control Rods will (1) .
CONTROL Bank Control Rods will (2) .
A. (1) INSERT (2) INSERT B. (1) INSERT (2) REMAIN OUT C. (1) REMAIN OUT (2) INSERT Y
KE D. (1) REMAIN OUT (2) REMAIN OUT 3-SPK Justifications:
- a. Correct.
- b. Inocrrect. Plausible if the examinee incorrectly believes that control bank control rods are controlled by train B DC.
- c. Incorrect. Plausible if the examinee incorrectly believes that shutdown bank control rods are controlled by train B DC.
- d. Incorrect. Plausible if the examinee incorrectly believes that no automatic funcations are available without both trains of DC power.
103
2020 ILT NRC EXAM RO EXAM K/A Number:
063 DC Electrical Distribution K4.04:
Knowledge of DC electrical system design feature(s) and/or interlock(s) which provide for the following:
Trips.
K/A Value: 2.6 Technical Reference(s): 1C20.9 AOP1 pg 4 Proposed references to be provided to applicants during examination: None Learning Objective: P8186L-005 Obj. 7 Predict the response of the system to a component failure.
Question Source: Bank #
Modified Bank # P8140L-246 001 (similar)
New X Question History: Last NRC Exam Question Cognitive Level:
Y 2012 (SIMILAR)
Memory or Fundamental Knowledge KE Comprehension or Analysis 10 CFR Part 55 Content: ?
Comments:
55.41 7 55.43 X
104
- 51. P8186L-004 056/064 K1.05/3.4/7//P8100/B28//2020 ILT NRC R51
- The D1 Starting Air System is DEPRESSURIZED.
D1 (1) be started REMOTELY and (2) be started LOCALLY.
A. (1) CAN (2) CAN B. (1) CAN (2) CAN NOT C. (1) CAN NOT (2) CAN D. (1) CAN NOT (2) CAN NOT 3-SPK Justifications:
Y
- a. Incorrect. Plausible if the examinee incorrectly believes that there is a backup starting motor that is used by both remote and local functions.
KE
- b. Incorrect. Plausible if the examinee incorrectly believes that remote start always uses an electric start (similar to pump CS in the control room often only close a breaker to supply power to a pump).
- c. Incorrect. Plausible if the examinee incorrectly beleives that a local switch must select the back up electric start (similar to local AFW start vai 3-way valve requires local manipulation).
- d. Correct. With starting air completely depressurized, the diesel can not be started.
105
2020 ILT NRC EXAM RO EXAM K/A Number:
064 Emergency Diesel Generator K1.05:
Knowledge of the physical connections and/or cause-effect relatioship between the ED/G system and the following systems:
Starting air system.
K/A Value: 3.4 Technical Reference(s): B38A pg 43 Proposed references to be provided to applicants during examination: None Learning Objective: P8186L-004 Obj. 7 For the D1 starting air system, predict the response of the system to a component failure.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y N/A Memory or Fundamental Knowledge KE Comprehension or Analysis 10 CFR Part 55 Content: ?
Comments:
55.41 8 55.43 X
106
- 52. P8182L-002 014/073 A2.01/2.5/10//P8100/TS 3.4.16//2020 ILT NRC R52
- Unit 1 and Unit 2 are both at 100% power.
- 1R-11, U1 CNTM/SHLD BLD VENT AIR PART, is OUT OF SERVICE.
- BOTH 1R-10, U1 CNTMT AIR PART, and 2R-10, U2 CNTMT AIR PART, are declared INOPERABLE due to common cause power supply failure.
What is the status of TS 3.4.16, RCS Leakage Detection Instrumentation, for Unit 1 and Unit 2?
UNIT 1 UNIT 2 A. MET MET B. MET NOT MET C. NOT MET MET D.
2RI NOT MET Y NOT MET KE Justifications:
- a. Incorrect. Plausible if the examinee incorrectly believes that the LCO is met unless R-10, R-11 and R-12 are all inoperable.
- b. Incorrect. Plausible if the examinee incorrectly believes that R-12 provides a backup on unit 1 but there is no backup on unit 2.
- c. Correct.
- d. Incorrect. Plausible if the examinee incorrectly believes that R-10, on its own, makes the LCO not met.
107
2020 ILT NRC EXAM RO EXAM K/A Number:
073 Process Radiation Monitoring A2.01:
Ability to (a) predict the impacts of the following malfunctions or operation on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Erratic or failed power supply.
K/A Value: 2.5 Technical Reference(s): TS 3.4.16 Proposed references to be provided to applicants during examination: None Learning Objective: P8182L-002 Obj. 10 For Radiation Monitors, apply technical specifications.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y N/A KE Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 10 55.43 X
108
- 53. P8176L-003 092/076 K2.04/2.5/3//P8100/B19//2020 ILT NRC R53
- CFCUs are being supplied by CHILLED WATER.
11 Chilled Water Pump is powered from (1) .
21 Chilled Water Pump is powered from (2) .
A. (1) SAFEGUARDS (2) SAFEGUARDS B. (1) SAFEGUARDS (2) NONSAFEGUARDS C. (1) NONSAFEGUARDS (2) SAFEGUARDS D. (1) NONSAFEGUARDS (2) NONSAFEGUARDS 1-F Justifications Y
- a. Incorrect. Plausible if the examinee incorrectly believes that containment and aux cooling is provided by KE the same chilled water system that provides control room cooling.
- b. Incorrect. Plausible if the examinee incorrectly believes that the original U1 system was required to be safeguards, but the U2 system was not required to be because of the addition of 121 MDCLP which can be aligned to either unit as a backup cooling water pump.
- c. Incorrect. "Travel stops" have been added to the CL side of the CC HX to prevent the CL valves from opening too far and starving downstream CFCUs of cooling water. Plausible if the examinee incorrectly believes that the problem of starving CFCUs was solved by adding a safeguards pump to the chilled water system during U2 construction and supplying CFCUs with chilled water.
- d. Correct. Containment and aux building chilled water is supplied by a non safeguards system.
109
2020 ILT NRC EXAM RO EXAM K/A Number:
076 Service Water K2.04:
Knowledge of bus power supplies to the following:
Reactor Building Closed Cooling Water.
K/A Value: 2.5 Technical Reference(s): P8140L-401C Pg 7 Proposed references to be provided to applicants during examination: None Learning Objective: P8140L-401C obj 3 For Chilled water pumps, describe the power supply.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level: Y N/A Memory or Fundamental Knowledge Comprehension or Analysis X
KE 10 CFR Part 55 Content:
Comments:
55.41 7 55.43 110
- 54. P8178L-005 050/078 A4.01/3.1/3.1/7//P8100/C34 AOP1/B34/2020 ILT NRC R54 Y
Instrument air pressure in UNIT 1 CONTAINMENT is approximately...
KE A. 0 psig.
B. 30 psig.
C. 90 psig.
D. 95 psig.
3-PEO Justifications:
- a. Correct.
- b. Incorrect. Plausible if the examinee incorrectly believes that the U1 RX building gage is failed low.
- c. Incorrect. Plausible if the examinee incorrectly believes that the Unit 1 indications are failed and u2 indications must be used.
- d. Incorrect. There is only 1 aux building. The two different pressures are different headers withing the same building. Plausible if the examinee incorrectly believes that the containment is aux building and not the reactor building and that the higher aux building header pressure is reported.
111
2020 ILT NRC EXAM RO EXAM K/A Number:
078 Instrument Air A4.01:
Ability to manually operate and/or monitor in the control room:
Pressure gauges.
K/A Value: 4.1 Technical Reference(s): B34 pg 20 Proposed references to be provided to applicants during examination: None Learning Objective: P8178L-005 Obj. 7 Predict the response of the system to a component failure.
Question Source: Bank # X Modified Bank #
New Question History: Last NRC Exam Question Cognitive Level: Y Memory or Fundamental Knowledge Comprehension or Analysis 2015 LOR X
KE 10 CFR Part 55 Content:
Comments:
55.41 7 55.43 112
- 55. P8180L-006 080/103 A3.01/3.9/4//P8100/1E-0 ATT L//2020 ILT NRC R55
- A SMALL Break LOCA has occurred.
- Safety Injection was manually actuated.
- Containment pressure is 7 psig.
Y KE Per 1E-0, Reactor Trip or Safety Injection, Attachment L, The Reactor Operator will...
A. RESET SAFETY INJECTION.
B. ACTUATE CONTAINMENT SPRAY.
C. MANUALLY ALIGN COMPONENTS.
D. RESET CONTAINMENT ISOLATION.
2-DR Justifications:
- a. Incorrect. SI could be reset during 1E-0, howver it is not directed by Attachment L and is not required by to actuate containment isolation. Plausible if the examinee incorrectly believes that resetting SI must be reset before CI can be actuated, similar to reactor trip breakers.
- b. Incorrect. This action is not procedurally directed at the current containment pressure. Plausible if the examinee incorrectly believes that Containment spary is required because CI can not be actuated.
- c. Correct.
- d. Incorrect. Containment isolation has not actuated. Plausible if the examinee incorrectly believes that only a partial CI has occurred and that CI must be reset so that it can be actuated again.
113
2020 ILT NRC EXAM RO EXAM K/A Number:
103 Containment A3.01:
Ability to monitor automatic operation of the containment system including:
Containment Isolation.
K/A Value: 3.9 Technical Reference(s): 1E-0 Att L pg 1 and 3 Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-006 Obj. 4 For Containment Isolation, describe the system flowpath and major components for emergency operations.
Question Source: Bank # X Modified Bank # P8180L-006 051 New Question History: Last NRC Exam Question Cognitive Level:
Y Memory or Fundamental Knowledge 2019 BRE / 2018 ILT NRC (SIG MOD)
KE Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 7 55.43 X
114
- 56. P8170L-003 063/002 K6.12/3.0/3.J.//P8100//1C4 AOP1/2020 ILT NRC R56
- Unit 1 is at 100% power.
- A pressurizer SAFETY valve fails FULL OPEN.
This leak (1) isolable from the control room.
After 20 minutes, LEVEL in the pressurizer will be (2) .
A. (1) IS NOT (2) 100%
B. (1) IS NOT (2) 0%
C. (1) IS (2) 100%
D. (1) IS (2) 0%
2-DR Y
KE Justifications:
- a. Correct. Initially, pressurizer level decreases for approximately the first 45 seconds after the initiating event, causing a reactor trip and safety injection. The PRT rupture disc fails and inventory is lost to containment. As the bubble transfers to the core, level refills to 100%. There are no isolation valves either in the outplant or in control room that can be operated to prevent this outcome.
- b. Incorrect. Plausible if examinee incorrectly believes that the loss of inventory will cause PRZR LVL to go down.
- c. Incorrect. Level will refill to 100% Plausible if examinee incorrectly believes safety valves operate the same as the PORV.
- d. Incorrect. Plausible if examinee incorrectly believes a safety valve operates the same as a PORV and incorrectly believes that the loss of inventory will drain the pressurizer prior to the valve being isolated.
115
2020 ILT NRC EXAM RO EXAM K/A Number:
002 Reactor Coolant System (RCS)
K6.12:
Knowledge of the effect or a loss or malfunction on the following RCS components:
Code Safety valves.
K/A Value: 3.0 Technical Reference(s): 1C4 AOP1 page 11 Proposed references to be provided to applicants during examination: None Learning Objective: P8170L-003 Obj 3.J.
For the pressurizer, describe the normal values of significant indications and relationships between values.
Question Source: Bank # P8170L-003 063 Modified Bank #
New Question History: Last NRC Exam Question Cognitive Level:
Y Memory or Fundamental Knowledge 2016 ILT NRC KEComprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 5 55.43 X
116
- 57. P8184L-005 144/014 K4.06/3.4/3//P8100/B5//2020 ILT NRC R57
- STARTUP is in progress on Unit 1.
GROUP D will begin WITHDRAWING when GROUP C is at steps.
A. 30 B. 128 C. 225 D. 384 1-I Justifications:
- a. Incorrect. Plausible if examinee incorrectly believes Group D will move when the Rod at Bottom light goes out.
Y
- b. Correct. Overlap between each bank is 97 steps.
- c. Incorrect. Plausible if the examinee incorrectly believes that Group D will not move out until Group C is fully withdrawn.
- d. Incorrect. Plausible if examinee incorrectly believes that number of total steps from ARI is the reading on Group C RPI when Group D begins to move.
KE 117
2020 ILT NRC EXAM RO EXAM K/A Number:
014 Rod Position Indication System (RPIS)
K4.06:
Knowledge of RPIS design feature(s) and/or interlock(s) which provide for the following:
Individual and group misalignment.
K/A Value: 3.4 Technical Reference(s): B7 pg 25 Proposed references to be provided to applicants during examination: None.
Learning Objective: P8184L-005 Obj 3.
For major system components, descripe the automatic functions including start, trips, and interlocks and their setpoints.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level: Y N/A Memory or Fundamental Knowledge Comprehension or Analysis X
KE 10 CFR Part 55 Content:
Comments:
55.41 2 55.43 118
- 58. P8140L-200 ATT 23 014/015 A2.04/3.3/5//P8100/C5 AOP1//2020 ILT NRC R58
- Unit 1 is at 100% power.
- Control Rods are in AUTO.
- DELTA I is 0.
- CONTROL RODS begin stepping IN UNCONTROLLABLY.
Reactor Power indicated on nuclear instruments is (1) .
DELTA I will be (2) .
A. (1) RISING (2) POSITIVE B. (1) RISING (2) NEGATIVE C. (1) LOWERING (2) POSITIVE D. (1) LOWERING (2) NEGATIVE Y
2-RI KE Justifications:
- a. Incorrect. Plausible if the examinee incorrectly believes that the control rods are adding reactivity.
- b. Incorrect. Plausible if the examinee incorrectly beleives that the impact of AFD peaking lower is an overall increase in Rx power.
- c. Incorrect. Plausible if the examinee incorrectly beleives that neutron flux will be higher in the top half of the core to counteract the impact of rods.
- d. Correct.
119
2020 ILT NRC EXAM RO EXAM K/A Number:
015 Nuclear Instrumentation A2.04:
Ability to (a) predict the impacts of the following malfunctions or operations on the NIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.
Effects on axial flux density of control rod alignment and sequencing, xenon production and decay, and boron vs. control rod reactivity changes.
K/A Value: 3.2 Technical Reference(s): 1C5 AOP1 pg 3 Proposed references to be provided to applicants during examination: None Learning Objective: P8140L-200 att 23 Obj. 5 During a power range nuclear instrument failure, demonstrate the ability to predict and/or monitor changes in parameters associated with plant operating systems to determine to Bank # Y determine if systems are operating properly.
Question Source:
Modified Bank #
New X KE Question History: Last NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
55.41 5 55.43 N/A X
Comments:
120
- 59. P8180L-003 079/016 2.1.19/3.9/3I//P8100/B15//2020 ILT NRC R59 Train A RHR is aligned for ________(1)________.
Train B RHR is aligned for ________(2)________.
A. (1) injection (2) injection B. (1) injection (2) cooldown C. (1) cooldown (2) injection Y 1-F KE D. (1) cooldown (2) cooldown Justification:
A. Incorrect. Plausible if the examinee incorrectly believes that train A RHR is aligned for RX vessel injection and train B RHR is aligned for cold leg injection.
B. Correct.
C. Incorrect. Plausible if the examinee confuses train A RHR with Train B RHR.
D. Incorrect. Plausible if the examinee incorrectly believes that train A RHR is aligned for RX vessel cooldown and train B RHR is aligned for cold leg cooldown.
121
2020 ILT NRC EXAM RO EXAM K/A Number:
016 Non-Nuclear Instrumentation 2.1.19 Ability to use plant computer to evaluate system or component status.
K/A Value: 3.9 Technical Reference(s): B15 pages 22 & 23 Proposed references to be provided to applicants during examination: NONE Learning Objective: P8180L-003 Obj. 3i For each of the system major components describe the: computer indications.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Y Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
X KE Comments:
55.41 55.43 8
122
- 60. P8180L-008 020/028 K2.01/2.9*/3//P8100/B19//2020 ILT NRC R60 What is the power supply to 11 Hydrogen Recombiner?
A. MCC 1B1 B. MCC 1L1 C. MCC 1AB1 D. MCC 1MA1 1-F Justifications:
- a. Incorrect. Plausible if the examinee incorrectly believes that 11 recombiner is powered from MCC 1B1.
- b. Correct
- c. Incorrect. Plausible if the examinee incorrectly believes that 11 recombiner is powered from MCC 1AB1.
Y
- d. Incorrect. Plausible if the examinee incorrectly believes that 11 recombiner is powered from MCC 1MA1.
KE 123
2020 ILT NRC EXAM RO EXAM K/A Number:
028 Hydrogen Recombiners K2.01:
Knowledge of bus power supplies to the following:
Hydrogen Recombiners.
K/A Value: 2.5*
Technical Reference(s): B19 pg 16 Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-008 Obj. 3 For the Hydrogen Recombiners, describe the power supply.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level: Y N/A Memory or Fundamental Knowledge Comprehension or Analysis X
KE 10 CFR Part 55 Content:
Comments:
55.41 8 55.43 124
- 61. P8182L-003 106/034 A1.02/2.9/2/NO/P8100/FIG C1-40//2020 ILT NRC R61
- 2L0458A, RX REFUELING CANAL L, is being trended on ERCS.
- 2L0470A, RCS B LVL, is being trended on ERCS.
Y KE Core offload can not occur because...
A. 2L0458A is too HIGH.
B. 2L0458A is too LOW.
C. 2L0470A is too HIGH.
D. 2L0470A is too LOW.
3-SPR Justifications:
- a. Incorrect. Plausible if the examinee incorrectly believes that refueling canal level must be lowered to match RCS level to prevent wetting personnel and equipment.
- b. Correct. RCS level is actually matching refueling canal level but this indication is off scale high and will not read higher. Refueling canal level must be raised to refueling height for core off load to begin. If refueling level is too high, people and equipment on the refueling platform may be wetted. If level is too low, sufficient water for shielding will not be provided.
- c. Incorrect. Plausible if the examinee incorrectly believes that RCS level must be lowered to maintain a minimum DP to ensure cantamination stays in the RCS.
- d. Incorrect. Plausible if the examinee incorrectly believes that RCS level must be raised to match refueling canal level to allow for step-less transfer of fuel.
125
2020 ILT NRC EXAM RO EXAM K/A Number:
034 Fuel Handling Equipment A1.02:
Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the Fuel Handling System Controls including:
Water level in the refueling canal.
K/A Value: 2.9 Technical Reference(s): FIG C1-40 Proposed references to be provided to applicants during examination: FIG C1-40 Learning Objective: P8182L-003 Obj. 2 For each of the following system components (Refueling Cavity), state the normal values of significant indications and relationships between indications.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y N/A KE Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 9 55.43 X
126
- 62. P8182L-001C 020/071 A4.14/2.8/5H//P9100/C47024/C47047/C47048/2020 ILT NRC R62
- A radioactive gas release is in progress in accordance with C21.3-10.5, Releasing Radioactive Gas From 125 Low Level Gas Decay Tank.
- 47024-0108, HI RADIATION TRAIN B PANEL ALARM, is in ALARM.
- 47024-0109, HI RADIATION TRAIN A PANEL ALARM, is in ALARM.
- 2R-30, AUX BLDG VENT GAS MONITOR B, is reading off-scale HIGH.
- 2R-37, AUX BLDG VENT GAS MONITOR A, is reading off-scale HIGH.
- No automatic actions have occurred.
The crew will...
A. stop the release.
B. start SFP special ventilation.
Y C. start shield building ventilation.
D. evacuate the auxiliary building.
3-PEO KE Justifications:
- a. Correct. High rad alarms on 2R-30 and 2R-37 will stop any radioactive release in progress and start Aux Bldg special. The crew should manually perform these actions if they do happen automatically.
- b. Incorrect. Plausible if examinee incorrectly believes 2R-30 & 2R-37, vice R-25 and R-31, auto starts spent fuel pool ventilation.
- c. Incorrect. Plausible if examinee incorrectly believes 2R-30 & 2R-37, vice a safety injection signal, auto starts shield building ventilation.
- d. Incorrect. Plausible if examinee incorrectly believes a high radiation condition exists in the auxiliary building.
127
2020 ILT NRC EXAM RO EXAM K/A Number:
071 Waste Gas Disposal System A4.14:
Ability to manually operate and/or monitor in the control room:
WDGS status alarms K/A Value: 2.8 Technical Reference(s): C47047- 2R-37 & C47048- 2R-30 Proposed references to be provided to applicants during examination: None Learning Objective: P8182L-001C Obj. 5h State the functional interrealationship between the Radioactive Waste Gas System and the following: Radiation Monitoring System.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level: Y Memory or Fundamental Knowledge Comprehension or Analysis N/A X
KE 10 CFR Part 55 Content:
Comments:
55.41 13 55.43 128
- 63. P9130L-003 051/029 K3.02/2.9*/P8182L-005 12//P8100/FP-IH-SAF-01/F2/2020 ILT NRC R63
- It is January.
- Containment entry is being made for valve alignments.
- During the containment entry, Containment In-Service Purge MALFUNCTIONS.
- Containment WET BULB temperature is 88°F.
- The Containment entry requires a SINGLE LAYER OF COVERALLS.
- The work is categorized as MODERATE.
Without Containment Purge, temperature in Containment will (1) .
Per FP-IH-SAF-01, the MAXIMUM allowed work time is (2) minutes.
A. (1) RISE (2) 70 B. (1) RISE (2) 60 C. (1) LOWER Y
3-SPRKE (2) 70 D. (1) LOWER (2) 60 Justification:
- a. Incorrect. Plausible if examinee uses correct WBGT but chooses wrong clothing column.
- b. Correct. .
- c. Incorrect. Plausible if examinee uses correct WBGT but chooses wrong clothing column AND incorrectly believes that containment purge is removing heat from the core into the containment atmosphere.
- d. Incorrect. Plausible if the examinee incorrectly believes that containment purge is removing heat from the core into containment atmosphere.
129
2020 ILT NRC EXAM RO EXAM K/A Number:
029 Containment Purge K3.02:
Knowledge of the effect that a loss or malfunction of the CPS will have on the following:
Containment entry K/A Value: 2.9*
Technical Reference(s): FP-IH-SAF-01 pg 13 (Attachment 1)
Proposed references to be provided to applicants during examination: FP-IH-SAF-01 pg 13 Learning Objective: P8182L-005 Obj. 12 Using F2, determine the requirements for Containment without error.
Question Source: Bank #
Modified Bank # P9130L-003 053 New Question History: Last NRC Exam Question Cognitive Level:
Y Memory or Fundamental Knowledge 2019 BRE, 2016 ILT AUDIT (SIG MOD)
KE Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 10 55.43 X
130
- 64. P8178L-005 008/079 K1.01/3.0/3.1/3//P8100/B34//2020 ILT NRC R64
- CP-40-7, STA AIR RCVRS X-CONN TO INSTR AIR, is OPEN.
- MV-32318, SERVICE AIR HDR ISOL VLV, is OPEN.
Instrument Air Header pressure RAPIDLY LOWERS to 55 psig.
What is the status of CP-40-7 and MV-32318?
CP-40-7 MV-32318 A. OPEN OPEN B. OPEN CLOSED C. CLOSED OPEN D. CLOSED CLOSED 2-RI Justifications:
Y
- a. Incorrect. Mv-32318 closes when IA drops below 85 lbs. Plausible if the examinee incorrectly believes there are no automatic actions for cross connect valves in this system.
KE
- b. Correct.
- c. Incorrect. MV-32318 closes when IA drops below 85 psig. CP-40-7 does not have any automatic actions. Plausible if the examinee incorrectly believes that the CP valve is the valve in the system that has the auto close signal becuase the physical valve is not easily accessible (located in the overhead).
- d. Incorrect. CP-40-7 does not have an auto close feature. Plausible if the examinee incorrectly believes that all cross connect vavles automatically close to isolate SA form IA.
131
2020 ILT NRC EXAM RO EXAM K/A Number:
079 Station Air System (SAS)
K1.01:
Knowledge of the physical connections and/or cause-effect relationships between SAS and the following systems:
IAS K/A Value: 3.0/3.1 Technical Reference(s): B34 pg 17 Proposed references to be provided to applicants during examination: None Learning Objective: P8178L-005 Obj. 3 For Instrument and Station Air motor valves, describe the automatic actions including starts, trips, and interlocks and their set points.
Question Source: Bank #
Modified Bank #
Question History: Last NRC Exam Question Cognitive Level:
Y New X (Similar to 2016 ILT)
N/A KE Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 4 55.43 X
132
- 65. P8178L-002 050/086 K5.04/2.9/3.5*/6//P8100/C31//2020 ILT NRC R65 The RELAY ROOM is protected by a (1) fire supression system.
A breathing device (2) required to enter the relay room after system actuation.
A. (1) CARDOX (2) IS B. (1) CARDOX (2) IS NOT C. (1) HALON (2) IS D. (1) HALON (2) IS NOT 1-P Justifications:
- a. Correct. Y
- b. Incorrect. Per note prior to 6.17.6 of C 31, a breathing device is required. Plausible if the examinee KE incorrectly believes that it is just goo practice to wear a breathing device for cardox, similar to Halon.
- c. Incorrect. The relay room is protected by Cardox system. Plausible if the examinee incorrectly believes that the protection scheme for the relay room is the same as the service building computer room but correctly recalls the note prior to 6.17.6.
- d. Incorrect. The relay room is protected by Cardox system. Plausible if the examinee incorrectly believes that the protection scheme for the relay room is the same as the service building computer room.
133
2020 ILT NRC EXAM RO EXAM K/A Number:
086 Fire Protection System (FPS)
K5.04:
Knowledge of the operation implication of the following concepts as they apply to the Fire Protection System:
Hazards to personnel as a result of fire type and methods of protection.
K/A Value: 2.9/3.5*
Technical Reference(s): C31 pg 76 Proposed references to be provided to applicants during examination: None Learning Objective: P8178L-002 Obj. 6 Recall precautions, limitations, and hazards associated with system operation, their bases, and required safety equipment.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level:
Y N/A KE Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 4 55.43 X
134
- 66. P8140L-201 068/2.1.1/3.8/5//P8100/FP-OP-COO-01//2020 ILT NRC R66
- Unit 1 is at 90% power.
- No control room activities are in progress.
- The Reactor Operator must move 'Control Bank D' IN one step for a minor routine adjustment of Axial Flux Deviation.
For this activity, a PEER CHECK is ________(1)________, and Shift Supervisor MONITORING is ________(2)_________.
A. (1) required (2) required B. (1) required (2) NOT required C. (1) NOT required (2) required D. (1) NOT required 1-P (2) NOT required Y KE Justifications:
- a. Correct. FP-OP-COO-21 states that all reactivity manipulations SHALL use peer check and STAR; also, for routine flux control, SS notification and monitoring for proper peer check is required.
- b. Incorrect. Plausible if examinee incorrectly believes that peer checks are only required if positive reactivity is added, but SS monitoring is required for all reactivity manipulations.
- c. Incorrect. Plausible if examinee incorrectly believes that peer checks are only required if positive reactivity is added.
- d. Incorrect. Plausible if examinee incorrectly believes minor reactivity manipulations can be handled like abnormal or emergency condition.
135
2020 ILT NRC EXAM RO EXAM K/A Number:
2.1.1 Knowledge of conduct of operations requirements.
K/A Value: 3.8 Technical Reference(s): FP-OP-COO-21 pg. 21 Proposed references to be provided to applicants during examination: None Learning Objective: P8140L-201 Obj. 5 Discuss the FP-OP-COO series, 'Conduct of Operations'.
Question Source: Bank # X Modified Bank #
New Question History: Last NRC Exam N/A Question Cognitive Level:
Y Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
55.41 10 X
KE Comments:
55.43 136
- 67. P8180L-005 019/022 2.2.42/4.6/P8180L-005 OBJ 10C///T.S 3.5.4/TS 3.5.1/2020 ILT NRC R67
- Unit 1 is in Mode 1.
- Chemistry has just reported the following:
- RCS boron concentration is 1050 ppm.
- SI Accumulator boron concentration is 1100 ppm.
- RWST boron concentration is 1250 ppm.
LCO 3.5.1, Accumulators, is (1) .
LCO 3.5.4, Refueling Water Storage Tank, is (2) .
A. (1) MET (2) MET B. (1) MET (2) NOT MET C. (1) NOT MET (2) MET D. (1) NOT MET Y
1-I KE (2) NOT MET Justifications:
- a. Incorrect. Plausible if the examinee incorrectly believes that RWST and accumulator concentration only haveto be above RCS boron concentration.
- b. Incorrect. Plausible if the examinee incorrectly believes that accumulator concentration only has to be between RCS and RWST.
- c. Incorrect. Plausible if examinee incorrectly believes RWST does not have a requirement for boron concentration because BA is added from the BAST during injection.
- d. Correct.
137
2020 ILT NRC EXAM RO EXAM K/A Number:
2.1.34:
Knowledge of primary and secondary chemistry limits.
K/A Value: 2.7 Technical Reference(s): T.S. 3.5.1 and 3.5.4 Proposed references to be provided to applicants during examination: None Learning Objective: P8180L-005 Obj 10c Apply technical specifications for given plant conditions to determine required actions.
Question Source: Bank #
Modified Bank#
New x Question History: Last NRC Exam N/A Question Cognitive Level:
Comprehension or Analysis 10CFR Part 55 Content:
55.41 Y
Memory or Fundamental Knowledge 10 X
KE 55.43 138
- 68. PI-OPS-GFE-192004 001/2.1.43/4.1/ELO 2.5//P9100/PI-OPS-GFE-192004/FIG C1-7A/2020 ILT NRC R68
- Unit 1 is at 50% power.
- Core exposure is 23,000 MWd/MTU.
- Reactor power is raised from 50% to 100%.
The change in Total Power Defect is negative ___________.
A. 21 pcm B. 46 pcm C. 1052 pcm D. 2318 pcm 3-SPR Justification:
Y A. Incorrect. Plausible if the examinee incorrectly believes they have to divide the correct answer of 1052 pcm by 50% for PCM change per % reactor power change.
B. Incorrect. Plausible if the examinee incorrectly believes they have to divide the total power defect at 100% (2318 pcm) by 50% for PCM change per % reactor power change.
KE C. Correct.
D. Incorrect. Plausible if the examinee incorrectly believes the answer is the total Power Defect at 100%
at that core exposure.
139
2020 ILT NRC EXAM RO EXAM K/A Number:
2.1.43 Ability to use procedures to determine the effects on reactivity of plant changes.
K/A Value: 4.1 Technical Reference(s): PI-OPS-GFE-192004 Student Guide Pages 47-49 Proposed references to be provided to applicants during examination: FIG C1-7A Learning Objective: PI-OPS-GFE-192004 ELO 2.5 Explain how the Power Defect affects the reactivity balance on reactor power opearations.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
10 CFR Part 55 Content:
Y Memory or Fundamental Knowledge Comprehension or Analysis 55.41 5 X
KE Comments:
55.43 140
- 69. P8140L-201 072/2.2.7/2.9/5//P8100/FP-OP-COO-01/1C1.4/2020 ILT NRC R69
- Unit 1 has been at 90% power for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with LEFM out of service.
- Unit 2 has been at 7% power for 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> due to a generator malfunction.
In accordance with FP-OP-COO-21, Reactivity Control, prior to taking the duty an Infrequently Performed Test or Evolution (IPTE) brief for Control Room personnel is ________(1)_________ on Unit 1 and is ________(2)_________ on Unit 2.
A. (1) required (2) required B. (1) required (2) NOT required C. (1) NOT required (2) required D. (1) NOT required (2) NOT required Y
1-P KE Justifications:
- a. Incorrect. Plausible if examinee incorrectly believes any operation without LEFM requires IPTE brief.
- b. Incorrect. Plausible if examinee incorrectly believes any ooperation without LEFM requires IPTE brief and <10% power is normal.
- c. Correct. FP-OP-COO-21 requires an IPTE brief for CR personnel when in low power (<10%) for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- d. Incorrect. Plausible if examinee incorrectly believes <10% power is a normal condition.
141
2020 ILT NRC EXAM RO EXAM K/A Number:
2.2.7 Knowledge of the process for conducting special or infrequent tests.
K/A Value: 3.8 Technical Reference(s): FP-OP-COO-21 pgs. 27-28, 1c1.4 pg 7 Proposed references to be provided to applicants during examination: None Learning Objective: P8140L-201 Obj. 5 Discuss the FP-OP-COO series, 'Conduct of Operations'.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Y Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
55.41 10 X
KE Comments:
55.43 142
- 70. FL-WMN-SHE-002L 001/2.2.13/4.1/2//P8100/FP-OP-TAG-01/5AWI 15.5.1/2020 ILT NRC R70
- CAUTION tags are identified by black text on a ___(1)___ and white background.
- CAUTION tags _____(2)_____ worker protection.
A. (1) RED (2) provide B. (1) RED (2) DO NOT provide C. (1) YELLOW (2) provide D. (1) YELLOW (2) DO NOT provide 1-D Justifications:
Y
- a. Incorrect. Plausible if examinee incorrectly believes CTs are red and that they provide protection.
- b. Incorrect. Plausible as CTs do not provide protection and if examinee incorrectly believes they are red.
- c. Incorrect. Plausible as CTs are yellow and if examinee incorrectly believes they provide protection.
- d. Correct. Per FP-OP-TAG-01, CTs are black text on yellow and white background and DO NOT provide KE worker protection.
143
2020 ILT NRC EXAM RO EXAM K/A Number:
2.2.13 Knowledge of tagging and clearance procedures.
K/A Value: 4.1 Technical Reference(s): FP-OP-TAG-01 pgs. 8 & 10 Proposed references to be provided to applicants during examination: None Learning Objective: FL-WMN-SHE-002L Obj. 2 Discuss the Fleet Tagging Procedure including: Tags Plus, Operating Permit requirements, etc...
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Y Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
X KE Comments:
55.41 10 55.43 144
- 71. P8182L-002 095/2.3.5/2.9/3H//P8100/C21.1-5.1/PI-OPS-GFE-048L/2020 ILT NRC R71 Y
KE How is the R-18 Source Check performed?
A. ADD background reading TO check source reading B. DIVIDE background reading BY check source reading C. MULTIPLY background reading BY check source reading D. SUBTRACT background reading FROM check source reading 1-P Justifications:
- a. Incorrect. Plausible if examinee incorrectly believes sum of CSR and BR must be on scale.
- b. Incorrect. Plausible if examinee incorrectly beleives that ratio of CSR to BR must fall within 0.8-1.2.
- c. Incorrect. Plausible if the examinee incorrectly believes the purpose of source check is ot determine if backrground radiation is too high for the meter to adequately function.
- d. Correct.
145
2020 ILT NRC EXAM RO EXAM K/A Number:
2.3.5 Ability to use radiation monitoring systems.
Technical Reference(s): C21.1-5.1 pg. 9; PI-OPS-GFE-048L pgs. 7-9.
Proposed references to be provided to applicants during examination: None Learning Objective: P8182L-002 Obj. 3H Describe control room controls and indications for major system components.
Question Source: Bank # X Modified Bank #
New Question History: Last NRC Exam 2014 ILT NRC Exam Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
Y 55.41 13 55.43 X
KE Comments:
146
- 72. P8182L-005 002/2.3.7/3.5/3.6/2//P8100/F2/RWP 200005/2020 ILT NRC R72
- An operator is hanging a tagout in a Contaminated Area.
- The task will require the operator to perform the following:
- Kneeling in certain areas
- Work in tight spaces
- The work requires the operator to be signed onto RWP 200005, STANDARD WORK ACTIVITIES - ONLINE.
- Contamination level in the area is 65,000 dpm/100cm 2.
What is the MINIMUM required protective clothing?
A. Shoe covers and surgeon's gloves.
B. Single suit-up ONLY.
C. Single suit-up of Ultras with knee pads.
D. Double suit-up.
2-RW Justifications:
Y met.
KE
- a. Incorrect. Plausible as booty/gloves are allowed for tagouts with RP permission; however, since it is above 10,000 dpm/100cm2 and kneeling/tight spaces is required, knee pads and single set of ultras are required.
- b. Incorrect. Plausible if examinee incorrectly believes the requirements for single set w/o knee pads are
- c. Correct. Per RWP 200005 Task 202, >10,000 but <100,000 dmp/cm2, avtivities inside CA that require kneeling and are in tight spaces require single suit-up of Ultras with knee pads.
- d. Incorrect. Plausible if examinee incorrectly confuses dpm/cm2 with cpm and believes the requirements for Task 203 are met (>50,000 cpm).
147
2020 ILT NRC EXAM RO EXAM K/A Number:
2.3.7:
Abi;ity to comply with radiation work permit requirements during normal or abnormal conditions.
K/A Value: 3.5 Technical Reference(s): RWP 200005 Proposed references to be provided to applicants during examination: RWP 200005; F2 pgs.
34-35 Learning Objective: P8182L-002 Obj. 2 Discuss the Generic RWP requirements IAW F2.
Question Source: Bank # X Modified Bank #
New Question History: Last NRC Exam N/A Question Cognitive Level:
Y Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
X KE Comments:
55.41 12 55.43 148
- 73. P8197L-010 058/2.4.14/3.5/3.H//P8100/SWI O-10//2020 ILT NRC R73 A DELTA symbol in the left margin of an EOP indicates a...
A. OPTIONAL Action Step.
B. IMMEDIATE Action Step.
C. CONTINUOUS Action Step.
D. CONTINGENCY Action Step.
1-F Justifications:
Y KE
- a. Incorrect. Plausible if the examinee incorrectly believes that some steps may not always apply and it is the operators discretion whether they should be performed.
- b. Incorrect. Plausible if the examinee incorrectly believes that immediate actions steps are indicated by a traingle similar to road signs for hazards.
- c. Correct.
- d. Incorrect. Plausible if the examinee incorrectly believes that this symbol indicates that it is only performed in the event that other steps have not been successful.
149
2020 ILT NRC EXAM RO EXAM K/A Number:
2.4.14 Knowledge of general guidelines for EOP usage.
K/A Value: 3.5 Technical Reference(s): SWI O-10 pg 10 Proposed references to be provided to applicants during examination: None Learning Objective: P8107L-010 Obj. 3H Explain or demonstrate, given the EOPs, the usage of the two colum format EOPs in terms of step or sub step sequencing for each of the following:
Use of continuous action steps.
Question Source: Bank #
Question History: Last NRC Exam Question Cognitive Level:
Y Modified Bank #
New X N/A KE Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
Comments:
55.41 10 55.43 X
150
- 74. P8197L-009 040/2.2.34/4.2/3//P8100/F5 APP B//2020 ILT NRC R74
- Unit 1 is at 100% power.
- Unit 2 is at 100% power.
- A FIRE is occurring in the Control Room.
- The crew is performing F5 Appendix B, Control Room Evacuation (FIRE).
The Unit 1 RO will trip the reactor from the (1) .
The Unit 1 RO will control Decay Heat Removal from the (2) .
A. (1) Control Room (2) Auxiliary Building B. (1) Control Room (2) Hot Shutdown Panel C. (1) Hot Shutdown Panel (2) Auxiliary Building D. (1) Hot Shutdown Panel Y
1-P KE (2) Hot Shutdown Panel Justifications:
A. Incorrect. Plausible if the examinee incorrectly believethat AFW can be controlled from the aux building similar to PRZR level being able to be controlled from both AFW room and Aux building. The reactor would be tripped from the control room; however, in this case F5 App B directs the RO to start AFW for decay heat removal from the HSP.
B. Correct. F5 App B directs the Unit 1 RO to trip the reactor from the CR (among other actions), then proceed to the HSP to start AFW for both units for decay heat removal.
C. Incorrect. Plausible if the examinee incorrectly believethat AFW can be controlled from the aux building similar to PRZR level being able to be controlled from both AFW room and Aux building. Plausible if examinee incorrectly believes the reactor can be shutdown from the HSP as the name suggests.
D. Incorrect. Plausible as DHR would be controlled from the HSP and if examinee incorrectly believes there is a reactor trip switch at the HSP.
151
2020 ILT NRC EXAM RO EXAM K/A Number:
2.4.34:
Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects.
K/A Value: 4.2 Technical Reference(s): F5 AppB pgs. 7, 21-22 Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-009 Obj.31 Describe the initial control room evacuation assignments (reporting areas) for all crew members.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam Question Cognitive Level: Y N/A Memory or Fundamental Knowledge Comprehension or Analysis X
KE 10 CFR Part 55 Content:
Comments:
55.41 10 55.43 152
- 75. P8197L-012 256/2.4.45/4.1/8//P8100/1E-1/SWI O-10/2020 ILT NRC R75
- A Large Break LOCA has occurred on Unit 1.
- The crew is currently performing 1E-1, Loss of Reactor or Secondary Coolant.
Y KE The crew is REQUIRED to respond to which annunciator FIRST?
A. 47016-0204, 11 RWST LO LVL B. 47016-0304, CONTAINMENT SUMP A HI LVL C. 47016-0504, CONTAINMENT SUMP C HI LVL D. 47016-0601, 122 SPENT FUEL PIT HI TEMP 153
2020 ILT NRC EXAM RO EXAM 2-RI Justifications:
- a. Correct. ARP & 1E-1 step 22 bases requires the crew to immediately transition to 1ES-1.2, Transfer to Recirculation, in order to maintain cooling flow to the core. This transition criteria is also found on the 1E-1 Info Page. SWI O-10 requires the crew to immediately perform the actions found on the Info Page once that criteria is met.
- b. Incorrect. Plausible as this alarm is expected for a LOCA and the crew is not required to respond to this ARP as a higher priority than 0204.
- c. Incorrect. Plausible as this alarm is expected for a LOCA and the crew is not required to respond to this ARP as a higher priority than 0204.
- d. Incorrect. Plausible if examinee incorrectly believes Component Cooling was isolated to the SFP HXs on the SI signal.
K/A Number:
2.4.45:
Ability to prioritize and interpret the significance of each annunciator or alarm..
K/A Value: 4.1 Technical Reference(s): 1E-1, pg. 12, 1E-1 Info Page, 1E-1 step 22 bases pg. 7, SWI O-10 pg. 11 Y
Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-012 Obj. 8 KE Identify any steps that must be performed in associated E series EOP and what indications are available in the control room for verification of those steps.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content:
55.41 10 55.43 Comments:
You have completed the test!
154
QF-1 030-03, Revision 5 (FP-T-SAT-30) Page 1 of 1
'U XrelEnergy- WRITTEN/ORAL EXAMINATION KEY COVERSHEET PI.ILT.NRC.2OO6E 2O2O ILT NRC SENIOR REACTOR OPERATOR WRITTEN EXAM Training Program. FL.ILT Lesson Plan Number(s):
Total Points Possible:
EXAMINATION REVIEW AND APPROVAL:
Submitted by lnstructor:
Reviewed by SME: Fredrick Collins Approved by Training Supervisor: Date: ?bq Written/Oral Attach key to this page.
Key should contain the followin tr Learning Obi Number tr Test lte oO or o All ible an Answer lndi oP alue efe [icable) r.rlruc PnoceounE TAIN GUTDANcE spEctFtc ro NRC EXAMS.
lndicate the following any changes are made to the exam after approval:
DESCRIPTION OF CHANGE REASON FOR CHANGE SUPERVISOR Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.
- 76. P8140L-239 002/040 AA2.05/2.9 / 4.6/B.3/YES/P8100/1ES-1.2/1FR-P.1/2020 ILT NRC S76
- A Large Break LOCA has occurred on Unit 1.
- The crew is performing 1E-1, Loss of Reactor of Secondary Coolant.
Which procedure will the Shift Supervisor use to secure SI pumps?
A. 1FR-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION B. 1E-1, LOSS OF REACTOR OR SECONDARY COOLANT C. 1E-2, FAULTED STEAM GENERATOR ISOLATION D. 1ES-1.2, TRANSFER TO RECIRCULATION 3 SPK Justification:
- a. Incorrect. A red path will be in for Integrity during certain points in a LB LOCA. Plausible if the examinee inadvertantly beleives that actions will be completed in FR-P.1.
- b. Incorrect. Plausible if the student believes they should stay in 1E-1 to terminate SI vice transition to 1ES-1.2.
- c. Incorrect. Plausible if the student incorrectly believes that 1E-2 is briefly entered due to high containment pressure.
- d. Correct.
EXPLANATION:
This question is linked to 10 CFR 55.43(b)(5) Assessment and selection of procedures. The question can NOT be answered by solely knowing "systems knowledge" OR by solely knowing immediate operator actions OR by solely knowing entry conditions for AOPs or plant parameters that require direct entry to MAJOR EOPs OR by solely knowing the purpose overall sequence of events or overall mitigative strategy of a procedure. The question requires the knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event specific sub-procedures or emergency contingency procedures.
1
2020 ILT NRC EXAM SRO EXAM K/A Number: AA2.05 040 Steam Line Rupture AA2.05:
Ability to determine and interpret the following as they apply to the Steam Line Rupture::
When ESFAS systems may be secured.
K/A Value: 4.6 Technical Reference(s): 1F-0 pages 1, 2 Proposed references to be provided to applicants during examination: None Learning Objective: P8140L-239 Obj. B3 EXPLAIN the purpose of and descibe desired end point of plant conditions for associated E or FR series EOP Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content:
55.41 55.43 5 Comments:
2
- 77. P8197L-011 206/055 EA2.03/3.9/4.7/GEN OBJ/YES/P8100/1ECA-0.0//2020 ILT NRC S77
- The crew has entered 1ECA-0.0, Loss of All Safeguards AC Power.
- Offsite power is NOT available.
- D2 Diesel Generator is OOS.
- The Unit 2 Safeguard busses are energized from their respective diesels.
- Bus 15 is LOCKED OUT.
Under the direciton of the Shift Supervisor, on which step of 1ECA-0.0 will power be restored to a Unit 1 Safeguards Bus?
A. step 6 B. step 7 C. step 10 D. step 11 3
2020 ILT NRC EXAM SRO EXAM 2-RI Justifications:
- a. Incorrect. Plausible if examinee incorrectly believes a Unit 1 source is available; however, since Bus 15 is locked out, D2 OOS, and NO offsite power, there is NO unit 1 source available.
- b. Correct. Bus 16 is available. Bus 16 will be energized from U2 per step 7.
- c. Incorrect. Plausible if examinee incorrectly believes a that no Unit 1 sequencers are available for loading, but a Unit 1 source is available.
- d. Incorrect. Plausible if the examinee incorrectly believes that the load sequencers are NOT available, but correctly believes the Unit 1 sources are NOT available.
EXPLANATION:
This question tests knowledge/ability that is unique to the SRO position. This question is linked to a learning objective labeled in the lesson plan as being SRO-only.
At PI, the verb "Direct" is used within learning objectives to denote the SRO ONLY mental processes of working through procedure steps to address and event. The verb "Implement" is used to denote the RO skills and knowledge of carrying out the actions directed by the SRO.
K/A Number:
055 Loss of Offsite and Onsite Power (Station Blackout)
EA2.03:
Ability to determine or interpret the following as they apply to a Station Blackout:
Actions necessary to restore power Technical Reference(s): 1ECA-0.0 pages 5 - 12 Proposed references to be provided to applicants during examination: All steps of 1ECA-0.0, but no background information.
Learning Objective: P8140S-200 Att 47 4.c During a loss of all AC power, demonstrate the ability to:
Direct crew response to abnormal operating events in accordance with appropriate Alarm Response/Abnormal/Emergency Operating Procedures. (SRO ONLY).
Question Source: Bank # _______
Modified Bank # _P8197L-011 105______
New _______
Question History: Last NRC Exam ___2014 ILT (SIG MOD)________
Question Cognitive Level:
Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content:
55.41 _____
55.43 __NA___
Comments:
4
- 78. P8186L-015 031/057 2.2.40/4.7/9C/YES/P8100/TS 3.8.7/TS 3.8.9/2020 ILT NRC S78
- Unit 1 is at 100% power.
- The crew is performing 1C20.8 AOP1, Abnormal Operation, Instrument AC Inverters.
- 11 Inverter has the following indications:
Question continued on next page.
5
- 78. P8186L-015 031/057 2.2.40/4.7/9C/YES/P8100/TS 3.8.7/TS 3.8.9/2020 ILT NRC S78 Question continued from previous page.
The Shift Supervisor will enter T.S. LCO...
A. 3.8.7 Condition A ONLY.
B. 3.8.9 Condition C ONLY.
C. 3.8.7 Condition A and 3.8.9 Condition C.
D. 3.8.7 Condition A and 3.8.9 Condition E.
3-SPR Justifications:
- a. Correct.
- b. Incorrect. Plausible if examinee incorrectly believes only 111 instrument bus is inoperable; however, in this case the 11 inverter is on its alternate source and is considered inoperable.
- c. Incorrect. Plausible if the examinee incorrectly beleives that 111 instrument bus is inoperable because it is fed from unregulated power.
- d. Incorrect. Plausible as 11 inverter is inoperable and if examinee incorrectly believes the 11 inverter supplies more than one RP instrument AC bus.
EXPLANATION:
This question is linked to 10 CFR 55.43(b)(2) Tech Specs. The question can NOT be answered by solely knowing < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TS actions OR by solely knowing the LCO "above the line" information OR by solely knowing TS Safety Limits. The question requires the knowledge of TS bases that is required to analyze TS required actions and terminology.
6
2020 ILT NRC EXAM SRO EXAM K/A Number:
057 Loss of Vital AC Electrical Instrument Bus 2.2.40:
Ability to apply technical specifications for a system.
KA Value: 4.7 Technical Reference(s): 1C20.8 AOP1 pgs. 4-8, T.S. LCOs 3.8.7 & 3.8.9, T.S. Bases 3.8.7 &
3.8.9.
Proposed references to be provided to applicants during examination: TS LCO 3.8.7 & 3.8.9 Learning Objective: P8186L-015 Obj. 9c Apply technical specifications to given plant conditions to determine required actions.
Question Source: Bank # _ _
Modified Bank # _ __
New _X_____
Question History: Last NRC Exam ___N/A_________
Question Cognitive Level:
Memory or Fundamental Knowledge __ __
Comprehension or Analysis __X _
10 CFR Part 55 Content:
55.41 __ ___
55.43 __2_ _
Comments:
7
- 79. P7410L-034 146/058 2.4.41/4.6/8/YES/P8100/PINGP 1576/F3-2/2020 ILT NRC S79
- 21 and 22 Battery Chargers have FAILED.
- Attempts to start-up the PORTABLE BATTERY CHARGER have FAILED.
The following is observed:
What is the Highest Emergency Classification Level currently met?
A. NOTIFICATION OF UNUSUAL EVENT B. ALERT C. SITE AREA EMERGENCY D. GENERAL EMERGENCY 8
2020 ILT NRC EXAM SRO EXAM 3-SPR Justification:
- a. Incorrect. Plausible if the examinee incorrectly believes there is a loss of DC power that caused an unplanned loss of control room indications.
- b. Incorrect. Plausible if the examinee incorrectly believes there is a loss of DC that affects the control power supply to safeguards bus breakers.
- c. Correct.
- d. Incorrect. Plausible if the examinee incorrectly believes there is a loss of DC power that affects control power to AC safeguards busses along with the low DC voltage on Unit 2.
EXPLANATION:
This question is not linked to 10 CFR 55.43(b) but is still classified as SRO-only because it is unituqe to the SRO position at Prairie Island. This question is linked to a learning objective in an SRO-ONLY lesson plan.
K/A Number:
058 Loss of DC Power 2.4.41:
Emergency Procedures / Plan:
Knowledge of the emergency action level thersholds and classifcations.
K/A Value: 4.6 Technical Reference(s): PINGP 1576 page 4 Proposed references to be provided to applicants during examination: PINGP 1576 Learning Objective: P7410LL-034 Obj. 8 Given the definition of an emergency classification, be able to identify that classification.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content:
55.41 55.43
- Comments:
9
- 80. P8186L-002 091/077 2.1.23/4.4/9C/YES/P8100/T.S. 3.8.1//2020 ILT NRC S80
- The 10 Bank Transformer is lost due to a grid disurbance.
What conditions will the Shift Supervisor enter for T.S. LCO 3.8.1, AC Sources -
Operating?
Unit 1 Unit 2 A. A A B. A C C. C A D. C C 3-SPR Justification:
- a. Correct.
- b. Incorrect. Plausible if the examinee incorrectly believes that 1R will be operable ONLY as a back up path to bus 16 because of spring creek AND CT2 bus provides a primary 26 and a backup path for bus 25 that are both inoperable.
- c. Incorrect. Plausible if the examinee incorrectly believes that the 1R source can not supply both U1 busses and spring creek causing a DG start AND that a running DG is considered another inoperable path.(note: in some instances, a running EDG is considered inoperable)
- d. Incorrect. Plausible if the examinee incorrectly believes that condition renders bus ties on both units inoperable because both safeguards busses are running on the same unit and that the bus ties count as a separate path.
EXPLANATION:
This question is linked to 10 CFR 55.43(b)(2) Tech Specs. The question can NOT be answered by solely knowing < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TS actions OR by solely knowing the LCO "above the line" information OR by solely knowing TS Safety Limits. The question requires the application of required actions for T.S.
10
2020 ILT NRC EXAM SRO EXAM K/A Number:
077 Generator Voltage and Electric Grid Disturbances 2.1.23:
Conduct of Operations:
Ability to perform specific system and integrated plant procedures during all modes of plant operation.
K/A Value: 4.4 Technical Reference(s): C20.3 AOP7 Page 5 Proposed references to be provided to applicants during examination: Tech Spec 3.8.1 for both units Learning Objective: P8186L-002 Obj. 9c Apply technical specifications to given plant conditions to determine required actions.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content:
55.41 55.43 2 Comments:
11
- 81. P8171L-014 062/E04 EA2.2/4.2/4/YES/P8100/T.S. 3.4..14//2020 ILT NRC S81
- RCS temperature is 300°F and STABLE.
- RHR Train B is in service.
- There is UNISOLABLE RCS PRESSURE BOUNDARY leakage outside Containment.
- Leak rate has been quantified at 25 GPM.
- 1C1.6 AOP2, Shutdown Loss of Inventory, has been entered.
In accordance with LCO 3.4.14, RCS Operation Leakage, the Shift Supervisor will place the Unit in...
A. MODE 2.
B. MODE 3.
C. MODE 4.
D. MODE 5.
3-SPR Justification:
- a. Incorrect. Plausible if the examinee incorrectly believes taking the plant critical will maintain RCS pressure but believes that power operation is not allowed because of the operability of the RHR safety system.
- b. Incorrect. Plausible if the examinee incorrectly believes that raising pressure would passivly isolate leakage but does not believe that criticality is allowed due to risk associated with safety system operability.
- c. Incorrect. Plausible if the examinee incorrectly believes the plant is in mode 3 and has to take the plant to mode 4 before mode 5.
- d. Correct.
EXPLANATION:
This question is linked to 10 CFR 55.43(b)(2) Tech Specs. The question can NOT be answered by solely knowing < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TS actions OR by solely knowing the LCO "above the line" information OR by solely knowing TS Safety Limits. The question requires the application of required actions for [enter T.S., TRM, or ODCM].
12
2020 ILT NRC EXAM SRO EXAM K/A Number:
E04 LOCA Outside of Containment EA2.2:
Ability to determine and interpret the following as they apply to the (LOCA Outside Containment)
Adherence to appropriate procedures and operation within limitations in the facility's license and amendments K/A Value: 4.2 Technical Reference(s): Unit 1 Tech Spec 3.4.14 pages 1&2 Proposed references to be provided to applicants during examination: None Learning Objective: P8171L-014 Obj. 4 Given plant status, apply Technical Specifications.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content:
55.41 55.43 2 Comments:
13
- 82. P8140L-237 001/028 A2.12/3.5/3C/YES/P8100/1C51.1//2020 ILT NRC S82
- 47012-0507, PRZR LVL DEVIATION, alarm is LIT.
The Shift Supervisor will direct the crew to enter...
A. 1C51.1, INSTRUMENT FAILURE GUIDE.
B. 1C51.2, INSTRUMENT FAILURE GUIDE.
C. 1C51.3, INSTRUMENT FAILURE GUIDE.
D. 1C51.4, INSTRUMENT FAILURE GUIDE.
14
2020 ILT NRC EXAM SRO EXAM 3-SPK Justification:
- a. Correct.
- b. Incorrect. Plausible if the examinee incorrectly believes white channel is failed low and blue channel is averaging white channel and red channel.
- c. Incorrect. Plausible if the examinee incorrectly believes blue channel is failed low, red channel is rejected and white channel is the average of blue and cold cal.
- d. Incorrect. Plausible if the examinee incorrectly believes cold cal is failed as it.
EXPLANATION:
This question is linked to 10 CFR 55.43(b)(5) Assessment and selection of procedures. The question can NOT be answered by solely knowing "systems knowledge" OR by solely knowing immediate operator actions OR by solely knowing entry conditions for AOPs or plant parameters that require direct entry to MAJOR EOPs OR by solely knowing the purpose overall sequence of events or overall mitigative strategy of a procedure. The question requires assessing plant conditions (normal, abnormal, or emergency) and then selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed.
15
2020 ILT NRC EXAM SRO EXAM K/A Number:
028 Pressurizer Level Malfunction A2.12:
Ability to determine and interpret the following as they apply to the Pressurizer Level Control Malfunctions:
Cause for PZR level deviation alarm:
Controller malfunction or other instrumentation malfunction K/A Value: 3.5 Technical Reference(s): 1C51.1 Pressurizer Level 1L-426 High page 1&2 Proposed references to be provided to applicants during examination: NONE Learning Objective: P8140L-237 Obj. 3c During a PRZR level failure, demonstrate the ability to: Direct crew response to abnormal operating events in accordance with appropriate Alarm Response/Abnormal Operating Procedures.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content:
55.41 55.43 5 Comments:
16
- 83. P8184L-002 143/032 A2.02/3.9/10C/YES/P8100/T.S. 3.3.1//2020 ILT NRC S83
- Unit 1 Reactor start-up is in progress.
- N31 is 2000 CPS and stable.
- N32 is 2000 CPS and stable.
- The RO is withdrawing RODS to criticality.
- 47013-0401, SOURCE RANGE LOSS OF DETECTOR VOLT, ALARMS.
- N31 is 0 CPS and stable.
IMMEDIATELY after the RO stops withdrawing rods, N32 count rate will be (1) .
The Shift Supervisor will enter T.S. 3.3.1 Condition A and (2) .
A. (1) RISING (2) H B. (1) RISING (2) J C. (1) STABLE (2) H D. (1) STABLE (2) J 3-SPR Justification:
- a. Correct
- b. Incorrect. Plausible if the examinee incorrectly believes the plant is not in Mode 2.
- c. Incorrect. Plausible if the examinee incorrectly believes neutron flux stops going up immediately when rod motion stops.
- d. Incorrect. Plausible if the examinee incorrectly believes the plant is not in Mode 2 and neutron flux stops going up immediately when rod motion stops.
EXPLANATION:
This question is linked to 10 CFR 55.43(b)(2) Tech Specs. The question can NOT be answered by solely knowing < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TS actions OR by solely knowing the LCO "above the line" information OR by solely knowing TS Safety Limits. The question requires the application of required actions for T.S.
17
2020 ILT NRC EXAM SRO EXAM K/A Number:
032 A2.02:
Ability to determine and interpret the following as they apply to the Loss of Source Range Nuclear Instrumentation:
Expected change in source range count rate when rods are moved.
K/A Value: 3.9 Technical Reference(s): Unit 1 T.S. 3.3.1 pages 3.3.1-1, 3.3.1-5, and 3.3.1-18 Proposed references to be provided to applicants during examination: Unit 1 T.S. 3.3.1 Learning Objective: P8184L-002 Obj. 10c Apply Technical Specifications given plant conditions to determine required actions.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content:
55.41 55.43 b2 Comments:
18
- 84. P8140L-229 005/067 2.4.30/4.1/3C/YES/P8100/SWI O-28//2020 ILT NRC S84
- A waste basket fire has occured in the D5 Emergency Diesel Generator room.
- The fire was extinguished in 5 minutes.
- The OCC has been activated.
- D5 Emergency Diesel Generator was not damaged.
What notification is required per station Section Work Instructions (SWIs)?
A. NRC Resident Inspector B. Prarie Island Indian Community C. Minnesota Pollution Control Agency D. Minnesota State and Local Authorities 3-SPK Justification:
a.Correct. NRC Resident Inspector must be notified because of OCC activation.
- b. Incorrect. Plausible if the examinee incorrectly believes the fire requires a PINGP 577 Block 10 C EAL notification.
- c. Incorrect. Plausible if the examinee incorrectly believes the fire meets environmental reporting requirements of FP-OP-REP-01.
- d. Incorrect. Plausible if the examinee incorrectly believes the fire requires a PINGP 577 EAL notification.
EXPLANATION:
This question is not linked to 10 CFR 55.43(b) but is still classified as SRO-only because it is unique to the SRO position at Prairie Island. This question is linked to a learning objective in an SRO-ONLY lesson plan.
19
2020 ILT NRC EXAM SRO EXAM K/A Number:
067 Plant Fire On-Site 2.4.30:
Emergency Procedures / Plan Knowledge of events related to system operations / status that must be reported to internal organizations or outside agencies such as the State, the NRC, or the transmission system operator.
K/A Value: 4.1 Technical Reference(s): SWI O-28 pages 2 & 3.
Proposed references to be provided to applicants during examination: None Learning Objective: P8140L-229 Obj. 3c During a plant fire, demonstrate the ability to: Direct crew response to abnormal operating events in accordance with appropriate Alarm Reponse/Abnormal Operating Procedures. (SRO Only)
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content:
55.41 55.43
- Comments:
20
- 85. P8197L-011 239/E09 2.2.44/4.4/C2/YES/P8100/1ES-0.1//2020 ILT NRC S85
- 1ES-0.1, Reactor Trip Recovery, has been completed.
The Shift Supervisor will transition to...
A. 1C1.3, UNIT 1 SHUTDOWN.
B. 1ES-0.3, NATURAL CIRCULATION COOLDOWN.
C. 1E-1, LOSS OF REACTOR OR SECONDARY COOLANT.
D. 1C3 AOP1, POST ACCIDENT EMERGENCY START OF A REACTOR COOLANT PUMP.
21
2020 ILT NRC EXAM SRO EXAM 3-SPK Justification:
- a. Incorrect. Plausible if the examinee incorrectly believes that a RCP is running, this is the normal transition path.
- b. Correct.
- c. Incorrect. Plausible if the examinee incorrectly believes that there are indications of a loss of Reactor Coolant.
- d. Incorrect. Plausible if the examinee incorrectly believes that there are indications of an accident and emergency start of a RCP is necessary.
EXPLANATION:
This question is linked to 10 CFR 55.43(b)(5) Assessment and selection of procedures. The question can NOT be answered by solely knowing "systems knowledge" OR by solely knowing immediate operator actions OR by solely knowing entry conditions for AOPs or plant parameters that require direct entry to MAJOR EOPs OR by solely knowing the purpose overall sequence of events or overall mitigative strategy of a procedure. The question requires assessing plant conditions (normal, abnormal, or emergency) and then selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed.
K/A Number:
E09 Natural Circ 2.2.44:
Equipment Control Ability to interpret control room indications to verify the status and operation of a system and understand how operator actions and directives affect plant and system conditions.
K/A Value: 4.4 Technical Reference(s): 1ES-0.1 Page 17 Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-011 Obj. C2 Evaluate plant conditions to determine if natural circulation is in progress.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content:
55.41 55.43 5 Comments:
22
- 86. P8197L-012 251/006 A2.02/3.9/4.3/20/YES/P8100/1ECA-1.3/ES-1.2/2020 ILT NRC S86
- A Large Break LOCA occurred on Unit 1.
- 12 RHR pump is LOCKED OUT.
- 11 RHR pump is RUNNING in recirculation mode aligned to Sump B per 1ES-1.2, Transfer to Recirculation.
- RWST level is 15% and STABLE.
- CTMT pressure is 24 psig and STABLE.
- 11 RHR pump flow is NOT STABLE.
- 11 RHR pump pressure is NOT STABLE.
The Shift Supervisor will transition to...
A. 1FR-I.2, Response to Low System Inventory.
B. 1E-1, Loss of Reactor or Secondary Coolant.
C. 1ECA-1.3, Recirculation Sump Blockage.
D. 1ES-1.2, Transfer to Recirculation.
23
2020 ILT NRC EXAM SRO EXAM 3-SPK Justifications:
- a. Incorrect. Plausible if the examinee incorrectly believes that FR-I.2 will be used to resolve the low inventory (LOCA) condition. The more immediate concern that the question is testing is the sump blockage, which will not be addressed by FR-I.2.
- b. Incorrect. Plausible if examinee incorrectly believes ECCS pumps are functioning normally, 1ES-1.2 is complete, and transition can be made back to procedure and step in effect, 1E-1 step 23, to isolate SI accumulators.
- c. Correct. Both trains of ECCS are affected such that at least one train of recirc flow cannot be established or maintained per step 25 of 1ES-1.2. RHR pump flow & pressure instability indicates sump blockage and the SS will transition to 1ECA-1.3.
- d. Incorrect. Plausible if examinee incorrectly believes the cause of the ECCS pump instability is due to pump cavitation caused by insufficient RWST level; however, procedurally that would not occur until RWST level is less than 8%.
EXPLANATION:
This question is linked to 10 CFR 55.43(b)(5) Assessment and selection of procedures. The question can NOT be answered by solely knowing "systems knowledge" OR by solely knowing immediate operator actions OR by solely knowing entry conditions for AOPs or plant parameters that require direct entry to MAJOR EOPs OR by solely knowing the purpose overall sequence of events or overall mitigative strategy of a procedure. The question requires the knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event specific sub-procedures or emergency contingency procedures.
24
2020 ILT NRC EXAM SRO EXAM K/A Number:
006 Emergency Core Cooling System A2.02:
Ability to (a) predict the impacts of the following malfunctions on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Loss of flow path K/A Value: 4.3 Technical Reference(s): 1ES-1.2 step 25; 1ECA-1.3 step 1 Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-012 Obj. 17 For ES-1.2 & ECA-1.3, identify any steps that must be performed in associated E series EOP and what indications are avilable in the control room for verification of those steps.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam NA Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content:
55.41 55.43 5 Comments:
25
- 87. P7410L-034 030/012 A2.06/4.4/4.7//YES/P8100/F3-2/F3-2.1 BASES/2020 ILT NRC S87
- Unit 1 is at 100% power and stable.
- 47017-0202, PRZR LO Press Reactor Trip, is LIT.
- Pressurizer Pressure is 1890 psig and lowering.
- The Reactor fails to automatically trip.
- ALL attempts to trip the Reactor from the control room FAIL.
- ALL attempts to insert control rods and Borate the reactor have FAILED.
- The Turbine Building Operator opens the Reactor Trip Breakers locally.
The Shift Supervisor will declare...
A. Notification of Unusual Event B. Alert C. Site Area Emergency D. General Emergency 3 -SPR Justification:
- a. Incorrect. Plausible if it is assumed that since the corrective actions have been taken and it only meets the level of an NUE.
- b. Correct.
- c. Incorrect. Plausible if the examinee incorrectly believes that the inability to shutdown the reactor has challenged the heat sink or core cooling.
- d. Incorrect. Incorrect. Plausible if the examinee incorrectly believes that the inability to shutdown the reactor has challenged all three fisson product barriers.
EXPLANATION:
This question is not linked to 10 CFR 55.43(b) but is still classified as SRO-only because it is unituqe to the SRO position at Prairie Island. This question is linked to a learning objective in an SRO-ONLY lesson plan.
26
2020 ILT NRC EXAM SRO EXAM K/A Number:
012 Reactor Protection A2.06:
Ability to (a) predict the impacts of the following malfunctions on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Failure of RPS signal to trip the reactor.
K/A Value: 4.7 Technical Reference(s): PINGP 1576 page 5 Proposed references to be provided to applicants during examination: PINGP 1576.
Learning Objective: P7410L-034 Obj 10 Using F3-2, corectly classify emergency conditions within 15 minutes of being given a set of Emergency Action Levels.
Question Source: Bank # _______
Modified Bank # _______
New __X_____
Question History: Last NRC Exam ___2010 ILT NRC EXAM________
Question Cognitive Level:
Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content:
55.41 _____
55.43 __*___
Comments:
27
- 88. P8180L-009H 060/022 A2.05/3.5/10D/YES/P8100/C35 AOP1/C35 AOP4/2020 ILT NRC S88
- Unit 1 is in Mode 3.
- 14 CFCU has a significant water leak.
- A water sample determines the water is from the river.
- All actions of C35 AOP4, Cooling Water Leakage in Containment, are complete.
What is the OPERABILITY status of Containment and 14 CFCU?
Containment 14 CFCU A. OPERABLE OPERABLE B. OPERABLE INOPERABLE C. INOPERABLE OPERABLE D. INOPERABLE INOPERABLE 3-PEO Justifications:
- a. Incorrect. Plausible if examinee does not realize the impact on the leak has on the containment boundary and incorrectly believes the CFCU is still operable because it still provides cooling. If the stem was changed such that, "A water sample determines the water is from condensation" would make "a" the correct answer.
- b. Correct. Once C35 AOP4 actions are complete, CTMT is restored to operable but 14 CFCU is still inoperable until leak is fixed.
- c. Incorrect. Plausible if examinee incorrectly believes C35 AOP4 actions will render 14 CFCU operable and CTMT inoperable.
- d. Incorrect. Plausible as both would be inoperable if no operator actions are taken.
EXPLANATION:
This question is linked to 10 CFR 55.43(b)(2) Tech Specs. The question can NOT be answered by solely knowing < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TS actions OR by solely knowing the LCO "above the line" information OR by solely knowing TS Safety Limits. The question requires the knowledge of TS bases that is required to analyze TS required actions and terminology.
28
2020 ILT NRC EXAM SRO EXAM K/A Number:
022 Containment Cooling A2.05:
Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Major leak in CCS.
K/A Value: 3.5 Technical Reference(s): C35 AOP4 page 6 Proposed references to be provided to applicants during examination: C35 AOP4 Learning Objective: P8180L-009H Obj. 10D Determine basis for technical specification requirements.
Question Source: Bank #: X Modified Bank #: ____
New: __
Question History: Last NRC Exam: 2016 ILT Question Cognitive Level:
Memory or Fundamental Knowledge:
Comprehension or Analysis: X 10 CFR Part 55 Content:
55.41:
55.43: 2 Comments:
29
- 89. P8140L-241 002/059 2.4.6/4.7/B2/YES/P8100/1FR-H.1//2020 ILT NRC S89
- The crew is performing 1FR-H.1, Loss of Heat Sink.
- Unit 1 Auxiliary Feed Water is NOT available.
- Both Steam Generator WIDE RANGE levels are 38% and stable.
- 21 MDAFW pump is Out of Service.
The Shift Supervisor will direct the crew to establish a heat sink via...
A. BLEED AND FEED.
B. MAIN FEED WATER PUMPS.
D. UNIT 2 AUX FEEDWATER PUMPS.
3-SPK Justifications:
- a. Incorrect. Feed and Bleed would only be performed if the steam generators were below 17% WR.
Plausible if the examinee incorrectly believes that main feed is not available during FR-H.1.
- b. Correct.
- c. Incorrect. Plausible if the examinee incorrectly believes that Attachment N will be directed to implement flex strategies.
- d. Incorrect. Cross connect to U2 AFW is not available when 21 is out of service. Plausible if the examinee incorrectly believes that 22 TDAFW can be use to connect AFW to unit 1.
EXPLANATION:
This question tests knowledge/ability that is unique to the SRO position. This question is linked to a learning objective labeled in the lesson plan as being SRO-only.
30
2020 ILT NRC EXAM SRO EXAM K/A Number:
059 Main Feedwater 2.4.6:
Knowledge of EOP mitigation strategies.
K/A Value: 4.7 Technical Reference(s): FR-H.1 pg 6 Proposed references to be provided to applicants during examination: None Learning Objective: P8140S-200 Att41 5.c.
During the Loss of Heat Sink, demonstrate the ability to:
Direct crew response to abnormal operating events in accordance with appropriate Alarm Response/Abnormal/Emergency Operating Procedures (SRO ONLY).
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content:
55.41 55.43 NA Comments:
31
- 90. P8186L-014 084/064 2.2.25/4.2/10D/YES/P8100/1C37.10/2C37.10/2020 ILT NRC S90 Are D5 and D6 Emergency Diesel Generators OPERABLE?
D5 EDG D6 EDG A. OPERABLE OPERABLE B. OPERABLE NOT OPERABLE C. NOT OPERABLE OPERABLE D. NOT OPERABLE NOT OPERABLE 3-PEO Justification:
- a. Incorrect. Unit 2 EDG are not operable based on the low outdoor temperature. Plausible if the examinee incorrectly believes that both sets of EDG take suction from the room they are in.
- b. Incorrect. Plausible if the examinee incorrectly believes that only B train takes suction from outdoor air to prevent common failure of outdoor temp.
- c. Incorrrect. Plausible if the examinee incorrectly believes that only A train takes suction from outdoor air to prevent common failure of outdoor temp.
- d. Correct.
EXPLANATION:
This question is linked to 10 CFR 55.43(b)(2) Tech Specs. The question can NOT be answered by solely knowing < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TS actions OR by solely knowing the LCO "above the line" information OR by solely knowing TS Safety Limits. The question requires the knowledge of TS bases that is required to analyze TS required actions and terminology.
32
2020 ILT NRC EXAM SRO EXAM K/A Number:
064 Emergency Diesel Generators 2.2.25:
Knowledge of the bases in technical specifications for limiting conditions for operations and safety limits.
K/A Value: 4.2 Technical Reference(s): 1C37.10 pg 3, 2C37.10 pg 4 Proposed references to be provided to applicants during examination: None Learning Objective: P8186L-014 Obj. 10D Determine the basis for technical specificaion requirements.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content:
55.41 55.43 2 Comments:
33
- 91. P8140L-224 005/001 A2.07/4.4/7/YES/P8100/2ES-0.1//2020 ILT NRC S91
- Unit 2 is at 100% power.
- A spurious REACTOR TRIP ocurred.
- One Control Rod is STUCK and DID NOT MOVE.
- Main Feed Regulating Valves are OPEN.
The Shift Supervisor will direct the crew to reduce MFRV demand to ZERO in accordance with...
A. 2ES-0.1, REACTOR TRIP RECOVERY.
B. 2E-0, REACTOR TRIP OR SAFETY INJECTION.
C. 2C1.3-BOP, UNIT 2 BALANCE OF PLANT SYSTEM SHUTDOWN.
D. 2FR-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS.
3-SPK Justification:
- a. Correct. The crew will transition to ES-0.1 after completing immediate actions of E-0. Step 6 closes MFRV.
- b. Incorrect. The crew will transition out of E-0 after immediate actions are complete without an SI present.
Pressurizer pressure will lower on a reactor trip, but will not lower to the SI set point without other complicating factors. Plausible if the examinee incorrectly believes that SI will actuate based on rate at which pressurizer pressure is decreasing.
- c. Incorrect. The crew will not enter the BOP procedure until the EOP network has been exited. The MFRVs will be closed prior to that point in ES-0.1. Plausible if the examinee incorrectly believes that since there is no major casualty, that the EOP network will not be entered during the trip.
- d. Incorrect. The crew will not enter the FR series procedure from E-0 because reactor power will be below 5%. Plausible if the examinee incorrectly believes that the lack of a single rod at bottom light is sufficient to cause a transition to FR-S.1.
EXPLANATION:
This question is linked to 10 CFR 55.43(b)(5) Assessment and selection of procedures. The question can NOT be answered by solely knowing "systems knowledge" OR by solely knowing immediate operator actions OR by solely knowing entry conditions for AOPs or plant parameters that require direct entry to MAJOR EOPs OR by solely knowing the purpose overall sequence of events or overall mitigative strategy of a procedure. The question requires assessing plant conditions (normal, abnormal, or emergency) and then selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed.
34
2020 ILT NRC EXAM SRO EXAM K/A Number:
010 Control Rod Drive A2.07:
Ability to (a) predict the impacts of the following malfunctions on the CRDS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Effect of reactor trip on primary and secondary parameters and systems.
K/A Value: 4.4 Technical Reference(s): 2ES-0.1 pg 5 Proposed references to be provided to applicants during examination: None Learning Objective: P8140L-224 Obj. 7 For 2ES-0.1, explain the purpose of any step or series of steps.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content:
55.41 55.43 5 Comments:
35
- Unit 2 is at 100% power.
- 2R-48, U2 CNTMT HI RNG AREA MON B, has been OOS for the past 2 days.
- T.S. LCO 3.3.3 Condition A was entered 2 days ago for 2R-48.
- A power supply fuse blows for 2R-49, U2 CNTMT HI RNG AREA MON A.
What T.S. LCO 3.3.3 Conditions will the Shift Supervisor enter at this time?
A. A ONLY B. A and D ONLY C. A, D, and I ONLY D. A, D, G, and I ONLY 3-SPR Justifications:
- a. Incorrect. Condition D is required to be entered because both high range montors are inoperable.
Plausible if examinee incorrectly believes that a third channel is available and so Condition D is not required.
- b. Correct. Per Table 3.3.3-1, two Containment High Range Area Monitors are required to be operable.
With two required channels inoperable, Condition D is entered with required action of restoring one channel to operable status within 7 days. A second entry of Condition A is also required.
- c. Incorrect. Conditions G and I are not required for 7 days after entry into condition D. Plausible if examinee implements T.S. 3.3.3 similiar to TS 3.3.1 and 3.3.1 by going to the table first and entering the condition listed in the table (in this case "I").
- d. Incorrect. Conditions G and I are not required for 7 days after entry into condition D. Plausible if examinee implements T.S. 3.3.3 similiar to TS 3.3.1 and 3.3.1 by going to the table first and entering the condition listed in the table (in this case "I") and determining that condition G must also be required based on the table column heading.
EXPLANATION:
This question is linked to 10 CFR 55.43(b)(2) Tech Specs. The question can NOT be answered by solely knowing < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TS actions OR by solely knowing the LCO "above the line" information OR by solely knowing TS Safety Limits. The question requires the application of required actions for TS 3.3.3.
36
2020 ILT NRC EXAM SRO EXAM K/A Number:
072 Area Radiation Monitoring (ARM) System A2.03:
Ability to (a) predict the impacts of the following malfunctions or operations on the ARM system- and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Blown power supply fuses.
Technical Reference(s): T.S. LCO 3.3.3 Proposed references to be provided to applicants during examination: T.S. LCO 3.3.3 Learning Objective: P8182L-002 Obj. 10C Apply technical specifications to given plant conditions to determine required actions.
Question Source: Bank # _P8182L-002 089______
Modified Bank # _______
New _______
Question History: Last NRC Exam ___2014 ILT_________
Question Cognitive Level:
Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content:
55.41 _____
55.43 __2___
Comments:
37
- 93. P8197L-009 036/086 2.2.4/3.6/1/YES/P8100/F5 APP B//2020 ILT NRC S93
- Unit 1 is at 100% power.
- Unit 2 is at 100% power.
- A FIRE is occurring in the Control Room.
- The crew is performing F5 Appendix B, Control Room Evacuation (FIRE).
The Unit (a) Shift Supervisor will determine if Control Room Evacuation is required.
The Unit (b) Shift Supervisor will align equipment for control from the Hot Shutdown Panel.
A. (a) 1 (b) 1 B. (a) 1 (b) 2 C. (a) 2 (b) 1 D. (a) 2 (b) 2 1-P Justifications:
- a. Correct.
- b. Incorrect. Plausible if the examinee incorrectly believes that the U2 SS is responsible for aligning controls in the HSP while the U1 SS aligns controls in the MCR.
- c. Incorrect. Plausible if the examinee incorrectly believes that the U2 SS is responsible for executing F5 App B CR actions to promote PI simulator training capability since the simulator is U1.
- d. Incorrect. Plausible if the examinee incorrectly believes that the U2 SS is responsible for executing all steps of F5 App B because the STA automatically takes over U2 in that situation.
EXPLANATION:
This question is linked to 10 CFR 55.43(b)(5) Assessment and selection of procedures. The question can NOT be answered by solely knowing "systems knowledge" OR by solely knowing immediate operator actions OR by solely knowing entry conditions for AOPs or plant parameters that require direct entry to MAJOR EOPs OR by solely knowing the purpose overall sequence of events or overall mitigative strategy of a procedure. The question requires the knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures.
38
2020 ILT NRC EXAM SRO EXAM K/A Number:
086 Fire Protection 2.2.4:
Ability to explain the variations in control board layouts, systems, instrumentation, and procedural actions between units at a facility. (multi unit)
K/A Value: 3.6 Technical Reference(s): F5 AppB page 7 Proposed references to be provided to applicants during examination: None Learning Objective: P8197L-009 Obj. 1 Discuss the basic overall purpose of F5 APP B.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content:
55.41 55.43 5 Comments:
39
- 94. P8182L-003 058/2.1.40/3.9/5/YES/P8100/D5.2/T.S. 3.9.4/2020 ILT NRC S94 In accordance with D5.2, Reactor Refueling Operations, what is the MINIMUM time the reactor must be SUBCRITICAL prior to movement of irradiated fuel assemblies within the reactor core?
A. 12 HOURS B. 24 HOURS C. 50 HOURS D. 168 HOURS 1-P Justifications:
- a. Incorrect. Plausible if the examinee incorrectly believes that this time is to ensure that power is less than 5%.
- b. Incorrect. Plausible if the examinee incorrectly believes that this time limit is related to the time to boil point for shutdown safety spent fuel pool decay heat removal.
- c. Correct.
- d. Incorrect. Plausible if the examinee incorrectly believes that one week is administratively required between shutdown and offload to ensure adequate margin to the TS requirement.
EXPLANATION:
This question is linked to 10 CFR 55.43(b)(6) Procedures and limitations involved in alterations in core configuration. This question requires knowledge of administrative requirements associated with refueling activities.
40
2020 ILT NRC EXAM SRO EXAM K/A Number:
2.1.40:
Knowledge of refueling administrative requirements.
Technical Reference(s): D5.2 page 16, Proposed references to be provided to applicants during examination: None Learning Objective: P8182L-003 Obj. 5 Recall precautions, limitations, and hazards associated with system operations, their bases, and required safety equipment.
Question Source: Bank # X Modified Bank #
New Question History: Last NRC Exam 2018 AUDIT Question Cognitive Level:
Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content:
55.41 55.43 6 Comments:
41
- 95. P9150L-024 044/2.1.29/4.0/6/YES/P9100/C1.1/5 AWI 3.10.1/2020 ILT NRC S95
- There is a C Section checklist is in progress for a planned reactor startup.
- The operator performing the Independant Verification (IV) has found a valve that does not match the position on the checklist.
- The valve has been placed in the correct position.
In accordance with C1.1, Perfromance of C and D Section Checklists, the applicable unit Shift Supervisor will direct...
A. the system engineer to perform an IV of the repositioned valve.
B. an additional operator to perform an IV on the repositioned valve.
C. two additional operators to perform a concurrent verification of the repositioned valve.
D. the system engineer and engineering supervisor to perform a concurrent verification of the repositioned valve.
2-DS Justifications:
- a. Incorrect. Plausible if the examinee incorrectly believes that the system engineer is qualified to perform an IV and C1.1 requires the system engineer to perform the IV.
- b. Correct.
- c. Incorrect. Plausible if the examinee incorrectly believes that a concurrent verification would be required C1.1.
- d. Incorrect. Plausible if the examinee incorrectly believes that a concurrent verification would be required C1.1 and the system engineer and engineering supervisor are qualified to perform a CV.
EXPLANATION:
This question is not linked to 10 CFR 55.43(b) but is still classified as SRO-only because it is uniuqe to the SRO position at Prairie Island. This question is linked to a learning objective in an SRO-ONLY lesson plan.
42
2020 ILT NRC EXAM SRO EXAM K/A Number:
2.1.29:
Knowledge of how to conduct system lineups, such as valves, breakers, and switches, etc..
K/A Value: 4.0 Technical Reference(s): C1.1 pg 8, 5AWI 3.10.1 pg 17 (fig 1)
Proposed references to be provided to applicants during examination: NONE Learning Objective: P8140S-200 Att 09 Obj.2d During preparation for unit startup IAW 1C1.2-M5 and 1C1.2-BOP, demonstarte the ability to:
Direct plant operations such that requirements of Normal Operating Procedures and Technical Specifications are implemented. (SRO only)
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content:
55.41 55.43
- Comments:
43
- 96. P8171L-014 061/2.2.23/4.6/4/YES/P8100/TS//2020 ILT NRC S96
- Unit 1 is at 100% power.
- A valve was declared inoperable 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.
- The Shift Supervisor entered Condition A 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.
- The valve is currently INOPERABLE.
From NOW, the MAXIMUM amount of time to place the unit in MODE 3 is hour(s).
A. 2 B. 6 C. 10 D. 12 44
2020 ILT NRC EXAM SRO EXAM 3-SPR Justifications:
- a. Incorrect. the plant has 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> from entry into condition B to be in mode 3. Plausible if the examinee incorrectly believes that the consequences of failing to complete the action for condition A is NRC enforcement action instead of required entry into condition B AND the examinee incorrectly also beleives that all actions are simultaneously entered when a TS is NOT met.
- b. Correct.
- c. Incorrect. the plant has 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> from entry into condition B to be in mode 3. Plausible if the examinee incorrectly believes that each condition is worked sequentially once one is entered and that B is entered 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after A is competed.
- d. Incorrect. the plant has 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> from entry into condition B to be in mode 3. Plausible if the exmainee incorrectly believes the plant has to go through mode 4 to get to mode 3 and has 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to do so.
EXPLANATION:
This question is linked to 10 CFR 55.43(b)(2) Tech Specs. The question can NOT be answered by solely knowing < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TS actions OR by solely knowing the LCO "above the line" information OR by solely knowing TS Safety Limits. The question requires the application of required actions for T.S.
K/A Number:
2.2.23:
Ability to track Technical Specification limiting conditions for operations.
K/A Value: 4.6 Technical Reference(s): TS 1.3-5 to 1.3-12 Proposed references to be provided to applicants during examination: Table from example 1.3-4 (Located in Stem)
Learning Objective: P8171L-014 Obj. 4 Given plant status, apply technical specifications.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content:
55.41 55.43 2 Comments:
45
- 97. P8171L-009 010/2.2.37/4.6/3/YES/P8100/FP-OP-OL-01//2020 ILT NRC S97
- Both Units are at 100% power.
- A pump did NOT meet the acceptance criteria of a surveillance.
- The pump is AVAILABLE.
In accordance with FP-OP-OL-01, Operability/Functionality Determination, and Technical Specifications, the pump is...
A. OPERABLE.
B. OPERABLE BUT DEGRADED.
C. OPERABLE BUT NON-CONFORMING.
D. NOT OPERABLE.
3 - SPK Justifications:
- a. Incorrect. Plausible if the examinee incorrectly believes that any equipment that is available is operable.
- b. Incorrect. Plausible if the examinee incorrectly believes that since the surveillance was completed but not within the acceptance criteria, it is degraded.
- c. Incorrect. Plausible if the examinee incorrectly believes that a failure to meet the surveillance is evidence of a degradation.
- d. Correct. any equipment that doesn't meet acceptance criteria of a surveillance is inoperable.
EXPLANATION:
This question is linked to 10 CFR 55.43(b)(2) Tech Specs. The question can NOT be answered by solely knowing < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TS actions OR by solely knowing the LCO "above the line" information OR by solely knowing TS Safety Limits. The question requires the knowledge of TS bases that is required to analyze TS required actions and terminology.
46
2020 ILT NRC EXAM SRO EXAM K/A Number:
2.2.37:
Ability to determine operability and/or availability of safety related equipment.
K/A Value: 4.6 Technical Reference(s): FP-OP-OL-01 page 14 and 15 Proposed references to be provided to applicants during examination: None Learning Objective: P8171L-009 Obj. 3 Apply the Operability Determination process to perform and Immediate Operability Determination.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content:
55.41 55.43 2 Comments:
47
- 98. P8182L-002 017/2.3.14/3.8/12B/YES/P8100/H4//2020 ILT NRC S98
- Steam Generator blowdown is aligned to the river.
- Secondary coolant specific activity is <0.01uCi/gram DOSE EQUIVALENT I-131.
- R-21, CIRC WATER DISCH MONITOR, fails low and is OOS.
In accordance with H4, Offsite Dose Calculation Manual (ODCM), the Shift Supervisor will ensure...
A. flow rate is estimated every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
B. two HPs independently verify release rate calculations.
C. grab samples are collected and analyzed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D. grab samples are collected and analyzed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2-RI Justifications:
- a. Incorrect. Plausible if examinee incorrectly believes blowdown flows into circ water upstream of R-21 to allow flow-compensated R-21 to be considered a blowdown flow isntrument.
- b. Incorrect. Plausible if examinee incorrectly believes that circ water leaving the plant is considered an effluent line.
- c. Correct. Per Table 2.2 of H4, if the discharge canal monitor is inoperable then action 6 is required.
- d. Incorrect. Plausible if examinee incorrectly believes R-21 is used to measure Steam Generator Blowdown effluent; however, R-19 is used to measure blowdown effluent.
EXPLANATION:
This question is linked to 10 CFR 55.43(b)(2) Tech Specs. The question can NOT be answered by solely knowing < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TS actions OR by solely knowing the LCO "above the line" information OR by solely knowing TS Safety Limits. The question requires the application of required actions for the Offsite Dose Calculation Manual. ODCM required actions is a SRO only function.
48
2020 ILT NRC EXAM SRO EXAM K/A Number:
2.3.14:
Knowledge of radiation or contaimation hazards that may arise during normal, abnormal, or emergency conditions or activities.
Technical Reference(s): H4 pages 101-102.
Proposed references to be provided to applicants during examination: Table 2.2 of H4 Learning Objective: P8182L-002 Obj. 12B Describe required ODCM actions for applicable Radiation Monitors out of service.
Question Source: Bank # _ X _
Modified Bank # _
New _______
Question History: Last NRC Exam ___2014 ILT_______
Question Cognitive Level:
Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content:
55.41 _____
55.43 __2__
Comments:
49
- 99. FL-BEP-ORO-001F 001/2.4.37/4.1/9/YES/P8100/E-PLAN//2020 ILT NRC S99
- It is Wednesday at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />.
- The site is normally manned.
- Unit 1 is at 100% power.
- A LOCA is occurring on UNIT 2.
- Activation of the TSC is required and is IN PROGRESS.
- The Shift Manager is NOT available.
In accordance with the E-Plan, the Emergency Director duties will be carried out by...
A. the Site Vice President.
B. the Operations Manager.
C. the Unit 1 Shift Supervisor.
D. the Unit 2 Shift Supervisor.
1 - Facts Justifications:
- a. Incorrect. Plausible if the examinee incorrectly believes that the SVP will absorb these duties until the TSC is manned.
- b. Incorrect. Plausible if the examinee incorrectly believes that the duties must be tansferred to a higher level manager.
- c. Correct.
- d. Incorrect. Plausible if the examinee incorrectly believes that the SS responsible for the unit must absorb these duties.
EXPLANATION:
This question is linked to 10 CFR 55.43(b)(5) Assessment and selection of procedures. The question can NOT be answered by solely knowing "systems knowledge" OR by solely knowing immediate operator actions OR by solely knowing entry conditions for AOPs or plant parameters that require direct entry to MAJOR EOPs OR by solely knowing the purpose overall sequence of events or overall mitigative strategy of a procedure. The question requires the knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures.
50
2020 ILT NRC EXAM SRO EXAM K/A Number:
2.4.37:
Knowledge of the lines of authority during implementation of an emergency plan.
K/A Value: 4.1 Technical Reference(s): E-Plan page 20 Proposed references to be provided to applicants during examination: None Learning Objective: FL-BEP-ORO-001F Obj. 9 Describe the ERO and the heirarchy of positions within the ERO.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content:
55.41 55.43 5 Comments:
51
2020 ILT NRC EXAM SRO EXAM 100. P7410L-034 145/2.4.43/3.8/8/YES/P8100/PINGP 1576/F3-2/2020 ILT NRC S100
- Unit 1 is at 100% power.
- Unit 2 is at 25% power.
- Plant Telephone Network has FAILED.
- Plant Paging System has FAILED.
- ENS Network has FAILED.
Which of the following EALs is MET?
A. CU 5.1 B. CU 5.3 C. SU 6.1 D. SU 6.3 3-SPR Justifications:
- a. Incorrect. Plausible if the examinee incorrectly believes that highest mode number is the highest power and that the EAL is met if ANY of the communcation systems are out of service.
- b. Incorrect. Plausible if the examinee incorrectly believes that the highest mode number is the highest power level.
- c. Incorrect. Plausible if the examinee incorrectly believes that the EAL is met if ANY of the communciation systems are out of service.
- d. Correct.
EXPLANATION:
This question is not linked to 10 CFR 55.43(b) but is still classified as SRO-only because it is unique to the SRO position at Prairie Island. This question is linked to a learning objective in an SRO-ONLY lesson plan.
52
2020 ILT NRC EXAM SRO EXAM K/A Number:
2.4.13:
Knowledge of emergency communication systems and techniques.
K/A Value: 3.8 Technical Reference(s): PINGP 1576 page 5 Proposed references to be provided to applicants during examination: PINGP 1576 Learning Objective: P7410LL-034 Obj. 8 Given the definition of an emergency classification, be able to identify that classification.
Question Source: Bank #
Modified Bank #
New X Question History: Last NRC Exam N/A Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content:
55.41 55.43
- Comments:
You have completed the test!
53