ML22010A199: Difference between revisions

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ES-301 Administrative Topics Outline Form ES-301-1
ES-301 Administrative Topics Outline Form ES-301-1 ES-301-1 (Revision 11)
 
Facility: ___Vogtle 1 & 2_____
Facility: ___Vogtle 1 & 2_____ Date of Examination: _11/15/2021_
Date of Examination: _11/15/2021_
Examination Level: RO SRO Operating Test Number: _ 2021-301_
Examination Level: RO SRO Operating Test Number: _2021-301_
 
Administrative Topic (see Note)
Administrative Topic (see Note) T ype Describe activity to be performed Code*
Type Code*
 
Describe activity to be performed Conduct of Operations R, M
Conduct of Operations R, M a. V-NRC-JP-14005-ILT23: Determine k eff with All Shutdown Bank Rods Withdrawn in Preparation for Reactor Startup
: a. V-NRC-JP-14005-ILT23: Determine keff with All Shutdown Bank Rods Withdrawn in Preparation for Reactor Startup  


== Description:==
==
Description:==
Unit 2 is performing a reactor startup following a reactor trip from steady state, 100% reactor power. Per 12003-2, Reactor Startup (Mode 3 to Mode 2), the applicant will be required to calculate keff for the given conditions using 14005-2, Shutdown Margin and keff Calculations, Data Sheet 3, and the Plant Technical Data Book and then determine if keff meets the acceptance criterion.
Unit 2 is performing a reactor startup following a reactor trip from steady state, 100% reactor power. Per 12003-2, Reactor Startup (Mode 3 to Mode 2), the applicant will be required to calculate keff for the given conditions using 14005-2, Shutdown Margin and keff Calculations, Data Sheet 3, and the Plant Technical Data Book and then determine if keff meets the acceptance criterion.
G2.1.43 RO 4.1
G2.1.43 RO 4.1 Conduct of Operations R, M
 
: b. V-NRC-JP-19263-ILT23: Determine Maximum Allowable Venting Time for Venting Voids in the Reactor Vessel  
Conduct of Operations R, M b. V-NRC-JP-19263-ILT23: Determine Maximum Allowable Venting Time for Venting Voids in the Reactor Vessel


== Description:==
==
Description:==
Unit 1 reactor tripped due to a LOCA.
Unit 1 reactor tripped due to a LOCA.
RCS pressure is recovering and the crew is making preparations to vent the reactor vessel by performing 19263-1, Response to Voids in Reactor Vessel. The applicant will be provided with pictures of various Control Board instruments, and will be directed to calculate the maximum allowable ventingtime using 19263-1, Attachment 3, Instructions for Determining Venting T im e.
RCS pressure is recovering and the crew is making preparations to vent the reactor vessel by performing 19263-1, Response to Voids in Reactor Vessel. The applicant will be provided with pictures of various Control Board instruments, and will be directed to calculate the maximum allowable venting time using 19263-1,, Instructions for Determining Venting Time.
G2.1.25 RO 3.9
G2.1.25 RO 3.9 Equipment Control R, M
 
: c. V-NRC-JP-14915-ILT23: Perform Quadrant Power Tilt Ratio (QPTR) Surveillance for Inoperable QPTR Monitor  
Equipment Control R, M c. V-NRC-JP-14915-ILT23: Perform Quadrant Power Tilt Ratio (QPTR) Surveillance for Inoperable QPTR Monitor


== Description:==
==
Description:==
The Unit 2 QPTR Monitor Alarm is declared inoperable. Using the Power Range NI data provided and the Plant Technical Data Book, the applicant will be required to calculate the current QPTR using 14915-2, Special Conditions Surveillance Logs, Data Sheet 8, Quadrant Power Tilt Ratio. The applicant will then determine that the calculated QPTR does not meet the acceptance criterion.
The Unit 2 QPTR Monitor Alarm is declared inoperable. Using the Power Range NI data provided and the Plant Technical Data Book, the applicant will be required to calculate the current QPTR using 14915-2, Special Conditions Surveillance Logs, Data Sheet 8, Quadrant Power Tilt Ratio. The applicant will then determine that the calculated QPTR does not meet the acceptance criterion.
G2.2.12 RO 3.7
G2.2.12 RO 3.7 ML22010A199
 
ES-301-1 (Revision 11)
ES-301 Administrative Topics Outline Form ES-301-1


Radiation Control R, P d. V-NRC-JP-NMP-HP-001-ILT23: Assess Radiological Conditions, Calculate Projected Dose to Determine Lowest Dose Route, and Determine if Task Can B e Performed Without Exceeding the Task Dose Limit
ES-301 Administrative Topics Outline Form ES-301-1 ES-301-1 (Revision 11)
Radiation Control R, P
: d. V-NRC-JP-NMP-HP-001-ILT23: Assess Radiological Conditions, Calculate Projected Dose to Determine Lowest Dose Route, and Determine if Task Can Be Performed Without Exceeding the Task Dose Limit  


== Description:==
==
Description:==
An operator will be dispatched to manually open an MOV in the Unit 1 RHR Pump Room. The applicant will be given two possible routes to the valve, the radiological conditions associated with each route, and the time required to complete the task. Two maps will also be provided that include the RHR A Heat Exchanger Rooms and the RHR A Pump Rooms, so the applicant must select the correct dose rate based on the location of the task. The applicant will then be directed to calculate the lowest dose route based on the projected dose to the operator and determine if the task can be performed without exceeding the established dose limit.
An operator will be dispatched to manually open an MOV in the Unit 1 RHR Pump Room. The applicant will be given two possible routes to the valve, the radiological conditions associated with each route, and the time required to complete the task. Two maps will also be provided that include the RHR A Heat Exchanger Rooms and the RHR A Pump Rooms, so the applicant must select the correct dose rate based on the location of the task. The applicant will then be directed to calculate the lowest dose route based on the projected dose to the operator and determine if the task can be performed without exceeding the established dose limit.
G2.3.12 RO 3. 2
G2.3.12 RO 3.2 Emergency Plan N/A N/A NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
 
* Type Codes & Criteria:
Emergency Plan N/A N/A
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)
 
NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
* T ype Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)
(N)ew or (M)odified from bank ( 1)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
(P)revious 2 exams ( 1; randomly selected)  
 
ES-301-1 (Revision 11 )
ES-301 Administrative Topics Outline Form ES-301-1


Facility: ___Vogtle 1 & 2_____ Date of Examination: _11/15/2021_
ES-301 Administrative Topics Outline Form ES-301-1 ES-301-1 (Revision 11)
Facility: ___Vogtle 1 & 2_____
Date of Examination: _11/15/2021_
Examination Level: RO SRO Operating Test Number: _2021-301_
Examination Level: RO SRO Operating Test Number: _2021-301_
Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations R, M
: a. V-NRC-JP-14228-ILT23: Review and Evaluate Monthly Surveillance Logs 14228-1.


Administrative Topic (see Note) Type Describe activity to be performed Code*
==
 
Description:==
Conduct of Operations R, M a. V-NRC-JP-14228-ILT23: Review and Evaluate Monthly Surveillance Logs 14228-1.
 
== Description:==
Unit 1 is at 100% reactor power. OATC has just completed 14228-1, Operations Monthly Surveillance Logs. The applicant is directed to perform a review of the Monthly Surveillance Logs for errors and determine if any Tech Specs are not met. There will be two out of spec readings. One for accumulator boron concentration and one for accumulator level. The applicant will then be required to determine the applicable Tech Spec / TRM Required Actions.
Unit 1 is at 100% reactor power. OATC has just completed 14228-1, Operations Monthly Surveillance Logs. The applicant is directed to perform a review of the Monthly Surveillance Logs for errors and determine if any Tech Specs are not met. There will be two out of spec readings. One for accumulator boron concentration and one for accumulator level. The applicant will then be required to determine the applicable Tech Spec / TRM Required Actions.
G2.1.2 SRO 4.4
G2.1.2 SRO 4.4 Conduct of Operations R, M
 
: b. V-NRC-JP-19200-HL23: Evaluate Critical Safety Function Status Trees (CSFSTs) with an Inoperable Integrated Plant Computer (IPC)  
Conduct of Operations R, M b. V-NRC-JP-19200-HL23: Evaluate Critical Safety Function Status Trees (CSFSTs) with an Inoperable Integrated Plant Computer (IPC)


== Description:==
==
Description:==
Unit 1 reactor tripped from full power, and the crew transitioned from 19000-1, Reactor Trip or Safety Injection. The applicant will be directed to monitor and evaluate all CSFSTs, identify the highest priority critical safety function, and determine any required procedure transition using 19200-1, Critical Safety Function Status Trees. With the IPC not available, the applicant will be given data for multiple parameters to be used in the evaluation.
Unit 1 reactor tripped from full power, and the crew transitioned from 19000-1, Reactor Trip or Safety Injection. The applicant will be directed to monitor and evaluate all CSFSTs, identify the highest priority critical safety function, and determine any required procedure transition using 19200-1, Critical Safety Function Status Trees. With the IPC not available, the applicant will be given data for multiple parameters to be used in the evaluation.
G2.1.7 SRO 4.7
G2.1.7 SRO 4.7  
 
ES-301-1 (Revision 11)
ES-301 Administrative Topics Outline Form ES-301-1


Equipment Control R, M c. V-NRC-JP-14915-ILT23: Perform Quadrant Power Tilt Ratio (QPTR) Surveillance for Inoperable QPTR Monitor and Evaluate Tech Spec / TRM Required Actions
ES-301 Administrative Topics Outline Form ES-301-1 ES-301-1 (Revision 11)
Equipment Control R, M
: c. V-NRC-JP-14915-ILT23: Perform Quadrant Power Tilt Ratio (QPTR) Surveillance for Inoperable QPTR Monitor and Evaluate Tech Spec / TRM Required Actions  


== Description:==
==
Description:==
The Unit 2 QPTR Monitor Alarm is declared inoperable. Using the Power Range NI data provided and the Plant Technical Data Book, the applicant will be required to calculate the current QPTR using 14915-2, Special Conditions Surveillance Logs, Data Sheet 8, Quadrant Power Tilt Ratio. Based on the calculation results, the applicant will determine what Tech Spec / TRM Required Actions are required to be taken.
The Unit 2 QPTR Monitor Alarm is declared inoperable. Using the Power Range NI data provided and the Plant Technical Data Book, the applicant will be required to calculate the current QPTR using 14915-2, Special Conditions Surveillance Logs, Data Sheet 8, Quadrant Power Tilt Ratio. Based on the calculation results, the applicant will determine what Tech Spec / TRM Required Actions are required to be taken.
The calculated QPTR will not meet the Tech Spec requirement and will require a Unit 2 reactor power reduction within two hours.
The calculated QPTR will not meet the Tech Spec requirement and will require a Unit 2 reactor power reduction within two hours.
G2.2.45 SRO 4.7
G2.2.45 SRO 4.7 Radiation Control R, D
: d. V-NRC-JP-NMP-EP-144-ILT23: Assess Radiological Conditions in a Declared Emergency and Review and Approve Emergency Exposure Authorizations


Radiation Control R, D d. V-NRC-JP-NMP-EP-144-ILT23: Assess Radiological Conditions in a Declared Emergency and Review and Approve Emergency Exposure Authorizations
==
 
Description:==
== Description:==
During a General Emergency, three System Operators are to be dispatched to operate vital equipment. The applicant will be given the component identifier, a room map with radiological conditions, and three completed NMP-EP-144-F02, Emergency Exposure Authorizations, for the System Operators. The applicant, serving as the Emergency Director, will be directed to calculate the projected dose to the System Operators and to review and approve, or disapprove if required, the three Emergency Exposure Authorizations in accordance with NMP-EP-144-F02. One of the Emergency Exposure Permits will be completed incorrectly and should not be approved.
During a General Emergency, three System Operators are to be dispatched to operate vital equipment. The applicant will be given the component identifier, a room map with radiological conditions, and three completed NMP-EP-144-F02, Emergency Exposure Authorizations, for the System Operators. The applicant, serving as the Emergency Director, will be directed to calculate the projected dose to the System Operators and to review and approve, or disapprove if required, the three Emergency Exposure Authorizations in accordance with NMP-EP-144-F02. One of the Emergency Exposure Permits will be completed incorrectly and should not be approved.
G2.3.14 SRO 3.8
G2.3.14 SRO 3.8 Emergency Plan R, D
: e. V-NRC-JP-NMP-EP-141-ILT23: Evaluate Conditions on Both Units and Determine the Highest Emergency Event Classification


Emergency Plan R, D e. V-NRC-JP-NMP-EP-141-ILT23: Evaluate Conditions on Both Units and Determine the Highest Emergency Event Classification
==
 
Description:==
== Description:==
Unit 1 is initially at 100% reactor power with Unit 2 in Mode 5. Using the conditions provided for both units that lead to classifiable plant events, the applicant will be directed to determine the highest emergency classification level for the given conditions using NMP-EP-141, Event Classification, and NMP-EP-141-F01, Emergency Classification Determination. This JPM is Time Critical.
Unit 1 is initially at 100% reactor power with Unit 2 in Mode 5. Using the conditions provided for both units that lead to classifiable plant events, the applicant will be directed to determine the highest emergency classification level for the given conditions using NMP-EP-141, Event Classification, and NMP-EP-141-F01, Emergency Classification Determination. This JPM is Time Critical.
G2.4.41 SRO 4.6
G2.4.41 SRO 4.6  
 
ES-301-1 (Revision 11)
ES-301 Administrative Topics Outline Form ES-301-1


ES-301 Administrative Topics Outline Form ES-301-1 ES-301-1 (Revision 11)
NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
* Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)
* Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)
(N)ew or (M)odified from bank ( 1)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
(P)revious 2 exams ( 1; randomly selected)  
 
ES-301-1 (Revision 11)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
 
Facility: ___Vogtle 1 & 2___ Date of Examination: _ 11/ 15/2021_
Exam Level: RO SRO -I SRO -U Operating Test Number: _2021-301_
 
Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO -U
 
System / JPM Title T ype Code* Safety Function
: a. V-NRC-JP-14410- ILT23: Perform Control Rod Shutdown Bank A, M, S 1 Operability Test
 
== Description:==
Unit 1 is at 100% reactor power. Control rod operability testing is in progress. The Control Bank rods have been successfully tested using 14410- 1, Control Rod Operability Test, so the applicant will be directed to perform the control rod operability test on the Shutdown Banks. As Shutdown Bank A rods are being withdrawn following the 10 step insertion, a control rod will dr op, which will require the applicant to enter 18003-C, Rod Control System Malfunction. After entering 18003-C, a second control rod will drop, which will require a manual reactor trip.


(RO / SRO-I)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ES-301-2 (Revision 11)
Facility: ___Vogtle 1 & 2___
Date of Examination: _11/15/2021_
Exam Level: RO SRO-I SRO-U Operating Test Number: _2021-301_
Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System / JPM Title Type Code*
Safety Function
: a. V-NRC-JP-14410-ILT23: Perform Control Rod Shutdown Bank Operability Test


001A2.24 RO 3.5 SRO 4.1
==
: b. V-NRC-JP-19014-ILT23: Transfer ECCS Pumps to Hot Leg A, EN, L, M, S 3 Recirculation
Description:==
Unit 1 is at 100% reactor power. Control rod operability testing is in progress. The Control Bank rods have been successfully tested using 14410-1, Control Rod Operability Test, so the applicant will be directed to perform the control rod operability test on the Shutdown Banks. As Shutdown Bank A rods are being withdrawn following the 10 step insertion, a control rod will drop, which will require the applicant to enter 18003-C, Rod Control System Malfunction. After entering 18003-C, a second control rod will drop, which will require a manual reactor trip.
(RO / SRO-I) 001A2.24 RO 3.5 SRO 4.1 A, M, S 1
: b. V-NRC-JP-19014-ILT23: Transfer ECCS Pumps to Hot Leg Recirculation  


== Description:==
==
Description:==
Unit 1 reactor trip and SI occurred due to a large break LOCA approximately 7.5 hours ago. The ECCS pumps are operating and are aligned for cold leg recirculation. The applicant will be directed to re-align all ECCS pumps for hot leg recirculation using 19014-1, Transfer to Hot Leg Recirculation. During the RHR re-alignment, 1HV-8840, RHR to Hot Leg Isolation, will not open, so the applicant will be required to restore both RHR Trains to cold leg recirculation and then align both SI Trains for hot leg recirculation.
Unit 1 reactor trip and SI occurred due to a large break LOCA approximately 7.5 hours ago. The ECCS pumps are operating and are aligned for cold leg recirculation. The applicant will be directed to re-align all ECCS pumps for hot leg recirculation using 19014-1, Transfer to Hot Leg Recirculation. During the RHR re-alignment, 1HV-8840, RHR to Hot Leg Isolation, will not open, so the applicant will be required to restore both RHR Trains to cold leg recirculation and then align both SI Trains for hot leg recirculation.
(RO / SRO-I / SRO-U) 011EA1.13 RO/SRO 4.3 A, EN, L, M, S 3


(RO / SRO-I / SRO-U)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ES-301-2 (Revision 11)
 
: c. V-NRC-JP-19231-ILT23: Establish RCS Bleed and Feed Following a Loss of Secondary Heat Sink  
011EA1.13 RO/SRO 4.3
 
ES-301-2 (Revision 11)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
: c. V-NRC-JP-19231-ILT23: Establish RCS Bleed and Feed Following a A, L, M, S 4P Loss of Secondary Heat Sink
 
== Description:==
U nit 1 reactor was manually tripped following a low suction pressure trip of both MFPs. No AFW was available, so the crew entered 19231-1, Response to Loss of Secondar y Heat Sink. The applicant will be directed to continue performing 1923 1-1 and to establish bleed and feed for RCS heat removal. The applicant will be required to start one CCP or SI pump, which should have automatically started, to establish minimum feed flow. Also, when establishing the bleed path, one pressurizer PORV will not open, which will require the reactor vessel head vent valves to be opened to provide an additional bleed path.


==
Description:==
Unit 1 reactor was manually tripped following a low suction pressure trip of both MFPs. No AFW was available, so the crew entered 19231-1, Response to Loss of Secondary Heat Sink. The applicant will be directed to continue performing 19231-1 and to establish bleed and feed for RCS heat removal. The applicant will be required to start one CCP or SI pump, which should have automatically started, to establish minimum feed flow. Also, when establishing the bleed path, one pressurizer PORV will not open, which will require the reactor vessel head vent valves to be opened to provide an additional bleed path.
(RO / SRO-I / SRO-U)
(RO / SRO-I / SRO-U)
WE05EA1.11 RO/SRO 3.5 A, L, M, S 4P
: d. V-NRC-JP-13601-ILT23: Transfer RCS Temperature Control from the ARVs to the Steam Dumps


W E05EA1.11RO/SRO 3.5
==
: d. V-NRC-JP-13601-ILT23: Transfer RCS Temperature Control from D, L, S 4S the ARVs to the Steam Dumps
Description:==
Unit 1 is in Mode 3 and preparing the secondary systems for a reactor startup. RCS temperature is being controlled by the SG ARVs in manual. To continue with start-up preparations, the applicant will be directed to manually transfer RCS temperature control from the SG ARVs to the Steam Dumps using Section 4.4.7.3 of 13601-1, Steam Generator and Main Steam Operation, and then control RCS temperature at 557 +/-2 F.
(RO / SRO-I) 041A4.02 RO/SRO 3.6 D, L, S 4S
: e. V-NRC-JP-13130-ILT23: Reduce Containment Hydrogen Concentration Using the Post-LOCA Containment Hydrogen Purge System


== Description:==
==
U nit 1 is in Mode 3 and preparing the secondary s ystems for a reactor startup. RCS temperature is being controlled by the SG ARVs in manual. To continue with start-up preparations, the applicant will be directed to manually t ransfer RCS temperature control from the SG ARVs to the Steam Dumps using Section 4.4.7.3 of 13601-1, Steam Generator and Main Steam Operation, and then control RCS temperature at 557 +/-2 F.
Description:==
Unit 1 reactor trip and SI occurred due to a LOCA. The crew is performing 19010-1, Loss of Reactor or Secondary Coolant.
Attempts to lower hydrogen concentration in containment using Service Air dilution were not successful, so the applicant will be required to place the Post-LOCA Containment Hydrogen Purge system in operation to reduce hydrogen concentration in the containment atmosphere using 13130-1, Post-Accident Hydrogen Control.
(RO / SRO-I / SRO-U) 028A2.02 RO 3.2 SRO 3.4 D, EN, L, S 5


(RO / SRO-I)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ES-301-2 (Revision 11)
: f.
V-NRC-JP-13427-ILT23: Discontinue Parallel Operation by Removing DG1A from Bus 1AA02


041A4.02 RO/SRO 3.6
==
: e. V-NRC-JP-13130- ILT23: Reduce Containment Hydrogen D, EN, L, S 5 Concentration Using the Post-LOCA Containment Hydrogen Purge System
Description:==
Unit 1 is at 100% reactor power. DG1A is operating in parallel with RAT 1A for a post-maintenance test. The test is complete, so the applicant will be required to discontinue parallel operation by transferring the remaining load to RAT 1A and removing DG1A from bus 1AA02 using 13427A-1, 4160 VAC Bus 1AA02 1E Electrical Distribution System. When the applicant begins the DG1A load reduction, ALB35-D06 DG1A GEN UNDER FREQ will be received in conjunction with indication of low bus frequency. The Annunciator Response Procedure will direct the applicant to verify bus frequency is low and then trip the DG1A output breaker and stop the DG1A engine.
(RO / SRO-I) 064A4.06 RO/SRO 3.9 A, D, P, S 6
: g. V-NRC-JP-13125-ILT23: Place Containment Main (Pre-access)
Purge in Service


== Description:==
==
Unit 1 reactor trip and SI occurred due to a LOCA. The crew is performing 19010- 1, Loss of Reactor or Secondary Coolant.
Description:==
Attempts to lower hydrogen concentration in containment using Service Air dilution were not successful, so the applicant will be required to place the Post-LOCA Containment Hydrogen Purge system in operation to reduce hydrogen concentration in the containment atmosphere using 13130- 1, Post-Accident Hydrogen Control.
Unit 1 is in Mode 5 for an outage. Chemistry has requested that Containment Main Purge be placed in service. With the containment Equipment Hatch open, the applicant will be directed to place the Main Purge in service using 13125-1, Containment Purge System. Based on the current operating Mode and the Equipment Hatch configuration, the applicant will be required to align dampers and start the Main Purge Exhaust Fan, but the Main Purge Supply Fan will be required to remain off.
(RO / SRO-I) 029A4.01 RO/SRO 2.7 L, M, S 8
: h. V-NRC-JP-13301-ILT23: Respond to Control Room High Radiation


(RO / SRO-I / SRO-U)
==
Description:==
Unit 1 is at 100% reactor power with the applicant assigned to perform the duties of the Unit Operator. High radiation alarms will be received when radiation is detected in the Control Room ventilation system. Control Room Isolation will fail to automatically actuate, so the applicant will be required to manually align the Control Room ventilation system using 13301-C, CBCR Normal HVAC and Emergency Filtration System.
(RO) 050A2.03 RO 3.5 SRO 3.8 D, EN, S 9
RO ONLY


028A2.02 RO 3.2 SRO 3.4
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ES-301-2 (Revision 11)
In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
: i.
V-NRC-JP-16900-ILT23: Place RWST Sludge Mixing Isolation Valve on the Jack


ES-301-2 (Revision 11)
==
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
Description:==
: f. V-NRC-JP-13427-ILT23: Discontinue Parallel Operation by A, D, P, S 6 Removing DG1A from Bus 1AA02
Unit 2 is at 100% reactor power with the RWST Sludge Mixing system in service for water temperature control. A maintenance activity will temporarily remove DC power to a Sludge Mixing isolation valve solenoid. To keep Sludge Mixing in service during the maintenance activity, the applicant will be directed to place the RWST Sludge Mixing isolation valve on the jack using 16900-C, Air Operated Valve Manual Jack Operation.
(RO / SRO-I / SRO-U) 006G2.1.30 RO 4.4 SRO 4.0 D, EN, R 2
: j.
V-NRC-JP-13145-ILT23: Perform a Local Emergency Stop of DG1A  


== Description:==
==
Unit 1 is at 100% reactor power. DG1A is operating in parallel with RAT 1A for a post-maintenance test. The test is complete, so the applicant will be required to discontinue parallel operation by transferring the remaining load to RAT 1A and removing DG1A from bus 1AA02 using 13427A-1, 4160 VAC Bus 1AA02 1E Electrical Distribution System. W hen the applicant begins the DG1A load reduction, ALB35-D06 DG1A GEN UNDER FREQ will be received in conjunction with indication of low bus frequency. The Annunciator Response Procedure will direct the applicant to verify bus frequency is low and then trip the DG1A output breaker and stop the DG1A engine.
Description:==
Unit 1 is at 100% reactor power. DG1A is running in Unit Mode for testing. During the test run, personnel in the DG1A Building report damage to the turbocharger is beginning to release exhaust gases into the building. The applicant will be directed to emergency stop DG1A from the local Engine Control Panel and then reset the emergency stop signal by performing Section 4.4.2 of 13145A-1, Diesel Generator Train A.
(RO / SRO-I) 062A2.18 RO 4.0 SRO 4.3 D, E, EN 6
: k. V-NRC-JP-18038-ILT23: Establish Local Control of Train A and Train B 4160 VAC Switchgears Following a Control Room Evacuation


(RO / SRO-I)
==
 
Description:==
064A4.06 RO/SRO 3.9
: g. V-NRC-JP-13125-ILT23: Place Containment Main (Pre -access) L, M, S 8 Purge in Service
 
== Description:==
Unit 1 is in Mode 5 for an outage. Chemistry has requested that Containment Main Purge be placed in service. W ith the containment Equipment Hatch open, the applicant will be directed to place the Main Purge in service using 13125-1, Containment Purge System. Based on the current operating Mode and the Equipment Hatch configuration, the applicant will be required to align dampers and start the Main Purge Exhaust Fan, but the Main Purge Supply Fan will be required to remain off.
 
(RO / SRO-I)
 
029A4.01 RO/SRO 2.7
: h. V-NRC-JP-13301-ILT23: Respond to Control Room High Radiation D, EN, S 9
 
== Description:==
Unit 1 is at 100% reactor power with the applicant RO ONLY assigned to perform the duties of the Unit Operator. High radiation alarms will be received when radiation is detected in the Control Room ventilation s ystem. Control Room Isolation will fail to automatically actuate, so the applicant will be required to manually align the Control Room ventilation system using 13301-C, CBCR Normal HVAC and Emergency Filtration System.
 
(RO)
 
050A2.03 RO 3.5 SRO 3.8
 
ES-301-2 (Revision 11)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
 
In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO -U
: i. V-NRC-JP-16900- ILT23: Place RWST Sludge Mixing Isolation Valve D, EN, R 2 on the Jack
 
== Description:==
U nit 2 is at 100% reactor power with the RW ST Sludge Mixing system in service for water temperature control. A maintenance activit y will temporarily remove DC power to a Sludge Mixing isolation valve solenoid. To keep Sludge Mixing in service during the maintenance activity, the applicant will be directed to place the RW ST Sludge Mixing isolation valve on the jack using 16900- C, Air Operated Valve Manual Jack Operation.
 
(RO / SRO-I / SRO-U)
 
006G2.1.30RO 4.4 SRO 4.0
: j. V-NRC-JP-13145-ILT23: Perform a Local Emergency Stop of DG1A D, E, EN 6
 
== Description:==
Unit 1 is at 100% reactor power. DG1A is running in Unit Mode for testing. During the test run, personnel in the DG1A Building report damage to the turbocharger is beginning to releas e exhaust gases into the building. The applicant will be directed to emergency stop DG1A from the local Engine Control Panel and then reset the emergency stop signal by performing Section 4.4.2 of 13145A-1, Diesel Generator Train A.
 
(RO / SRO-I)
 
062A2.18 RO 4.0 SRO 4.3
: k. V-NRC-JP-18038 -ILT23: Establish Local Control of Train A and A, D, E, L 8 Train B 4160 VAC Switchgears Following a Control Room Evacuation
 
== Description:==
The Unit 2 Control Room has been evacuated and local control has been established at Shutdown Panel A and Shutdown Panel B. The applicant will be directed to establish local control of the Train A and Train B 4160 VAC switchgears and check ACCW pump status using 18038-2, Operation from Remote Shutdown Panels. The applicant will determine that no ACCW pump is running, so the stopping the RCPs and isolating letdown will be required.
The Unit 2 Control Room has been evacuated and local control has been established at Shutdown Panel A and Shutdown Panel B. The applicant will be directed to establish local control of the Train A and Train B 4160 VAC switchgears and check ACCW pump status using 18038-2, Operation from Remote Shutdown Panels. The applicant will determine that no ACCW pump is running, so the stopping the RCPs and isolating letdown will be required.
(RO / SRO-I / SRO-U) 068AA1.12 RO/SRO 4.2 A, D, E, L 8
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.


(RO / SRO-I / SRO-U)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ES-301-2 (Revision 11)
 
* Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
068AA1.12 RO /SRO 4.2
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1 / 1 / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1  
* All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions,
all five SRO-U systems must serve diffe rent safety functions, and in-plant systems and functions may overlap those tested in the control room.
 
ES-301-2 (Revision 11)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
* Type Codes Criteria for RO / SRO-I / SRO -U
 
(A)lternate path 4-6 / 4 -6 / 2-3 (C)ontrol room (D)irect from bank 9 / 8 / 4 (E)mergency or abnormal in-plant 1 / 1 / 1 (EN)gineered safety feature 1 / 1 / 1 (control room system)
(L)ow-Power / Shutdown 1 / 1 / 1 (N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)
(R)CA 1 / 1 / 1 (S)imulator
 
ES-301-2 (Revision 11)
ES-301 Operating Test Review Worksheet Form ES-301-7
 
Facility: Vogtle 1,2 Exam Date: November 15, 2021 1 2 3 4 5 6 RO Admin ADMIN LOD Attributes Job Content JPMs Topic and (1-5) U/E/S Explanation K/A I/C Critical Scope Perf.
Cues Overlap Key Minutia Job Link Focus Steps (N/B) Std.
a COO V-NRC-JP-G2.1.43 2 S See attached comments.
14005-ILT23 b COO V-NRC-JP-G2.1.25 2 X X E See attached comments.
19263-ILT23 c EC V-NRC-JP-G2.2.12 2 X X E See attached comments.
14915-ILT23 d Rad V-NRC-JP-NMP-G2.3.12 2 X E See attached comments.
HP-001-ILT23 ES-301 Operating Test Review Worksheet Form ES-301-7
 
Facility: Vogtle 1,2 Exam Date: November 15, 2021 1 2 3 4 5 6 SRO Admin ADMIN LOD Attributes Job Content JPMs Topic and (1-5) U/E/S Explanation K/A I/C Critical Scope Perf.
Cues Overlap Key Minutia Job Link Focus Steps (N/B) Std.
a COO V-NRC-JP-G2.1.43 2 X X U See attached comments.
14005-ILT23 a COO V-NRC-JP-G2.1.2 2 S See attached comments.
14228-ILT23 b COO V-NRC-JP-G2.1.25 2 X X U See attached comments.
19263-ILT23 b COO V-NRC-JP-G2.1.7 2 S See attached comments.
19200-HL23 c EC V-NRC-JP-G2.2.45 2 X X E See attached comments.
14915-ILT23 d Rad V-NRC-JP-NMP-G2.3.14 2 X X E See attached comments.
EP-144-ILT23 e EP V-NRC-JP-NMP-G2.4.41 2 X E See attached comments.
EP-141-ILT23 ES-301 Operating Test Review Worksheet Form ES-301-7


Attributes 4 Simulator/In Safety Job Content Plant Function and LOD U/E/S Explanation JPMs K/A (1-5) I/C Critical Scope Perf.
ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: Vogtle 1,2 Exam Date: November 15, 2021 1
Focus Cues Steps (N/B) Overlap Std. Key Minutia Job Link
2 3
Attributes 4
Job Content 5
6 RO Admin JPMs ADMIN Topic and K/A LOD (1-5)
U/E/S Explanation I/C Cues Critical Scope Overlap Perf.
Key Minutia Job Link Focus Steps (N/B)
Std.
a V-NRC-JP-14005-ILT23 COO G2.1.43 2
S See attached comments.
b V-NRC-JP-19263-ILT23 COO G2.1.25 2
X X
E See attached comments.
c V-NRC-JP-14915-ILT23 EC G2.2.12 2
X X
E See attached comments.
d V-NRC-JP-NMP-HP-001-ILT23 Rad G2.3.12 2
X E
See attached comments.


a SF 1 V-NRC-JP- 001A2.24 2 S See attached comments.
ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: Vogtle 1,2 Exam Date: November 15, 2021 1
14410-ILT23 b SF 3 V-NRC-JP- 011EA1.13 2 S See attached comments.
2 3
19014-ILT23 c SF 4P V-NRC-JP-WE05EA1.11 2 S See attached comments.
Attributes 4
19231-ILT23 d SF 4S V-NRC-JP- 041A4.02 2 S See attached comments.
Job Content 5
13601-ILT23 e SF 5 V-NRC-JP- 028A2.02 2 S See attached comments.
6 SRO Admin JPMs ADMIN Topic and K/A LOD (1-5)
13130-ILT23 f SF 6 V-NRC-JP- 064A4.06 2 S See attached comments.
U/E/S Explanation I/C Cues Critical Scope Overlap Perf.
13427-ILT23 g SF 8 V-NRC-JP- 029A4.01 2 S See attached comments.
Key Minutia Job Link Focus Steps (N/B)
13125-ILT23 h SF 9 V-NRC-JP- 050A2.03 2 S See attached comments.
Std.
13301-ILT23 I SF 2 V-NRC-JP- 006G2.1.30 2 S See attached comments.
a V-NRC-JP-14005-ILT23 COO G2.1.43 2
16900-ILT23 j SF 6 V-NRC-JP- 062A2.18 2 S See attached comments.
X X
13145-ILT23 k SF 8 V-NRC-JP- 068AA1.12 2 S See attached comments.
U See attached comments.
18038-ILT23 ES-301 4 Form ES-301-7
a V-NRC-JP-14228-ILT23 COO G2.1.2 2
S See attached comments.
b V-NRC-JP-19263-ILT23 COO G2.1.25 2
X X
U See attached comments.
b V-NRC-JP-19200-HL23 COO G2.1.7 2
S See attached comments.
c V-NRC-JP-14915-ILT23 EC G2.2.45 2
X X
E See attached comments.
d V-NRC-JP-NMP-EP-144-ILT23 Rad G2.3.14 2
X X
E See attached comments.
e V-NRC-JP-NMP-EP-141-ILT23 EP G2.4.41 2
X E
See attached comments.  


Instructions for Completing This Table:
ES-301 Operating Test Review Worksheet Form ES-301-7 Simulator/In Plant JPMs Safety Function and K/A LOD (1-5)
Attributes 4
Job Content U/E/S Explanation I/C Focus Cues Critical Steps Scope (N/B)
Overlap Perf.
Std.
Key Minutia Job Link a
V-NRC-JP-14410-ILT23 SF 1 001A2.24 2
S See attached comments.
b V-NRC-JP-19014-ILT23 SF 3 011EA1.13 2
S See attached comments.
c V-NRC-JP-19231-ILT23 SF 4P WE05EA1.11 2
S See attached comments.
d V-NRC-JP-13601-ILT23 SF 4S 041A4.02 2
S See attached comments.
e V-NRC-JP-13130-ILT23 SF 5 028A2.02 2
S See attached comments.
f V-NRC-JP-13427-ILT23 SF 6 064A4.06 2
S See attached comments.
g V-NRC-JP-13125-ILT23 SF 8 029A4.01 2
S See attached comments.
h V-NRC-JP-13301-ILT23 SF 9 050A2.03 2
S See attached comments.
I V-NRC-JP-16900-ILT23 SF 2 006G2.1.30 2
S See attached comments.
j V-NRC-JP-13145-ILT23 SF 6 062A2.18 2
S See attached comments.
k V-NRC-JP-18038-ILT23 SF 8 068AA1.12 2
S See attached comments.


ES-301 4
Form ES-301-7 Instructions for Completing This Table:
Check or mark any item(s) requiring a comment and explain the issue in the space provided using the guide below.
Check or mark any item(s) requiring a comment and explain the issue in the space provided using the guide below.
: 1. Check each JPM for appropriate administrative topic requirements (COO, EC, Rad, and EP) or safety function requirements and corresponding K/A. Mark in column 1.
: 1.
Check each JPM for appropriate administrative topic requirements (COO, EC, Rad, and EP) or safety function requirements and corresponding K/A. Mark in column 1.
(ES-301, D.3 and D.4)
(ES-301, D.3 and D.4)
: 2. Determine the level of difficulty (LOD) using an established 1-5 rating scale. Levels 1 and 5 represent an inappropriate (low or high) discriminatory level for the license that is being tested. Mark in column 2 (Appendix D, C.1.f)
: 2.
: 3. In column 3, Attributes, check the appropriate box when an attribute is not met:
Determine the level of difficulty (LOD) using an established 1-5 rating scale. Levels 1 and 5 represent an inappropriate (low or high) discriminatory level for the license that is being tested. Mark in column 2 (Appendix D, C.1.f)
: 3.
In column 3, Attributes, check the appropriate box when an attribute is not met:
The initial conditions and/or initiating cue is clear to ensure the operator understands the task and how to begin. (Appendix C, B.4)
The initial conditions and/or initiating cue is clear to ensure the operator understands the task and how to begin. (Appendix C, B.4)
The JPM contains appropriate cues that clearly indicate when they should be provided to the examinee. Cues are objective and not leading. (Appendix C, D.1)
The JPM contains appropriate cues that clearly indicate when they should be provided to the examinee. Cues are objective and not leading. (Appendix C, D.1)
All critical ste ps (elements) are properly identified.
All critical steps (elements) are properly identified.
The scope of the task is not too narrow (N) or too broad (B).
The scope of the task is not too narrow (N) or too broad (B).
bxcsive ovls occith other parts of t operit orritt exination. (bp -.aI and bp -.O.
Excessive overlap does not occur with other parts of the operating test or written examination. (ES-301, D.1.a, and ES-301, D.2.a)
qkfmcstaclely descrishe expectcome (i.I d st. bach pfmcstep identifitandd fcsf ci ofhe step.
The task performance standard clearly describes the expected outcome (i.e., end state). Each performance step identifies a standard for successful completion of the step.
A valid marked up key was provided (e.g., graph interpretation, initialed steps for handouts).
A valid marked up key was provided (e.g., graph interpretation, initialed steps for handouts).
: 4. For column 4, Job Content, check the appropriate box if the job content flaw does not meet the following elements:
: 4.
For column 4, Job Content, check the appropriate box if the job content flaw does not meet the following elements:
Topics are linked to the job content (e.g., not a disguised task, task required in real job).
Topics are linked to the job content (e.g., not a disguised task, task required in real job).
qmM haseaningf perfmce requirestill ide a legitimate bisvuihict's underst nilityo safy ate tlant. (bp -301I.c)
The JPM has meaningful performance requirements that will provide a legitimate basis for evaluating the applicant's understanding and ability to safely operate the plant. (ES-301, D.2.c)
: 5.
Based on the reviewers judgment, is the JPM as written (U)nacceptable (requiring repair or replacement), in need of (E)nhancement, or (S)atisfactory? Mark the answer in column 5.
: 6.
In column 6, provide a brief description of any (U)nacceptable or (E)nhancement rating from column 5.
Save initial review comments and detail subsequent comment resolution so that each exam-bound JPM is marked by a (S)atisfactory resolution on this form.


Bed evis jumentIshe JmM asritten (r)nacceptable (rriepair epleme)Ifb)centI p)isfty kw in cumn
ES-301 5
Form ES-301-7 Facility: Vogtle 1,2 Scenario: 1 Exam Date: November 15, 2021 Event Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation 1
S See attached comments.
2 X
S See attached comments.
3 S
See attached comments.
4 X
S See attached comments.
5 S
See attached comments.
6 X
S See attached comments.
7 S
See attached comments.
8 X
S See attached comments.
9 E
See attached comments.


fn colum providi scriio yr)ccelb)nhancenting fromolu
ES-301 6
Form ES-301-7 Facility: Vogtle 1,2 Scenario: 2 Exam Date: November 15, 2021 1
2 3
4 5
6 7
8 9
10 Event Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation 1
S See attached comments.
2 S
See attached comments.
3 S
See attached comments.
4 S
See attached comments.
5 X
X S
See attached comments.
6 X
S See attached comments.
7 S
See attached comments.
8 X
S See attached comments.
9 S
See attached comments.
10 S
See attached comments.


pitiiments and dlubsequent cmeithat each exam -boumMsked by a (p)isfty rolithis fm.
ES-301 7
Form ES-301-7 Facility: Scenario: Exam Date: November 15, 2021 1
2 3
4 5
6 7
8 9
10 Event Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation Facility: Vogtle 1,2 Scenario: 3 Exam Date: November 15, 2021 1
2 3
4 5
6 7
8 9
10 Event Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation 1
S See attached comments.
2 X
S See attached comments.
3 X
S See attached comments.
4 S
See attached comments.
5 S
See attached comments.
6 X
S See attached comments.
7 S
See attached comments.
8 S
See attached comments.
9 S
See attached comments.
10 X
S See attached comments.  


ES-301 5 Form ES-301-7
ES-301 8
Form ES-301-7 Facility: Vogtle 1,2 Scenario: 4 Exam Date: November 15, 2021 1
2 3
4 5
6 7
8 9
10 Event Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation 1
S See attached comments.
2 X
E See attached comments.
3 S
See attached comments.
4 S
See attached comments.
5 S
See attached comments.
6 X
S See attached comments.
7 XX E
See attached comments.
8 S
See attached comments.
9 S
See attached comments.
10 S
See attached comments.


Facility: Vogtle 1,2 Scenario: 1 Exam Date: November 15, 2021
ES-301 9
Form ES-301-7 Facility: Scenario: Exam Date: November 15, 2021 1
2 3
4 5
6 7
8 9
10 Event Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation Facility: Vogtle 1,2 Scenario: 5 Exam Date: November 15, 2021 1
2 3
4 5
6 7
8 9
10 Event Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation 1
S See attached comments.
2 X
X S
See attached comments.
3 X
S See attached comments.
4 X
S See attached comments.
5 S
See attached comments.
6 S
See attached comments.
7 S
See attached comments.
8 X
S See attached comments.
9 S
See attached comments.


Event Realism/Cred. Required Verifiable LOD TS CTs Scen. U/E/S Explanation Actions actions Overlap
ES-301 10 Form ES-301-7 Instructions for Completing This Table:
 
1 S See attached comments.
2 X S See attached comments.
3 S See attached comments.
4 X S See attached comments.
5 S See attached comments.
6 X S See attached comments.
7 S See attached comments.
8 X S See attached comments.
9 E See attached comments.
 
ES-301 6 Form ES-301-7
 
Facility: Vogtle 1,2 Scenario: 2 Exam Date: November 15, 2021 1 2 3 4 5 6 7 8 9 10
 
Event Realism/Cred. Required Verifiable LOD TS CTs Scen. U/E/S Explanation Actions actions Overlap
 
1 S See attached comments.
2 S See attached comments.
3 S See attached comments.
4 S See attached comments.
5 X X S See attached comments.
6 X S See attached comments.
7 S See attached comments.
8 X S See attached comments.
9 S See attached comments.
10 S See attached comments.
 
ES-301 7 Form ES-301-7
 
Facility: Facility: Vogtle 1,2 Scenario: Scenario: 3 Exam Date: Exam Date: November 15, 2021 November 15, 2021 11 2 2 3 3 4 4 5 5 6 6 7 7 8 8 9 9 10 10
 
EventEvent Realism/Cred. Realism/Cred. Required Required Verifiable Verifiable LOD LOD TS TS CTs CTs Scen. Scen. U/E/S U/E/S ExplanationExplanation ActionsActions actionsactions Overlap Overlap
 
1 S See attached comments.
2 X S See attached comments.
3 X S See attached comments.
4 S See attached comments.
5 S See attached comments.
6 X S See attached comments.
7 S See attached comments.
8 S See attached comments.
9 S See attached comments.
10 X S See attached comments.
 
ES-301 8 Form ES-301-7
 
Facility: Vogtle 1,2 Scenario: 4 Exam Date: November 15, 2021 1 2 3 4 5 6 7 8 9 10
 
Event Realism/Cred. Required Verifiable LOD TS CTs Scen. U/E/S Explanation Actions actions Overlap
 
1 S See attached comments.
2 X E See attached comments.
3 S See attached comments.
4 S See attached comments.
5 S See attached comments.
 
6 X S See attached comments.
7 XX E See attached comments.
8 S See attached comments.
9 S See attached comments.
10 S See attached comments.
 
ES-301 9 Form ES-301-7
 
Facility: Facility: Vogtle 1,2 Scenario: Scenario: 5 Exam Date: Exam Date: November 15, 2021 November 15, 2021 11 2 2 3 3 4 4 5 5 6 6 7 7 8 8 9 9 10 10
 
EventEvent Realism/Cred. Realism/Cred. Required Required Verifiable Verifiable LOD LOD TS TS CTs CTs Scen. Scen. U/E/S U/E/S ExplanationExplanation ActionsActions actionsactions Overlap Overlap
 
1 S See attached comments.
2 X X S See attached comments.
3 X S See attached comments.
4 X S See attached comments.
5 S See attached comments.
6 S See attached comments.
7 S See attached comments.
8 X S See attached comments.
9 S See attached comments.
 
ES-301 10 Form ES-301-7
 
Instructions for Completing This Table:
Use this table for each scenario for evaluation.
Use this table for each scenario for evaluation.
2 Check this box if the events are not related (e.g., seismic event followed by a pipe rupture) OR if the events do not obey the laws of physics and thermodynamics.
2 Check this box if the events are not related (e.g., seismic event followed by a pipe rupture) OR if the events do not obey the laws of physics and thermodynamics.
3, 4 In columns 3 and 4, check the box if there is no verifiable or required action, as applicable. Examples of required actions are as follows: (ES-301, D.5f)
3, 4 In columns 3 and 4, check the box if there is no verifiable or required action, as applicable. Examples of required actions are as follows: (ES-301, D.5f) opening, closing, and throttling valves starting and stopping equipment raising and lowering level, flow, and pressure making decisions and giving directions acknowledging or verifying key alarms and automatic actions (Uncomplicated events that require no operator action beyond this should not be included on the operating test unless they are necessary to set the stage for subsequent events. (Appendix D, B.3).)
* opening, closing,tlingves
* sttind stnpme
* rsind liel,l, and se
* ming decisis anviirtions
* knowledginifyiey msomic actis( Uomicated es thatequirperctioyond ts shoul not be included on the operating test unless they are necessary to set the stage for subsequent events. (Appendix D, B.3).)
5 Check this box if the level of difficulty is not appropriate.
5 Check this box if the level of difficulty is not appropriate.
6 Check this box if the event has a TS.
6 Check this box if the event has a TS.
Line 391: Line 462:
8 Check this box if the event overlaps with another event on any of the last two NRC examinations. (Appendix D, C.1.f) 9 Based on the reviewers judgment, is the event as written (U)nacceptable (requiring repair or replacement), in need of (E)nhancement, or (S)atisfactory? Mark the answer in column 9.
8 Check this box if the event overlaps with another event on any of the last two NRC examinations. (Appendix D, C.1.f) 9 Based on the reviewers judgment, is the event as written (U)nacceptable (requiring repair or replacement), in need of (E)nhancement, or (S)atisfactory? Mark the answer in column 9.
10 Record any explanations of the events here.
10 Record any explanations of the events here.
In the shaded boxes, sum the number of check marks in each column.
In the shaded boxes, sum the number of check marks in each column.
* In columumhe nb events.
In column 1, sum the number of events.
* In lus 2 d t number of cck mks f eachol
In columns 2-4, record the total number of check marks for each column.
* In colum based evi'sudgement, plcckmk onlyfcis LODs appropri
In column 5, based on the reviewer's judgement, place a checkmark only if the scenario's LOD is not appropriate.
* In column 6, TS are required to be 2 for each scenario. (ES-301, D.5.d)
In column 6, TS are required to be 2 for each scenario. (ES-301, D.5.d)
* In column 7, preidentified CTs should be 2 for each scenario. (Appendix p -.p -301 -
In column 7, preidentified CTs should be 2 for each scenario. (Appendix D; ES-301, D.5.d; ES-301-4)
* In columd tber ofventssed wevisRCnitiiceins. A scenario isonsided unsatisfty ifherisew evts.(ES -.b;ppendi* D, C.1.f)
In column 8, record the number of events not used on the two previous NRC initial licensing exams. A scenario is considered unsatisfactory if there is < 2 new events. (ES-301, D.5.b; Appendix D, C.1.f)
* In columd whher thscio asrittU)nceabled ofE)ancent, orS)isfactyrom cumn 1he simat scenariol
In column 9, record whether the scenario as written (U)nacceptable, in need of (E)nhancement, or (S)atisfactory from column 11 of the simulator scenario table.  
 
ES-301 11 Form ES-301-7
 
Facility: Vogtle 1,2 Exam Date: November 15, 2021 1 2 3 4 5 6 7 8 11 Scenario Event Events TS TS CT CT % Unsat.
Totals Unsat. Total Unsat. Total Unsat. Scenario U/E/S Explanation Elements 1 9 0 2 0 2 0 0 E 2 10 0 2 0 2 0 0 S
 
3 10 0 2 0 2 0 0 S
 
4 10 0 2 0 2 0 0 E
 
5 9 0 3 0 2 0 0 S


Instructions for Completing This Table:
ES-301 11 Form ES-301-7 Facility: Vogtle 1,2 Exam Date: November 15, 2021 Scenario 1
2 3
4 5
6 7
8 11 Event Totals Events Unsat.
TS Total TS Unsat.
CT Total CT Unsat.
% Unsat.
Scenario Elements U/E/S Explanation 1
9 0
2 0
2 0
0 E
2 10 0
2 0
2 0
0 S
3 10 0
2 0
2 0
0 S
4 10 0
2 0
2 0
0 E
5 9
0 3
0 2
0 0
S Instructions for Completing This Table:
Check or mark any item(s) requiring comment and explain the issue in the space provided.
Check or mark any item(s) requiring comment and explain the issue in the space provided.
1, 3, 5 For each simulator scenario, enter the total number of events (column 1), TS entries/actions (column 3), and CTs (column 5).
1, 3, 5 For each simulator scenario, enter the total number of events (column 1), TS entries/actions (column 3), and CTs (column 5).
This number should match the respective scenario from the event-based scenario tables (the sum from columns 1, 6, and 7, respectively).
This number should match the respective scenario from the event-based scenario tables (the sum from columns 1, 6, and 7, respectively).
2, 4, 6 For each simulator scenario, evaluate each event, TS, and CT as (S)atisfactory, (E)nhance, or (U)nsatisfactory based on the following criteria:
2, 4, 6 For each simulator scenario, evaluate each event, TS, and CT as (S)atisfactory, (E)nhance, or (U)nsatisfactory based on the following criteria:
: a. Events. Each event is described on a Form ES-D-2, including all switch manipulations, pertinent alarms, and verifiable actions. Event actions are balanced between at-the -controls and balance-of -plant applicants during the scenario. All event-related attributes on Form ES-301-4 are met. Enter the total number of unsatisfactory events in column2.
: a.
: b. TS. A scenario includes at least two TS entries/actions across at least two different events. TS entries and actions are detailed on Form ES-D -2. Enter the total number of unsatisfactory TS entries/actions in column4. (ES-301, D.5d)
Events. Each event is described on a Form ES-D-2, including all switch manipulations, pertinent alarms, and verifiable actions. Event actions are balanced between at-the-controls and balance-of-plant applicants during the scenario. All event-related attributes on Form ES-301-4 are met. Enter the total number of unsatisfactory events in column 2.
: c. CT. Check that a scenario includes at least two preidentified CTs. This criterion is a target quantitative attribute, not an absolute minimum requirement. Check that each CT is explicitly bounded on Form ES-D -2 with measurable performance standards (see Appendix D). Enter the total number of unsatisfactory CTs in column 6.
: b.
7 In column 7, calculate the percentage of unsatisfactory scenario elements: 2 + 4 + 6 p 100%
TS. A scenario includes at least two TS entries/actions across at least two different events. TS entries and actions are detailed on Form ES-D-2. Enter the total number of unsatisfactory TS entries/actions in column 4. (ES-301, D.5d)
1 + 3 + 5 8 If the value in column 7 is > 20%, mark the scenario as (U)nsatisfactory in column 8. If column 7 is e withb)cent p)isftory.
: c.
9 fnn exain eh unsisfty eIpI and Cq. ti commesasbe add pitiiments and dlubsequent cmeithat each exam -bound scenario isked byp)atisftyion sm.
CT. Check that a scenario includes at least two preidentified CTs. This criterion is a target quantitative attribute, not an absolute minimum requirement. Check that each CT is explicitly bounded on Form ES-D-2 with measurable performance standards (see Appendix D). Enter the total number of unsatisfactory CTs in column 6.
ES-301 12 Form ES-301-7
7 In column 7, calculate the percentage of unsatisfactory scenario elements:
 
8 If the value in column 7 is > 20%, mark the scenario as (U)nsatisfactory in column 8. If column 7 is 20%, annotate with (E)nhancement or (S)atisfactory.
Site name: Vogtle 1,2 Exam Date: November 15, 2021
9 In column 9, explain each unsatisfactory event, TS, and CT. Editorial comments can also be added here.
 
Save initial review comments and detail subsequent comment resolution so that each exam-bound scenario is marked by a (S)atisfactory resolution on this form.
OPERATING TEST TOTALS Total Total Total Total %
2 + 4 + 6 1 + 3 + 5100%  
Unsat. Edits Sat. Unsat. Explanation


ES-301 12 Form ES-301-7 Site name: Vogtle 1,2 Exam Date: November 15, 2021 OPERATING TEST TOTALS Total Total Unsat.
Total Total Unsat.
Explanation Edits Sat.
Admin.
Admin.
JPMs 9 2 6 1 22
JPMs 9
 
2 6
Sim./In-Plant JPMs 11 0 0 11 0
1 22 Sim./In-Plant JPMs 11 0
 
0 11 0
Scenarios 5 0 2 3 0
Scenarios 5
 
0 2
Op. Test Totals: 25 2 8 15 8
3 0
 
Op. Test Totals:
25 2
8 15 8
Instructions for Completing This Table:
Instructions for Completing This Table:
Update data for this table from quality reviews and totals in the previous tables and then calculate the percentage of total items that are unsatisfactory and give an explanation in the space provided.
Update data for this table from quality reviews and totals in the previous tables and then calculate the percentage of total items that are unsatisfactory and give an explanation in the space provided.
: 1. Enter the total number of items submitted for the operating test in the Total column. For example, if nine administrative JPMs were submitted, enter 9 in the Total items column for administrative JPMs.
: 1.
Enter the total number of items submitted for the operating test in the Total column. For example, if nine administrative JPMs were submitted, enter 9 in the Total items column for administrative JPMs.
For scenarios, enter the total number of simulator scenarios.
For scenarios, enter the total number of simulator scenarios.
: 2. Enter the total number of (U)nsatisfactory JPMs and scenarios from the two JPMs column 5 and simulator scenarios column 8 in the previous tables. Provide an explanation in the space provided.
: 2.
: 3. Enter totals for (E)nhancements needed and (S)atisfactory JPMs and scenarios from the previous tables. This task is for tracking only.
Enter the total number of (U)nsatisfactory JPMs and scenarios from the two JPMs column 5 and simulator scenarios column 8 in the previous tables. Provide an explanation in the space provided.
: 4. Total each column and enter the amounts in the Op. Test Totals row.
: 3.
: 5. Calculate the percentage of the operating test that is (U)nsatisfactory (Op. Test Total Unsat.)/(Op. Test Total) and place this value in the bolded % Unsat. cell.
Enter totals for (E)nhancements needed and (S)atisfactory JPMs and scenarios from the previous tables. This task is for tracking only.
 
: 4.
Total each column and enter the amounts in the Op. Test Totals row.
: 5.
Calculate the percentage of the operating test that is (U)nsatisfactory (Op. Test Total Unsat.)/(Op. Test Total) and place this value in the bolded % Unsat. cell.
Refer to ES-501, E.3.a, to rate the overall operating test as follows:
Refer to ES-501, E.3.a, to rate the overall operating test as follows:
* satisfactory, if the Op. Test Total % Unsat. is O0%
* satisfactory, if the Op. Test Total % Unsat. is 20%
* unsatisfactory, if Op. Test Total % Unsat. is > 20%
* unsatisfactory, if Op. Test Total % Unsat. is > 20%
: 6. Update this table and the tables above with post -exam changes if the as -administered operating test required content changes, including the following:
: 6.
Update this table and the tables above with post-exam changes if the as-administered operating test required content changes, including the following:
* The JPM performance standards were incorrect.
* The JPM performance standards were incorrect.
x The administrative JPM tasks/keys were incorrect.
* The administrative JPM tasks/keys were incorrect.
x CTs were incorrect in the scenarios (not including postscenario critical tasks defined in Appendix D).
* CTs were incorrect in the scenarios (not including postscenario critical tasks defined in Appendix D).
x The EOP strategy was incorrect in a scenario(s).
* The EOP strategy was incorrect in a scenario(s).
x TS entries/actions were determined to be incorrect in a scenario(s).
* TS entries/actions were determined to be incorrect in a scenario(s).  


ES-301 13 Form ES-301-7
ES-301 13 Form ES-301-7 Vogtle 1,2 2021-301 NRC Exam Operating Test Review Comments A) RO Admin JPMs a) RO Admin JPM a i) JPM is Satisfactory. Will validate with an operator during on-site validation.
 
Vogtle 1,2 2021-301 NRC Exam Operating Test Review Comments A) RO Admin JPMs a) RO Admin JPM a i) JPM is Satisfactory. Will validate with an operator during on-site validation.
b) RO Admin JPM b i) The concept of the JPM is good. The body of the JPM is constructed so that there is only one critical step containing the final answer. The JPM needs to be constructed to follow the steps of attachment 3. You could make a note in the body of the JPM that the highlighted portions of the key are critical steps. Each intermediate calculation is a critical step needed to arrive at the final answer. This will prevent an applicant from getting the correct answer for the wrong reason. The key is good. Will validate with an operator during on-site validation.
b) RO Admin JPM b i) The concept of the JPM is good. The body of the JPM is constructed so that there is only one critical step containing the final answer. The JPM needs to be constructed to follow the steps of attachment 3. You could make a note in the body of the JPM that the highlighted portions of the key are critical steps. Each intermediate calculation is a critical step needed to arrive at the final answer. This will prevent an applicant from getting the correct answer for the wrong reason. The key is good. Will validate with an operator during on-site validation.
ii) 10/28/2021 - Licensee made corrections to address the concerns as stated above. The JPM is now Satisfactory.
ii) 10/28/2021 - Licensee made corrections to address the concerns as stated above. The JPM is now Satisfactory.
c) RO admin JPM c i) Same comment as listed above for RO Admin JPM b. Will validate with an operator during on -site validation.
c) RO admin JPM c i) Same comment as listed above for RO Admin JPM b. Will validate with an operator during on-site validation.
ii) 10/28/2021 - Licensee made corrections to address the concerns as stated above. The JPM is now Satisfactory.
ii) 10/28/2021 - Licensee made corrections to address the concerns as stated above. The JPM is now Satisfactory.
d) RO admin JPM d i) Need to put varied radiation levels for the other rooms/compartments on the map for each level.
d) RO admin JPM d i) Need to put varied radiation levels for the other rooms/compartments on the map for each level.
Otherwise, this is just a simple high school math problem. Will validate with an operator during on-site validation.
Otherwise, this is just a simple high school math problem. Will validate with an operator during on-site validation.
ii) 10/28/2021 - Licensee made corrections to address the concerns as stated above. The JPM is now Satisfactory.
ii) 10/28/2021 - Licensee made corrections to address the concerns as stated above. The JPM is now Satisfactory.
B) SRO Admin JPMs a) SRO Admin JPM a i) Simply reviewing a task that an RO performed and identifying an error does not meet the requirements for an SRO Admin JPM. The skill set required to perform this task is no different than the skill set used on RO Admin JPM a. Performing the calculat ion/review and then identifying the appropriate technical specification entry, procedure to direct, etc. would turn this type of JPM into an SRO Admin JPM. SRO Admin JPMs should test knowledge/skills above that required for an RO.
B) SRO Admin JPMs a) SRO Admin JPM a i) Simply reviewing a task that an RO performed and identifying an error does not meet the requirements for an SRO Admin JPM. The skill set required to perform this task is no different than the skill set used on RO Admin JPM a. Performing the calculation/review and then identifying the appropriate technical specification entry, procedure to direct, etc. would turn this type of JPM into an SRO Admin JPM. SRO Admin JPMs should test knowledge/skills above that required for an RO.
ii) 10/28/2021 - Licensee submitted a different conduct of operations JPM that tests an SRO Technical Specification evaluation. This JPM is Satisfactory.
ii) 10/28/2021 - Licensee submitted a different conduct of operations JPM that tests an SRO Technical Specification evaluation. This JPM is Satisfactory.
b) SRO Admin JPM b i) Other that giving the SRO applicants the step number to compare parameters given in the initial condition, this JPM does not require any SRO knowledge above that of an RO. The SRO would read step 20 to the ROs and they would be the ones to get the information. This is not an SRO level Administrative JPM.
b) SRO Admin JPM b i) Other that giving the SRO applicants the step number to compare parameters given in the initial condition, this JPM does not require any SRO knowledge above that of an RO. The SRO would read step 20 to the ROs and they would be the ones to get the information. This is not an SRO level Administrative JPM.
ii) 10/28/2021 - Licensee submitted a different JPM that tests SRO procedure direction. The JPM is Satisfactory.
ii) 10/28/2021 - Licensee submitted a different JPM that tests SRO procedure direction. The JPM is Satisfactory.
c) SRO Admin JPM c i) See comments above for RO JPMs a and b concerning intermediate critical steps. Will validate with an operator during on-site validation.
c) SRO Admin JPM c i) See comments above for RO JPMs a and b concerning intermediate critical steps. Will validate with an operator during on-site validation.
ii) 10/28/2021 - Licensee made corrections to address the concerns as stated above. The JPM is now Satisfactory.
ii) 10/28/2021 - Licensee made corrections to address the concerns as stated above. The JPM is now Satisfactory.  
 
ES-301 14 Form ES-301-7


d) SRO Admin JPM d i) Do not need to tell the applicant the reference to use when approving the dose extensions in the initiating cue. Would somebody tell them that when they are the Emergency Director? It is on the form they are looking at anyway. Will validate with an operator during on-site validation.
ES-301 14 Form ES-301-7 d) SRO Admin JPM d i) Do not need to tell the applicant the reference to use when approving the dose extensions in the initiating cue. Would somebody tell them that when they are the Emergency Director? It is on the form they are looking at anyway. Will validate with an operator during on-site validation.
ii) 10/28/2021 - Licensee made corrections to address the concerns as stated above. The JPM is now Satisfactory.
ii) 10/28/2021 - Licensee made corrections to address the concerns as stated above. The JPM is now Satisfactory.
e) SRO Admin JPM e i) Need to add something to the cue stating something to the effect that Emergency Directors Judgement should not be used for the classification.
e) SRO Admin JPM e i) Need to add something to the cue stating something to the effect that Emergency Directors Judgement should not be used for the classification.
Line 483: Line 576:
C) Simulator/In-Plant JPMs a) Simulator JPM a i) JPM is Satisfactory. Will validate with an operator during on-site validation.
C) Simulator/In-Plant JPMs a) Simulator JPM a i) JPM is Satisfactory. Will validate with an operator during on-site validation.
b) Simulator JPM b i) JPM is Satisfactory. Will validate with an operator during on-site validation.
b) Simulator JPM b i) JPM is Satisfactory. Will validate with an operator during on-site validation.
c) Simulator JPM c i) JPM is Satisfactory. Will validate with an operator during on -site validation.
c) Simulator JPM c i) JPM is Satisfactory. Will validate with an operator during on-site validation.
d) Simulator JPM d i) JPM is Satisfactory. Will validate with an operator during on-site validation.
d) Simulator JPM d i) JPM is Satisfactory. Will validate with an operator during on-site validation.
e) Simulator JPM e i) JPM is Satisfactory. Will validate with an operator during on-site validation.
e) Simulator JPM e i) JPM is Satisfactory. Will validate with an operator during on-site validation.
Line 497: Line 590:
b) Scenario #2 i) No concerns identified during in-office review. Will validate with operators during on-site validation.
b) Scenario #2 i) No concerns identified during in-office review. Will validate with operators during on-site validation.
ii) 10/28/2021 - Due to reduction in number of applicants, Scenario #2 is not needed for this operating test.
ii) 10/28/2021 - Due to reduction in number of applicants, Scenario #2 is not needed for this operating test.
c) Scenario #3 i) No concerns identified during in-office review. Will validate with operators during on-site validation.
c) Scenario #3 i) No concerns identified during in-office review. Will validate with operators during on-site validation.  
 
ES-301 15 Form ES-301-7


d) Scenario #4 i) Event 2 - Does not really have verifiable actions for the OATC as is stated on the event description on the ES-D-1. None are needed because credit is only being given to the SS for the TS call.
ES-301 15 Form ES-301-7 d) Scenario #4 i) Event 2 - Does not really have verifiable actions for the OATC as is stated on the event description on the ES-D-1. None are needed because credit is only being given to the SS for the TS call.
ii) Event 7 - Need to discuss if tripping reactor coolant pumps is really a critical task for this scenario. Is the scenario set up where RCS inventory will be less than the critical inventory during the run time of the scenario?
ii) Event 7 - Need to discuss if tripping reactor coolant pumps is really a critical task for this scenario. Is the scenario set up where RCS inventory will be less than the critical inventory during the run time of the scenario?
iii) Will validate with operators during on-site validation.
iii) Will validate with operators during on-site validation.
iv) 10/28/2021 - Licensee submitted correction to verifiable action statement. Licensee verified that tripping RCPs is a critical task based on Westinghouse Owners group criteria. Event 3 was changed to a heater drain pump trip due to some similar symptoms/actions between the ACCW pump trip which was previously in the scenario and Event 4. This scenario is now Satisfactory. Scenario #4 has been designated as the spare scenario and will only be run if necessary.
iv) 10/28/2021 - Licensee submitted correction to verifiable action statement. Licensee verified that tripping RCPs is a critical task based on Westinghouse Owners group criteria. Event 3 was changed to a heater drain pump trip due to some similar symptoms/actions between the ACCW pump trip which was previously in the scenario and Event 4. This scenario is now Satisfactory. Scenario #4 has been designated as the spare scenario and will only be run if necessary.
e) Scenario #5 i) No concerns identified during in-office review. Will validate with operators during on-site validation.
e) Scenario #5 i) No concerns identified during in-office review. Will validate with operators during on-site validation.  
 
ES-401 PWR Examination Outline Form ES-401-2
 
Facility: Vogtle Units 1 & 2 Date of Exam: November 15, 2021 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total
: 1. 1 3 3 3 3 3 3 18 3 3 6 Emergency and 2 1 1 1 2 2 2 9 2 2 4 Abnormal Plant N/A N/A Evolutions Tier Totals 4 4 4 5 5 5 27 5 5 10
 
1 3 3 3 3 3 3 2 2 2 2 2 28 2 3 5 2.
Plant 2 1 1 1 1 1 1 1 1 1 1 0 10 2 1 3 Systems Tier Totals 4 4 4 4 4 4 3 3 3 3 2 38 8
: 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 1 3 2 2 1 2
 
Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)
: 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points, and the SRO-only exam must total 25 points.
: 3. Systems/evolutions within each group are identified on the outline. Systems or evolutions that do not apply at the facility should be deleted with justification. Operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
: 4. Select topics from as many systems and evolutions as possible. Sample every system or evolution in the group before selecting a second topic for any system or evolution.
: 5. Absent a plant -specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO -only portions, respectively.
: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
: 7. The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
: 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics IRs for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. If fuel -h andling equipment is sampled in a category other than Category A2 or G* on the SRO -only exam, enter it on the left side of Column A2 for Tier 2, Group 2. (Note 1 does not apply). Use duplicate pages for RO and SRO -only exams.
: 9. For Tier 3, select topics from Section 2 of the K/A catalog and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES -401 -3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
 
G* Generic K/As
* These systems/evolutions must be included as part of t he sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.
** These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.
 
ES-401 2 Form ES-401-2
 
ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions Tier 1/Group 1 (RO/SRO)
 
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #
000007 (EPE 7; BW E02&E10; CE E02) X EA1.05: Ability to operate and/or monitor NIs as 3.9 1 Reactor Trip, Stabilization, Recovery / 1 they apply to a Reactor Trip -
 
000008 (APE 8) Pressurizer Vapor Space X AA2.06: Ability to determine and/or interpret the 3.0 2 Accident / 3 following as they apply to a Pressurizer Vapor Space Accident - PORV logic control under low -
pressure conditions
 
000009 (EPE 9) Small Break LOCA / 3 X G2.2.22: Knowledge of limiting conditions for 4.0 3 operation and safety limits
 
000011 (EPE 11) Large Break LOCA / 3 X EK1.03: Knowledge of the operational implications 4.14 and/or cause and effect relationships of the following as they apply to a Large-Break LOCA -
Long-term containment of radioactivity X G2.4.30 Knowledge of events related to system 4.1 76 operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator
 
000015 (APE 15) Reactor Coolant Pump X AA2.01: Ability to determine and/or interpret the 3.5 77 Malfunctions / 4 following as they apply to Reactor Coolant Pump Malfunctions: Cause of RCP failure
 
000022 (APE 22) Loss of Reactor Coolant X AK2.10: Knowledge of the relationship between 3.8 5 Makeup / 2 Loss of Reactor Coolant Makeup and the following systems or components: PZR LCS 000025 (APE 25) Loss of Residual Heat X G2.1.32: Ability to explain and apply system 4.0 78 Removal System / 4 precautions, limitations, notes, or cautions 000026 (APE 26) Loss of Component X AK3.02: Knowledge of the reasons for the following 3.9 6 Cooling Water / 8 responses and/or actions as they apply to Loss of Component Cooling Water - The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS 000027 (APE 27) Pressurizer Pressure X AA1.06: Ability to operate and/or monitor 3.6 7 Control System Malfunction / 3 Operable control channels with a Pressurizer Pressure Control System Malfunction
 
000029 (EPE 29) Anticipated Transient X EA2.13: Ability to determine and/or interpret the 3.9 8 Without Scram / 1 following as they apply to an Anticipated Transient Without Scram: RCS cooldown or heatup
 
000038 (EPE 38) Steam Generator Tube X G2.4.50: Ability to verify system alarm setpoints and 4.2 9 Rupture / 3 operate controls identified in the alarm response procedure
 
000040 (APE 40; BW E05; CE E05; W E12) X AA2.01: Ability to determine and/or interpret the 4.0 79 Steam Line Rupture Excessive Heat following as they apply to a Steamline Rupture; Transfer / 4 Occurrence and location of a steamline rupture from pressure and flow indications
 
000054 (APE 54; CE E06) Loss of Main X AK1.02: Cause and effect relationships of 4.0 10 Feedwater /4 feedwater introduction on a dry S/G (Loss of Main Feedwater) 000055 (EPE 55) Station Blackout / 6 X EK2.04: Knowledge of the relationship between a 4.2 11 Station Blackout and the following systems or components; AFW system ES-401 3 Form ES-401-2
 
000056 (APE 56) Loss of Offsite Power / 6 X AK3.01: Knowledge of the reasons for the following 3.6 12 responses and/or actions as they apply to Loss of Offsite Power; Order and time to initiation of power for the load sequencer
 
000057 (APE 57) Loss of Vital AC X AA1.04: Ability to operate and/or monitor the 3.8 13 Instrument Bus / 6 following as they apply to Loss of Vital AC Electrical Instrument Bus; RWST and VCT valves
 
000058 (APE 58) Loss of DC Power / 6 X G2.2.40 : Ability to apply TS with action statements 4.7 80 of less than or equal to 1 hour


000062 (APE 62) Loss of Nuclear Service X AA2.05: Ability to determine and/or interpret the 3.0 81 Water / 4 following as they apply to Loss of Service Water; The normal values for the SWS -header flow rate and the flow rates to the components cooled by the SWS
ES-401 PWR Examination Outline Form ES-401-2 Facility: Vogtle Units 1 & 2 Date of Exam: November 15, 2021 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
Total A2 G*
Total
: 1.
Emergency and Abnormal Plant Evolutions 1
3 3
3 N/A 3
3 N/A 3
18 3
3 6
2 1
1 1
2 2
2 9
2 2
4 Tier Totals 4
4 4
5 5
5 27 5
5 10
: 2.
Plant Systems 1
3 3
3 3
3 3
2 2
2 2
2 28 2
3 5
2 1
1 1
1 1
1 1
1 1
1 0
10 2
1 3
Tier Totals 4
4 4
4 4
4 3
3 3
3 2
38 8
: 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
3 3
1 3
2 2
1 2
Note: 1.
Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)
: 2.
The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points, and the SRO-only exam must total 25 points.
: 3.
Systems/evolutions within each group are identified on the outline. Systems or evolutions that do not apply at the facility should be deleted with justification. Operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
: 4.
Select topics from as many systems and evolutions as possible. Sample every system or evolution in the group before selecting a second topic for any system or evolution.
: 5.
Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
: 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
: 7.
The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
: 8.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics IRs for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. If fuel-handling equipment is sampled in a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2. (Note 1 does not apply). Use duplicate pages for RO and SRO-only exams.
: 9.
For Tier 3, select topics from Section 2 of the K/A catalog and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
G* Generic K/As These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.
These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.


000065 (APE 65) Loss of Instrument Air / 8 X AA2.03: Ability to determine and/or interpret the 4.0 14 following as they apply to Loss of Instrument Air; Location and isolation of leaks
ES-401 2
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 000007 (EPE 7; BW E02&E10; CE E02)
Reactor Trip, Stabilization, Recovery / 1 X
EA1.05: Ability to operate and/or monitor NIs as they apply to a Reactor Trip -
3.9 1
000008 (APE 8) Pressurizer Vapor Space Accident / 3 X
AA2.06: Ability to determine and/or interpret the following as they apply to a Pressurizer Vapor Space Accident - PORV logic control under low-pressure conditions 3.0 2
000009 (EPE 9) Small Break LOCA / 3 X
G2.2.22: Knowledge of limiting conditions for operation and safety limits 4.0 3
000011 (EPE 11) Large Break LOCA / 3 X
X EK1.03: Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to a Large-Break LOCA -
Long-term containment of radioactivity G2.4.30 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator 4.1 4.1 4
76 000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 X
AA2.01: Ability to determine and/or interpret the following as they apply to Reactor Coolant Pump Malfunctions: Cause of RCP failure 3.5 77 000022 (APE 22) Loss of Reactor Coolant Makeup / 2 X
AK2.10: Knowledge of the relationship between Loss of Reactor Coolant Makeup and the following systems or components: PZR LCS 3.8 5
000025 (APE 25) Loss of Residual Heat Removal System / 4 X
G2.1.32: Ability to explain and apply system precautions, limitations, notes, or cautions 4.0 78 000026 (APE 26) Loss of Component Cooling Water / 8 X
AK3.02: Knowledge of the reasons for the following responses and/or actions as they apply to Loss of Component Cooling Water - The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS 3.9 6
000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 X
AA1.06: Ability to operate and/or monitor Operable control channels with a Pressurizer Pressure Control System Malfunction 3.6 7
000029 (EPE 29) Anticipated Transient Without Scram / 1 X
EA2.13: Ability to determine and/or interpret the following as they apply to an Anticipated Transient Without Scram: RCS cooldown or heatup 3.9 8
000038 (EPE 38) Steam Generator Tube Rupture / 3 X
G2.4.50: Ability to verify system alarm setpoints and operate controls identified in the alarm response procedure 4.2 9
000040 (APE 40; BW E05; CE E05; W E12)
Steam Line RuptureExcessive Heat Transfer / 4 X
AA2.01: Ability to determine and/or interpret the following as they apply to a Steamline Rupture; Occurrence and location of a steamline rupture from pressure and flow indications 4.0 79 000054 (APE 54; CE E06) Loss of Main Feedwater /4 X
AK1.02: Cause and effect relationships of feedwater introduction on a dry S/G (Loss of Main Feedwater) 4.0 10 000055 (EPE 55) Station Blackout / 6 X
EK2.04: Knowledge of the relationship between a Station Blackout and the following systems or components; AFW system 4.2 11


000077 (APE 77) Generator Voltage and X G2.4.49: Ability to perform without reference to 4.6 15 Electric Grid Disturbances / 6 procedures those actions that require immediate operation of system components and controls
ES-401 3
Form ES-401-2 000056 (APE 56) Loss of Offsite Power / 6 X
AK3.01: Knowledge of the reasons for the following responses and/or actions as they apply to Loss of Offsite Power; Order and time to initiation of power for the load sequencer 3.6 12 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 X
AA1.04: Ability to operate and/or monitor the following as they apply to Loss of Vital AC Electrical Instrument Bus; RWST and VCT valves 3.8 13 000058 (APE 58) Loss of DC Power / 6 X
G2.2.40: Ability to apply TS with action statements of less than or equal to 1 hour 4.7 80 000062 (APE 62) Loss of Nuclear Service Water / 4 X
AA2.05: Ability to determine and/or interpret the following as they apply to Loss of Service Water; The normal values for the SWS-header flow rate and the flow rates to the components cooled by the SWS 3.0 81 000065 (APE 65) Loss of Instrument Air / 8 X
AA2.03: Ability to determine and/or interpret the following as they apply to Loss of Instrument Air; Location and isolation of leaks 4.0 14 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 X
G2.4.49: Ability to perform without reference to procedures those actions that require immediate operation of system components and controls 4.6 15 (W E04) LOCA Outside Containment / 3 X
EK1.05: Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to LOCA Outside Containment; Leakage accumulation in RHR pump area 3.6 16 (W E11) Loss of Emergency Coolant Recirculation / 4 X
EK2.04: Knowledge of the relationship between Loss of Emergency Coolant Recirculation and the following systems or components; Incore Temperature Monitoring (ITM) 3.8 17 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 X
EK3.16: Knowledge of the reasons for the following responses and/or actions as they apply to Loss of Secondary Heat Sink: Establishing maximum charging flow 3.5 18 K/A Category Totals:
3 3
3 3
3/3 3/3 Group Point Total:
18/6


(W E04) LOCA Outside Containment / 3 X EK1.05: Knowledge of the operational implications 3.6 16 and/or cause and effect relationships of the following as they apply to LOCA Outside Containment; Leakage accumulation in RHR pump area (W E11) Loss of Emergency Coolant X EK2.04: Knowledge of the relationship between 3.8 17 Recirculation / 4 Loss of Emergency Coolant Recirculation and the following systems or components; Incore Temperature Monitoring (ITM)
ES-401 4
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 000001 (APE 1) Continuous Rod Withdrawal / 1 NA NA 000003 (APE 3) Dropped Control Rod / 1 X
2.4.29: Knowledge of the emergency plan implementing procedures 4.4 82 000005 (APE 5) Inoperable/Stuck Control Rod / 1 X
AA1.05: Ability to operate and/or monitor the following as they apply to an Inoperable/Stuck Control Rod; RPI 3.8 19 000024 (APE 24) Emergency Boration / 1 NA NA 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 X
AA2.03: Ability to determine and/or interpret the following as they apply to a Pressurizer Level Control Malfunction; Charging flow 3.4 20 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 X
G2.4.2: Knowledge of system setpoints, interlocks, and automatic actions associated with emergency and abnormal operating procedure entry conditions 4.5 21 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 X
AK1.01: Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to Loss of Intermediate Range Nuclear Instrumentation; Effects of voltage changes on performance 2.9 22 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 X
AA2.05: Ability to determine and/or interpret the following as they apply to Fuel Handling Incidents: Containment isolation/closure 3.8 83 000037 (APE 37) Steam Generator Tube Leak / 3 NA NA 000051 (APE 51) Loss of Condenser Vacuum / 4 X
AK2.10: Knowledge of the relationship between Loss of Condenser Vacuum and the following systems or components:
Main turbine system 3.3 23 000059 (APE 59) Accidental Liquid Radwaste Release / 9 X
G2.4.30: Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator 4.1 84 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 NA NA 000061 (APE 61) Area Radiation Monitoring System Alarms
/ 7 NA NA 000067 (APE 67) Plant Fire On Site / 8 X
AK3.02: Knowledge of the reasons for the following responses and/or actions as they apply to Plant Fire on Site; Steps called out in the site fire protection plan, FPS manual, and fire zone manual 3.3 24 000068 (APE 68; BW A06) Control Room Evacuation / 8 NA NA


(BW E04; W E05) Inadequate Heat X EK3.16: Knowledge of the reasons for the following 3.5 18 Transfer Loss of Secondary Heat Sink / 4 responses and/or actions as they apply to Loss of Secondary Heat Sink: Establishing maximum charging flow
ES-401 5
Form ES-401-2 000069 (APE 69; W E14) Loss of Containment Integrity / 5 X
AA1.03: Ability to operate and/or monitor the following as they apply to a Loss of Containment Integrity; Fluid systems penetrating containment 3.5 25 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling /
4 NA NA 000076 (APE 76) High Reactor Coolant Activity / 9 X
AA2.04: Ability to determine and/or interpret the following as they apply to High Reactor Coolant Activity; High process radiation levels 3.2 26 000078 (APE 78*) RCS Leak / 3 X
G2.4.18: Knowledge of the specific bases for emergency and abnormal operating procedures 3.3 27 (W E01 & E02) Rediagnosis & SI Termination / 3 NA NA (W E13) Steam Generator Overpressure / 4 X
EA2.04: Ability to determine and /
or interpret the following as they apply to Steam Generator Overpressure; Feedwater isolation 3.7 85 (W E15) Containment Flooding / 5 NA NA (W E16) High Containment Radiation /9 NA NA K/A Category Point Totals:
1 1
1 2
2/2 2/2 Group Point Total:
9/4


K/A Category Totals: 3 3 3 3 3/3 3/3 Group Point Total: 18/6
ES-401 6
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)
System # / Name K
1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 003 (SF4P RCP) Reactor Coolant Pump X
K1.10: Knowledge of the physical connections and/or cause and effect relationships between the Reactor Coolant Pump System and the following systems; RCS 3.9 28 004 (SF1; SF2 CVCS) Chemical and Volume Control X
X K2.02: Knowledge of electrical power supplies to the following: Pumps used to makeup to CVCS G2.2.37: Ability to determine operability or availability of safety-related equipment 3.0 4.6 29 86 005 (SF4P RHR) Residual Heat Removal X
X K3.02: Knowledge of the effect that a loss or malfunction of the Residual Heat Removal System will have on the following systems or system parameters; RCPS A2.05: Ability to (a) predict the impacts of the following on the Residual Heat Removal System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations; RHR heat exchanger malfunction 2.9 3.5 30 87 006 (SF2; SF3 ECCS) Emergency Core Cooling X
K4.13: Reset of containment isolation 3.7 31 007 (SF5 PRTS) Pressurizer Relief/Quench Tank X
K5.07: PZR safety tailpipe temperature variations with PRT/quench tank pressure 3.7 32 008 (SF8 CCW) Component Cooling Water X
X K6.09: SWS K1.14: RCPS 3.8 4.0 33 34 010 (SF3 PZR PCS) Pressurizer Pressure Control X
A1.09: Tail pipe temperature and acoustic monitors 3.6 35 012 (SF7 RPS) Reactor Protection X
A2.01: Ability to (a) predict the impacts of the following on the Reactor Protection System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations:
Faulty bistable operation 3.8 36 013 (SF2 ESFAS) Engineered Safety Features Actuation X
A3.11: Ability to monitor automatic operation of the Engineered Safety Features Actuation System, including; Safeguards equipment control 3.9 37 022 (SF5 CCS) Containment Cooling X
X A4.01: Ability to manually operate and/or monitor in the control room; CCS fans K4.04: Knowledge of Containment Cooling System design features and/or interlocks that provide for the following; Cooling of CRDMs 3.7 3.1 38 39 025 (SF5 ICE) Ice Condenser NA NA


ES-401 4 Form ES-401-2
ES-401 7
Form ES-401-2 026 (SF5 CSS) Containment Spray X G2.1.27: Knowledge of system purpose and/or function 3.9 40 039 (SF4S MSS) Main and Reheat Steam X
X K1.08: Knowledge of the physical connections and/or cause and effect relationships between the Main and Reheat Steam System and the following systems: MFW K6.11: SDS 3.6 3.4 41 42 059 (SF4S MFW) Main Feedwater X
K3.01: Knowledge of the effect that a loss or malfunction of the Main Feedwater System will have on the following systems or system parameters; CDS 3.2 43 061 (SF4S AFW)
Auxiliary/Emergency Feedwater X
K3.02: Knowledge of the effect that a loss or malfunction of the Auxiliary/Emergency Feedwater System will have on the following systems or system parameters; S/G system 4.3 44 062 (SF6 ED AC) AC Electrical Distribution X
K4.02: Knowledge of AC Electrical Distribution System design features and/or interlocks that provide for the following; Circuit breaker automatic trips 3.6 45 063 (SF6 ED DC) DC Electrical Distribution X
X K5.04: Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the DC Electrical Distribution System; System ground G 2.2.25: Knowledge of the bases in TS for limiting conditions for operation and safety limits (SRO Only) 2.9 4.2 46 88 064 (SF6 EDG) Emergency Diesel Generator X
X K6.09: Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the Emergency Diesel Generators; EDG building ventilation K5.06: Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the Emergency Diesel Generators; Unloading before securing an EDG 3.2 3.5 47 48 073 (SF7 PRM) Process Radiation Monitoring X
A1.01: Ability to predict and/or monitor changes in parameters associated with operation of the Process Radiation Monitoring System, including; Radiation levels 3.5 49 076 (SF4S SW) Service Water X
X A2.05: Ability to (a) predict the impacts of the following on the Service Water System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations; Sensor and detector failure K2.09: Knowledge of electrical power supplies to the following; Intake screens 2.6 2.6 50 51 078 (SF8 IAS) Instrument Air X
X A3.05: Ability to monitor automatic features of the Instrument Air System, including; Isolation of instrument air to containment K2.01; Knowledge of electrical power supplies to the following; Instrument air compressor 3.3 3.3 52 53


ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions Tier 1/Group 2 (RO/SRO)
ES-401 8
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #
Form ES-401-2 103 (SF5 CNT) Containment X
000001 (APE 1) Continuous Rod Withdrawal / 1 NA NA 000003 (APE 3) Dropped Control Rod / 1 X 2.4.29: Knowledge of the 4.4 82 emergency plan implementing procedures 000005 (APE 5) Inoperable/Stuck Control Rod / 1 X AA1.05: Ability to operate and/or 3.8 19 monitor the following as they apply to an Inoperable/Stuck Control Rod; RPI 000024 (APE 24) Emergency Boration / 1 NA NA 000028 (APE 28) Pressurizer (PZR) Level Control X AA2.03: Ability to determine 3.4 20 Malfunction / 2 and/or interpret the following as they apply to a Pressurizer Level Control Malfunction; Charging flow 000032 (APE 32) Loss of Source Range Nuclear X G2.4.2: Knowledge of system 4.5 21 Instrumentation / 7 setpoints, interlocks, and automatic actions associated with emergency and abnormal operating procedure entry conditions 000033 (APE 33) Loss of Intermediate Range Nuclear X AK1.01 : Knowledge of the 2.9 22 Instrumentation / 7 operational implications and/or cause and effect relationships of the following as they apply to Loss of Intermediate Range Nuclear Instrumentation ; Effects of voltage changes on performance 000036 (APE 36; BW/A08) Fuel - Handling Incidents / 8 X AA2.05 : Ability to determine 3.8 83 and/or interpret the following as they apply to Fuel Handling Incidents: Containment isolation/closure 000037 (APE 37) Steam Generator Tube Leak / 3 NA NA 000051 (APE 51) Loss of Condenser Vacuum / 4 X AK2.10 : Knowledge of the 3.3 23 relationship between Loss of Condenser Vacuum and the following systems or components:
X G2.2.3: Knowledge of the design, procedural, and/or operational differences between units A2.10: FHS malfunctions 3.8 2.9 54 89 053 (SF1; SF4P ICS*) Integrated Control (IPC)
Main turbine system 000059 (APE 59) Accidental Liquid Radwaste Release / 9 X G2.4.30 : Knowledge of events 4. 1 84 related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 NA NA 000061 (APE 61) Area Radiation Monitoring System Alarms NA NA
X X
/ 7 000067 (APE 67) Plant Fire On Site / 8 X AK3.02 : Knowledge of the 3.3 24 reasons for the following responses and/or actions as they apply to Plant Fire on Site; Steps called out in the site fire protection plan, FPS manual, and fire zone manual 000068 (APE 68; BW A06) Control Room Evacuation / 8 NA NA ES-401 5 Form ES-401-2
A4.03; Ability to manually operate and/or monitor in the control room; S/G and/or reactor demand G2.1.30: Ability to locate and operate components, including local controls 3.9 4.0 55 90 K/A Category Point Totals:
3 3 3
3 3
3 2
2/
2 2
2 2/
3 Group Point Total:
28/5 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO/SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 001 (SF1 CRDS) Control Rod Drive X K1.12: Knowledge of the physical connections and/or cause and effect relationships between the Control Rod Drive System and the following system; RPIS 3.8 56 002 (SF2; SF4P RCS) Reactor Coolant X
K3.03: Knowledge of the effect that a loss or malfunction of the Reactor Coolant System will have on the following systems or system parameters: CNT 4.0 57 011 (SF2 PZR LCS) Pressurizer Level Control NA NA 014 (SF1 RPI) Rod Position Indication NA NA 015 (SF7 NI) Nuclear Instrumentation X
A2.04: Ability to use procedures to correct, control, or mitigate the consequences of those abnormal operations: Effects on axial flux density of control rod alignment and sequencing, xenon production and decay, and boron versus control rod reactivity changes 3.7 91 016 (SF7 NNI) Nonnuclear Instrumentation X
K2.03: Knowledge of electrical power supplies to the following; Primary system control circuits 3.4 58 017 (SF7 ITM) In-Core Temperature Monitor NA NA 027 (SF5 CIRS) Containment Iodine Removal X
K5.01: Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the Containment Iodine Removal System:
Purpose of charcoal filters 2.9 59 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control X
K4.02: Knowledge of Hydrogen Recombiner and Purge Control System design features and/or interlocks that provide for the following; Containment hydrogen concentration monitoring 2.8 60


000069 (APE 69; W E14) Loss of Containment Integrity / 5 X AA1.03: Ability to operate and/or 3.5 25 monitor the following as they apply to a Loss of Containment Integrity; Fluid systems penetrating containment 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling / NA NA 4
ES-401 9
000076 (APE 76) High Reactor Coolant Activity / 9 X AA2.04: Ability to determine 3.2 26 and/or interpret the following as they apply to High Reactor Coolant Activity; High process radiation levels 000078 (APE 78*) RCS Leak / 3 X G2.4.18: Knowledge of the 3.3 27 specific bases for emergency and abnormal operating procedures (W E01 & E02) Rediagnosis & SI Termination / 3 NA NA (W E13) Steam Generator Overpressure / 4 X EA2.04: Ability to determine and / 3.7 85 or interpret the following as they apply to Steam Generator Overpressure; Feedwater isolation (W E15) Containment Flooding / 5 NA NA (W E16) High Containment Radiation /9 NA NA K/A Category Point Totals: 1 1 1 2 2/2 2/2 Group Point Total: 9/4
Form ES-401-2 029 (SF8 CPS) Containment Purge X
K6.10: Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the Containment Purge System; Containment air cleanup and recirculation system 2.6 61 033 (SF8 SFPCS) Spent Fuel Pool Cooling NA NA 034 (SF8 FHS) Fuel-Handling Equipment NA NA 035 (SF 4P SG) Steam Generator X
G2.1.19: Ability to use available indications to evaluate system or component status 92 041 (SF4S SDS) Steam Dump/Turbine Bypass Control X
A2.02: Ability to (a) predict the impacts of the following on the Steam Dump System and Turbine Bypass Control and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations; Steam valve stuck open 3.8 93 045 (SF 4S MTG) Main Turbine Generator X
A1.07: Ability to predict and/or monitor changes in parameters associated with operation of the Main Turbine Generator System, including; Lights and alarms 3.1 62 055 (SF4S CARS) Condenser Air Removal NA NA 056 (SF4S CDS) Condensate X
A2.08: Ability to (a) predict the impacts of the following on the Condensate System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Feedwater heater tube leak 3.3 63 068 (SF9 LRS) Liquid Radwaste X
A3.02: Ability to monitor automatic features of the Liquid Radwaste System, including; Automatic isolation 3.6 64 071 (SF9 WGS) Waste Gas Disposal NA NA 072 (SF7 ARM) Area Radiation Monitoring 075 (SF8 CW) Circulating Water NA NA 079 (SF8 SAS**) Station Air NA NA 086 Fire Protection NA NA 050 (SF 9 CRV*) Control Room Ventilation X
A4.01: Ability to manually operate and/or monitor in the control room: Initiate/reset system 3.8 65 K/A Category Point Totals:
1 1
1 1
1 1
1 1/
2 1
1 0/
1 Group Point Total:
10/3


ES-401 6 Form ES-401-2
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility: Vogtle Units 1 & 2 Date of Exam: November 15, 2021 Category K/A #
Topic RO SRO-only IR IR
: 1. Conduct of Operations 2.1.34 Knowledge of RCS or balance-of-plant chemistry controls, including parameters measured and reasons for the control 2.7 66 2.1.21 Ability to verify that a copy of a controlled procedure is the proper revision 3.5 67 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, and maintenance of active license status, 10 CFR Part 55 3.3 68 2.1.39 Knowledge of conservative decision-making practices 4.3 94 2.1.8 Ability to coordinate personnel activities outside the control room 4.1 95 Subtotal 3
2
: 2. Equipment Control 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity 4.5 69 2.2.21 Knowledge of pre-and post-maintenance operability requirements 2.9 70 2.2.7 Knowledge of the process for conducting infrequently performed tests or evolutions 2.9 71 2.2.5 Knowledge of the process for making design or operating changes to the facility, such as 10 CFR 50.59, Changes, Tests and Experiments, screening and evaluation processes, administrative processes for temporary modifications, disabling annunciators, or installation of temporary equipment 3.2 96 2.2.23 Ability to track TS limiting conditions for operation 4.6 97 Subtotal 3
2
: 3. Radiation Control 2.3.12 Knowledge of radiological safety principles and procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, or alignment of filters 3.2 72 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities, such as analysis and interpretation of radiation and activity readings as they pertain to administrative, normal, abnormal, and emergency procedures or to analysis and interpretation of coolant activity, including comparison to emergency plan or regulatory limits (SRO Only) 3.8 98


ES-401 PWR Examination Outline Form ES-401Plant SystemsTier 2/Group 1 (RO/SRO) - 2
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
 
Form ES-401-3 Subtotal 1
System # / Name K K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #
1
1
: 4. Emergency Procedures/Plan 2.4.12 Knowledge of operating crew responsibilities during emergency and abnormal operations 4.0 73 2.4.6 Knowledge of emergency and abnormal operating procedures major action categories 3.7 74 2.4.14 Knowledge of general guidelines for emergency and abnormal operating procedures usage 3.8 75 2.4.18 Knowledge of the specific bases for emergency and abnormal operating procedures 4.0 99 2.4.26 Knowledge of facility protection requirements, including fire brigade and portable firefighting equipment usage 3.6 100 Subtotal 3
2 Tier 3 Point Total 10 7


003 (SF4P RCP) Reactor Coolant X K1.10: Knowledge of the physical connections 3.9 28 Pump and/or cause and effect relationships between the Reactor Coolant Pump System and the following systems; RCS
ES-401 Record of Rejected K/As Form ES-401-4 Tier /
 
Group Randomly Selected K/A Reason for Rejection T2 / G1 039K6.07 Operation of the ARVs or ARV failure have minimal impact on the operation of the Main Steam System. K/A changed to 039K6.11 T1 / G2 003AG2.4.04 Difficultly making AOP and EOP entry condition SRO only. K/A Changed to 003G2.4.29 T3 G2.1.14 Unable to make plant announcements SRO only. K/A changed to G2.1.8 T1 / G2 059AG2.4.35 Unable to write SRO only question about NLO responsibilities during accidental liquid radwaste release. K/A changed to 059AG2.4.30
004 (SF1; SF2 CVCS) Chemical and X K2.02: Knowledge of electrical power supplies 3.029 Volume Control to the following: Pumps used to makeup to CVCS G2.2.37: Ability to determine operability or X availability of safety-related equipment 4.6 86
 
005 (SF4P RHR) Residual Heat X K3.02: Knowledge of the effect that a loss or 2.930 Removal malfunction of the Residual Heat Removal System will have on the following systems or system parameters; RCPS
 
X A2.05: Ability to (a) predict the impacts of the 3.5 87 following on the Residual Heat Removal System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations; RHR heat exchanger malfunction
 
006 (SF2; SF3 ECCS) Emergency X K4.13: Reset of containment isolation 3.7 31 Core Cooling
 
007 (SF5 PRTS) Pressurizer X K5.07: PZR safety tailpipe temperature 3.7 32 Relief/Quench Tank variations with PRT/quench tank pressure
 
008 (SF8 CCW) Component Cooling X K6.09: SWS 3.833 Water
 
X K1.14: RCPS 4.0 34
 
010 (SF3 PZR PCS) Pressurizer X A1.09: Tail pipe temperature and acoustic 3.6 35 Pressure Control monitors
 
012 (SF7 RPS) Reactor Protection X A2.01: Ability to (a) predict the impacts of the 3.8 36 following on the Reactor Protection System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations:
Faulty bistable operation
 
013 (SF2 ESFAS) Engineered X A3.11: Ability to monitor automatic operation of 3.9 37 Safety Features Actuation the Engineered Safety Features Actuation System, including; Safeguards equipment control
 
022 (SF5 CCS) Containment Cooling X A4.01: Ability to manually operate and/or 3.738 monitor in the control room ; CCS fans
 
X K4.04: Knowledge of Containment Cooling 3.1 39 System design features and/or interlocks that provide for the following; Cooling of CRDMs
 
025 (SF5 ICE) Ice Condenser NA NA ES-401 7 Form ES-401-2
 
026 (SF5 CSS) Containment Spray X G2.1.27: Knowledge of system purpose 3.9 40 and/or function
 
039 (SF4S MSS) Main and Reheat X K1.08: Knowledge of the physical connections 3.6 41 Steam and/or cause and effect relationships between the Main and Reheat Steam System and the following systems: MFW
 
X K6.11: SDS 3.4 42
 
059 (SF4S MFW) Main Feedwater X K3.01: Knowledge of the effect that a loss or 3.2 43 malfunction of the Main Feedwater System will have on the following systems or system parameters; CDS
 
061 (SF4S AFW) X K3.02: Knowledge of the effect that a loss or 4.3 44 Auxiliary/Emergency Feedwater malfunction of the Auxiliary/Emergency Feedwater System will have on the following systems or system parameters; S/G system
 
062 (SF6 ED AC) AC Electrical X K4.02: Knowledge of AC Electrical Distribution 3.6 45 Distribution System design features and/or interlocks that provide for the following; Circuit breaker automatic trips
 
063 (SF6 ED DC) DC Electrical X K5.04 : Knowledge of the operational 2.946 Distribution implications or cause and effect relationships of the following concepts as they apply to the DC Electrical Distribution System; System ground G 2.2.25 : Knowledge of the bases in TS for 4.2 88 X limiting conditions for operation and safety limits (SRO Only)
 
064 (SF6 EDG) Emergency Diesel X K6.09: Knowledge of the effect of the following 3.2 47 Generator plant conditions, system malfunctions, or component malfunctions on the Emergency Diesel Generators; EDG building ventilation K5.06: Knowledge of the operational implications or cause and effect relationships X of the following concepts as they apply to the 3.5 48 Emergency Diesel Generators; Unloading before securing an EDG
 
073 (SF7 PRM) Process Radiation X A1.01: Ability to predict and/or monitor 3.5 49 Monitoring changes in parameters associated with operation of the Process Radiation Monitoring System, including; Radiation levels


076 (SF4S SW) Service Water X A2.05: Ability to (a) predict the impacts of the 2.650 following on the Service Water System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations ; Sensor and detector failure K2.09: Knowledge of electrical power supplies 51 X to the following; Intake screens 2.6
Digitally signed by Daniel M. Bacon Date: 2021.10.28 16:04:34 -04'00' Eugene Guthrie Digitally signed by Eugene Guthrie Date: 2021.11.05 15:43:03 -04'00'


078 (SF8 IAS) Instrument Air X A3.05: Ability to monitor automatic features of 3.352 the Instrument Air System, including; Isolation of instrument air to containment X K2.01; Knowledge of electrical power supplies 3.3 53 to the following; Instrument air compressor ES-401 8 Form ES-401-2
Vogtle 1&2 2021-301 Initial Operator License Exam ES-401 Written Examination Review Worksheet Form ES-401-9 Q#
 
: 1.
103 (SF5 CNT) Containment X G2.2.3: Knowledge of the design, procedural, 3.854 and/or operational differences between units
LOK (F/H)
 
: 2.
X 2.9 89 A2.10: FHS malfunctions
LOD (1-5)
 
: 3. Psychometric Flaws
053 (SF1; SF4P ICS*) Integrated X A4.03; Ability to manually operate and/or 3.9 55 Control ( IPC) monitor in the control room; S/G and/or reactor demand X G2.1.30: Ability to locate and operate components, including local controls 4.0 90
: 4. Job Content Flaws
 
: 5. Other
K/A Category Point Totals: 3 3 3 3 3 3 2 2/2 2 2/Group Point Total: 28/5 2 3
: 6.
 
B/M/N
ES-401 PWR Examination Outline Form ES-401-2 Plant Systems Tier 2/Group 2 (RO/SRO)
: 7.
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #
U/E/S
001 (SF1 CRDS) Control Rod Drive X K1.12: Knowledge of the physical connections 3.8 56 and/or cause and effect relationships between the Control Rod Drive System and the following system; RPIS 002 (SF2; SF4P RCS) Reactor X K3.03: Knowledge of the effect that a loss or 4.0 57 Coolant malfunction of the Reactor Coolant System will have on the following systems or system parameters: CNT 011 (SF2 PZR LCS) Pressurizer NA NA Level Control 014 (SF1 RPI) Rod Position NA NA Indication 015 (SF7 NI) Nuclear X A2.04: Ability to use procedures to correct, 3.7 91 Instrumentation control, or mitigate the consequences of those abnormal operations: Effects on axial flux density of control rod alignment and sequencing, xenon production and decay, and boron versus control rod reactivity changes 016 (SF7 NNI) Nonnuclear X K2.03: Knowledge of electrical power supplies 3.4 58 Instrumentation to the following; Primary system control circuits 017 (SF7 ITM) In-Core Temperature NA NA Monitor 027 (SF5 CIRS) Containment Iodine X K5.01: Knowledge of the operational 2.9 59 Removal implications or cause and effect relationships of the following concepts as they apply to the Containment Iodine Removal System:
: 8.
Purpose of charcoal filters 028 (SF5 HRPS) Hydrogen X K4.02: Knowledge of Hydrogen Recombiner 2.8 60 Recombiner and Purge Control and Purge Control System design features and/or interlocks that provide for the following; Containment hydrogen concentration monitoring ES-401 9 Form ES-401-2
Explanation Stem Focus Cues T/F Cred.
 
Dist.
029 (SF8 CPS) Containment Purge X K6.10: Knowledge of the effect of the following 2.6 61 plant conditions, system malfunctions, or component malfunctions on the Containment Purge System; Containment air cleanup and recirculation system
Partial Job-Link Minutia  
 
#/
033 (SF8 SFPCS) Spent Fuel Pool NA NA Cooling 034 (SF8 FHS) Fuel-Handling NA NA Equipment 035 (SF 4P SG) Steam Generator X G2.1.19: Ability to use available indications to 92 evaluate system or component status 041 (SF4S SDS) Steam X A2.02: Ability to (a) predict the impacts of the 3.8 93 Dump/Turbine Bypass Control following on the Steam Dump System and Turbine Bypass Control and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations; Steam valve stuck open 045 (SF 4S MTG) Main Turbine X A1.07: Ability to predict and/or monitor 3.1 62 Generator changes in parameters associated with operation of the Main Turbine Generator System, including; Lights and alarms 055 (SF4S CARS) Condenser Air NA NA Removal 056 (SF4S CDS) Condensate X A2.08: Ability to (a) predict the impacts of the 3.3 63 following on the Condensate System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Feedwater heater tube leak 068 (SF9 LRS) Liquid Radwaste X A3.02: Ability to monitor automatic features of 3.6 64 the Liquid Radwaste System, including; Automatic isolation 071 (SF9 WGS) Waste Gas NA NA Disposal 072 (SF7 ARM) Area Radiation Monitoring 075 (SF8 CW) Circulating Water NA NA 079 (SF8 SAS**) Station Air NA NA 086 Fire Protection NA NA 050 (SF 9 CRV*) Control Room X A4.01: Ability to manually operate and/or 3.8 65 Ventilation monitor in the control room: Initiate/reset system
units Back-ward Q=
 
K/A SRO Only 1
K/A Category Point Totals: 1 1 1 1 1 1 1 1/1 1 0/Group Point Total: 10/3 2 1
F 2
 
M S
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3
K/A 001K1.12 T2 G2 Question is Satisfactory.
 
2 H
Facility: Vogtle Units 1 & 2 Date of Exam: November 15, 2021
2 X
 
B E
Category K/A # Topic RO SRO-only IR # IR #
K/A 002K3.03 T2 G2
2.1.34 Knowledge of RCS or balance -of -plant chemistry 2.7 66 controls, including parameters measured and reasons for the control 2.1.21 Ability to verify that a copy of a controlled procedure is 3.5 67 the proper revision 2.1.4 Knowledge of individual licensed operator 3.3 68
: 1. Auctioneered High is not plausible for an answer to this question because you are not asking about a protective or control function. You could use highest.
: 1. Conduct of responsibilities related to shift staffing, such as medical Operations requirements, no-solo operation, and maintenance of active license status, 10 CFR Part 55 2.1.39 Knowledge of conservative decision-making practices 4.3 94 2.1.8 Ability to coordinate personnel activities outside the 4.1 95 control room
 
Subtotal 3 2 2.2.1 Ability to perform pre-startup procedures for the facility, 4.5 69 including operating those controls associated with plant equipment that could affect reactivity 2.2.21 Knowledge of pre-and post-maintenance operability 2.9 70 requirements 2.2.7 Knowledge of the process for conducting infrequently 2.9 71 performed tests or evolutions
: 2. Equipment 2.2.5 Knowledge of the process for making design or 3.2 96 Control operating changes to the facility, such as 10 CFR 50.59, Changes, Tests and Experiments, screening and evaluation processes, administrative processes for temporary modifications, disabling annunciators, or installation of temporary equipment 2.2.23 Ability to track TS limiting conditions for operation 4.6 97
 
Subtotal 3 2 2.3.12 Knowledge of radiological safety principles and 3.2 72 procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, or alignment of filters
: 3. Radiation Control
 
2.3.14 Knowledge of radiation or contamination hazards that 3.8 98 may arise during normal, abnormal, or emergency conditions or activities, such as analysis and interpretation of radiation and activity readings as they pertain to administrative, normal, abnormal, and emergency procedures or to analysis and interpretation of coolant activity, including comparison to emergency plan or regulatory limits (SRO Only)
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3
 
Subtotal 1 1 2.4.12 Knowledge of operating crew responsibilities during 4.0 73 emergency and abnormal operations 2.4.6 Knowledge of emergency and abnormal operating 3.7 74 procedures major action categories 2.4.14 Knowledge of general guidelines for emergency and 3.8 75
: 4. Emergency abnormal operating procedures usage Procedures/Plan 2.4.18 Knowledge of the specific bases for emergency and 4.0 99 abnormal operating procedures 2.4.26 Knowledge of facility protection requirements, including 3.6 100 fire brigade and portable firefighting equipment usage
 
Subtotal 3 2 Tier 3 Point Total 10 7
 
ES-401 Record of Rejected K/As Form ES-401-4
 
Tier / Randomly Reason for Rejection Group Selected K/A
 
T2 / G1 039K6.07 Operation of the ARVs or ARV failure have minimal impact on the operation of the Main Steam System. K/A changed to 039K6.11
 
T1 / G2 003AG2.4.04 Difficultly making AOP and EOP entry condition SRO only. K/A Changed to 003G2.4.29
 
T3 G2.1.14 Unable to make plant announcements SRO only. K/A changed to G2.1.8 Unable to write SRO only question about NLO responsibilities T1 / G2 059AG2.4.35 during accidental liquid radwaste release. K/A changed to 059AG2.4.30
 
Digitally signed by Daniel M. Bacon Date: 2021.10.28 16:04:34 -04'00' Eugene Guthrie Digitally signed by Eugene Guthrie Date: 2021.11.05 15:43:03 -04'00' Vogtle 1&2 2021-301 Initial Operator License Exam
 
ES-401 Written Examination Review Worksheet Form ES-401-9
: 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job-Minutia #/ Back - Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only
 
K/A 001K1.12 T2 G2 1 F 2 M S Question is Satisfactory.
K/A 002K3.03 T2 G2 2 H 2 X B E 1. Auctioneered High is not plausible for an answer to this question because you are not asking about a protective or control function. You could use highest.
: 2. The explanation of required knowledge is missing the less than or in the first sentence and the between or the greater than and less than in the second sentence that are needed to make them technically accurate.
: 2. The explanation of required knowledge is missing the less than or in the first sentence and the between or the greater than and less than in the second sentence that are needed to make them technically accurate.
10/28/2021 - Licensee made corrections to address the concerns as stated above. The question is now Satisfactory.
10/28/2021 - Licensee made corrections to address the concerns as stated above. The question is now Satisfactory.
K/A 003K1.10 T2 G1 3 H 2 B E 1. The reason given to consider the first part of Choice C plausible is not acceptable.
3 H
2 B
E K/A 003K1.10 T2 G1
: 1. The reason given to consider the first part of Choice C plausible is not acceptable.
Misreading a given condition in the stem and subtracting a pressure from a temperature does not make the choice plausible. Something such as requiring RCS pressure to be greater than 325 psi prior to starting a RCP for filling and venting would be a good basis.
Misreading a given condition in the stem and subtracting a pressure from a temperature does not make the choice plausible. Something such as requiring RCS pressure to be greater than 325 psi prior to starting a RCP for filling and venting would be a good basis.
10/28/2021 - Licensee made corrections to address the concerns as stated above. The question is now Satisfactory.
10/28/2021 - Licensee made corrections to address the concerns as stated above. The question is now Satisfactory.
K/A 004K2.02 T2 G1 4 H 3 M S Question is Satisfactory.
4 H
 
3 M
S K/A 004K2.02 T2 G1 Question is Satisfactory.
5 F
2 X
M U
K/A 005AA1.05 T1 G2 This question directly tests procedure knowledge.
K/A 005AA1.05 T1 G2 This question directly tests procedure knowledge.
5 F 2 X M U 1. Question is Unsatisfactory because it does not test the K/A. It tests knowledge of the rod control system manual rod speeds and the rod control system malfunction procedure.
: 1. Question is Unsatisfactory because it does not test the K/A. It tests knowledge of the rod control system manual rod speeds and the rod control system malfunction procedure.
 
10/28/21 - Licensee submitted a different question that meets the K/A. The new question is Satisfactory.
10/28/21 - Licensee submitted a different question that meets the K/A. The new question is Satisfactory.
K/A 005K3.02 Question submitted for preliminary review. T2 G1 6 H 3 N S Question is Satisfactory.
6 H
K/A 006K4.13 T2 G1 7 F 2 X M U 1. Unsatisfactory due to overlap with the operating test. On Scenario #5, the UO is required to reset containment isolation to restore instrument air following a steam line break.
3 N
 
S K/A 005K3.02 Question submitted for preliminary review. T2 G1 Question is Satisfactory.
7 F
2 X
M U
K/A 006K4.13 T2 G1
: 1. Unsatisfactory due to overlap with the operating test. On Scenario #5, the UO is required to reset containment isolation to restore instrument air following a steam line break.
10/28/2021 - Licensee made minor change to first part question. This question does not overlap with the conditions present during Scenario #5. The question is Satisfactory.
10/28/2021 - Licensee made minor change to first part question. This question does not overlap with the conditions present during Scenario #5. The question is Satisfactory.
K/A 007EA1.05 T1 G1 Question tests #2 of FAQ 401. 55.
8 H
8 H 2 B S Question is Satisfactory.
2 B
 
S K/A 007EA1.05 T1 G1 Question tests #2 of FAQ 401.55.
K/A 007K5.07 T2 G1 9 H 2 M S Question is Satisfactory.
Question is Satisfactory.
 
9 H
K/A 008AA2.06 T1 G1 This question directly tests procedure knowledge.
2 M
10 H 2 M S Question is Satisfactory.
S K/A 007K5.07 T2 G1 Question is Satisfactory.
 
10 H
K/A 008K1.14 T2 G1 11 H 2 B S Question is Satisfactory.
2 M
 
S K/A 008AA2.06 T1 G1 This question directly tests procedure knowledge.
K/A 008 K6.09 T2 G1 Question 12 on Vogtle 2015 NRC Exam 12 F 2 B S Question is Satisfactory.
Question is Satisfactory.
K/A 009EG2.2.22 T1 G1 This question directly tests procedure knowledge.
11 H
13 H 2 N S Question is Satisfactory.
2 B
K/A 010A1.09 T2 G1 14 F 2 M S Question is Satisfactory.
S K/A 008K1.14 T2 G1 Question is Satisfactory.
Vogtle 1&2 2021-301 Initial Operator License Exam
12 F
: 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
2 B
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job-Minutia #/ Back - Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only
S K/A 008K6.09 T2 G1 Question 12 on Vogtle 2015 NRC Exam Question is Satisfactory.
 
13 H
K/A 011EK1.03 T1 G1 This question directly tests procedure knowledge 15 F 2 M S Question is Satisfactory.
2 N
 
S K/A 009EG2.2.22 T1 G1 This question directly tests procedure knowledge.
K/A 012A2.01 T2 G1 16 F 2 X B E 1. An applicant potentially mis-reading a question does not support the plausibility of a distractor. Is there any coincidence at your plant that requires 3 out of x to trip? If not, then choices C(1) and D(1) are not plausible. You could potentially ask if the coincidence for the pressurizer pressure high trip is 2/3 or 2/4.
Question is Satisfactory.
14 F
2 M
S K/A 010A1.09 T2 G1 Question is Satisfactory.  


Vogtle 1&2 2021-301 Initial Operator License Exam Q#
: 1.
LOK (F/H)
: 2.
LOD (1-5)
: 3. Psychometric Flaws
: 4. Job Content Flaws
: 5. Other
: 6.
B/M/N
: 7.
U/E/S
: 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
#/
units Back-ward Q=
K/A SRO Only 15 F
2 M
S K/A 011EK1.03 T1 G1 This question directly tests procedure knowledge Question is Satisfactory.
16 F
2 X
B E
K/A 012A2.01 T2 G1
: 1. An applicant potentially mis-reading a question does not support the plausibility of a distractor. Is there any coincidence at your plant that requires 3 out of x to trip? If not, then choices C(1) and D(1) are not plausible. You could potentially ask if the coincidence for the pressurizer pressure high trip is 2/3 or 2/4.
10/28/2021 - Licensee submitted a different question to address the concerns as listed above. The question is Satisfactory.
10/28/2021 - Licensee submitted a different question to address the concerns as listed above. The question is Satisfactory.
K/A 013A3.11 T2 G1 17 H 3 M S Question is Satisfactory.
17 H
 
3 M
K/A 016K2.03 T2 G2 18 H 3 N S Question is Satisfactory.
S K/A 013A3.11 T2 G1 Question is Satisfactory.
 
18 H
K/A 022A4.01 T2 G1 19 F 3 M S Question is Satisfactory.
3 N
 
S K/A 016K2.03 T2 G2 Question is Satisfactory.
K/A 022AK2.10 T1 G1 Question tests procedure knowledge.
19 F
20 H 2 M S Question is Satisfactory.
3 M
K/A 022K4.04 T2 G1 21 F 3 B S Question is Satisfactory.
S K/A 022A4.01 T2 G1 Question is Satisfactory.
K/A 026AK3.02 T1 G1 Question tests #4 of FAQ 401.55.
20 H
22 H 2 B S Question is Satisfactory.
2 M
K/A 026G2.1.27 T2 G1.
S K/A 022AK2.10 T1 G1 Question tests procedure knowledge.
23 F 2 M S Question is Satisfactory.
Question is Satisfactory.
K/A 027AA1.06 T1 G1 Question tests #2 of FAQ 401.55.
21 F
24 H 2 M S Question is Satisfactory.
3 B
K/A 027K5.01 T2 G2 25 F 2 B S Question is Satisfactory.
S K/A 022K4.04 T2 G1 Question is Satisfactory.
K/A 028AA2.03 T1 G2 Question tests #2 of FAQ 401.55 26 H 3 M S Question is Satisfactory.
22 H
 
2 B
K/A 028K4.02 T2 G2 27 F 2 N S Question is Satisfactory.
S K/A 026AK3.02 T1 G1 Question tests #4 of FAQ 401.55.
 
Question is Satisfactory.
K/A 029EA2.13 T1 G1 Question #29 on Vogtle 2019 NRC Exam. Question tests procedure 28 H 2 B S knowledge.
23 F
 
2 M
K/A 029K6.10 Question submitted for preliminary review. T2 G2 29 F 2 M S Question is Satisfactory.
S K/A 026G2.1.27 T2 G1.
 
Question is Satisfactory.
K/A 032AG2.4.02 T1 G2 Question tests procedure knowledge.
24 H
30 H 2 N S Question is Satisfactory.
2 M
K/A 033AK1.01 T1 G2 31 F 2 M S Question is Satisfactory. Question tests procedure knowledge.
S K/A 027AA1.06 T1 G1 Question tests #2 of FAQ 401.55.
K/A 038EG2.4.50 T1 G1 Question tests procedure knowledge.
Question is Satisfactory.
32 H 2 M S Question is Satisfactory.
25 F
K/A 039K1.08 T2 G1 Question #33 on Vogtle 2019 NRC Exam.
2 B
33 F 2 B S Question is Satisfactory.
S K/A 027K5.01 T2 G2 Question is Satisfactory.
K/A 039K6.11 T2 G1 34 H 3 B S Question is Satisfactory.
26 H
K/A 045A1.07 T2 G2 35 F 2 M S Question is Satisfactory.
3 M
Vogtle 1&2 2021-301 Initial Operator License Exam
S K/A 028AA2.03 T1 G2 Question tests #2 of FAQ 401.55 Question is Satisfactory.
: 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
27 F
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job-Minutia #/ Back -Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only
2 N
 
S K/A 028K4.02 T2 G2 Question is Satisfactory.
K/A 050A4.01 T2 G2 36 F 2 M S Question is Satisfactory.
28 H
2 B
S K/A 029EA2.13 T1 G1 Question #29 on Vogtle 2019 NRC Exam. Question tests procedure knowledge.
29 F
2 M
S K/A 029K6.10 Question submitted for preliminary review. T2 G2 Question is Satisfactory.
30 H
2 N
S K/A 032AG2.4.02 T1 G2 Question tests procedure knowledge.
Question is Satisfactory.
31 F
2 M
S K/A 033AK1.01 T1 G2 Question is Satisfactory. Question tests procedure knowledge.
32 H
2 M
S K/A 038EG2.4.50 T1 G1 Question tests procedure knowledge.
Question is Satisfactory.
33 F
2 B
S K/A 039K1.08 T2 G1 Question #33 on Vogtle 2019 NRC Exam.
Question is Satisfactory.
34 H
3 B
S K/A 039K6.11 T2 G1 Question is Satisfactory.
35 F
2 M
S K/A 045A1.07 T2 G2 Question is Satisfactory.  


Vogtle 1&2 2021-301 Initial Operator License Exam Q#
: 1.
LOK (F/H)
: 2.
LOD (1-5)
: 3. Psychometric Flaws
: 4. Job Content Flaws
: 5. Other
: 6.
B/M/N
: 7.
U/E/S
: 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
#/
units Back-ward Q=
K/A SRO Only 36 F
2 M
S K/A 050A4.01 T2 G2 Question is Satisfactory.
37 H
2 X
B U
K/A 051AK2.10 T1 G2 Question tests procedure knowledge.
K/A 051AK2.10 T1 G2 Question tests procedure knowledge.
37 H 2 X B U Question is unsatisfactory due to more than one non-credible distractor. The first part of choices C and D are not credible with the conditions given. The second part of choice D is not plausible given the initial conditions.
Question is unsatisfactory due to more than one non-credible distractor. The first part of choices C and D are not credible with the conditions given. The second part of choice D is not plausible given the initial conditions.
 
10/28/2021 - The licensee made changes to the question to address the concerns as listed above. The question is now Satisfactory.
10/28/2021 - The licensee made changes to the question to address the concerns as listed above. The question is now Satisfactory.
K/A 053A4.03 T2 G1 38 H 2 X N E 1. Second part question should be less than or equal to in order to be fully technically correct.
38 H
10/28/2021 - The answer chosen is less than 551 F because the Technical Specification Minimum Temperature for Criticality allows operation at 551 F although t he Rapid Power Reduction Procedure directs a trip if equal to 551 F. Since the distractor is 557 F, the chosen answer is fully correct. The question is Satisfactory.
2 X
K/A 054AK1.02 T1 G1 Question tests #1 of FAQ 401.55.
N E
39 F 2 X X M E 1. First part question does not seem related to K/A. It appears to be a tack on to achieve a two part question. Both parts could easily be related to establishing feed to a dry steam generator.
K/A 053A4.03 T2 G1
 
: 1. Second part question should be less than or equal to in order to be fully technically correct.
10/28/2021 - The answer chosen is less than 551 F because the Technical Specification Minimum Temperature for Criticality allows operation at 551 F although the Rapid Power Reduction Procedure directs a trip if equal to 551 F. Since the distractor is 557 F, the chosen answer is fully correct. The question is Satisfactory.
39 F
2 X
X M
E K/A 054AK1.02 T1 G1 Question tests #1 of FAQ 401.55.
: 1. First part question does not seem related to K/A. It appears to be a tack on to achieve a two part question. Both parts could easily be related to establishing feed to a dry steam generator.
10/28/2021 - The licensee changed the first part question so that it is more related to the K/A. The question is now Satisfactory.
10/28/2021 - The licensee changed the first part question so that it is more related to the K/A. The question is now Satisfactory.
K/A 055EK2.04 T1 G1 Question tests procedure knowledge. Question was on Vogtle 2014 40 H 2 X B E NRC Exam.
40 H
2 X
B E
K/A 055EK2.04 T1 G1 Question tests procedure knowledge. Question was on Vogtle 2014 NRC Exam.
: 1. Adding to minimize battery drain to the second part question gives teaching in the stem and provides a cue.
: 1. Adding to minimize battery drain to the second part question gives teaching in the stem and provides a cue.
10/28/2021 - The licensee made changes to the second part question to address the concerns as listed above. The question is now Satisfactory.
10/28/2021 - The licensee made changes to the second part question to address the concerns as listed above. The question is now Satisfactory.
41 H
2 X
M S
K/A 056A2.08 T2 G2 Question was on Vogtle 2015 NRC Exam.
K/A 056A2.08 T2 G2 Question was on Vogtle 2015 NRC Exam.
41 H 2 X M S Question is Satisfactory.
Question is Satisfactory.
K/A 056K3.01 T1 G1 Question tests #4 of FAQ 401.55.
42 F
42 F 2 M S Question is Satisfactory.
2 M
K/A 057AA1.04 T1 G1 Question tests #4 of FAQ 401.55.
S K/A 056K3.01 T1 G1 Question tests #4 of FAQ 401.55.
43 H 2 M S Question is Satisfactory.
Question is Satisfactory.
 
43 H
K/A 059K3.01 T2 G1 44 H 2 N S Question is Satisfactory.
2 M
 
S K/A 057AA1.04 T1 G1 Question tests #4 of FAQ 401.55.
K/A 061K3.02 T2 G1 45 H 2 M S Question is Satisfactory.
Question is Satisfactory.
 
44 H
K/A 062K4.02 T2 G1 46 F 2 X B E 1. Based on 13435-C, it seems that taking the switch to the maintenance position enables an instantaneous trip rather than disabling a time delay trip.
2 N
 
S K/A 059K3.01 T2 G1 Question is Satisfactory.
45 H
2 M
S K/A 061K3.02 T2 G1 Question is Satisfactory.
46 F
2 X
B E
K/A 062K4.02 T2 G1
: 1. Based on 13435-C, it seems that taking the switch to the maintenance position enables an instantaneous trip rather than disabling a time delay trip.
10/28/2021 - Based on the difficulty of finding documentation to prove first part answer, the licensee submitted a different question. The question is Satisfactory.
10/28/2021 - Based on the difficulty of finding documentation to prove first part answer, the licensee submitted a different question. The question is Satisfactory.
K/A 063K5.04 T2 G1 47 F 2 M S Question is Satisfactory.
47 F
K/A 064K5.06 T2 G1 48 H 2 M S Question is Satisfactory.
2 M
Vogtle 1&2 2021-301 Initial Operator License Exam
S K/A 063K5.04 T2 G1 Question is Satisfactory.
: 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
48 H
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job-Minutia #/ Back -Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only
2 M
 
S K/A 064K5.06 T2 G1 Question is Satisfactory.  
K/A 064K6.09 T2 G1 49 H 2 X B E 1. The first and second parts of choice D are not credible distractors when combined. No fans running with the EDG running does not seem cre dible.


Vogtle 1&2 2021-301 Initial Operator License Exam Q#
: 1.
LOK (F/H)
: 2.
LOD (1-5)
: 3. Psychometric Flaws
: 4. Job Content Flaws
: 5. Other
: 6.
B/M/N
: 7.
U/E/S
: 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
#/
units Back-ward Q=
K/A SRO Only 49 H
2 X
B E
K/A 064K6.09 T2 G1
: 1. The first and second parts of choice D are not credible distractors when combined. No fans running with the EDG running does not seem credible.
10/28/2021 - The licensee changed the second part question to address the concerns as listed above. The question is now Satisfactory.
10/28/2021 - The licensee changed the second part question to address the concerns as listed above. The question is now Satisfactory.
K/A 065AA2.03 T1 G1 Question tests #1, #3, and #4 of FAQ 401.55.
50 H
50 H 2 M S Question is Satisfactory.
2 M
K/A 067AK3.02 Question submitted for preliminary review. T1 G2 Question tests procedure 51 F 2 B S knowledge.
S K/A 065AA2.03 T1 G1 Question tests #1, #3, and #4 of FAQ 401.55.
Question is Satisfactory.
51 F
2 B
S K/A 067AK3.02 Question submitted for preliminary review. T1 G2 Question tests procedure knowledge.
Question is Satisfactory.
Question is Satisfactory.
K/A 068K3.02 T2 G2 52 H 2 M S Question is Satisfactory.
52 H
 
2 M
K/A 069AA1.03 T1 G2 Question tests procedure knowledge. Question used on 2014 Vogtle 53 F 2 B S NRC exam.
S K/A 068K3.02 T2 G2 Question is Satisfactory.
53 F
2 B
S K/A 069AA1.03 T1 G2 Question tests procedure knowledge. Question used on 2014 Vogtle NRC exam.
Question is Satisfactory.
Question is Satisfactory.
K/A 073A1.01 T2 G1 54 F 2 M S Question is Satisfactory.
54 F
 
2 M
K/A 076A2.05 T2 G1 55 H 2 X X N U 1.Question is Unsatisfactory because it does not meet the second part of the K/A (using procedures). This is required for an A.2 K/A.
S K/A 073A1.01 T2 G1 Question is Satisfactory.
55 H
2 X
X N
U K/A 076A2.05 T2 G1 1.Question is Unsatisfactory because it does not meet the second part of the K/A (using procedures). This is required for an A.2 K/A.
: 2. It does not seem that the demineralized water valve being required to be open is a credible distractor for a level transmitter failure. Whether or not it automatically opened or not is a different story.
: 2. It does not seem that the demineralized water valve being required to be open is a credible distractor for a level transmitter failure. Whether or not it automatically opened or not is a different story.
10/28/2021 - Licensee changed second part question to include procedure. Question is Satisfactory.
10/28/2021 - Licensee changed second part question to include procedure. Question is Satisfactory.
K/A 076AA2.04 T1 G2 Question tests procedure knowledge.
56 H
56 H 2 M S Question is Satisfactory.
2 M
 
S K/A 076AA2.04 T1 G2 Question tests procedure knowledge.
K/A 076K2.09 T2 G1 57 F 2 X X N E 1. The first part question is a tack on that does not relate to the selected K/A.
Question is Satisfactory.
 
57 F
2 X
X N
E K/A 076K2.09 T2 G1
: 1. The first part question is a tack on that does not relate to the selected K/A.
10/28/2021 - Licensee changed first part question to relate directly to the K/A. The question is now Satisfactory.
10/28/2021 - Licensee changed first part question to relate directly to the K/A. The question is now Satisfactory.
K/A 077AG2.4.49 T1 G1 Question tests procedure knowledge.
58 H
58 H 2 B S Question is Satisfactory.
2 B
K/A 078A3.05 T2 G1 59 F 2 M S Question is Satisfactory.
S K/A 077AG2.4.49 T1 G1 Question tests procedure knowledge.
K/A 078G2.4.18 T1 G2 Question tests procedure knowledge.
Question is Satisfactory.
60 F 2 M S Question is Satisfactory.
59 F
K/A 078K2.01 T2 G1 Question #57 on 2017 Vogtle NRC exam.
2 M
61 H 3 B S Question is Satisfactory.
S K/A 078A3.05 T2 G1 Question is Satisfactory.
 
60 F
K/A 103G2.2.03 T2 G1 62 F 3 N S Question is Satisfactory.
2 M
 
S K/A 078G2.4.18 T1 G2 Question tests procedure knowledge.
K/A G2.1.04 T3 63 F 2 X X N E 1. Does Vogtle have a mixed shift schedule? If not, there is no correct answer.
Question is Satisfactory.
61 H
3 B
S K/A 078K2.01 T2 G1 Question #57 on 2017 Vogtle NRC exam.
Question is Satisfactory.
62 F
3 N
S K/A 103G2.2.03 T2 G1 Question is Satisfactory.
63 F
2 X
X N
E K/A G2.1.04 T3
: 1. Does Vogtle have a mixed shift schedule? If not, there is no correct answer.
: 2. The stem of the question does not in any way get to the fact that you can not truncate shifts at the correct number of hours. This seems to be negative training.
: 2. The stem of the question does not in any way get to the fact that you can not truncate shifts at the correct number of hours. This seems to be negative training.
: 3. The second part question should ask if the requirement is per month or quarter.
: 3. The second part question should ask if the requirement is per month or quarter.
4 There is no need for the given conditions.
4 There is no need for the given conditions.
10/28/2021 - Licensee submitted new question. The new question is Satisfactory.


10/28/2021 - Licensee submitted new question. The new question is Satisfactory.
Vogtle 1&2 2021-301 Initial Operator License Exam Q#
Vogtle 1&2 2021-301 Initial Operator License Exam
: 1.
: 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
LOK (F/H)
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job-Minutia #/ Back - Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only
: 2.
 
LOD (1-5)
K/A G2.1.21 T3 64 F 2 N E 1. Choice B does not seem to be a credible distractor. It does not seem that it could be correct that you would be required to version check the actual transient response procedure, but not a system operating procedure that it references.
: 3. Psychometric Flaws
 
: 4. Job Content Flaws
: 5. Other
: 6.
B/M/N
: 7.
U/E/S
: 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia  
#/
units Back-ward Q=
K/A SRO Only 64 F
2 N
E K/A G2.1.21 T3
: 1. Choice B does not seem to be a credible distractor. It does not seem that it could be correct that you would be required to version check the actual transient response procedure, but not a system operating procedure that it references.
10/28/2021 - Licensee changed question to address the concerns stated above. The question is now Satisfactory.
10/28/2021 - Licensee changed question to address the concerns stated above. The question is now Satisfactory.
K/A G2.1.34 T3 Question used on 2013 Vogtle NRC exam.
65 F
65 F 2 B S Question is Satisfactory.
2 B
K/A G2.2.01 T3 66 H 2 B S Question is Satisfactory.
S K/A G2.1.34 T3 Question used on 2013 Vogtle NRC exam.
 
Question is Satisfactory.
K/A G2.2.07 T3 67 F 2 X M S Question is Satisfactory.
66 H
 
2 B
K/A G2.2.21 Question submitted for preliminary review. T3 68 H 2 M S Question is Satisfactory.
S K/A G2.2.01 T3 Question is Satisfactory.
 
67 F
K/A G2.3.12 T3 69 F 2 B S Question is Satisfactory.
2 X
K/A G2.4.06 T3 Question #65 on 2019 Vogtle NRC exam.
M S
70 F 2 B S Question is Satisfactory.
K/A G2.2.07 T3 Question is Satisfactory.
K/A G2.4.12 T3 71 H 2 B S Question is Satisfactory.
68 H
K/A G2.4.14 T3 72 F 2 M S Question is Satisfactory.
2 M
 
S K/A G2.2.21 Question submitted for preliminary review. T3 Question is Satisfactory.
K/A WE04EK1.05 T1 G1 Question tests procedure knowledge.
69 F
73 H 2 N S Question is Satisfactory.
2 B
S K/A G2.3.12 T3 Question is Satisfactory.
70 F
2 B
S K/A G2.4.06 T3 Question #65 on 2019 Vogtle NRC exam.
Question is Satisfactory.
71 H
2 B
S K/A G2.4.12 T3 Question is Satisfactory.
72 F
2 M
S K/A G2.4.14 T3 Question is Satisfactory.
73 H
2 N
S K/A WE04EK1.05 T1 G1 Question tests procedure knowledge.
Question is Satisfactory.
74 F
2 X
N U
K/A WE05K3.16 T1 G1 Question tests procedure knowledge.
K/A WE05K3.16 T1 G1 Question tests procedure knowledge.
74 F 2 X N U 1. Question us Unsatisfactory due to more than on non -credible distractor. Emergency boration is not a plausible distractor as the reason for RCS feed flow during a loss of secondary heat sink when bleed and feed is required.
: 1. Question us Unsatisfactory due to more than on non-credible distractor. Emergency boration is not a plausible distractor as the reason for RCS feed flow during a loss of secondary heat sink when bleed and feed is required.
 
10/28/2021 - The licensee changed the second part question to address the concerns as listed above. The question is now Satisfactory.
10/28/2021 - The licensee changed the second part question to address the concerns as listed above. The question is now Satisfactory.
K/A WE11EK2.04 T1 G1 Question tests procedure knowledge.
75 H
75 H 2 M S Question is Satisfactory.
2 M
S K/A WE11EK2.04 T1 G1 Question tests procedure knowledge.
Question is Satisfactory.
76 (1)
H 2
M S
K/A 003AG2.4.29 Question submitted for preliminary review. T1 G2 Question is Satisfactory.
77 (2)
H 3
N S
K/A 004G2.2.37 T2 G1 Question is Satisfactory.
78 (3)
H 2
B S
K/A 005A2.05 T2 G1 Question is Satisfactory.  


K/A 003AG2.4.29 Question submitted for preliminary review. T1 G2 76 H 2 M S Question is Satisfactory.
Vogtle 1&2 2021-301 Initial Operator License Exam Q#
(1)
: 1.
 
LOK (F/H)
K/A 004G2.2.37 T2 G1 77 H 3 N S Question is Satisfactory.
: 2.
(2)
LOD (1-5)
K/A 005A2.05 T2 G1 78 H 2 B S Question is Satisfactory.
: 3. Psychometric Flaws
(3)
: 4. Job Content Flaws
Vogtle 1&2 2021-301 Initial Operator License Exam
: 5. Other
: 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
: 6.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job-Minutia #/ Back - Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only
B/M/N
 
: 7.
K/A 011EG2.4.30 Question submitted for preliminary review. T1 G1 79 F 2 M S Question is Satisfactory.
U/E/S
(4)
: 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia  
#/
units Back-ward Q=
K/A SRO Only 79 (4)
F 2
M S
K/A 011EG2.4.30 Question submitted for preliminary review. T1 G1 Question is Satisfactory.
80 (5)
H 2
B S
K/A 015A2.04 T2 G2 Question used on 2013 Vogtle NRC exam.
K/A 015A2.04 T2 G2 Question used on 2013 Vogtle NRC exam.
80 H 2 B S Question is Satisfactory.
Question is Satisfactory.
(5)
81 (6)
 
H 2
K/A 015AA2.01 T1 G1 81 H 2 M S Question is Satisfactory.
M S
(6)
K/A 015AA2.01 T1 G1 Question is Satisfactory.
 
82 (7)
K/A 025AG2.1.32 Question submitted for preliminary review. T1 G1 82 H 2 M S Question is Satisfactory.
H 2
(7)
M S
 
K/A 025AG2.1.32 Question submitted for preliminary review. T1 G1 Question is Satisfactory.
K/A 035G2.1.19 T2 G2 83 H 2 B S Question is Satisfactory.
83 (8)
(8)
H 2
 
B S
K/A 036AA2.05 T1 G2 84 F 2 M S Question is Satisfactory.
K/A 035G2.1.19 T2 G2 Question is Satisfactory.
(9)
84 (9)
K/A 040AA2.01 T1G1 85 2 X M E 1. The second part question does not s eem to be related to the K/A in any way. This appears (10) H to be a tack on to make a two part question.
F 2
 
M S
K/A 036AA2.05 T1 G2 Question is Satisfactory.
85 (10)
H 2
X M
E K/A 040AA2.01 T1G1
: 1. The second part question does not seem to be related to the K/A in any way. This appears to be a tack on to make a two part question.
10/28/2021 - The licensee changed the second part question to relate to the K/A. The question is now Satisfactory.
10/28/2021 - The licensee changed the second part question to relate to the K/A. The question is now Satisfactory.
K/A 041A2.02 Question submitted for preliminary review. T2 G2 86 F 2 N S Question is Satisfactory.
86 (11)
(11)
F 2
 
N S
K/A 053G2.1.30 Question submitted for preliminary review. T2 G1 87 H 4 M S Verified with operations representative that a technical specification reference was not needed for the second part question.
K/A 041A2.02 Question submitted for preliminary review. T2 G2 Question is Satisfactory.
(12)
87 (12)
K/A 058G2.2.40 T1 G1 88 H 3 N S Question is Satisfactory.
H 4
(13)
M S
 
K/A 053G2.1.30 Question submitted for preliminary review. T2 G1 Verified with operations representative that a technical specification reference was not needed for the second part question.
K/A 059G2.4.35 T1 G2 89 H 2 X X M E 1. The second part question does not seem to be related to the K/A in any way. This appears to be a tack on to make a two part question.
88 (13)
(14) 10/28/2021 - Licensee was unable to write an SRO only question to the origi nal K/A.
H 3
N S
K/A 058G2.2.40 T1 G1 Question is Satisfactory.
89 (14)
H 2
X X
M E
K/A 059G2.4.35 T1 G2
: 1. The second part question does not seem to be related to the K/A in any way. This appears to be a tack on to make a two part question.
10/28/2021 - Licensee was unable to write an SRO only question to the original K/A.
Selected K/A G2.4.30. Licensee submitted a different question for the new K/A. The question is Satisfactory.
Selected K/A G2.4.30. Licensee submitted a different question for the new K/A. The question is Satisfactory.
90 (15)
H 2
B S
K/A 062AA2.05 T1 G1 Question was used on 2014 Vogtle NRC exam.
K/A 062AA2.05 T1 G1 Question was used on 2014 Vogtle NRC exam.
90 H 2 B S Question is Satisfactory.
Question is Satisfactory.  
 
(15)
Vogtle 1&2 2021-301 Initial Operator License Exam
: 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job-Minutia #/ Back -Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only
 
K/A 063G2.2.25 T2 G1 91 F 2 M S Question is Satisfactory.
(16)
K/A 103A2.10 T2 G1 92 F 2 X M U Question is Unsatisfactory due to not meeting the K/A. The question does not relate to the Containment system.
(17) 10/28/2021 - Licensee submitted a different question that matched the K/A. The question is Satisfactory.
K/A G2.1.14 T3 93 F 2 X X N E 1. I see where the reactor startup is required to be announced to plant personnel in 12003-1, but do not see where the Shift Supervisor is required to announce Mode 2 specifically. This (18) is a potential cue since pulling control banks is what causes the mode change.


Vogtle 1&2 2021-301 Initial Operator License Exam Q#
: 1.
LOK (F/H)
: 2.
LOD (1-5)
: 3. Psychometric Flaws
: 4. Job Content Flaws
: 5. Other
: 6.
B/M/N
: 7.
U/E/S
: 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
#/
units Back-ward Q=
K/A SRO Only 91 (16)
F 2
M S
K/A 063G2.2.25 T2 G1 Question is Satisfactory.
92 (17)
F 2
X M
U K/A 103A2.10 T2 G1 Question is Unsatisfactory due to not meeting the K/A. The question does not relate to the Containment system.
10/28/2021 - Licensee submitted a different question that matched the K/A. The question is Satisfactory.
93 (18)
F 2
X X
N E
K/A G2.1.14 T3
: 1. I see where the reactor startup is required to be announced to plant personnel in 12003-1, but do not see where the Shift Supervisor is required to announce Mode 2 specifically. This is a potential cue since pulling control banks is what causes the mode change.
10/28/2021 - Licensee was unable to write an SRO only question to the original K/A.
10/28/2021 - Licensee was unable to write an SRO only question to the original K/A.
Selected K/A G2.1.8. Licensee submitted a different question for the new K/A. The question is Satisfactory.
Selected K/A G2.1.8. Licensee submitted a different question for the new K/A. The question is Satisfactory.
K/A G2.1.39 T3 94 F 2 X B E 1. Choice A is not credible when power was initially at 100% and is now rising.
94 (19)
 
F 2
(19) 10/28/2021 - Licensee developed a two part question to address the concerns as listed above. The new question is Satisfactory.
X B
K/A G2.2.05 T3 95 F 2 X M U 1. Question is Unsatisfactory due to more than on non -credible distractor. Replacing with a solid blue window is not credible. A semi -annual audit is also not very credible for disabled (20) annunciators. With those distractors, this question is not discriminating at all.
E K/A G2.1.39 T3
 
: 1. Choice A is not credible when power was initially at 100% and is now rising.
10/28/2021 - Licensee developed a two part question to address the concerns as listed above. The new question is Satisfactory.
95 (20)
F 2
X M
U K/A G2.2.05 T3
: 1. Question is Unsatisfactory due to more than on non-credible distractor. Replacing with a solid blue window is not credible. A semi-annual audit is also not very credible for disabled annunciators. With those distractors, this question is not discriminating at all.
10/28/2021 - Licensee changed the distractors to address the concerns as listed above. The question is now Satisfactory.
10/28/2021 - Licensee changed the distractors to address the concerns as listed above. The question is now Satisfactory.
96 (21)
H 2
B S
K/A G2.2.23 T3 Question #21 on 2017 Vogtle SRO NRC exam.
K/A G2.2.23 T3 Question #21 on 2017 Vogtle SRO NRC exam.
96 H 2 B S Question is Satisfactory.
Question is Satisfactory.
(21)
97 (22)
 
F 2
K/A G2.3.14 T3 97 F 2 M S Question is Satisfactory.
M S
(22)
K/A G2.3.14 T3 Question is Satisfactory.
K/A G2.4.18 T3 98 F 2 B S Question is Satisfactory.
98 (23)
(23)
F 2
B S
K/A G2.4.18 T3 Question is Satisfactory.
99 (24)
F 2
B S
K/A G2.4.26 T3 Question was used on 2015 Vogtle NRC exam.
K/A G2.4.26 T3 Question was used on 2015 Vogtle NRC exam.
99 F 2 B S Question is Satisfactory.
Question is Satisfactory.
(24)
100 (25)
 
H 2
K/A WE13A2.04 T1 G2 100 H 2 M S Question is Satisfactory.
M S
(25)
K/A WE13A2.04 T1 G2 Question is Satisfactory.  
Vogtle 1&2 2021-301 Initial Operator License Exam


Instructions
Vogtle 1&2 2021-301 Initial Operator License Exam Instructions
[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]
[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]
: 1. Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.
: 1.
: 2. Enter the level of difficulty (LOD) of each question using a 1 - 5 (easy - difficult) rating scale (questions in the 2 - 4 range are acceptable).
Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.
: 3. Check the appropriate box if a psychometric flaw is identified:
: 2.
* The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
Enter the level of difficulty (LOD) of each question using a 1 - 5 (easy - difficult) rating scale (questions in the 2 - 4 range are acceptable).
* The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).
: 3.
* The answer choices are a collection of unrelated true/false statements.
Check the appropriate box if a psychometric flaw is identified:
* The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
* One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).
: 4. Check the appropriate box if a job content error is identified:
The answer choices are a collection of unrelated true/false statements.
* The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).
The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
* The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).
One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
* The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
: 4.
* The question requires reverse logic or application compared to the job requirements.
Check the appropriate box if a job content error is identified:
: 5. Check questions that are sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).
The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).
: 6. Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.
The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).
: 7. Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
: 8. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).}}
The question requires reverse logic or application compared to the job requirements.
: 5.
Check questions that are sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).
: 6.
Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.
: 7.
Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
: 8.
At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).}}

Latest revision as of 19:17, 27 November 2024

301 Exam Administrative Items (2 Year Delayed Release) (ADAMS-2A-3)
ML22010A199
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 01/10/2022
From:
NRC/RGN-II
To:
References
Download: ML22010A199 (46)
v • d • e


Text

____________________________________________________________________________

ES-301 Administrative Topics Outline Form ES-301-1 ES-301-1 (Revision 11)

Facility: ___Vogtle 1 & 2_____

Date of Examination: _11/15/2021_

Examination Level: RO SRO Operating Test Number: _2021-301_

Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations R, M

a. V-NRC-JP-14005-ILT23: Determine keff with All Shutdown Bank Rods Withdrawn in Preparation for Reactor Startup

==

Description:==

Unit 2 is performing a reactor startup following a reactor trip from steady state, 100% reactor power. Per 12003-2, Reactor Startup (Mode 3 to Mode 2), the applicant will be required to calculate keff for the given conditions using 14005-2, Shutdown Margin and keff Calculations, Data Sheet 3, and the Plant Technical Data Book and then determine if keff meets the acceptance criterion.

G2.1.43 RO 4.1 Conduct of Operations R, M

b. V-NRC-JP-19263-ILT23: Determine Maximum Allowable Venting Time for Venting Voids in the Reactor Vessel

==

Description:==

Unit 1 reactor tripped due to a LOCA.

RCS pressure is recovering and the crew is making preparations to vent the reactor vessel by performing 19263-1, Response to Voids in Reactor Vessel. The applicant will be provided with pictures of various Control Board instruments, and will be directed to calculate the maximum allowable venting time using 19263-1,, Instructions for Determining Venting Time.

G2.1.25 RO 3.9 Equipment Control R, M

c. V-NRC-JP-14915-ILT23: Perform Quadrant Power Tilt Ratio (QPTR) Surveillance for Inoperable QPTR Monitor

==

Description:==

The Unit 2 QPTR Monitor Alarm is declared inoperable. Using the Power Range NI data provided and the Plant Technical Data Book, the applicant will be required to calculate the current QPTR using 14915-2, Special Conditions Surveillance Logs, Data Sheet 8, Quadrant Power Tilt Ratio. The applicant will then determine that the calculated QPTR does not meet the acceptance criterion.

G2.2.12 RO 3.7 ML22010A199

ES-301 Administrative Topics Outline Form ES-301-1 ES-301-1 (Revision 11)

Radiation Control R, P

d. V-NRC-JP-NMP-HP-001-ILT23: Assess Radiological Conditions, Calculate Projected Dose to Determine Lowest Dose Route, and Determine if Task Can Be Performed Without Exceeding the Task Dose Limit

==

Description:==

An operator will be dispatched to manually open an MOV in the Unit 1 RHR Pump Room. The applicant will be given two possible routes to the valve, the radiological conditions associated with each route, and the time required to complete the task. Two maps will also be provided that include the RHR A Heat Exchanger Rooms and the RHR A Pump Rooms, so the applicant must select the correct dose rate based on the location of the task. The applicant will then be directed to calculate the lowest dose route based on the projected dose to the operator and determine if the task can be performed without exceeding the established dose limit.

G2.3.12 RO 3.2 Emergency Plan N/A N/A NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

  • Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 ES-301-1 (Revision 11)

Facility: ___Vogtle 1 & 2_____

Date of Examination: _11/15/2021_

Examination Level: RO SRO Operating Test Number: _2021-301_

Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations R, M

a. V-NRC-JP-14228-ILT23: Review and Evaluate Monthly Surveillance Logs 14228-1.

==

Description:==

Unit 1 is at 100% reactor power. OATC has just completed 14228-1, Operations Monthly Surveillance Logs. The applicant is directed to perform a review of the Monthly Surveillance Logs for errors and determine if any Tech Specs are not met. There will be two out of spec readings. One for accumulator boron concentration and one for accumulator level. The applicant will then be required to determine the applicable Tech Spec / TRM Required Actions.

G2.1.2 SRO 4.4 Conduct of Operations R, M

b. V-NRC-JP-19200-HL23: Evaluate Critical Safety Function Status Trees (CSFSTs) with an Inoperable Integrated Plant Computer (IPC)

==

Description:==

Unit 1 reactor tripped from full power, and the crew transitioned from 19000-1, Reactor Trip or Safety Injection. The applicant will be directed to monitor and evaluate all CSFSTs, identify the highest priority critical safety function, and determine any required procedure transition using 19200-1, Critical Safety Function Status Trees. With the IPC not available, the applicant will be given data for multiple parameters to be used in the evaluation.

G2.1.7 SRO 4.7

ES-301 Administrative Topics Outline Form ES-301-1 ES-301-1 (Revision 11)

Equipment Control R, M

c. V-NRC-JP-14915-ILT23: Perform Quadrant Power Tilt Ratio (QPTR) Surveillance for Inoperable QPTR Monitor and Evaluate Tech Spec / TRM Required Actions

==

Description:==

The Unit 2 QPTR Monitor Alarm is declared inoperable. Using the Power Range NI data provided and the Plant Technical Data Book, the applicant will be required to calculate the current QPTR using 14915-2, Special Conditions Surveillance Logs, Data Sheet 8, Quadrant Power Tilt Ratio. Based on the calculation results, the applicant will determine what Tech Spec / TRM Required Actions are required to be taken.

The calculated QPTR will not meet the Tech Spec requirement and will require a Unit 2 reactor power reduction within two hours.

G2.2.45 SRO 4.7 Radiation Control R, D

d. V-NRC-JP-NMP-EP-144-ILT23: Assess Radiological Conditions in a Declared Emergency and Review and Approve Emergency Exposure Authorizations

==

Description:==

During a General Emergency, three System Operators are to be dispatched to operate vital equipment. The applicant will be given the component identifier, a room map with radiological conditions, and three completed NMP-EP-144-F02, Emergency Exposure Authorizations, for the System Operators. The applicant, serving as the Emergency Director, will be directed to calculate the projected dose to the System Operators and to review and approve, or disapprove if required, the three Emergency Exposure Authorizations in accordance with NMP-EP-144-F02. One of the Emergency Exposure Permits will be completed incorrectly and should not be approved.

G2.3.14 SRO 3.8 Emergency Plan R, D

e. V-NRC-JP-NMP-EP-141-ILT23: Evaluate Conditions on Both Units and Determine the Highest Emergency Event Classification

==

Description:==

Unit 1 is initially at 100% reactor power with Unit 2 in Mode 5. Using the conditions provided for both units that lead to classifiable plant events, the applicant will be directed to determine the highest emergency classification level for the given conditions using NMP-EP-141, Event Classification, and NMP-EP-141-F01, Emergency Classification Determination. This JPM is Time Critical.

G2.4.41 SRO 4.6

ES-301 Administrative Topics Outline Form ES-301-1 ES-301-1 (Revision 11)

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

  • Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ES-301-2 (Revision 11)

Facility: ___Vogtle 1 & 2___

Date of Examination: _11/15/2021_

Exam Level: RO SRO-I SRO-U Operating Test Number: _2021-301_

Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System / JPM Title Type Code*

Safety Function

a. V-NRC-JP-14410-ILT23: Perform Control Rod Shutdown Bank Operability Test

==

Description:==

Unit 1 is at 100% reactor power. Control rod operability testing is in progress. The Control Bank rods have been successfully tested using 14410-1, Control Rod Operability Test, so the applicant will be directed to perform the control rod operability test on the Shutdown Banks. As Shutdown Bank A rods are being withdrawn following the 10 step insertion, a control rod will drop, which will require the applicant to enter 18003-C, Rod Control System Malfunction. After entering 18003-C, a second control rod will drop, which will require a manual reactor trip.

(RO / SRO-I) 001A2.24 RO 3.5 SRO 4.1 A, M, S 1

b. V-NRC-JP-19014-ILT23: Transfer ECCS Pumps to Hot Leg Recirculation

==

Description:==

Unit 1 reactor trip and SI occurred due to a large break LOCA approximately 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ago. The ECCS pumps are operating and are aligned for cold leg recirculation. The applicant will be directed to re-align all ECCS pumps for hot leg recirculation using 19014-1, Transfer to Hot Leg Recirculation. During the RHR re-alignment, 1HV-8840, RHR to Hot Leg Isolation, will not open, so the applicant will be required to restore both RHR Trains to cold leg recirculation and then align both SI Trains for hot leg recirculation.

(RO / SRO-I / SRO-U) 011EA1.13 RO/SRO 4.3 A, EN, L, M, S 3

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ES-301-2 (Revision 11)

c. V-NRC-JP-19231-ILT23: Establish RCS Bleed and Feed Following a Loss of Secondary Heat Sink

==

Description:==

Unit 1 reactor was manually tripped following a low suction pressure trip of both MFPs. No AFW was available, so the crew entered 19231-1, Response to Loss of Secondary Heat Sink. The applicant will be directed to continue performing 19231-1 and to establish bleed and feed for RCS heat removal. The applicant will be required to start one CCP or SI pump, which should have automatically started, to establish minimum feed flow. Also, when establishing the bleed path, one pressurizer PORV will not open, which will require the reactor vessel head vent valves to be opened to provide an additional bleed path.

(RO / SRO-I / SRO-U)

WE05EA1.11 RO/SRO 3.5 A, L, M, S 4P

d. V-NRC-JP-13601-ILT23: Transfer RCS Temperature Control from the ARVs to the Steam Dumps

==

Description:==

Unit 1 is in Mode 3 and preparing the secondary systems for a reactor startup. RCS temperature is being controlled by the SG ARVs in manual. To continue with start-up preparations, the applicant will be directed to manually transfer RCS temperature control from the SG ARVs to the Steam Dumps using Section 4.4.7.3 of 13601-1, Steam Generator and Main Steam Operation, and then control RCS temperature at 557 +/-2 F.

(RO / SRO-I) 041A4.02 RO/SRO 3.6 D, L, S 4S

e. V-NRC-JP-13130-ILT23: Reduce Containment Hydrogen Concentration Using the Post-LOCA Containment Hydrogen Purge System

==

Description:==

Unit 1 reactor trip and SI occurred due to a LOCA. The crew is performing 19010-1, Loss of Reactor or Secondary Coolant.

Attempts to lower hydrogen concentration in containment using Service Air dilution were not successful, so the applicant will be required to place the Post-LOCA Containment Hydrogen Purge system in operation to reduce hydrogen concentration in the containment atmosphere using 13130-1, Post-Accident Hydrogen Control.

(RO / SRO-I / SRO-U) 028A2.02 RO 3.2 SRO 3.4 D, EN, L, S 5

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ES-301-2 (Revision 11)

f.

V-NRC-JP-13427-ILT23: Discontinue Parallel Operation by Removing DG1A from Bus 1AA02

==

Description:==

Unit 1 is at 100% reactor power. DG1A is operating in parallel with RAT 1A for a post-maintenance test. The test is complete, so the applicant will be required to discontinue parallel operation by transferring the remaining load to RAT 1A and removing DG1A from bus 1AA02 using 13427A-1, 4160 VAC Bus 1AA02 1E Electrical Distribution System. When the applicant begins the DG1A load reduction, ALB35-D06 DG1A GEN UNDER FREQ will be received in conjunction with indication of low bus frequency. The Annunciator Response Procedure will direct the applicant to verify bus frequency is low and then trip the DG1A output breaker and stop the DG1A engine.

(RO / SRO-I) 064A4.06 RO/SRO 3.9 A, D, P, S 6

g. V-NRC-JP-13125-ILT23: Place Containment Main (Pre-access)

Purge in Service

==

Description:==

Unit 1 is in Mode 5 for an outage. Chemistry has requested that Containment Main Purge be placed in service. With the containment Equipment Hatch open, the applicant will be directed to place the Main Purge in service using 13125-1, Containment Purge System. Based on the current operating Mode and the Equipment Hatch configuration, the applicant will be required to align dampers and start the Main Purge Exhaust Fan, but the Main Purge Supply Fan will be required to remain off.

(RO / SRO-I) 029A4.01 RO/SRO 2.7 L, M, S 8

h. V-NRC-JP-13301-ILT23: Respond to Control Room High Radiation

==

Description:==

Unit 1 is at 100% reactor power with the applicant assigned to perform the duties of the Unit Operator. High radiation alarms will be received when radiation is detected in the Control Room ventilation system. Control Room Isolation will fail to automatically actuate, so the applicant will be required to manually align the Control Room ventilation system using 13301-C, CBCR Normal HVAC and Emergency Filtration System.

(RO) 050A2.03 RO 3.5 SRO 3.8 D, EN, S 9

RO ONLY

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ES-301-2 (Revision 11)

In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i.

V-NRC-JP-16900-ILT23: Place RWST Sludge Mixing Isolation Valve on the Jack

==

Description:==

Unit 2 is at 100% reactor power with the RWST Sludge Mixing system in service for water temperature control. A maintenance activity will temporarily remove DC power to a Sludge Mixing isolation valve solenoid. To keep Sludge Mixing in service during the maintenance activity, the applicant will be directed to place the RWST Sludge Mixing isolation valve on the jack using 16900-C, Air Operated Valve Manual Jack Operation.

(RO / SRO-I / SRO-U) 006G2.1.30 RO 4.4 SRO 4.0 D, EN, R 2

j.

V-NRC-JP-13145-ILT23: Perform a Local Emergency Stop of DG1A

==

Description:==

Unit 1 is at 100% reactor power. DG1A is running in Unit Mode for testing. During the test run, personnel in the DG1A Building report damage to the turbocharger is beginning to release exhaust gases into the building. The applicant will be directed to emergency stop DG1A from the local Engine Control Panel and then reset the emergency stop signal by performing Section 4.4.2 of 13145A-1, Diesel Generator Train A.

(RO / SRO-I) 062A2.18 RO 4.0 SRO 4.3 D, E, EN 6

k. V-NRC-JP-18038-ILT23: Establish Local Control of Train A and Train B 4160 VAC Switchgears Following a Control Room Evacuation

==

Description:==

The Unit 2 Control Room has been evacuated and local control has been established at Shutdown Panel A and Shutdown Panel B. The applicant will be directed to establish local control of the Train A and Train B 4160 VAC switchgears and check ACCW pump status using 18038-2, Operation from Remote Shutdown Panels. The applicant will determine that no ACCW pump is running, so the stopping the RCPs and isolating letdown will be required.

(RO / SRO-I / SRO-U) 068AA1.12 RO/SRO 4.2 A, D, E, L 8

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ES-301-2 (Revision 11)

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1 / 1 / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: Vogtle 1,2 Exam Date: November 15, 2021 1

2 3

Attributes 4

Job Content 5

6 RO Admin JPMs ADMIN Topic and K/A LOD (1-5)

U/E/S Explanation I/C Cues Critical Scope Overlap Perf.

Key Minutia Job Link Focus Steps (N/B)

Std.

a V-NRC-JP-14005-ILT23 COO G2.1.43 2

S See attached comments.

b V-NRC-JP-19263-ILT23 COO G2.1.25 2

X X

E See attached comments.

c V-NRC-JP-14915-ILT23 EC G2.2.12 2

X X

E See attached comments.

d V-NRC-JP-NMP-HP-001-ILT23 Rad G2.3.12 2

X E

See attached comments.

ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: Vogtle 1,2 Exam Date: November 15, 2021 1

2 3

Attributes 4

Job Content 5

6 SRO Admin JPMs ADMIN Topic and K/A LOD (1-5)

U/E/S Explanation I/C Cues Critical Scope Overlap Perf.

Key Minutia Job Link Focus Steps (N/B)

Std.

a V-NRC-JP-14005-ILT23 COO G2.1.43 2

X X

U See attached comments.

a V-NRC-JP-14228-ILT23 COO G2.1.2 2

S See attached comments.

b V-NRC-JP-19263-ILT23 COO G2.1.25 2

X X

U See attached comments.

b V-NRC-JP-19200-HL23 COO G2.1.7 2

S See attached comments.

c V-NRC-JP-14915-ILT23 EC G2.2.45 2

X X

E See attached comments.

d V-NRC-JP-NMP-EP-144-ILT23 Rad G2.3.14 2

X X

E See attached comments.

e V-NRC-JP-NMP-EP-141-ILT23 EP G2.4.41 2

X E

See attached comments.

ES-301 Operating Test Review Worksheet Form ES-301-7 Simulator/In Plant JPMs Safety Function and K/A LOD (1-5)

Attributes 4

Job Content U/E/S Explanation I/C Focus Cues Critical Steps Scope (N/B)

Overlap Perf.

Std.

Key Minutia Job Link a

V-NRC-JP-14410-ILT23 SF 1 001A2.24 2

S See attached comments.

b V-NRC-JP-19014-ILT23 SF 3 011EA1.13 2

S See attached comments.

c V-NRC-JP-19231-ILT23 SF 4P WE05EA1.11 2

S See attached comments.

d V-NRC-JP-13601-ILT23 SF 4S 041A4.02 2

S See attached comments.

e V-NRC-JP-13130-ILT23 SF 5 028A2.02 2

S See attached comments.

f V-NRC-JP-13427-ILT23 SF 6 064A4.06 2

S See attached comments.

g V-NRC-JP-13125-ILT23 SF 8 029A4.01 2

S See attached comments.

h V-NRC-JP-13301-ILT23 SF 9 050A2.03 2

S See attached comments.

I V-NRC-JP-16900-ILT23 SF 2 006G2.1.30 2

S See attached comments.

j V-NRC-JP-13145-ILT23 SF 6 062A2.18 2

S See attached comments.

k V-NRC-JP-18038-ILT23 SF 8 068AA1.12 2

S See attached comments.

ES-301 4

Form ES-301-7 Instructions for Completing This Table:

Check or mark any item(s) requiring a comment and explain the issue in the space provided using the guide below.

1.

Check each JPM for appropriate administrative topic requirements (COO, EC, Rad, and EP) or safety function requirements and corresponding K/A. Mark in column 1.

(ES-301, D.3 and D.4)

2.

Determine the level of difficulty (LOD) using an established 1-5 rating scale. Levels 1 and 5 represent an inappropriate (low or high) discriminatory level for the license that is being tested. Mark in column 2 (Appendix D, C.1.f)

3.

In column 3, Attributes, check the appropriate box when an attribute is not met:

The initial conditions and/or initiating cue is clear to ensure the operator understands the task and how to begin. (Appendix C, B.4)

The JPM contains appropriate cues that clearly indicate when they should be provided to the examinee. Cues are objective and not leading. (Appendix C, D.1)

All critical steps (elements) are properly identified.

The scope of the task is not too narrow (N) or too broad (B).

Excessive overlap does not occur with other parts of the operating test or written examination. (ES-301, D.1.a, and ES-301, D.2.a)

The task performance standard clearly describes the expected outcome (i.e., end state). Each performance step identifies a standard for successful completion of the step.

A valid marked up key was provided (e.g., graph interpretation, initialed steps for handouts).

4.

For column 4, Job Content, check the appropriate box if the job content flaw does not meet the following elements:

Topics are linked to the job content (e.g., not a disguised task, task required in real job).

The JPM has meaningful performance requirements that will provide a legitimate basis for evaluating the applicant's understanding and ability to safely operate the plant. (ES-301, D.2.c)

5.

Based on the reviewers judgment, is the JPM as written (U)nacceptable (requiring repair or replacement), in need of (E)nhancement, or (S)atisfactory? Mark the answer in column 5.

6.

In column 6, provide a brief description of any (U)nacceptable or (E)nhancement rating from column 5.

Save initial review comments and detail subsequent comment resolution so that each exam-bound JPM is marked by a (S)atisfactory resolution on this form.

ES-301 5

Form ES-301-7 Facility: Vogtle 1,2 Scenario: 1 Exam Date: November 15, 2021 Event Realism/Cred.

Required Actions Verifiable actions LOD TS CTs Scen.

Overlap U/E/S Explanation 1

S See attached comments.

2 X

S See attached comments.

3 S

See attached comments.

4 X

S See attached comments.

5 S

See attached comments.

6 X

S See attached comments.

7 S

See attached comments.

8 X

S See attached comments.

9 E

See attached comments.

ES-301 6

Form ES-301-7 Facility: Vogtle 1,2 Scenario: 2 Exam Date: November 15, 2021 1

2 3

4 5

6 7

8 9

10 Event Realism/Cred.

Required Actions Verifiable actions LOD TS CTs Scen.

Overlap U/E/S Explanation 1

S See attached comments.

2 S

See attached comments.

3 S

See attached comments.

4 S

See attached comments.

5 X

X S

See attached comments.

6 X

S See attached comments.

7 S

See attached comments.

8 X

S See attached comments.

9 S

See attached comments.

10 S

See attached comments.

ES-301 7

Form ES-301-7 Facility: Scenario: Exam Date: November 15, 2021 1

2 3

4 5

6 7

8 9

10 Event Realism/Cred.

Required Actions Verifiable actions LOD TS CTs Scen.

Overlap U/E/S Explanation Facility: Vogtle 1,2 Scenario: 3 Exam Date: November 15, 2021 1

2 3

4 5

6 7

8 9

10 Event Realism/Cred.

Required Actions Verifiable actions LOD TS CTs Scen.

Overlap U/E/S Explanation 1

S See attached comments.

2 X

S See attached comments.

3 X

S See attached comments.

4 S

See attached comments.

5 S

See attached comments.

6 X

S See attached comments.

7 S

See attached comments.

8 S

See attached comments.

9 S

See attached comments.

10 X

S See attached comments.

ES-301 8

Form ES-301-7 Facility: Vogtle 1,2 Scenario: 4 Exam Date: November 15, 2021 1

2 3

4 5

6 7

8 9

10 Event Realism/Cred.

Required Actions Verifiable actions LOD TS CTs Scen.

Overlap U/E/S Explanation 1

S See attached comments.

2 X

E See attached comments.

3 S

See attached comments.

4 S

See attached comments.

5 S

See attached comments.

6 X

S See attached comments.

7 XX E

See attached comments.

8 S

See attached comments.

9 S

See attached comments.

10 S

See attached comments.

ES-301 9

Form ES-301-7 Facility: Scenario: Exam Date: November 15, 2021 1

2 3

4 5

6 7

8 9

10 Event Realism/Cred.

Required Actions Verifiable actions LOD TS CTs Scen.

Overlap U/E/S Explanation Facility: Vogtle 1,2 Scenario: 5 Exam Date: November 15, 2021 1

2 3

4 5

6 7

8 9

10 Event Realism/Cred.

Required Actions Verifiable actions LOD TS CTs Scen.

Overlap U/E/S Explanation 1

S See attached comments.

2 X

X S

See attached comments.

3 X

S See attached comments.

4 X

S See attached comments.

5 S

See attached comments.

6 S

See attached comments.

7 S

See attached comments.

8 X

S See attached comments.

9 S

See attached comments.

ES-301 10 Form ES-301-7 Instructions for Completing This Table:

Use this table for each scenario for evaluation.

2 Check this box if the events are not related (e.g., seismic event followed by a pipe rupture) OR if the events do not obey the laws of physics and thermodynamics.

3, 4 In columns 3 and 4, check the box if there is no verifiable or required action, as applicable. Examples of required actions are as follows: (ES-301, D.5f) opening, closing, and throttling valves starting and stopping equipment raising and lowering level, flow, and pressure making decisions and giving directions acknowledging or verifying key alarms and automatic actions (Uncomplicated events that require no operator action beyond this should not be included on the operating test unless they are necessary to set the stage for subsequent events. (Appendix D, B.3).)

5 Check this box if the level of difficulty is not appropriate.

6 Check this box if the event has a TS.

7 Check this box if the event has a critical task (CT). If the same CT covers more than one event, check the event where the CT started only.

8 Check this box if the event overlaps with another event on any of the last two NRC examinations. (Appendix D, C.1.f) 9 Based on the reviewers judgment, is the event as written (U)nacceptable (requiring repair or replacement), in need of (E)nhancement, or (S)atisfactory? Mark the answer in column 9.

10 Record any explanations of the events here.

In the shaded boxes, sum the number of check marks in each column.

In column 1, sum the number of events.

In columns 2-4, record the total number of check marks for each column.

In column 5, based on the reviewer's judgement, place a checkmark only if the scenario's LOD is not appropriate.

In column 6, TS are required to be 2 for each scenario. (ES-301, D.5.d)

In column 7, preidentified CTs should be 2 for each scenario. (Appendix D; ES-301, D.5.d; ES-301-4)

In column 8, record the number of events not used on the two previous NRC initial licensing exams. A scenario is considered unsatisfactory if there is < 2 new events. (ES-301, D.5.b; Appendix D, C.1.f)

In column 9, record whether the scenario as written (U)nacceptable, in need of (E)nhancement, or (S)atisfactory from column 11 of the simulator scenario table.

ES-301 11 Form ES-301-7 Facility: Vogtle 1,2 Exam Date: November 15, 2021 Scenario 1

2 3

4 5

6 7

8 11 Event Totals Events Unsat.

TS Total TS Unsat.

CT Total CT Unsat.

% Unsat.

Scenario Elements U/E/S Explanation 1

9 0

2 0

2 0

0 E

2 10 0

2 0

2 0

0 S

3 10 0

2 0

2 0

0 S

4 10 0

2 0

2 0

0 E

5 9

0 3

0 2

0 0

S Instructions for Completing This Table:

Check or mark any item(s) requiring comment and explain the issue in the space provided.

1, 3, 5 For each simulator scenario, enter the total number of events (column 1), TS entries/actions (column 3), and CTs (column 5).

This number should match the respective scenario from the event-based scenario tables (the sum from columns 1, 6, and 7, respectively).

2, 4, 6 For each simulator scenario, evaluate each event, TS, and CT as (S)atisfactory, (E)nhance, or (U)nsatisfactory based on the following criteria:

a.

Events. Each event is described on a Form ES-D-2, including all switch manipulations, pertinent alarms, and verifiable actions. Event actions are balanced between at-the-controls and balance-of-plant applicants during the scenario. All event-related attributes on Form ES-301-4 are met. Enter the total number of unsatisfactory events in column 2.

b.

TS. A scenario includes at least two TS entries/actions across at least two different events. TS entries and actions are detailed on Form ES-D-2. Enter the total number of unsatisfactory TS entries/actions in column 4. (ES-301, D.5d)

c.

CT. Check that a scenario includes at least two preidentified CTs. This criterion is a target quantitative attribute, not an absolute minimum requirement. Check that each CT is explicitly bounded on Form ES-D-2 with measurable performance standards (see Appendix D). Enter the total number of unsatisfactory CTs in column 6.

7 In column 7, calculate the percentage of unsatisfactory scenario elements:

8 If the value in column 7 is > 20%, mark the scenario as (U)nsatisfactory in column 8. If column 7 is 20%, annotate with (E)nhancement or (S)atisfactory.

9 In column 9, explain each unsatisfactory event, TS, and CT. Editorial comments can also be added here.

Save initial review comments and detail subsequent comment resolution so that each exam-bound scenario is marked by a (S)atisfactory resolution on this form.

2 + 4 + 6 1 + 3 + 5100%

ES-301 12 Form ES-301-7 Site name: Vogtle 1,2 Exam Date: November 15, 2021 OPERATING TEST TOTALS Total Total Unsat.

Total Total Unsat.

Explanation Edits Sat.

Admin.

JPMs 9

2 6

1 22 Sim./In-Plant JPMs 11 0

0 11 0

Scenarios 5

0 2

3 0

Op. Test Totals:

25 2

8 15 8

Instructions for Completing This Table:

Update data for this table from quality reviews and totals in the previous tables and then calculate the percentage of total items that are unsatisfactory and give an explanation in the space provided.

1.

Enter the total number of items submitted for the operating test in the Total column. For example, if nine administrative JPMs were submitted, enter 9 in the Total items column for administrative JPMs.

For scenarios, enter the total number of simulator scenarios.

2.

Enter the total number of (U)nsatisfactory JPMs and scenarios from the two JPMs column 5 and simulator scenarios column 8 in the previous tables. Provide an explanation in the space provided.

3.

Enter totals for (E)nhancements needed and (S)atisfactory JPMs and scenarios from the previous tables. This task is for tracking only.

4.

Total each column and enter the amounts in the Op. Test Totals row.

5.

Calculate the percentage of the operating test that is (U)nsatisfactory (Op. Test Total Unsat.)/(Op. Test Total) and place this value in the bolded % Unsat. cell.

Refer to ES-501, E.3.a, to rate the overall operating test as follows:

  • satisfactory, if the Op. Test Total % Unsat. is 20%
  • unsatisfactory, if Op. Test Total % Unsat. is > 20%
6.

Update this table and the tables above with post-exam changes if the as-administered operating test required content changes, including the following:

  • The JPM performance standards were incorrect.
  • The administrative JPM tasks/keys were incorrect.
  • CTs were incorrect in the scenarios (not including postscenario critical tasks defined in Appendix D).
  • The EOP strategy was incorrect in a scenario(s).
  • TS entries/actions were determined to be incorrect in a scenario(s).

ES-301 13 Form ES-301-7 Vogtle 1,2 2021-301 NRC Exam Operating Test Review Comments A) RO Admin JPMs a) RO Admin JPM a i) JPM is Satisfactory. Will validate with an operator during on-site validation.

b) RO Admin JPM b i) The concept of the JPM is good. The body of the JPM is constructed so that there is only one critical step containing the final answer. The JPM needs to be constructed to follow the steps of attachment 3. You could make a note in the body of the JPM that the highlighted portions of the key are critical steps. Each intermediate calculation is a critical step needed to arrive at the final answer. This will prevent an applicant from getting the correct answer for the wrong reason. The key is good. Will validate with an operator during on-site validation.

ii) 10/28/2021 - Licensee made corrections to address the concerns as stated above. The JPM is now Satisfactory.

c) RO admin JPM c i) Same comment as listed above for RO Admin JPM b. Will validate with an operator during on-site validation.

ii) 10/28/2021 - Licensee made corrections to address the concerns as stated above. The JPM is now Satisfactory.

d) RO admin JPM d i) Need to put varied radiation levels for the other rooms/compartments on the map for each level.

Otherwise, this is just a simple high school math problem. Will validate with an operator during on-site validation.

ii) 10/28/2021 - Licensee made corrections to address the concerns as stated above. The JPM is now Satisfactory.

B) SRO Admin JPMs a) SRO Admin JPM a i) Simply reviewing a task that an RO performed and identifying an error does not meet the requirements for an SRO Admin JPM. The skill set required to perform this task is no different than the skill set used on RO Admin JPM a. Performing the calculation/review and then identifying the appropriate technical specification entry, procedure to direct, etc. would turn this type of JPM into an SRO Admin JPM. SRO Admin JPMs should test knowledge/skills above that required for an RO.

ii) 10/28/2021 - Licensee submitted a different conduct of operations JPM that tests an SRO Technical Specification evaluation. This JPM is Satisfactory.

b) SRO Admin JPM b i) Other that giving the SRO applicants the step number to compare parameters given in the initial condition, this JPM does not require any SRO knowledge above that of an RO. The SRO would read step 20 to the ROs and they would be the ones to get the information. This is not an SRO level Administrative JPM.

ii) 10/28/2021 - Licensee submitted a different JPM that tests SRO procedure direction. The JPM is Satisfactory.

c) SRO Admin JPM c i) See comments above for RO JPMs a and b concerning intermediate critical steps. Will validate with an operator during on-site validation.

ii) 10/28/2021 - Licensee made corrections to address the concerns as stated above. The JPM is now Satisfactory.

ES-301 14 Form ES-301-7 d) SRO Admin JPM d i) Do not need to tell the applicant the reference to use when approving the dose extensions in the initiating cue. Would somebody tell them that when they are the Emergency Director? It is on the form they are looking at anyway. Will validate with an operator during on-site validation.

ii) 10/28/2021 - Licensee made corrections to address the concerns as stated above. The JPM is now Satisfactory.

e) SRO Admin JPM e i) Need to add something to the cue stating something to the effect that Emergency Directors Judgement should not be used for the classification.

ii) 10/28/2021 - Licensee made corrections to address the concerns as stated above. The JPM is now Satisfactory.

C) Simulator/In-Plant JPMs a) Simulator JPM a i) JPM is Satisfactory. Will validate with an operator during on-site validation.

b) Simulator JPM b i) JPM is Satisfactory. Will validate with an operator during on-site validation.

c) Simulator JPM c i) JPM is Satisfactory. Will validate with an operator during on-site validation.

d) Simulator JPM d i) JPM is Satisfactory. Will validate with an operator during on-site validation.

e) Simulator JPM e i) JPM is Satisfactory. Will validate with an operator during on-site validation.

f) Simulator JPM f i) JPM is Satisfactory. Will validate with an operator during on-site validation.

g) Simulator JPM g i) JPM is Satisfactory. Will validate with an operator during on-site validation.

h) Simulator JPM h i) JPM is Satisfactory. Will validate with an operator during on-site validation.

i) In-Plant JPM i i) JPM is Satisfactory. Will validate with an operator during on-site validation.

j) In-Plant JPM j i) JPM is Satisfactory. Will validate with an operator during on-site validation.

k) In-Plant JPM k i) JPM is Satisfactory. Will validate with an operator during on-site validation.

D) Simulator Scenarios a) Scenario #1 i) Event 9 (page 26 of 37) - Do not believe the answer to step 6.b (PRZR PORVs-CLOSED) is yes. 1PV-455 failed open in previous event.

ii) Will validate with operators during on-site validation.

iii) 10/28/2021 - Licensee submitted correction to event 9. Scenario #1 is now Satisfactory.

b) Scenario #2 i) No concerns identified during in-office review. Will validate with operators during on-site validation.

ii) 10/28/2021 - Due to reduction in number of applicants, Scenario #2 is not needed for this operating test.

c) Scenario #3 i) No concerns identified during in-office review. Will validate with operators during on-site validation.

ES-301 15 Form ES-301-7 d) Scenario #4 i) Event 2 - Does not really have verifiable actions for the OATC as is stated on the event description on the ES-D-1. None are needed because credit is only being given to the SS for the TS call.

ii) Event 7 - Need to discuss if tripping reactor coolant pumps is really a critical task for this scenario. Is the scenario set up where RCS inventory will be less than the critical inventory during the run time of the scenario?

iii) Will validate with operators during on-site validation.

iv) 10/28/2021 - Licensee submitted correction to verifiable action statement. Licensee verified that tripping RCPs is a critical task based on Westinghouse Owners group criteria. Event 3 was changed to a heater drain pump trip due to some similar symptoms/actions between the ACCW pump trip which was previously in the scenario and Event 4. This scenario is now Satisfactory. Scenario #4 has been designated as the spare scenario and will only be run if necessary.

e) Scenario #5 i) No concerns identified during in-office review. Will validate with operators during on-site validation.

ES-401 PWR Examination Outline Form ES-401-2 Facility: Vogtle Units 1 & 2 Date of Exam: November 15, 2021 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

Total A2 G*

Total

1.

Emergency and Abnormal Plant Evolutions 1

3 3

3 N/A 3

3 N/A 3

18 3

3 6

2 1

1 1

2 2

2 9

2 2

4 Tier Totals 4

4 4

5 5

5 27 5

5 10

2.

Plant Systems 1

3 3

3 3

3 3

2 2

2 2

2 28 2

3 5

2 1

1 1

1 1

1 1

1 1

1 0

10 2

1 3

Tier Totals 4

4 4

4 4

4 3

3 3

3 2

38 8

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

2 3

4 7

3 3

1 3

2 2

1 2

Note: 1.

Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)

2.

The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points, and the SRO-only exam must total 25 points.

3.

Systems/evolutions within each group are identified on the outline. Systems or evolutions that do not apply at the facility should be deleted with justification. Operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

4.

Select topics from as many systems and evolutions as possible. Sample every system or evolution in the group before selecting a second topic for any system or evolution.

5.

Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6.

Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7.

The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.

8.

On the following pages, enter the K/A numbers, a brief description of each topic, the topics IRs for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. If fuel-handling equipment is sampled in a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2. (Note 1 does not apply). Use duplicate pages for RO and SRO-only exams.

9.

For Tier 3, select topics from Section 2 of the K/A catalog and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

G* Generic K/As These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.

These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.

ES-401 2

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR 000007 (EPE 7; BW E02&E10; CE E02)

Reactor Trip, Stabilization, Recovery / 1 X

EA1.05: Ability to operate and/or monitor NIs as they apply to a Reactor Trip -

3.9 1

000008 (APE 8) Pressurizer Vapor Space Accident / 3 X

AA2.06: Ability to determine and/or interpret the following as they apply to a Pressurizer Vapor Space Accident - PORV logic control under low-pressure conditions 3.0 2

000009 (EPE 9) Small Break LOCA / 3 X

G2.2.22: Knowledge of limiting conditions for operation and safety limits 4.0 3

000011 (EPE 11) Large Break LOCA / 3 X

X EK1.03: Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to a Large-Break LOCA -

Long-term containment of radioactivity G2.4.30 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator 4.1 4.1 4

76 000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 X

AA2.01: Ability to determine and/or interpret the following as they apply to Reactor Coolant Pump Malfunctions: Cause of RCP failure 3.5 77 000022 (APE 22) Loss of Reactor Coolant Makeup / 2 X

AK2.10: Knowledge of the relationship between Loss of Reactor Coolant Makeup and the following systems or components: PZR LCS 3.8 5

000025 (APE 25) Loss of Residual Heat Removal System / 4 X

G2.1.32: Ability to explain and apply system precautions, limitations, notes, or cautions 4.0 78 000026 (APE 26) Loss of Component Cooling Water / 8 X

AK3.02: Knowledge of the reasons for the following responses and/or actions as they apply to Loss of Component Cooling Water - The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS 3.9 6

000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 X

AA1.06: Ability to operate and/or monitor Operable control channels with a Pressurizer Pressure Control System Malfunction 3.6 7

000029 (EPE 29) Anticipated Transient Without Scram / 1 X

EA2.13: Ability to determine and/or interpret the following as they apply to an Anticipated Transient Without Scram: RCS cooldown or heatup 3.9 8

000038 (EPE 38) Steam Generator Tube Rupture / 3 X

G2.4.50: Ability to verify system alarm setpoints and operate controls identified in the alarm response procedure 4.2 9

000040 (APE 40; BW E05; CE E05; W E12)

Steam Line RuptureExcessive Heat Transfer / 4 X

AA2.01: Ability to determine and/or interpret the following as they apply to a Steamline Rupture; Occurrence and location of a steamline rupture from pressure and flow indications 4.0 79 000054 (APE 54; CE E06) Loss of Main Feedwater /4 X

AK1.02: Cause and effect relationships of feedwater introduction on a dry S/G (Loss of Main Feedwater) 4.0 10 000055 (EPE 55) Station Blackout / 6 X

EK2.04: Knowledge of the relationship between a Station Blackout and the following systems or components; AFW system 4.2 11

ES-401 3

Form ES-401-2 000056 (APE 56) Loss of Offsite Power / 6 X

AK3.01: Knowledge of the reasons for the following responses and/or actions as they apply to Loss of Offsite Power; Order and time to initiation of power for the load sequencer 3.6 12 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 X

AA1.04: Ability to operate and/or monitor the following as they apply to Loss of Vital AC Electrical Instrument Bus; RWST and VCT valves 3.8 13 000058 (APE 58) Loss of DC Power / 6 X

G2.2.40: Ability to apply TS with action statements of less than or equal to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 4.7 80 000062 (APE 62) Loss of Nuclear Service Water / 4 X

AA2.05: Ability to determine and/or interpret the following as they apply to Loss of Service Water; The normal values for the SWS-header flow rate and the flow rates to the components cooled by the SWS 3.0 81 000065 (APE 65) Loss of Instrument Air / 8 X

AA2.03: Ability to determine and/or interpret the following as they apply to Loss of Instrument Air; Location and isolation of leaks 4.0 14 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 X

G2.4.49: Ability to perform without reference to procedures those actions that require immediate operation of system components and controls 4.6 15 (W E04) LOCA Outside Containment / 3 X

EK1.05: Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to LOCA Outside Containment; Leakage accumulation in RHR pump area 3.6 16 (W E11) Loss of Emergency Coolant Recirculation / 4 X

EK2.04: Knowledge of the relationship between Loss of Emergency Coolant Recirculation and the following systems or components; Incore Temperature Monitoring (ITM) 3.8 17 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 X

EK3.16: Knowledge of the reasons for the following responses and/or actions as they apply to Loss of Secondary Heat Sink: Establishing maximum charging flow 3.5 18 K/A Category Totals:

3 3

3 3

3/3 3/3 Group Point Total:

18/6

ES-401 4

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR 000001 (APE 1) Continuous Rod Withdrawal / 1 NA NA 000003 (APE 3) Dropped Control Rod / 1 X

2.4.29: Knowledge of the emergency plan implementing procedures 4.4 82 000005 (APE 5) Inoperable/Stuck Control Rod / 1 X

AA1.05: Ability to operate and/or monitor the following as they apply to an Inoperable/Stuck Control Rod; RPI 3.8 19 000024 (APE 24) Emergency Boration / 1 NA NA 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 X

AA2.03: Ability to determine and/or interpret the following as they apply to a Pressurizer Level Control Malfunction; Charging flow 3.4 20 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 X

G2.4.2: Knowledge of system setpoints, interlocks, and automatic actions associated with emergency and abnormal operating procedure entry conditions 4.5 21 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 X

AK1.01: Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to Loss of Intermediate Range Nuclear Instrumentation; Effects of voltage changes on performance 2.9 22 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 X

AA2.05: Ability to determine and/or interpret the following as they apply to Fuel Handling Incidents: Containment isolation/closure 3.8 83 000037 (APE 37) Steam Generator Tube Leak / 3 NA NA 000051 (APE 51) Loss of Condenser Vacuum / 4 X

AK2.10: Knowledge of the relationship between Loss of Condenser Vacuum and the following systems or components:

Main turbine system 3.3 23 000059 (APE 59) Accidental Liquid Radwaste Release / 9 X

G2.4.30: Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator 4.1 84 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 NA NA 000061 (APE 61) Area Radiation Monitoring System Alarms

/ 7 NA NA 000067 (APE 67) Plant Fire On Site / 8 X

AK3.02: Knowledge of the reasons for the following responses and/or actions as they apply to Plant Fire on Site; Steps called out in the site fire protection plan, FPS manual, and fire zone manual 3.3 24 000068 (APE 68; BW A06) Control Room Evacuation / 8 NA NA

ES-401 5

Form ES-401-2 000069 (APE 69; W E14) Loss of Containment Integrity / 5 X

AA1.03: Ability to operate and/or monitor the following as they apply to a Loss of Containment Integrity; Fluid systems penetrating containment 3.5 25 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling /

4 NA NA 000076 (APE 76) High Reactor Coolant Activity / 9 X

AA2.04: Ability to determine and/or interpret the following as they apply to High Reactor Coolant Activity; High process radiation levels 3.2 26 000078 (APE 78*) RCS Leak / 3 X

G2.4.18: Knowledge of the specific bases for emergency and abnormal operating procedures 3.3 27 (W E01 & E02) Rediagnosis & SI Termination / 3 NA NA (W E13) Steam Generator Overpressure / 4 X

EA2.04: Ability to determine and /

or interpret the following as they apply to Steam Generator Overpressure; Feedwater isolation 3.7 85 (W E15) Containment Flooding / 5 NA NA (W E16) High Containment Radiation /9 NA NA K/A Category Point Totals:

1 1

1 2

2/2 2/2 Group Point Total:

9/4

ES-401 6

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)

System # / Name K

1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR 003 (SF4P RCP) Reactor Coolant Pump X

K1.10: Knowledge of the physical connections and/or cause and effect relationships between the Reactor Coolant Pump System and the following systems; RCS 3.9 28 004 (SF1; SF2 CVCS) Chemical and Volume Control X

X K2.02: Knowledge of electrical power supplies to the following: Pumps used to makeup to CVCS G2.2.37: Ability to determine operability or availability of safety-related equipment 3.0 4.6 29 86 005 (SF4P RHR) Residual Heat Removal X

X K3.02: Knowledge of the effect that a loss or malfunction of the Residual Heat Removal System will have on the following systems or system parameters; RCPS A2.05: Ability to (a) predict the impacts of the following on the Residual Heat Removal System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations; RHR heat exchanger malfunction 2.9 3.5 30 87 006 (SF2; SF3 ECCS) Emergency Core Cooling X

K4.13: Reset of containment isolation 3.7 31 007 (SF5 PRTS) Pressurizer Relief/Quench Tank X

K5.07: PZR safety tailpipe temperature variations with PRT/quench tank pressure 3.7 32 008 (SF8 CCW) Component Cooling Water X

X K6.09: SWS K1.14: RCPS 3.8 4.0 33 34 010 (SF3 PZR PCS) Pressurizer Pressure Control X

A1.09: Tail pipe temperature and acoustic monitors 3.6 35 012 (SF7 RPS) Reactor Protection X

A2.01: Ability to (a) predict the impacts of the following on the Reactor Protection System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations:

Faulty bistable operation 3.8 36 013 (SF2 ESFAS) Engineered Safety Features Actuation X

A3.11: Ability to monitor automatic operation of the Engineered Safety Features Actuation System, including; Safeguards equipment control 3.9 37 022 (SF5 CCS) Containment Cooling X

X A4.01: Ability to manually operate and/or monitor in the control room; CCS fans K4.04: Knowledge of Containment Cooling System design features and/or interlocks that provide for the following; Cooling of CRDMs 3.7 3.1 38 39 025 (SF5 ICE) Ice Condenser NA NA

ES-401 7

Form ES-401-2 026 (SF5 CSS) Containment Spray X G2.1.27: Knowledge of system purpose and/or function 3.9 40 039 (SF4S MSS) Main and Reheat Steam X

X K1.08: Knowledge of the physical connections and/or cause and effect relationships between the Main and Reheat Steam System and the following systems: MFW K6.11: SDS 3.6 3.4 41 42 059 (SF4S MFW) Main Feedwater X

K3.01: Knowledge of the effect that a loss or malfunction of the Main Feedwater System will have on the following systems or system parameters; CDS 3.2 43 061 (SF4S AFW)

Auxiliary/Emergency Feedwater X

K3.02: Knowledge of the effect that a loss or malfunction of the Auxiliary/Emergency Feedwater System will have on the following systems or system parameters; S/G system 4.3 44 062 (SF6 ED AC) AC Electrical Distribution X

K4.02: Knowledge of AC Electrical Distribution System design features and/or interlocks that provide for the following; Circuit breaker automatic trips 3.6 45 063 (SF6 ED DC) DC Electrical Distribution X

X K5.04: Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the DC Electrical Distribution System; System ground G 2.2.25: Knowledge of the bases in TS for limiting conditions for operation and safety limits (SRO Only) 2.9 4.2 46 88 064 (SF6 EDG) Emergency Diesel Generator X

X K6.09: Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the Emergency Diesel Generators; EDG building ventilation K5.06: Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the Emergency Diesel Generators; Unloading before securing an EDG 3.2 3.5 47 48 073 (SF7 PRM) Process Radiation Monitoring X

A1.01: Ability to predict and/or monitor changes in parameters associated with operation of the Process Radiation Monitoring System, including; Radiation levels 3.5 49 076 (SF4S SW) Service Water X

X A2.05: Ability to (a) predict the impacts of the following on the Service Water System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations; Sensor and detector failure K2.09: Knowledge of electrical power supplies to the following; Intake screens 2.6 2.6 50 51 078 (SF8 IAS) Instrument Air X

X A3.05: Ability to monitor automatic features of the Instrument Air System, including; Isolation of instrument air to containment K2.01; Knowledge of electrical power supplies to the following; Instrument air compressor 3.3 3.3 52 53

ES-401 8

Form ES-401-2 103 (SF5 CNT) Containment X

X G2.2.3: Knowledge of the design, procedural, and/or operational differences between units A2.10: FHS malfunctions 3.8 2.9 54 89 053 (SF1; SF4P ICS*) Integrated Control (IPC)

X X

A4.03; Ability to manually operate and/or monitor in the control room; S/G and/or reactor demand G2.1.30: Ability to locate and operate components, including local controls 3.9 4.0 55 90 K/A Category Point Totals:

3 3 3

3 3

3 2

2/

2 2

2 2/

3 Group Point Total:

28/5 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO/SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR 001 (SF1 CRDS) Control Rod Drive X K1.12: Knowledge of the physical connections and/or cause and effect relationships between the Control Rod Drive System and the following system; RPIS 3.8 56 002 (SF2; SF4P RCS) Reactor Coolant X

K3.03: Knowledge of the effect that a loss or malfunction of the Reactor Coolant System will have on the following systems or system parameters: CNT 4.0 57 011 (SF2 PZR LCS) Pressurizer Level Control NA NA 014 (SF1 RPI) Rod Position Indication NA NA 015 (SF7 NI) Nuclear Instrumentation X

A2.04: Ability to use procedures to correct, control, or mitigate the consequences of those abnormal operations: Effects on axial flux density of control rod alignment and sequencing, xenon production and decay, and boron versus control rod reactivity changes 3.7 91 016 (SF7 NNI) Nonnuclear Instrumentation X

K2.03: Knowledge of electrical power supplies to the following; Primary system control circuits 3.4 58 017 (SF7 ITM) In-Core Temperature Monitor NA NA 027 (SF5 CIRS) Containment Iodine Removal X

K5.01: Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the Containment Iodine Removal System:

Purpose of charcoal filters 2.9 59 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control X

K4.02: Knowledge of Hydrogen Recombiner and Purge Control System design features and/or interlocks that provide for the following; Containment hydrogen concentration monitoring 2.8 60

ES-401 9

Form ES-401-2 029 (SF8 CPS) Containment Purge X

K6.10: Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the Containment Purge System; Containment air cleanup and recirculation system 2.6 61 033 (SF8 SFPCS) Spent Fuel Pool Cooling NA NA 034 (SF8 FHS) Fuel-Handling Equipment NA NA 035 (SF 4P SG) Steam Generator X

G2.1.19: Ability to use available indications to evaluate system or component status 92 041 (SF4S SDS) Steam Dump/Turbine Bypass Control X

A2.02: Ability to (a) predict the impacts of the following on the Steam Dump System and Turbine Bypass Control and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations; Steam valve stuck open 3.8 93 045 (SF 4S MTG) Main Turbine Generator X

A1.07: Ability to predict and/or monitor changes in parameters associated with operation of the Main Turbine Generator System, including; Lights and alarms 3.1 62 055 (SF4S CARS) Condenser Air Removal NA NA 056 (SF4S CDS) Condensate X

A2.08: Ability to (a) predict the impacts of the following on the Condensate System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Feedwater heater tube leak 3.3 63 068 (SF9 LRS) Liquid Radwaste X

A3.02: Ability to monitor automatic features of the Liquid Radwaste System, including; Automatic isolation 3.6 64 071 (SF9 WGS) Waste Gas Disposal NA NA 072 (SF7 ARM) Area Radiation Monitoring 075 (SF8 CW) Circulating Water NA NA 079 (SF8 SAS**) Station Air NA NA 086 Fire Protection NA NA 050 (SF 9 CRV*) Control Room Ventilation X

A4.01: Ability to manually operate and/or monitor in the control room: Initiate/reset system 3.8 65 K/A Category Point Totals:

1 1

1 1

1 1

1 1/

2 1

1 0/

1 Group Point Total:

10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility: Vogtle Units 1 & 2 Date of Exam: November 15, 2021 Category K/A #

Topic RO SRO-only IR IR

1. Conduct of Operations 2.1.34 Knowledge of RCS or balance-of-plant chemistry controls, including parameters measured and reasons for the control 2.7 66 2.1.21 Ability to verify that a copy of a controlled procedure is the proper revision 3.5 67 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, and maintenance of active license status, 10 CFR Part 55 3.3 68 2.1.39 Knowledge of conservative decision-making practices 4.3 94 2.1.8 Ability to coordinate personnel activities outside the control room 4.1 95 Subtotal 3

2

2. Equipment Control 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity 4.5 69 2.2.21 Knowledge of pre-and post-maintenance operability requirements 2.9 70 2.2.7 Knowledge of the process for conducting infrequently performed tests or evolutions 2.9 71 2.2.5 Knowledge of the process for making design or operating changes to the facility, such as 10 CFR 50.59, Changes, Tests and Experiments, screening and evaluation processes, administrative processes for temporary modifications, disabling annunciators, or installation of temporary equipment 3.2 96 2.2.23 Ability to track TS limiting conditions for operation 4.6 97 Subtotal 3

2

3. Radiation Control 2.3.12 Knowledge of radiological safety principles and procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, or alignment of filters 3.2 72 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities, such as analysis and interpretation of radiation and activity readings as they pertain to administrative, normal, abnormal, and emergency procedures or to analysis and interpretation of coolant activity, including comparison to emergency plan or regulatory limits (SRO Only) 3.8 98

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Subtotal 1

1

4. Emergency Procedures/Plan 2.4.12 Knowledge of operating crew responsibilities during emergency and abnormal operations 4.0 73 2.4.6 Knowledge of emergency and abnormal operating procedures major action categories 3.7 74 2.4.14 Knowledge of general guidelines for emergency and abnormal operating procedures usage 3.8 75 2.4.18 Knowledge of the specific bases for emergency and abnormal operating procedures 4.0 99 2.4.26 Knowledge of facility protection requirements, including fire brigade and portable firefighting equipment usage 3.6 100 Subtotal 3

2 Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier /

Group Randomly Selected K/A Reason for Rejection T2 / G1 039K6.07 Operation of the ARVs or ARV failure have minimal impact on the operation of the Main Steam System. K/A changed to 039K6.11 T1 / G2 003AG2.4.04 Difficultly making AOP and EOP entry condition SRO only. K/A Changed to 003G2.4.29 T3 G2.1.14 Unable to make plant announcements SRO only. K/A changed to G2.1.8 T1 / G2 059AG2.4.35 Unable to write SRO only question about NLO responsibilities during accidental liquid radwaste release. K/A changed to 059AG2.4.30

Digitally signed by Daniel M. Bacon Date: 2021.10.28 16:04:34 -04'00' Eugene Guthrie Digitally signed by Eugene Guthrie Date: 2021.11.05 15:43:03 -04'00'

Vogtle 1&2 2021-301 Initial Operator License Exam ES-401 Written Examination Review Worksheet Form ES-401-9 Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

  1. /

units Back-ward Q=

K/A SRO Only 1

F 2

M S

K/A 001K1.12 T2 G2 Question is Satisfactory.

2 H

2 X

B E

K/A 002K3.03 T2 G2

1. Auctioneered High is not plausible for an answer to this question because you are not asking about a protective or control function. You could use highest.
2. The explanation of required knowledge is missing the less than or in the first sentence and the between or the greater than and less than in the second sentence that are needed to make them technically accurate.

10/28/2021 - Licensee made corrections to address the concerns as stated above. The question is now Satisfactory.

3 H

2 B

E K/A 003K1.10 T2 G1

1. The reason given to consider the first part of Choice C plausible is not acceptable.

Misreading a given condition in the stem and subtracting a pressure from a temperature does not make the choice plausible. Something such as requiring RCS pressure to be greater than 325 psi prior to starting a RCP for filling and venting would be a good basis.

10/28/2021 - Licensee made corrections to address the concerns as stated above. The question is now Satisfactory.

4 H

3 M

S K/A 004K2.02 T2 G1 Question is Satisfactory.

5 F

2 X

M U

K/A 005AA1.05 T1 G2 This question directly tests procedure knowledge.

1. Question is Unsatisfactory because it does not test the K/A. It tests knowledge of the rod control system manual rod speeds and the rod control system malfunction procedure.

10/28/21 - Licensee submitted a different question that meets the K/A. The new question is Satisfactory.

6 H

3 N

S K/A 005K3.02 Question submitted for preliminary review. T2 G1 Question is Satisfactory.

7 F

2 X

M U

K/A 006K4.13 T2 G1

1. Unsatisfactory due to overlap with the operating test. On Scenario #5, the UO is required to reset containment isolation to restore instrument air following a steam line break.

10/28/2021 - Licensee made minor change to first part question. This question does not overlap with the conditions present during Scenario #5. The question is Satisfactory.

8 H

2 B

S K/A 007EA1.05 T1 G1 Question tests #2 of FAQ 401.55.

Question is Satisfactory.

9 H

2 M

S K/A 007K5.07 T2 G1 Question is Satisfactory.

10 H

2 M

S K/A 008AA2.06 T1 G1 This question directly tests procedure knowledge.

Question is Satisfactory.

11 H

2 B

S K/A 008K1.14 T2 G1 Question is Satisfactory.

12 F

2 B

S K/A 008K6.09 T2 G1 Question 12 on Vogtle 2015 NRC Exam Question is Satisfactory.

13 H

2 N

S K/A 009EG2.2.22 T1 G1 This question directly tests procedure knowledge.

Question is Satisfactory.

14 F

2 M

S K/A 010A1.09 T2 G1 Question is Satisfactory.

Vogtle 1&2 2021-301 Initial Operator License Exam Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

  1. /

units Back-ward Q=

K/A SRO Only 15 F

2 M

S K/A 011EK1.03 T1 G1 This question directly tests procedure knowledge Question is Satisfactory.

16 F

2 X

B E

K/A 012A2.01 T2 G1

1. An applicant potentially mis-reading a question does not support the plausibility of a distractor. Is there any coincidence at your plant that requires 3 out of x to trip? If not, then choices C(1) and D(1) are not plausible. You could potentially ask if the coincidence for the pressurizer pressure high trip is 2/3 or 2/4.

10/28/2021 - Licensee submitted a different question to address the concerns as listed above. The question is Satisfactory.

17 H

3 M

S K/A 013A3.11 T2 G1 Question is Satisfactory.

18 H

3 N

S K/A 016K2.03 T2 G2 Question is Satisfactory.

19 F

3 M

S K/A 022A4.01 T2 G1 Question is Satisfactory.

20 H

2 M

S K/A 022AK2.10 T1 G1 Question tests procedure knowledge.

Question is Satisfactory.

21 F

3 B

S K/A 022K4.04 T2 G1 Question is Satisfactory.

22 H

2 B

S K/A 026AK3.02 T1 G1 Question tests #4 of FAQ 401.55.

Question is Satisfactory.

23 F

2 M

S K/A 026G2.1.27 T2 G1.

Question is Satisfactory.

24 H

2 M

S K/A 027AA1.06 T1 G1 Question tests #2 of FAQ 401.55.

Question is Satisfactory.

25 F

2 B

S K/A 027K5.01 T2 G2 Question is Satisfactory.

26 H

3 M

S K/A 028AA2.03 T1 G2 Question tests #2 of FAQ 401.55 Question is Satisfactory.

27 F

2 N

S K/A 028K4.02 T2 G2 Question is Satisfactory.

28 H

2 B

S K/A 029EA2.13 T1 G1 Question #29 on Vogtle 2019 NRC Exam. Question tests procedure knowledge.

29 F

2 M

S K/A 029K6.10 Question submitted for preliminary review. T2 G2 Question is Satisfactory.

30 H

2 N

S K/A 032AG2.4.02 T1 G2 Question tests procedure knowledge.

Question is Satisfactory.

31 F

2 M

S K/A 033AK1.01 T1 G2 Question is Satisfactory. Question tests procedure knowledge.

32 H

2 M

S K/A 038EG2.4.50 T1 G1 Question tests procedure knowledge.

Question is Satisfactory.

33 F

2 B

S K/A 039K1.08 T2 G1 Question #33 on Vogtle 2019 NRC Exam.

Question is Satisfactory.

34 H

3 B

S K/A 039K6.11 T2 G1 Question is Satisfactory.

35 F

2 M

S K/A 045A1.07 T2 G2 Question is Satisfactory.

Vogtle 1&2 2021-301 Initial Operator License Exam Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

  1. /

units Back-ward Q=

K/A SRO Only 36 F

2 M

S K/A 050A4.01 T2 G2 Question is Satisfactory.

37 H

2 X

B U

K/A 051AK2.10 T1 G2 Question tests procedure knowledge.

Question is unsatisfactory due to more than one non-credible distractor. The first part of choices C and D are not credible with the conditions given. The second part of choice D is not plausible given the initial conditions.

10/28/2021 - The licensee made changes to the question to address the concerns as listed above. The question is now Satisfactory.

38 H

2 X

N E

K/A 053A4.03 T2 G1

1. Second part question should be less than or equal to in order to be fully technically correct.

10/28/2021 - The answer chosen is less than 551 F because the Technical Specification Minimum Temperature for Criticality allows operation at 551 F although the Rapid Power Reduction Procedure directs a trip if equal to 551 F. Since the distractor is 557 F, the chosen answer is fully correct. The question is Satisfactory.

39 F

2 X

X M

E K/A 054AK1.02 T1 G1 Question tests #1 of FAQ 401.55.

1. First part question does not seem related to K/A. It appears to be a tack on to achieve a two part question. Both parts could easily be related to establishing feed to a dry steam generator.

10/28/2021 - The licensee changed the first part question so that it is more related to the K/A. The question is now Satisfactory.

40 H

2 X

B E

K/A 055EK2.04 T1 G1 Question tests procedure knowledge. Question was on Vogtle 2014 NRC Exam.

1. Adding to minimize battery drain to the second part question gives teaching in the stem and provides a cue.

10/28/2021 - The licensee made changes to the second part question to address the concerns as listed above. The question is now Satisfactory.

41 H

2 X

M S

K/A 056A2.08 T2 G2 Question was on Vogtle 2015 NRC Exam.

Question is Satisfactory.

42 F

2 M

S K/A 056K3.01 T1 G1 Question tests #4 of FAQ 401.55.

Question is Satisfactory.

43 H

2 M

S K/A 057AA1.04 T1 G1 Question tests #4 of FAQ 401.55.

Question is Satisfactory.

44 H

2 N

S K/A 059K3.01 T2 G1 Question is Satisfactory.

45 H

2 M

S K/A 061K3.02 T2 G1 Question is Satisfactory.

46 F

2 X

B E

K/A 062K4.02 T2 G1

1. Based on 13435-C, it seems that taking the switch to the maintenance position enables an instantaneous trip rather than disabling a time delay trip.

10/28/2021 - Based on the difficulty of finding documentation to prove first part answer, the licensee submitted a different question. The question is Satisfactory.

47 F

2 M

S K/A 063K5.04 T2 G1 Question is Satisfactory.

48 H

2 M

S K/A 064K5.06 T2 G1 Question is Satisfactory.

Vogtle 1&2 2021-301 Initial Operator License Exam Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

  1. /

units Back-ward Q=

K/A SRO Only 49 H

2 X

B E

K/A 064K6.09 T2 G1

1. The first and second parts of choice D are not credible distractors when combined. No fans running with the EDG running does not seem credible.

10/28/2021 - The licensee changed the second part question to address the concerns as listed above. The question is now Satisfactory.

50 H

2 M

S K/A 065AA2.03 T1 G1 Question tests #1, #3, and #4 of FAQ 401.55.

Question is Satisfactory.

51 F

2 B

S K/A 067AK3.02 Question submitted for preliminary review. T1 G2 Question tests procedure knowledge.

Question is Satisfactory.

52 H

2 M

S K/A 068K3.02 T2 G2 Question is Satisfactory.

53 F

2 B

S K/A 069AA1.03 T1 G2 Question tests procedure knowledge. Question used on 2014 Vogtle NRC exam.

Question is Satisfactory.

54 F

2 M

S K/A 073A1.01 T2 G1 Question is Satisfactory.

55 H

2 X

X N

U K/A 076A2.05 T2 G1 1.Question is Unsatisfactory because it does not meet the second part of the K/A (using procedures). This is required for an A.2 K/A.

2. It does not seem that the demineralized water valve being required to be open is a credible distractor for a level transmitter failure. Whether or not it automatically opened or not is a different story.

10/28/2021 - Licensee changed second part question to include procedure. Question is Satisfactory.

56 H

2 M

S K/A 076AA2.04 T1 G2 Question tests procedure knowledge.

Question is Satisfactory.

57 F

2 X

X N

E K/A 076K2.09 T2 G1

1. The first part question is a tack on that does not relate to the selected K/A.

10/28/2021 - Licensee changed first part question to relate directly to the K/A. The question is now Satisfactory.

58 H

2 B

S K/A 077AG2.4.49 T1 G1 Question tests procedure knowledge.

Question is Satisfactory.

59 F

2 M

S K/A 078A3.05 T2 G1 Question is Satisfactory.

60 F

2 M

S K/A 078G2.4.18 T1 G2 Question tests procedure knowledge.

Question is Satisfactory.

61 H

3 B

S K/A 078K2.01 T2 G1 Question #57 on 2017 Vogtle NRC exam.

Question is Satisfactory.

62 F

3 N

S K/A 103G2.2.03 T2 G1 Question is Satisfactory.

63 F

2 X

X N

E K/A G2.1.04 T3

1. Does Vogtle have a mixed shift schedule? If not, there is no correct answer.
2. The stem of the question does not in any way get to the fact that you can not truncate shifts at the correct number of hours. This seems to be negative training.
3. The second part question should ask if the requirement is per month or quarter.

4 There is no need for the given conditions.

10/28/2021 - Licensee submitted new question. The new question is Satisfactory.

Vogtle 1&2 2021-301 Initial Operator License Exam Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

  1. /

units Back-ward Q=

K/A SRO Only 64 F

2 N

E K/A G2.1.21 T3

1. Choice B does not seem to be a credible distractor. It does not seem that it could be correct that you would be required to version check the actual transient response procedure, but not a system operating procedure that it references.

10/28/2021 - Licensee changed question to address the concerns stated above. The question is now Satisfactory.

65 F

2 B

S K/A G2.1.34 T3 Question used on 2013 Vogtle NRC exam.

Question is Satisfactory.

66 H

2 B

S K/A G2.2.01 T3 Question is Satisfactory.

67 F

2 X

M S

K/A G2.2.07 T3 Question is Satisfactory.

68 H

2 M

S K/A G2.2.21 Question submitted for preliminary review. T3 Question is Satisfactory.

69 F

2 B

S K/A G2.3.12 T3 Question is Satisfactory.

70 F

2 B

S K/A G2.4.06 T3 Question #65 on 2019 Vogtle NRC exam.

Question is Satisfactory.

71 H

2 B

S K/A G2.4.12 T3 Question is Satisfactory.

72 F

2 M

S K/A G2.4.14 T3 Question is Satisfactory.

73 H

2 N

S K/A WE04EK1.05 T1 G1 Question tests procedure knowledge.

Question is Satisfactory.

74 F

2 X

N U

K/A WE05K3.16 T1 G1 Question tests procedure knowledge.

1. Question us Unsatisfactory due to more than on non-credible distractor. Emergency boration is not a plausible distractor as the reason for RCS feed flow during a loss of secondary heat sink when bleed and feed is required.

10/28/2021 - The licensee changed the second part question to address the concerns as listed above. The question is now Satisfactory.

75 H

2 M

S K/A WE11EK2.04 T1 G1 Question tests procedure knowledge.

Question is Satisfactory.

76 (1)

H 2

M S

K/A 003AG2.4.29 Question submitted for preliminary review. T1 G2 Question is Satisfactory.

77 (2)

H 3

N S

K/A 004G2.2.37 T2 G1 Question is Satisfactory.

78 (3)

H 2

B S

K/A 005A2.05 T2 G1 Question is Satisfactory.

Vogtle 1&2 2021-301 Initial Operator License Exam Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

  1. /

units Back-ward Q=

K/A SRO Only 79 (4)

F 2

M S

K/A 011EG2.4.30 Question submitted for preliminary review. T1 G1 Question is Satisfactory.

80 (5)

H 2

B S

K/A 015A2.04 T2 G2 Question used on 2013 Vogtle NRC exam.

Question is Satisfactory.

81 (6)

H 2

M S

K/A 015AA2.01 T1 G1 Question is Satisfactory.

82 (7)

H 2

M S

K/A 025AG2.1.32 Question submitted for preliminary review. T1 G1 Question is Satisfactory.

83 (8)

H 2

B S

K/A 035G2.1.19 T2 G2 Question is Satisfactory.

84 (9)

F 2

M S

K/A 036AA2.05 T1 G2 Question is Satisfactory.

85 (10)

H 2

X M

E K/A 040AA2.01 T1G1

1. The second part question does not seem to be related to the K/A in any way. This appears to be a tack on to make a two part question.

10/28/2021 - The licensee changed the second part question to relate to the K/A. The question is now Satisfactory.

86 (11)

F 2

N S

K/A 041A2.02 Question submitted for preliminary review. T2 G2 Question is Satisfactory.

87 (12)

H 4

M S

K/A 053G2.1.30 Question submitted for preliminary review. T2 G1 Verified with operations representative that a technical specification reference was not needed for the second part question.

88 (13)

H 3

N S

K/A 058G2.2.40 T1 G1 Question is Satisfactory.

89 (14)

H 2

X X

M E

K/A 059G2.4.35 T1 G2

1. The second part question does not seem to be related to the K/A in any way. This appears to be a tack on to make a two part question.

10/28/2021 - Licensee was unable to write an SRO only question to the original K/A.

Selected K/A G2.4.30. Licensee submitted a different question for the new K/A. The question is Satisfactory.

90 (15)

H 2

B S

K/A 062AA2.05 T1 G1 Question was used on 2014 Vogtle NRC exam.

Question is Satisfactory.

Vogtle 1&2 2021-301 Initial Operator License Exam Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

  1. /

units Back-ward Q=

K/A SRO Only 91 (16)

F 2

M S

K/A 063G2.2.25 T2 G1 Question is Satisfactory.

92 (17)

F 2

X M

U K/A 103A2.10 T2 G1 Question is Unsatisfactory due to not meeting the K/A. The question does not relate to the Containment system.

10/28/2021 - Licensee submitted a different question that matched the K/A. The question is Satisfactory.

93 (18)

F 2

X X

N E

K/A G2.1.14 T3

1. I see where the reactor startup is required to be announced to plant personnel in 12003-1, but do not see where the Shift Supervisor is required to announce Mode 2 specifically. This is a potential cue since pulling control banks is what causes the mode change.

10/28/2021 - Licensee was unable to write an SRO only question to the original K/A.

Selected K/A G2.1.8. Licensee submitted a different question for the new K/A. The question is Satisfactory.

94 (19)

F 2

X B

E K/A G2.1.39 T3

1. Choice A is not credible when power was initially at 100% and is now rising.

10/28/2021 - Licensee developed a two part question to address the concerns as listed above. The new question is Satisfactory.

95 (20)

F 2

X M

U K/A G2.2.05 T3

1. Question is Unsatisfactory due to more than on non-credible distractor. Replacing with a solid blue window is not credible. A semi-annual audit is also not very credible for disabled annunciators. With those distractors, this question is not discriminating at all.

10/28/2021 - Licensee changed the distractors to address the concerns as listed above. The question is now Satisfactory.

96 (21)

H 2

B S

K/A G2.2.23 T3 Question #21 on 2017 Vogtle SRO NRC exam.

Question is Satisfactory.

97 (22)

F 2

M S

K/A G2.3.14 T3 Question is Satisfactory.

98 (23)

F 2

B S

K/A G2.4.18 T3 Question is Satisfactory.

99 (24)

F 2

B S

K/A G2.4.26 T3 Question was used on 2015 Vogtle NRC exam.

Question is Satisfactory.

100 (25)

H 2

M S

K/A WE13A2.04 T1 G2 Question is Satisfactory.

Vogtle 1&2 2021-301 Initial Operator License Exam Instructions

[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]

1.

Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.

2.

Enter the level of difficulty (LOD) of each question using a 1 - 5 (easy - difficult) rating scale (questions in the 2 - 4 range are acceptable).

3.

Check the appropriate box if a psychometric flaw is identified:

The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).

The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).

The answer choices are a collection of unrelated true/false statements.

The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.

One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).

4.

Check the appropriate box if a job content error is identified:

The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).

The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).

The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).

The question requires reverse logic or application compared to the job requirements.

5.

Check questions that are sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).

6.

Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.

7.

Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?

8.

At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).

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