ML19115A049
| ML19115A049 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  (DPR-033, DPR-052, DPR-068) |
| Issue date: | 04/25/2019 |
| From: | NRC/RGN-II/DRS/OLB |
| To: | Tennessee Valley Authority |
| Shared Package | |
| ML19112A034 | List: |
| References | |
| 50-259/18-01, 50-260/18-01, 50-296/18-01 50-259/OL-18-01, 50-260/OL-18-01, 50-296/OL-18-01 | |
| Download: ML19115A049 (80) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 Facility Browns Ferry NPP Date of Examination: __ 07-16-18 ___
Examination Level: RO SRO Operating Test Number: _18-04_____
Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations R, D JPM 661 Determine Adequate Performance Of License Reactivation K/A 2.1.4 (RO 3.3)
Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.
Conduct of Operations R, D JPM 556 Drywell Leakage Calculation K/A 2.1.7 (RO 4.4)
Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
Equipment Control R, D JPM 510 Evaluate Recombiner Performance K/A 2.2.44 (RO 4.2)
Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
Radiation Control R, M JPM 693 Determine ALARA Path K/A 2.3.7 (RO 3.5)
Ability to comply with radiation work permit requirements during normal or abnormal conditions.
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 & RO retakes)
(N)ew or (M)odified frombank ( 1)
(P)revious 2 exams ( 1; randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1 Reactor Operator
- 1. Conduct of Ops - Determine Adequate Performance Of License Reactivation Using OPDP-10, License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions and a provided table determines which Unit Operator has performed the necessary steps to reactivate their license.
K/A 2.1.4: Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc. (RO 3.3)
- 2. Conduct of Ops - Drywell Leakage Calculation Using 2-SR-2, Instrument Checks and Observations, and given Floor and Equipment Drain readings calculates leak rates and determines if leak rates are acceptable within Technical Specification requirements.
K/A 2.1.7: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
(RO 4.4)
- 3. Equipment Control - Evaluate Recombiner Performance Using 3-OI-66, Off-Gas System, and values given performs a Recombiner Performance Evaluation.
K/A 2.2.44: Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. (RO 4.2)
- 4. Radiation Control - Determine ALARA Path Given three paths with dose rates to complete a job in the Drywell, calculates total dose for each path and decides which path would be the best with respect to maintaining the dose as low as possible.
K/A 2.3.7: Ability to comply with radiation work permit requirements during normal or abnormal conditions. (RO 3.5)
- 5. Emergency Plan - N/A
ES-301 Administrative Topics Outline Form ES-301-1 Facility Browns Ferry NPP Date of Examination: __ 07-16-18 ___
Examination Level: RO SRO Operating Test Number: _18-04_____
Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations R, M JPM 507 Fitness For Duty Determination K/A 2.1.13 (SRO 3.2)
Knowledge of facility requirements for controlling vital/controlled access.
Conduct of Operations R, D JPM 556 Drywell Leakage Calculation K/A 2.1.7 (SRO 4.7)
Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
Equipment Control R, D JPM 566 Evaluate Failed Shutdown Cooling Relay (10A-K97A)
K/A 2.2.15 (SRO 4.3)
Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc.
Radiation Control R, D JPM 645 Determine Radiation Exposure Limits Under Emergency Conditions K/A 2.3.4 (SRO 3.7)
Knowledge of radiation exposure limits under normal or emergency conditions.
Emergency Plan R, N JPM 723 Emergency Action Level Classification (3.1-G)
K/A 2.4.41 (SRO 4.6)
Knowledge of the emergency action level thresholds and classifications.
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 & RO retakes)
(N)ew or (M)odified frombank ( 1)
(P)revious 2 exams ( 1; randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1 Senior Reactor Operator
- 1. Conduct of Ops - Fitness for Duty Determination Given Fitness for Duty information on three employees, uses NPG-SPP-14.1, Fitness for Duty and Fatigue Management to determine which individuals can be called in to work and any action that must be taken upon arrival at the plant.
K/A 2.1.13: Knowledge of facility requirements for controlling vital/controlled access.
(SRO 3.2)
- 2. Conduct of Ops - Drywell Leakage Calculation Using 2-SR-2, Instrument Checks and Observations, and given Floor and Equipment Drain readings calculates leak rates and determines if leak rates are acceptable and what Technical Specification action must be taken.
K/A 2.1.7: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
(SRO 4.7)
- 3. Equipment Control - Evaluate Failed Shutdown Cooling Relay (10A-K97A)
Given a failure of an electrical relay, using drawings determines the effect of the relay failure and what Technical Specification actions must be taken.
K/A 2.2.15: Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc.
(SRO 4.3)
- 4. Radiation Control - Determine Radiation Exposure Limits Under Emergency Conditions Given dose rates for a job to be performed during an emergency, calculates expected dose and using EPIP-15, Emergency Exposure, determines if an individual could be allowed to perform the job and fills out required paperwork.
K/A 2.3.4: Knowledge of radiation exposure limits under normal or emergency conditions. (SRO 3.7)
ES-301 Administrative Topics Outline Form ES-301-1
- 5. Emergency Plan - Emergency Action Level Classification (3.1-G)
Given plant conditions uses EPIP-1, Emergency Classification Procedure classifies an event and fills out the required notification form.
K/A 2.4.41: Knowledge of the emergency action level thresholds and classifications.(SRO 4.6)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Browns Ferry NPP Date of Examination:
07/16/18 Exam Level: RO SRO-I SRO-U Operating Test No.:
18-04 Control Room Systems:@ 8 for RO, 7 for SRO-I, 2 or 3 for SRO-U, including 1 ESF System / JPM Title Type Code*
Safety Function
- c. JPM 48A Reduce Reactor Pressure per EOI Appendix-11F, Alternate RPV Pressure Control Systems-RFPT on Minimum Flow A,D,S 3
- d. JPM 201F Respond to a Loss of Shutdown Cooling per AOI-74-1, Loss of Shutdown Cooling A,D,EN,L,S 4
- e. JPM 634 Place Primary Containment Ventilation in Service per OI-64, Primary Containment System D,EN,S 5
- f. JPM 706 Prepare IRMs for Reactor Startup per OI-92A, Intermediate Range Monitors L,N,S 7
- g. JPM 724 Respond to Drywell/Suppression Chamber Radiation high per 2-ARP-9-7C, Alarm Response Procedure N,S 9
- h. JPM 39 Align CAD to Drywell Control Air per EOI Appendix-8G, Crosstie CAD to Drywell Control Air D,S 8
In-Plant Systems:@ 3 for RO, 3 for SRO-I, 3 or 2 for SRO-U
- i. JPM 683A Transfer Battery Charger SB-C AC Alternate Power Supply per 0-OI-57D, DC Electrical System A,D 6
- j. JPM 684 Insert Control Rods from the Auxiliary Instrument Room per AOI-100-2, Control Room Abandonment N,E 7
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- 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 Control Room/In-Plant Systems Outline Form ES-301-2 Reactor Operator Job Performance Measures
- a.
JPM 708F
Title:
Inject Boron during an ATWS per EOI Appendix-3A, SLC Injection
==
Description:==
The candidate will inject Standby Liquid Control (SLC) in accordance with EOI Appendix 3A. When an SLC Pump is started, Reactor Water Cleanup (RWCU) will fail to isolate and the RWCU Pumps will fail to trip. The candidate will manually isolate RWCU and verify the RWCU Pumps are tripped.
K/A:
211000 Standby Liquid Control System A1.08; Ability to predict and/or monitor changes in parameters associated with operating the STANDBY LIQUID CONTROL SYSTEM controls including: RWCU system lineup (3.7)
- b.
JPM 18A
Title:
Inject to the Reactor per EOI Appendix-5C, Injection System Lineup-RCIC
==
Description:==
The candidate will inject to the Reactor using Reactor Core Isolation Cooling (RCIC) to maintain Reactor Water Level, in accordance with EOI-Appendix 5C. After injection has begun, the RCIC Flow Controller will fail to operate in automatic, and the candidate will take manual control of the RCIC Flow Controller to continue injection.
K/A 217000 Reactor Core Isolation Cooling System (RCIC) A1.01; Ability to predict and/or monitor changes in parameters associated with operating the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) controls including: RCIC Flow (3.7)
- c. JPM 48A
Title:
Reduce Reactor Pressure per EOI Appendix-11F, Alternate RPV Pressure Control Systems - RFPT on Minimum Flow
==
Description:==
The candidate will line up to use a Reactor Feedwater Pump (RFPT) for RPV Pressure Control in accordance with EOI Appendix 11F. During the performance of EOI Appendix 11F, the first RFPT Discharge Valve will fail to close. The candidate will select another RFPT to use for RPV Pressure Control.
K/A 241000 Reactor/Turbine Pressure Regulating System A2.02; Ability to (a) predict the impacts of the following on the REACTOR/TURBINE PRESSURE REGULATING SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High Reactor Pressure (3.7)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
- d.
JPM 201F
Title:
Respond to a loss of Shutdown Cooling per AOI-74-1, Loss of Shutdown Cooling
==
Description:==
The candidate will be directed to restore Shutdown Cooling using B RHR pump in accordance with AOI-74-1. When the candidate attempts to start B RHR Pump it will not start. The candidate will start D RHR Pump and proceed with the restoration of Shutdown Cooling.
K/A 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode)
A2.05: Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System isolation (3.5)
- e.
JPM 634
Title:
Place Primary Containment Ventilation in Service per OI-64, Primary Containment System
==
Description:==
The candidate will place Primary Containment Ventilation in service in accordance with OI-64 Section 8.5, Placing Primary Containment Ventilation in Service.
K/A 223001 Primary Containment System and Auxiliaries A4.03: Ability to manually operate and/or monitor in the control room: Air dilution valves to drywell and suppression pool (3.4)
- f.
JPM 706
Title:
Prepare IRMs for Reactor Startup per OI-92A, Intermediate Range Monitors
==
Description:==
The candidate will prepare the Intermediate Range Monitors (IRMs) for Reactor Startup in accordance with OI-92A Section 5.1, Preparing Intermediate Range Monitors for Reactor Startup.
K/A 215003 Intermediate Range Monitor (IRM) System A4.07 Ability to manually operate and/or monitor in the control room: Verification of proper functioning/operability (3.6)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
- g.
JPM 724
Title:
Respond to Drywell/Suppression Chamber Radiation High per 2-ARP-9-7C, Alarm Response Procedure
==
Description:==
The candidate will respond to a High Radiation condition in the Drywell/Suppression Chamber in accordance with 2-ARP-9-7C, Window 15, Drywell/Suppression Chamber Radiation High 2-RA-90-272.
K/A 272000 Radiation Monitor System A2.01: Ability to (a) predict the impacts of the following on the RADIATION MONITORING SYSTEM ;
and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Fuel Element Failure. (3.7)
- h.
JPM 39
Title:
Align CAD to Drywell Control Air per EOI Appendix-8G, Crosstie CAD to Drywell Control Air
==
Description:==
The candidate will cross tie CAD to Drywell Control Air in accordance with EOI Appendix 8G.
K/A 295019 Partial or Complete Loss of Instrument Air AA1.01: Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: Backup air supply (3.5)
- i. JPM 683A
Title:
Transfer Battery Charger SB-C AC Alternate Power Supply per 0-OI-57D, DC Electrical System
==
Description:==
The candidate will transfer the AC Alternate Source to Battery Charger SB-C in accordance with 0-OI-57D Section 8.6, Transfer of AC Alternate Source to Battery Charger SB-C ONLY. The candidate will be presented with oscillating amps during the performance of the Operating Instruction steps, requiring that the system be placed in a safe condition.
K/A 263000 D.C. Electrical Distribution A3.01: Ability to monitor automatic operations of the D.C. ELECTRICAL DISTRIBUTION including:
Meters, dials, recorders, alarms, and indicating lights (3.2)
- j.
JPM 684
Title:
Insert Control Rods from the Auxiliary Instrument Room per AOI-100-2, Control Room Abandonment
==
Description:==
The candidate will remove the RPS Scram Solenoid fuses in accordance with AOI-100-2 Attachment 11, Removal and Replacement of RPS Scram Solenoid Fuses.
K/A 212000 Reactor Protection System A2.21: 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 conditions or operations: Failure of individual relays to reposition (3.6)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
- k. JPM 79
Title:
Start RCIC from outside the Control Room per AOI-100-2, Control Room Abandonment
==
Description:==
The candidate will start RCIC from outside the Control room in accordance with AOI-100-2 Attachment 3, Unit 2/3 Reactor Building Auxiliary Unit Operator Panel Checklist.
K/A 217000 Reactor Core Isolation Cooling System (RCIC) G2.4.34:
Knowledge of RO tasks performed outside the Main Control Room during an emergency and the resultant operational effects (4.2)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Browns Ferry NPP Date of Examination:
07/16/18 Exam Level: RO SRO-I SRO-U Operating Test No.:
18-04 Control Room Systems:@ 8 for RO, 7 for SRO-I, 2 or 3 for SRO-U, including 1 ESF System / JPM Title Type Code*
Safety Function
- c. JPM 48A Reduce Reactor Pressure per EOI Appendix-11F, Alternate RPV Pressure Control Systems-RFPT on Minimum Flow A,D,S 3
- d. JPM 201F Respond to a Loss of Shutdown Cooling per AOI-74-1, Loss of Shutdown Cooling A,D,EN,L,S 4
- e. JPM 634 Place Primary Containment Ventilation in Service per OI-64, Primary Containment System D,EN,S 5
- f. JPM 706 Prepare IRMs for Reactor Startup per OI-92A, Intermediate Range Monitors L,N,S 7
- g. JPM 724 Respond to Drywell/Suppression Chamber Radiation high per 2-ARP-9-7C, Alarm Response Procedure N,S 9
- h. N/A In-Plant Systems:@ 3 for RO, 3 for SRO-I, 3 or 2 for SRO-U
- i. JPM 683A Transfer Battery Charger SB-C AC Alternate Power Supply per 0-OI-57D, DC Electrical System A,D 6
- j. JPM 684 Insert Control Rods from the Auxiliary Instrument Room per AOI-100-2, Control Room Abandonment N,E 7
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- 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 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator (Instant)
- a.
JPM 708F
Title:
Inject Boron during an ATWS per EOI Appendix-3A, SLC Injection
==
Description:==
The candidate will inject Standby Liquid Control (SLC) in accordance with EOI Appendix 3A. When an SLC Pump is started, Reactor Water Cleanup (RWCU) will fail to isolate and the RWCU Pumps will fail to trip. The candidate will manually isolate RWCU and verify the RWCU Pumps are tripped.
K/A:
211000 Standby Liquid Control System A1.08; Ability to predict and/or monitor changes in parameters associated with operating the STANDBY LIQUID CONTROL SYSTEM controls including: RWCU system lineup (3.8)
- b.
JPM 18A
Title:
Inject to the Reactor per EOI Appendix-5C, Injection System Lineup-RCIC
==
Description:==
The candidate will inject to the Reactor using Reactor Core Isolation Cooling (RCIC) to maintain Reactor Water Level, in accordance with EOI-Appendix 5C. After injection has begun, the RCIC Flow Controller will fail to operate in automatic, and the candidate will take manual control of the RCIC Flow Controller to continue injection.
K/A 217000 Reactor Core Isolation Cooling System (RCIC) A1.01; Ability to predict and/or monitor changes in parameters associated with operating the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) controls including: RCIC Flow (3.7)
- c. JPM 48A
Title:
Reduce Reactor Pressure per EOI Appendix-11F, Alternate RPV Pressure Control Systems - RFPT on Minimum Flow
==
Description:==
The candidate will line up to use a Reactor Feedwater Pump (RFPT) for RPV Pressure Control in accordance with EOI Appendix 11F. During the performance of EOI Appendix 11F, the first RFPT Discharge Valve will fail to close. The candidate will select another RFPT to use for RPV Pressure Control.
K/A 241000 Reactor/Turbine Pressure Regulating System A2.02; Ability to (a) predict the impacts of the following on the REACTOR/TURBINE PRESSURE REGULATING SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High Reactor Pressure (3.7)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
- d.
JPM 201F
Title:
Respond to a loss of Shutdown Cooling per AOI-74-1, Loss of Shutdown Cooling
==
Description:==
The candidate will be directed to restore Shutdown Cooling using B RHR pump in accordance with AOI-74-1. When the candidate attempts to start B RHR Pump it will not start. The candidate will start D RHR Pump and proceed with the restoration of Shutdown Cooling.
K/A 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode)
A2.05: Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System isolation (3.7)
- e.
JPM 634
Title:
Place Primary Containment Ventilation in Service per OI-64, Primary Containment System
==
Description:==
The candidate will place Primary Containment Ventilation in service in accordance with OI-64 Section 8.5, Placing Primary Containment Ventilation in Service.
K/A 223001 Primary Containment System and Auxiliaries A4.03: Ability to manually operate and/or monitor in the control room: Air dilution valves to drywell and suppression pool (3.4)
- f.
JPM 706
Title:
Prepare IRMs for Reactor Startup per OI-92A, Intermediate Range Monitors
==
Description:==
The candidate will prepare the Intermediate Range Monitors (IRMs) for Reactor Startup in accordance with OI-92A Section 5.1, Preparing Intermediate Range Monitors for Reactor Startup.
K/A 215003 Intermediate Range Monitor (IRM) System A4.07 Ability to manually operate and/or monitor in the control room: Verification of proper functioning/operability (3.6)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
- g.
JPM 724
Title:
Respond to Drywell/Suppression Chamber Radiation High per 2-ARP-9-7C, Alarm Response Procedure
==
Description:==
The candidate will respond to a High Radiation condition in the Drywell/Suppression Chamber in accordance with 2-ARP-9-7C, Window 15, Drywell/Suppression Chamber Radiation High 2-RA-90-272.
K/A 272000 Radiation Monitor System A2.01: Ability to (a) predict the impacts of the following on the RADIATION MONITORING SYSTEM ;
and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Fuel Element Failure. (4.1)
- h.
N/A
- i. JPM 683A
Title:
Transfer Battery Charger SB-C AC Alternate Power Supply per 0-OI-57D, DC Electrical System
==
Description:==
The candidate will transfer the AC Alternate Source to Battery Charger SB-C in accordance with 0-OI-57D Section 8.6, Transfer of AC Alternate Source to Battery Charger SB-C ONLY. The candidate will be presented with oscillating amps during the performance of the Operating Instruction steps, requiring that the system be placed in a safe condition.
K/A 263000 D.C. Electrical Distribution A3.01: Ability to monitor automatic operations of the D.C. ELECTRICAL DISTRIBUTION including:
Meters, dials, recorders, alarms, and indicating lights (3.3)
- j.
JPM 684
Title:
Insert Control Rods from the Auxiliary Instrument Room per AOI-100-2, Control Room Abandonment
==
Description:==
The candidate will remove the RPS Scram Solenoid fuses in accordance with AOI-100-2 Attachment 11, Removal and Replacement of RPS Scram Solenoid Fuses.
K/A 212000 Reactor Protection System A2.21: 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 conditions or operations: Failure of individual relays to reposition (3.9)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
- k. JPM 79
Title:
Start RCIC from outside the Control Room per AOI-100-2, Control Room Abandonment
==
Description:==
The candidate will start RCIC from outside the Control room in accordance with AOI-100-2 Attachment 3, Unit 2/3 Reactor Building Auxiliary Unit Operator Panel Checklist.
K/A 217000 Reactor Core Isolation Cooling System (RCIC) G2.4.34:
Knowledge of RO tasks performed outside the Main Control Room during an emergency and the resultant operational effects (4.1)
ES-301 Operating Test Review Worksheet Form ES-301-7 Facility: Browns Ferry Exam Date: July 2018 1
2 3
Attributes 4
Job Content 5
6 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.
SRO A JPM 507 Conduct of Operations K/A 2.1.13 2
X
?
?
E What is the point in having a contract employee determined? It is not critical, so no judgement on competency is made in this determination. The standard states that the UE is probably not a true emergency situation. It is an emergency classification. If making repairs to get you out of a UE why would that not be considered an emergency? It is also listed as emergent work on the cue sheet.
One of the definitions of emergent according to Merriam-Webster is, calling for prompt action. How can we expect the applicant to determine that this is not a true emergency situation when an emergency classification is declared? If it is an emergency, it should be a critical step just like the others. Is an Alert an emergency?
There is no time for completion listed on coversheet.
7/3/18-Items listed above have been corrected.
SRO B JPM 556 Conduct of Operations K/A 2.1.7 2
X E
There is no time for completion listed on coversheet.
The Tuesday 1200 calculation for the Drywell Unidentified Leakage Key and Handout is not correct beginning in Column C.1.
The Tuesday 1200 calculation for the Drywell Identified Leakage and Total Leakage Key and Handout is not correct beginning in Column H.2.
7/3/18-Items listed above have been corrected.
ES-301 Operating Test Review Worksheet Form ES-301-7 Admin JPMs ADMIN Topic and K/A 3
Attributes 4
Job Content U/E/S Explanation LOD (1-5)
I/C Cues Critical Scope Overlap Perf.
Key Minutia Job Link SRO C JPM 566 Equipment Control K/A 2.2.15 3
X E
There is no time for completion listed on coversheet.
This JPM has the potential to be very time consuming. We will need to verify the 10-minute validation time with operators that are unfamiliar with it during on site validation.
Need to add a bullet stating that the relay failed in the energized state.
How will the drawings be made available to the applicants?
Need to add for the JPM step 4 critical step that determining either valve being closed will cause a loss of shutdown cooling is sufficient to meet the critical step.
7/3/18-Items listed above have been corrected. Validation time changed to 20 minutes.
SRO E JPM 645 Radiation Control K/A 2.3.4 2
X E
There is no time for completion listed on coversheet.
I do not believe that there is enough information given in the cue for the applicants to determine whether or not the large off-site release stated in the cue will cause extensive exposures to large populations.
7/3/18-Items listed above have been corrected.
ES-301 Operating Test Review Worksheet Form ES-301-7 Admin JPMs ADMIN Topic and K/A LOD (1-5) 3 Attributes 4
Job Content U/E/S Explanation I/C Cues Critical Scope Overlap Perf.
Key Minutia Job Link SRO D JPM 723 Emergency Protection K/A 2.4.41 3
X E
Ensure that there is a note or something as the completion time is not 30 min.
There are 2 time critical aspects to this JPM. One time is for classification (15 min). Once the event is classified you only have 15 min to complete the form.
Note: Concerning the cue prior to JPM Step 1, per NUREG-1021 requirements, the examiner cannot inform the applicants what the time allowed for a time critical JPM is or what portions of the JPM are time critical.
7/3/18-Items listed above have been corrected.
RO A JPM 661 Conduct of Operations K/A 2.1.4 2
S No comments RO B JPM 556 Conduct of Operations K/A 2.1.7 2
X X
E There is no time for completion listed on coversheet.
This is an RO JPM. The cue sheet states that they are the Unit Supervisor.
The days listed in the JPM performance standard do not match the data sheets.
They are mixed in with the SRO JPM.
7/3/18-Items listed above have been corrected.
RO C JPM 510 Equipment Control K/A 2.2.44 2
E Need to allow for either plotting or calculating.
Reactor power for initial conditions and cue is different.
7/3/18-Items listed above have been corrected.
RO D JPM 693 Radiation Control K/A 2.3.7 2
X E
There is no time for completion listed on coversheet.
The rounding on the key for Path 3 is different than the other 2 paths.
mrem/hour.
Step numbers need to be corrected.
7/3/18-Items listed above have been corrected.
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 Simulator JPM
- a. 708f (Unit 2)
Safety Function 1 K/A 211000 A1.08 2
X E
No completion time listed on cover sheet, but it says 4 min on page 2.
Will there be a staff member doing the actions to lower Reactor Water Level?
Why is closing both 2-FCV-69-1 and 2-FCV-69-12 a critical step?
7/3/18-Items listed above have been corrected.
Simulator JPM
- a. 708f (Unit 3)
Safety Function 1 K/A 211000 A1.08 2
X E
No completion time listed on cover sheet but it says 4 min on page 2.
Will there be a staff member doing the actions to lower Reactor Water Level?
Why is closing both 3-FCV-69-1 and 3-FCV-69-12 a critical step?
7/3/18-Items listed above have been corrected.
Simulator JPM
- b. 18a (Unit 2)
Reactor Coolant System Inventory Control K/A 217000 A1.01 2
X E
No completion time listed on cover sheet but it says 5 min on page 2.
Task Standard needs to be updated to more correctly match the task.
7/3/18-Items listed above have been corrected.
ES-301 Operating Test Review Worksheet Form ES-301-7 Simulator/In Plant JPMs Safety Function and K/A LOD (1-5)
Attributes Job Content U/E/S Explanation I/C Focus Cues Critical Steps Scope (N/B)
Overlap Perf.
Std.
Key Minutia Job Link Simulator JPM
- b. 18a (Unit 3)
Reactor Coolant System Inventory Control K/A 217000 A1.01 2
X E
No completion time listed on cover sheet but it says 5 min on page 2.
Task Standard needs to be updated to more correctly match the task.
7/3/18-Items listed above have been corrected.
Simulator JPM
- c. 48a (Unit 2)
Reactor Pressure Control K/A 241000 A2.02 2
X X
E Time for completion is N/A on cover page but says 10 min on page 2.
In the initial conditions, can you more accurately describe the reason the Turbine Bypass valves are not controlling properly?
Need to enhance initiating cue to specify establishing a cooldown with a cooldown rate limit.
Step 10 is not critical.
Critical step designation is missing for step 15.
7/3/18-Items listed above have been corrected.
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 Simulator JPM
- c. 48a (Unit 3)
Reactor Pressure Control K/A 241000 A2.02 2
X X
E Time for completion is N/A on cover page but says 10 min on page 2.
In the initial conditions, can you more accurately describe the reason the Turbine Bypass valves are not controlling properly?
Need to enhance initiating cue to specify establishing a cooldown with a cooldown rate limit.
Step 10 is not critical.
Critical step designation is missing for step 15.
7/3/18-Items listed above have been corrected.
Simulator JPM
- d. 201f (Unit 2)
Heat Removal form the Reactor Core K/A 205000 A2.05 2
X E
Time for completion is N/A on cover page but says 25 min on page 2.
Task Standard should include the procedure that is to be followed.
Note at the beginning include an examiner cue to state that the Unit Supervisor will refer to Tech Specs.
Step 7 standard, the unit is in mode 4 per the cue sheet, so is it necessary to verify that RHR discharge piping is >35 psig?
This is not an alternate path JPM.
7/3/18-Items listed above have been corrected.
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 Simulator JPM
- d. 201f (Unit 3)
Heat Removal from the Reactor Core K/A 205000 A2.05 2
X E
Time for completion is N/A on cover page but says 25 min on page 2.
Task Standard should include the procedure that is to be followed.
Note at the beginning include an examiner cue to state that the Unit Supervisor will refer to Tech Specs.
Step 7 standard, the unit is in mode 4 per the cue sheet, so is it necessary to verify that RHR discharge piping is >35 psig?
This is not an alternate path JPM.
7/3/18-Items listed above have been corrected.
Simulator JPM
- e. 634 (Unit 2)
Containment Integrity K/A 223001 A4.03 2
X X
E Time for completion is N/A on cover page but says 10 min on page 2.
Task standard needs to include placing in service per 2-OI-64.
Step 12 is not a critical step.
7/3/18-Items listed above have been corrected.
Simulator JPM
- e. 634 (Unit 3)
Containment Integrity K/A 223001 A4.03 2
X E
Time for completion is N/A on cover page but says 10 min on page 2.
Task standard needs to include placing in service per 2-OI-64.
Step 12 is not a critical step.
7/3/18-Items listed above have been corrected.
ES-301 Operating Test Review Worksheet Form ES-301-7 Simulator/In Plant JPMs Safety Function and K/A LOD (1-5)
Attributes Job Content U/E/S Explanation I/C Focus Cues Critical Steps Scope (N/B)
Overlap Perf.
Std.
Key Minutia Job Link Simulator JPM
- f. 706 (Unit 2)
Instrumentation K/A 215003 A4.07 2
X X
X U
Time for completion is N/A on cover page but says 15 min on page 2.
Task Standard should include in accordance with 2-OI-92A.
The procedure is a human error trap. Step 4.1 in procedure does not say specifically to depress 2-HS-92-7C/S1, instead it says SRM/ IRM Detector Pushbutton.
Also, the remaining steps do not say to depress any other channel other than (A) and we are testing (H). This could lead to confusion to the applicants if they do not read step 4.7 ahead of time.
Simulator setup does not match the procedure completion stated in the initiating cue.
7/3/18-Items listed above have been corrected.
Simulator JPM
- f. 706 (Unit 3)
Instrumentation K/A 215003 A4.07 2
X X`
X U
Time for completion is N/A on cover page but says 15 min on page 2.
Task Standard should include in accordance with 2-OI-92A.
The procedure is a human error trap. Step 4.1 in procedure does not say specifically to depress 2-HS-92-7C/S1, instead it says SRM/ IRM Detector Pushbutton.
Also, the remaining steps do not say to depress any other channel other than (A) and we are testing (H). This could lead to confusion to the applicants if they do not read step 4.7 ahead of time.
Simulator setup does not match the procedure completion stated in the initiating cue.
7/3/18-Items listed above have been corrected.
ES-301 Operating Test Review Worksheet Form ES-301-7 Simulator/In Plant JPMs Safety Function and K/A LOD (1-5)
Attributes Job Content U/E/S Explanation I/C Focus Cues Critical Steps Scope (N/B)
Overlap Perf.
Std.
Key Minutia Job Link Simulator JPM
- g. 724 (Unit 3)
Radioactivity Release K/A 272000 A2.01 2
X E
Time for completion is N/A on cover page but says 7 min on page 2.
For the initiating cue, state respond to plant conditions, instead of respond to the next event.
Is there going to be a staff member on the floor doing the RVL, RVP and Primary containment sprays in the simulator?
7/3/18-Items listed above have been corrected.
Simulator JPM
- g. 724 (Unit 2)
Radioactivity Release K/A 272000 A2.01 2
X E
Time for completion is N/A on cover page but says 7 min on page 2.
For the initiating cue, state respond to plant conditions, instead of respond to the next event.
Is there going to be a staff member on the floor doing the RVL, RVP and Primary containment sprays in the simulator?
7/3/18-Items listed above have been corrected.
Simulator JPM
- h. 39 (Unit 2)
Plant Service System K/A 295019 AA1.01 2
E Time for completion is N/A on cover page but says 10 min on page 2.
Task Standard on page 2 should include the procedure that is directed to be used.
7/3/18-Items listed above have been corrected.
ES-301 Operating Test Review Worksheet Form ES-301-7 Simulator/In Plant JPMs Safety Function and K/A LOD (1-5)
Attributes Job Content U/E/S Explanation I/C Focus Cues Critical Steps Scope (N/B)
Overlap Perf Std.
Key Minutia Job Link Simulator JPM
- h. 39 (Unit 3)
Plant Service System K/A 295019 AA1.01 2
E Time for completion is N/A on cover page but says 10 min on page 2.
Task Standard on page 2 should include the procedure that is directed to be used.
7/3/18-Items listed above have been corrected.
In Plant JPM i.
683A Electrical K/A 263000 A3.01 2
E Time for completion on page 1 says 15 min and on page 2 is says 20 min?
Ensure task standard has the procedure and section that will be used to accomplish task is included.
Place demarcation in JPM body where alternate path begins, also make note that step 9 may or may not be performed (i.e., the applicant may decide to open ac and dc breakers after step 8.
7/3/18-Items listed above have been corrected.
In Plant JPM j.
684 Instrumentation K/A 212000 A2.21 2
E Time for completion is blank on cover page but says 10 min on page 2. Include the procedure in task standard. Is there a picture that will be used when looking at the fuse cabinet or are we opening it?
7/3/18-Items listed above have been corrected.
In Plant JPM
- k.
79 Heat Removal From the Reactor Core K/A 295016 AA1.07 2
E Time for completion is blank on cover page but says 15 min on page 2. Are we opening the cabinets?
7/3/18-Items listed above have been corrected.
ES-301 11 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 12 Form ES-301-7 Facility: Browns Ferry Scenario: 4 (Unit 3) Exam Date: July 2018 Event Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation General Comments More information is needed for TS events. Need to clearly make the TS calls including TS, Conditions, required actions and functional units (if applicable).
7/3/2018-All issues identified below and during onsite validation have been corrected. The scenario is now Satisfactory and ready for administration.
Start C Standby Gas Treatment Train (SGT) for Unit 2 S
Raise Reactor Power using Control Rods X
S Source Range Monitor (SRM) A fails high X
U An Info-Only LCO cannot be used to grade a TS event. An action statement needs to be entered. This provides no discriminatory value.
Unsatisfactory as a TS event. Moved to event 5 as a component failure only for the OATC during onsite validation. Loss of indication for SDV drain valve added as event 7 for SRO TS call only.
3A Steam Packing Exhauster Discharge Valve Closure/Standby Steam Packing Exhauster Fails to Auto Start S
Moved to event 4 during onsite validation.
Loss of Rod Position Indication System (RPIS) for a Control Rod X
E Need to discuss how Technical specification entries are designated on the ES-D-2 for all scenarios. More detail is needed.
Moved to event #3 during onsite validation.
ES-301 13 Form ES-301-7 Event Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation 3A Reactor Building Closed Cooling Water (RBCCW) Pump trip, 3-FCV-70-48, RBCCW SECTIONALIZING VALVE, fails to auto close S
Loss of Indication for Scram Discharge Volume (SDV) Drain Valve X
S Added during onsite validation to make up for previously invalid TS event.
Suppression Pool Leak/Emergency Depressurization X (3)
X E
For critical task #3, Is there any objective criteria that could be used to determine that it took too long to initiate emergency depressurization?
This could be exceeding a design pressure or a pressure that would unnecessarily cause entry into another procedure and would therefore complicate the mitigation strategy.
Moved to event #8 during onsite validation.
3A EHC Pump Trips, Standby Pump Fails to Start S
Moved to event #9 during onsite validation.
2 ADS Valves (1-5 and 1-18) Fail To Open On Emergency Depressurization X
S Moved to event #10 during onsite validation.
ES-301 14 Form ES-301-7 Facility: Browns Ferry Scenario: 3 (Unit 2) Exam Date: July 2018 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 General Comments More information is needed for TS events. Need to clearly make the TS calls including TS, Conditions, required actions and functional units (if applicable).
7/3/2018-All issues identified below and during onsite validation have been corrected. The scenario is now Satisfactory and ready for administration.
Alternate EHC Pumps S
Raise Reactor Power Using Core Flow X
S Event removed during onsite validation.
Control Rod Drive (CRD)
Flow Controller failure S
Feedwater Level Control Input Failure (LT-3-53)
S Reactor Zone Radiation Monitors Fail Upscale X
E Need to clearly make the TS calls including TS, Conditions, required actions and functional units (if applicable).
ES-301 15 Form ES-301-7 Event Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation Standby Gas Train C Fails to Auto Start X
E Need to clearly make the TS calls including TS, Conditions, required actions and functional units (if applicable).
Main Condenser Tube Leak/High Conductivity S
TS portion of this malfunction removed during onsite validation.
Steam Leak In The Drywell X
X S
What is the time period available to the operators to meet the critical task?
Hydraulic Anticipated Transient Without SCRAM (ATWS)
X X
S How long until an automatic ADS actuation if applicants fail to inhibit?
Standby Liquid Control (SLC) Fails To Inject S
D DG Fails to Automatically Start X
S
ES-301 16 Form ES-301-7 Facility: Browns Ferry Scenario: 2 (Unit 2) Exam Date: July 2018 Event Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation Generic Comments More information is needed for TS events. Need to clearly make the TS calls including TS, Conditions, required actions and functional units (if applicable).
7/3/2018-All issues identified below and during onsite validation have been corrected. The scenario is now Satisfactory and ready for administration.
Start 2B Condensate and Condensate Booster Pumps S
Raise Reactor Power Using Core Flow X
S 2A Control Rod Drive (CRD) Pump trip X
S Loss Of 2A Steam Jet Air Ejector (SJAE)
S Reactor Core Isolation Cooling (RCIC) Logic Power Failure X
E Need to clearly make the TS calls including TS, Conditions, required actions and functional units (if applicable).
2A Stator Cooling Water (SCW)
Failure, Standby Pump Fails To Auto Start X
S Control Rod Drifts Out X
X E
Need to clearly make the TS calls including TS, Conditions, required actions and functional units (if applicable).
ES-301 17 Form ES-301-7 Event Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation Un-isolable Reactor Water Cleanup (RWCU) Leak S
Moved to after the multiple control rods drift out during onsite validation.
Multiple Control Rods Drift Out S
Fuel damage/Emergency Depressurization (2 Radiation Levels above Maximum Safe values)
X S
Ensure that plant data to support completion of critical task is captured as it will be hard to determine in real time.
What is the basis for the 10 minutes on Critical Task #2?
High Pressure Coolant Injection (HPCI) Controller Failure X
S
ES-301 18 Form ES-301-7 Facility: Browns Ferry Scenario: 1 (Unit 3) Exam Date: July 2018 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 More information is needed for TS events. Need to clearly make the TS calls including TS, Conditions, required actions and functional units (if applicable).
7/3/2018-All issues identified below and during onsite validation have been corrected. The scenario is now Satisfactory and ready for administration.
Alternate Reactor/Refuel Zone Fans S
Reactor High Pressure A1 Channel Fails High/Half Reactor SCRAM X
E Need to clearly make the TS calls including TS, Conditions, required actions and functional units (if applicable).
3C Reactor Feedwater Pump (RFPT)
Trip X
S 3A Bus Duct Fan Trip S
3A Standby Liquid Control (SLC) Low Oil Level X
E This is a TS only event. Need to clearly make the TS calls including TS, Conditions, required actions and functional units (if applicable).
3B Condenser Circulating Water Pump (CCW)
Trip/Discharge Valve Fails To Close/Lowering Main Condenser Vacuum X
S How much time is there without operator action prior to a turbine trip?
ES-301 19 Form ES-301-7 Event Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation SRV 1-22 Fails Open, Tailpipe Break In The Suppression Chamber X
S Ensure Critical Task Data is plotted to verify compliance within the curve with a time stamp that will show that the 90 seconds is met. What is the basis for the 90 seconds? Is there a parameter or procedure transition required that could be used to determine if the unit operator is not timely enough?
480V RMOV Board 3A trip S
Loop II Drywell Spray Outboard Isolation Valve Fails To Open S
Cannot seem to find where this failure is identified in the D-2. Need to clearly mark this event and what specific actions are expected by the applicants.
ES-301 20 Form ES-301-7 Facility: Browns Ferry Scenario: 5 (Unit 3) Exam Date: July 2018 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 General Comments According to Appendix D of NUREG 1021, Every required operator action is required to be in the D-2, Based on the format of the D-2 it is not clear what actions will be done by the applicants and what are non-applicable procedure steps. Difficult to determine verifiable actions. Critical Tasks are not clearly laid out in the D-2 should make sure the examiners have it called out in the D-2 to ensure completions We need to discuss before any changes are made based on this comment.
For this scenario, which events give the opportunity to evaluate Rating Factor 3.c for each control board operators?
7/3/2018-Scenario 5 was removed from the exam due to the number of applicants being reduced from thirteen to seven. The scenario is no longer needed. None of the metric for scenario 5 are included in the tables listed below.
Transfer 3C 4KV Unit Board To The USST Raise Reactor Power Using Core Flow X
Average Power Range Monitor 2 Critical Fault X
Need to be very specific on TS. (See above)
Inadvertent Initiation Of High Pressure Coolant Injection (HPCI)
X X
X Initial review only, will need to see it on validation to make final determination.
Critical task is not clearly identified in the ES-D-2 for this event. Are there any bounding criteria that could be used for this critical task in this event? Possibly an RPV level or power level or increase in power.
Need to be very specific on TS. (See above)
Loss Of Control Air X
Page 19 is blank should it be? How is it that as soon as you trip the leak is fixed? Not realistic. Need something or some kind of report that the leak was found and efforts to stop it are in progress. No time table to be given for the repair.
ES-301 21 Form ES-301-7 Event Realism/Cred.
Required Actions Verifiable actions LOD TS CTs Scen.
Overlap U/E/S Explanation Electrical Anticipated Transient Without SCRAM (ATWS) -
Alternate Rod Insertion (ARI)
Successful X
Steam Leak In The Steam Tunnel. D Inboard/Outboard Main Steam Isolation Valves (MSIVs) Fail to Close Loss Of Offsite Power X
3C Diesel Generator (DG)
Fails To Automatically Tie X
ES-301 22 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 23 Form ES-301-7 Facility: Browns Ferry Exam Date:
Scenario 1
2 3
4 5
6 7
8 11 Event Totals Events Unsat.
TS Total TS Unsat.
% Unsat.
Scenario Elements U/E/S Explanation 1
9 0
2 0
2 0
0 E
2 11 0
2 0
2 0
0 E
3 10 0
2 0
3 0
0 E
4 10 0
2 1
3 0
10 E
One TS event was initially Unsatisfactory because it was tracking only.
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 24 Form ES-301-7 Site name: Exam Date:
OPERATING TEST TOTALS Total Total Unsat.
Total Total Unsat.
Explanation Edits Sat.
Admin.
JPMs 9
0 8
1 0
Sim./In-Plant JPMs 11 1
10 0
9 The same simulator JPM tasks were provided for both Unit 2 and Unit 3 simulator. They were only counted once for the purpose of this table. Simulator JPM f was graded as Unsatisfactory because the simulator setup did not match the conditions given in the initial conditions/cue sheet.
Scenarios 4
0 4
0 0
Scenario 5 was removed due to a reduction in the number of applicants.
Op. Test Totals:
24 1
22 1
4 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-401 Record of Rejected K/As Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection RO 1 / 2 295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9 EA1.05 Ability to operate and/or monitor the following as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION: Fuel building ventilation: Plant-Specific Rejected K/A EA1.05 on the premise that it is plant design-specific and BFN does not have a Fuel Building. There is a specific K/A for Secondary Containment Ventilation under 295034 EA1.03 that our Refuel Floor is part of, which leads one to an understanding that Fuel Building has a specific connotation in this context.
Resolution: Replaced K/A EA1.05 with a randomly chosen K/A from the same EAPE K/A Section, yielding EA1.03: Secondary Containment Ventilation.
RO 1 / 2 295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5 G2.2.38 Knowledge of conditions and limitations in the facility license.
Rejected Generic K/A 2.2.38 on the premise that there is no reasonable linkage at BFN. Secondary Containment Sumps / Area Water Levels are not addressed in the facility license (Technical Specifications) in any manner.
Resolution: Keeping the same EAPE, replaced Generic K/A 2.2.38 with a randomly chosen K/A from the same Generic Section, yielding Secondary Containment High Sump/Area Water Level with G2.2.44:
Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
RO 2 / 1 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling K1.08 Knowledge of the physical connections and/or cause-effect relationships between the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) and the following: Line fill pump: Plant-Specific Rejected K/A K1.08 on the premise that it is plant design-specific and BFN does not have a Keep-Fill Pump associated with the RCIC System. The elevation difference (head) from the Condensate Storage Tank is utilized for that purpose at BFN.
Resolution: Replaced K/A K1.08 with a randomly chosen K/A from the same Plant Systems K/A Section, yielding K1.02: Nuclear boiler system.
ES-401 Record of Rejected K/As Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection RO 2 / 1 218000 (SF3 ADS) Automatic Depressurization K4.04 Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) design feature(s) and/or interlocks which provide for the following: Insures adequate air supply to ADS valves: Plant-Specific Rejected K/A K4.04 on the premise of overlap / double jeopardy, as an acceptable question could not be developed for the randomly selected K/A without overlapping concepts tested under a similar K/A on this Sample Plan (295019 AK2.18 / Tier 1 Group 1 below), due to the limited relationship between air supply design features / loss of air to the ADS Valves.
295019 AK2.18 Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the following: ADS: Plant-Specific Resolution: Replaced K/A K4.04 with a randomly chosen K/A from the same Plant Systems K/A Section, yielding K4.03: ADS logic control.
RO 2 / 1 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC)
G2.4.20 Knowledge of the operational implications of EOP warnings, cautions, and notes.
Rejected Generic K/A 2.4.20 on the premise that there is no reasonable linkage at BFN. There is no tie that exists between Uninterruptable Power Supplies and the Warnings, Cautions, or Notes contained in the BFN-specific EOIs (EOPs).
Resolution: Keeping the same System, replaced Generic K/A 2.4.20 with a randomly chosen K/A from the same Generic Section, yielding UPS with G2.4.31: Knowledge of annunciator alarms, indications, or response procedures.
RO 3
G2.4.41 Knowledge of the emergency action level thresholds and classifications.
Rejected Generic K/A 2.4.41on the premise that Unit Operators are not tasked with determining Emergency Action Levels or classifying events, and a discriminating valid question cannot be generated at the RO level.
Resolution: Replaced Generic K/A with a randomly chosen K/A from the same Generic Section, yielding G2.4.3: Ability to identify post-accident instrumentation.
ES-401 Record of Rejected K/As Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection RO 3
G2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
Rejected Generic K/A2.2.25 on the premise that Technical Specification Bases are not required knowledge for Unit Operators, and a discriminating valid question could not be generated at the RO level.
Resolution: Replaced Generic K/A with a randomly chosen K/A from the same Generic Section, yielding G2.2.12: Knowledge of surveillance procedures.
SRO 3
G2.1.3 (SRO Only)
Knowledge of shift or short-term relief turnover practices.
Rejected Generic K/A 2.1.3 on the premise that, in being selected for Tier 3 in particular, it does not meet the requirements of NUREG 1021, Rev 11, Form ES-401-1, Note 9, which specifies "For Tier 3Limit SRO selections to K/As that are linked to 10 CFR 55.43" and this K/A has no 55.43 linkage specified.
Resolution: Replaced Generic K/A 2.1.3 with a randomly chosen K/A from the same Generic Section, yielding G2.1.6: Ability to manage the control room crew during plant transients.
ES-401 Record of Rejected K/As Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection SRO 3
G2.3.12 (SRO Only)
Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
Rejected Generic K/A 2.3.12 on the premise that, in being selected for Tier 3 in particular, it does not meet the requirements of NUREG 1021, Rev 11, Form ES-401-1, Note 9, which specifies "For Tier 3Limit SRO selections to K/As that are linked to 10 CFR 55.43" and this K/A has no 55.43 linkage specified.
Resolution: Replaced Generic K/A 2.3.12 with a randomly chosen K/A from the same Generic Section, yielding G2.3.14: Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
SRO 2/2 259001 Feedwater G2.2.42 (SRO Only)
Ability to recognize system parameters that are entry-level conditions for Technical Specifications.
Rejected the System associated with a Generic K/A on the premise of overlap / double jeopardy, as an acceptable question could not be developed for the System with the randomly selected K/A without overlapping concepts tested under a similar K/A on this Sample Plan (295005 AA2.07 Tier 1 Group 1 below) due to the limited number of Technical Specification entry conditions for Feedwater.
295005 AA2.07 Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP: Reactor Water Level.
Resolution: Replaced System 259001, Feedwater, with a randomly chosen system from Tier 2 / Group 2, yielding System 216000, Nuclear Boiler Instrumentation. Retained K/A G2.2.42.
ES-401 Record of Rejected K/As Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection SRO 2/2 256000 (SF2 CDS) Condensate A2.08 Ability to (a) predict the impacts of the following on the REACTOR CONDENSATE SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High feedwater heater level Rejected the System and K/A based on the premise that based on the System and the K/A, an acceptable SRO level question could not be generated.
Resolution: Replaced System 256000 with a randomly chosen system from Tier 2 / Group 2, yielding system 290001, Secondary Containment. Replaced K/A A2.08 with a randomly chosen K/A A2.01: Ability to (a) predict the impacts of the following on the SECONDARY CONTAINMENT; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Personnel airlock failure.
ES-401 Written Examination Review Worksheet Form ES-401-9 Browns Ferry 2018-301 Q
- 1. LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist Partial Job-Link Minutia
- /Units Backward Q - K/A SRO Only 1
H 2
B S
K/A 95001AA1.02 Question was used on BFN 2009 NRC exam.
Question is Satisfactory.
2 F
2 B
S K/A 295003AA2.01 Question is Satisfactory.
3 H
2 X
M U
K/A 295004G2.4.9 Question was modified from question used on Pilgrim 2007 NRC exam.
Choices B and D are not plausible. For all injection valves to open, then both RHR Loop 1 and 2 would have had to receive automatic initiation signals. Why would either RHR pump not start, with the given conditions, if its associated injection valves received an open signal? Question is Unsatisfactory due to more than one implausible distractor.
6/6/2018-Licensee edited question. Question is now Satisfactory.
4 H
2 B
S K/A 295005AK2.02 Question was used on Brunswick 2010 NRC exam.
Question is Satisfactory.
5 F
2 X
B S
K/A 295006AK1.02 Question was used on BFN 2010 NRC exam.
Question is Satisfactory.
6 H
2 M
S K/A 295016AK3.01 Question was modified from question used on BFN 2015 NRC exam.
Question is Satisfactory.
ES-401 Written Examination Review Worksheet Form ES-401-9 Browns Ferry 2018-301 7
F 2
N S
K/A 295018AK3.03 Question is Satisfactory.
8 H
2 N
S K/A 295109AK2.18 Question is Satisfactory.
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 a 1 (easy) to 5 (difficult); questions with a difficulty between 2 and 4 are acceptable.
- 3.
Check the appropriate box if a psychometric flaw is identified:
Stem Focus: The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
Cues: The stem or distractors contain cues (e.g., clues, specific determiners, phrasing, length).
T/F: The answer choices are a collection of unrelated true/false statements.
Cred. Dist.: The distractors are not credible; single implausible distractors should be repaired, and more than one is unacceptable.
Partial: One or more distractors are partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by the stem).
- 4.
Check the appropriate box if a job content flaw is identified:
Job Link: 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).
Minutia: 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).
- /Units: The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
Backward: 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 K/As that are designated SRO-only. (K/A and license-level mismatches are unacceptable.)
- 6.
Enter questions source: (B)ank, (M)odified, or (N)ew. Verify that (M)odified questions meet the criteria of Form 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 status ratings (e.g., how the Appendix B psychometric attributes are not being met).
ES-401 3
Form ES-401-9 Q
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist Partial Job-Link Minutia
- / Units Backward Q - K/A SRO Only 9
H 2
M S
K/A 295021G2.2.38 Question is Satisfactory.
10 F
2 X
B E
K/A 295023AK3.02 Question was used on Riverbend 2014 NRC exam for a different K/A.
Choice D does not seem plausible for the reason of the One-Rod-Out interlock.
7/3/2018-The question has been edited. All distractors are now plausible. The question indirectly tests the reason for fuel handling equipment interlocks related to preventing refueling accidents. The question is now Satisfactory.
11 H
2 X
B E
K/A 295024EA2.08 Question was used on Riverbend 2007 NRC exam.
Choice A is not plausible. An inadvertent initiation of HPCI by itself will not cause any of the abnormal given conditions.
6/14/2018-Licensee replaced choice A. Question is now Satisfactory.
12 H
2 X
X B
E K/A 295025EK1.03 Submitted for preliminary review.
Taken from Hatch 2007 exam.
(#55)
I am concerned with the question for a couple of reasons. First, the only reference given for the correct answer to the second part question is simulator data after the valves have been cycling for 10 minutes.
Can you give me a steam table or Mollier diagram calculation that would arrive at the same answer for the second part question? I believe that an applicant could successfully argue that predicting the value of tailpipe temperatures given the listed conditions is not a reasonable job-link. We also do not know the frequency that the valves are cycling or their position when the temperatures are being monitored. Are we asking the applicant to model like a simulator? With all of that being said, I would expect them to know that the temperature would have to be less than the normal moderator temperature. So, by knowing that tailpipe temperature is normally less than normal moderator temperature and that the throttling process will lower temperature, the applicant can arrive at the correct answer by eliminating the distractor with basic GFES knowledge alone. The part of the question that tests the K/A is not discriminating.
6/6/2018-Licensee replaced temperature distractor, which made the question discriminating. The new distractor can be eliminated with basic knowledge of plant construction/operation. The question is now Satisfactory.
13 F
2 N
S K/A 295026EA1.03 Question is Satisfactory.
ES-401 4
Form ES-401-9 Q
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist Partial Job-Link Minutia
- / Units Backward Q - K/A SRO Only 14 F
2 M
S K/A 295028EA1.05 Question is Satisfactory.
15 H
3 B
S K/A 295030EK1.02 Question was used on BFN 2010 NRC exam.
Question is Satisfactory.
16 H
2 X
X B
E K/A 295031EA2.01 Choices B(2) and D(2) are not plausible. The correction curves only address pressure. There is no reference of temperature in the given conditions or the question stem.
6/14/2018-Licensee updated second part question and provided plausible answer choices. Question is now Satisfactory.
17 F
2 N
S K/A 295037G2.2.22 Question is Satisfactory.
18 F
2 B
S K/A 295038EK3.02 Based on question used on Grand Gulf 2013 NRC exam.
I do not believe that choices B and C are plausible. Unsatisfactory due to more than one implausible distractor.
6/6/2018-Licensee provided more detailed distractor analysis. The question is now Satisfactory.
19 F
2 M
S K/A 600000AK1.01 Modified from question used on Hatch 2013 NRC exam.
Question is Satisfactory.
ES-401 5
Form ES-401-9 Q
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist Partial Job-Link Minutia
- / Units Backward Q - K/A SRO Only 20 H
2 X
M E
K/A 700000AK2.07 Modified from question used on BFN 2013 NRC exam.
The applicant should know what initial VARS is prior to deciding whether or not he can raise or lower reactive power.
6/6/2018-The licensee provided VARS in the initial conditions. The question is now Satisfactory.
21 H
2 X
M E
K/A 295007AK3.02 Modified from question used on BFN 2011 NRC exam.
The use of the word manual in choices C and D provide a cue that those are not correct answer choices.
6/4/2018-The licensee edited the question to remove the word manual for choices C and D. The question is now Satisfactory.
22 H
2 X
M E
K/A 295008AA1.02 Modified from question used on Columbia 2003 NRC exam.
The question stem asks what the operator will do to restore the required band, when level is already in the required band. What is the purpose of providing the picture of the flow meter?
6/4/2018-The licensee explained the reason for the picture of the flow meter. The question was edited to correct the problem with the stem focus. The question is now Satisfactory.
23 H
2 N
S K/A 295010AK1.03 Question is Satisfactory.
24 H
2 B
S K/A 295014AK2.05 Question is Satisfactory.
25 H
2 X
N E
K/A 295032EA2.01 The orange EOI block on the picture of the alarm provides a cue to the second part question.
6/4/2018-The licensee removed the cue from the picture. The question is now Satisfactory.
26 H
3 M
S K/A 295034EA1.03 Modified from question used on Monticello 2007 NRC exam.
Question is Satisfactory.
ES-401 6
Form ES-401-9 Q
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist Partial Job-Link Minutia
- / Units Backward Q - K/A SRO Only 27 F
2 X
B S
K/A 295036G2.2.44 Question is Satisfactory.
28 H
2 X
B E
K/A 203000G2.2.37 Choices B(2) and D(2) are not plausible distractors due to the time versus flow rate aspect of the answer choices. The light is labeled LOCA Closure Time.
7/3/2018 - The question has been edited. All distractors are now plausible. The question is now Satisfactory.
29 H
2 X
M E
K/A 205000A1.09 Modified from question used on Quad cities 2009 NRC exam.
Choice B is not plausible. If you close the suction valves to a pump, how could the discharge pressure remain the same?
6/14/2018-Licensee provided plausible answer choices. Question is now Satisfactory.
30 H
2 M
S K/A 206000A2.08 Modified from question used on BFN 2012 NRC exam.
Question is Satisfactory.
31 H
2 B
S K/A 209001K5.05 Bank question used on Clinton 2013 NRC exam.
Question is Satisfactory.
32 H
2 B
S K/A 211000A2.07 Bank question used on BFN 2011 NRC exam.
Question is Satisfactory.
ES-401 7
Form ES-401-9 Q
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist Partial Job-Link Minutia
- / Units Backward Q - K/A SRO Only 33 F
2 B
S K/A 212000K4.01 Bank question used on LaSalle 2012 NRC exam.
Question is Satisfactory.
34 F
3 M
S K/A 215003A3.03 Modified from question used on BFN 2013 NRC exam.
Question is Satisfactory.
35 F
2 M
S K/A 215004K6.01 Question is Satisfactory.
36 H
2 B
S K/A 215005A1.02 Question is Satisfactory.
37 F
2 X
B E
K/A 215005K4.02 It seems that choices B and D can be logically eliminated because they are the same type of combination.
6/7/2018-The licensee changed distractor D to make it a different type of combination than B. The question is now Satisfactory.
38 F
2 B
S K/A 217000K1.02 Bank question used on Vermont Yankee 2010 NRC exam.
Question is Satisfactory.
39 F
2 X
N U
K/A 218000K4.03 It seems to me that choices B and D are not plausible distractors because they reset a normal logic rather than inhibit as stated in the question. Question is unsatisfactory due to more than one implausible distractor.
6/7/2018-The licensee provided a new question because changes required to correct the chief examiners concerns on the previous question would cause an overlap problem with question #40. The new question is Satisfactory.
ES-401 8
Form ES-401-9 Q
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist Partial Job-Link Minutia
- / Units Backward Q - K/A SRO Only 40 H
3 B
S K/A 218000K5.01 Bank question used on BFN 2011 NRC exam.
Question is Satisfactory.
41 H
2 X
M E
K/A 223002K1.12 Modified from question used on Fermi 2012 NRC exam.
Need a comma after VENT in the question stem 6/7/2018-Comma has been added. Question is now Satisfactory.
42 F
2 X
M E
K/A 239002K3.03 Modified from question used on BFN 2015 NRC exam.
The second part question is not discriminating as written and reduces the plausibility of the distractors. Add the word previously to the question stem. Remove the word partially from the question stem. This will test the same knowledge, but will reduce the possibility of an applicant merely guessing the correct answer.
6/7/2018-The licensee corrected the issues stated above. The question is now Satisfactory.
43 H
2 X
N E
K/A 259002A4.03 Submitted for preliminary review.
The combination of the first and second parts of choice C is not plausible. With the label saying push for manual control and the second part choice telling you to pull up on the switch, it removes the plausibility that 2-SIC-46-10 is controlling in manual. Also, need to ensure that the component nomenclature (2-SIC-46-10 and 2-HS-10A) is readable on the picture. It just seems a little blurry to me.
6/7/2018-The licensee removed the push for manual control from below the switch. The nomenclature is readable. The question is now Satisfactory.
44 H
3 B
S K/A 261000A1.02 Bank question used on BFN 2015 NRC exam.
Question is Satisfactory.
ES-401 9
Form ES-401-9 Q
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist Partial Job-Link Minutia
- / Units Backward Q - K/A SRO Only 45 F
2 N
S K/A 262001K2.01 Question is Satisfactory. Need to verify that the reference is correct in the WOOTF statement. Is it 500 KV or 161 KV?
46 F
2 B
S K/A 262002A4.01 Bank question used on BFN 2015 NRC exam.
Question is Satisfactory.
47 H
3 B
S K/A 262002G2.4.31 Bank question used on BFN 2012 NRC exam.
Question is Satisfactory.
48 F
2 B
S K/A 263000K2.01 Bank question used on BFN 2014 NRC exam.
Question is Satisfactory.
49 H
2
?
X B
E K/A 264000G2.4.47 ALL needs to be added to the beginning of choices A(2) and B(2).
6/7/2018-Licensee made the changes listed above. The question is now Satisfactory.
50 F
2 X
M E
K/A 300000A3.02 Modified from question used on BFN 2014 NRC exam.
Question does not test the ability to monitor automatic operations. It only tests whether or not an automatic operation exists. This is a very weak match to the K/A, so it was not counted as Unsatisfactory. The question needs to be enhanced so that it better meets the intent of the K/A.
6/4/2018-Licensee edited question so that it tests the ability to monitor automatic operations. The question is now Satisfactory.
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist Partial Job-Link Minutia
- / Units Backward Q - K/A SRO Only 51 F
2 M
S K/A 300000K1.04 Modified from question used on Quad Cities 2012 NRC exam.
Question is Satisfactory.
52 H
2 X
B E
K/A 400000A4.01 Submitted for preliminary review.
Do not believe that choices B(2) and D(2), continues to run, are plausible distractors given the fact that they are the same type load on the same shutdown board. You could just ask, after a specified amount of time, if 1C RBCCW pump will or will not be running.
6/4/2018-Licensee edited the question as discussed above. The question is now Satisfactory.
53 H
2 M
S K/A 400000K3.01 Question is Satisfactory.
54 F
2 N
S K/A 201001K2.04 Question is Satisfactory. Need to verify that Unit Preferred, by itself is how the power supply is normally referred to. It just kind of sounds like something is missing to me.
55 H
2 X
X M
E K/A 201003G2.4.47 Modified from question used on Fitzpatrick 2008 NRC exam.
Need to discuss. I do not believe that choice A is plausible. It seems that choice B could also be correct.
6/7/2018-Licensee changed distractor A to a plausible choice. The question is now Satisfactory.
56 H
2 B
S K/A 202002K6.04 Question is Satisfactory.
57 H
2 X
B E
K/A 215002A3.06 I believe the second bullet in the given conditions needs the word is inserted prior to bypassed. I am not sure what the flow signal failed upscale has to do with the choice B distractor analysis.
6/7/2018-Licensee corrected issues stated above. The question is now Satisfactory.
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist Partial Job-Link Minutia
- / Units Backward Q - K/A SRO Only 58 H
2 X
X M
E K/A 223001K4.02 Modified from question used on Limerick 2012 NRC exam.
Choice B does not seem to be a plausible distractor.
6/7/2018-Licensee replaced distractor B with a plausible choice.
59 H
3 M
S K/A 230000K2.02 Question is Satisfactory.
60 F
2 X
B E
K/A 234000A1.01 Bank question used on BFN 2014 NRC exam.
For the first part question, need to ask the minimum radiation level that will cause the alarm to prevent two correct answers.
6/7/2018-The licensee edited the first part question to prevent two correct answers. The question is now Satisfactory.
61 H
2 X
N S
K/A 241000A4.12 Submitted for preliminary review.
Question is Satisfactory.
62 H
2 M
S K/A 245000A2.09 Question is Satisfactory.
63 F
2 M
S K/A 259001K5.03 Question is Satisfactory.
64 H
2 B
S K/A 272000K3.05 Bank question used on BFN 2011 NRC exam.
Question is Satisfactory.
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist Partial Job-Link Minutia
- / Units Backward Q - K/A SRO Only 65 F
2 X
N S
K/A 286000K1.09 Question is Satisfactory.
66 F
2 X
B E
K/A G2.1.23 Choice C is not plausible.
6/7/2018-Licensee edited distractors C and D. All choices appear to be plausible. The question is now Satisfactory.
67 H
2 X
M E
K/A G2.1.30 Submitted for preliminary review.
ES-401 D.2.a (page 7 of 52) states, Ensure that the questions selected for Tier 3 maintain their focus on plant wide generic K/As and do not become an extension of Tier 2. For this K/A in Tier 3 you could ask how to operate a certain type of valve (MOV), controller, breaker, etc. that is common to multiple systems. The question meets the selected K/A, but not the generic intent of Tier 3. The question was not counted as Unsatisfactory, but needs to be more generic.
6/4/2018-Licensee submitted a question that generically asks about over speed trip devices. Question is now Satisfactory.
68 F
2 X
X B
E K/A G2.1.42 Choice A is not a plausible distractor. The given conditions and question stem do not provide sufficient focus.
6/7/2018-Licensee corrected issues stated above. The question is now Satisfactory.
69 F
2 X
B E
K/A G2.2.20 Bank question used on Sequoyah 2012 NRC exam.
Choices B and C are not plausible. This question can very easily be repaired.
6/7/2018-Licensee changed second part question to ask about work orders for tracking fuse replacement. All choices are plausible. The question is now Satisfactory.
70 F
2 B
E K/A G2.2.12 Bank question used on Hope Creek 2009 NRC exam.
ES-401 D.2.a (page 7 of 52) states, Ensure that the questions selected for Tier 3 maintain their focus on plant wide generic K/As and do not become an extension of Tier 2. The question meets the selected K/A, but not the generic intent of Tier 3. The question was not counted as Unsatisfactory, but needs to be more generic.
6/4/2018-Licensee submitted a question asking about a generic heat up rate surveillance. The question is now satisfactory.
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist Partial Job-Link Minutia
- / Units Backward Q - K/A SRO Only 71 F
3 N
S K/A G2.2.3 Question is Satisfactory.
72 F
2 B
S K/A G2.3.11 Question is Satisfactory.
73 F
2 M
S K/A G2.3.7 Modified from question used on Vermont Yankee 2014 NRC exam.
Question is Satisfactory.
74 H
2 N
S K/A G2.4.2 Question is Satisfactory.
75 F
2 X
B E
K/A G2.4.3 Bank question used on BFN 2012 NRC exam.
Choices B(2) and D(2) are not plausible distractors.
6/7/2018-Licensee changed choices B(2) and D(2) to more plausible distractors.
76 F
2 X
X
?
M E
K/A 295001AA2.01 Modified from question used on Susquehanna 2011 NRC exam.
There exists a high potential for multiple answers to be identified as correct for this question (specifically answer choice A). Based on the wording of the question, operator action is required IAW 2-AOI-68-1A Step [4] only. Although this step mandates referring to the RCP (which could contain operator action), there is no implicit procedural direction to carry out actions of the RCP when AOI entry is undertaken, only to lower power below the 74% load line IAW the AOI. As-written, the correct answer to this question is answer choice A. Enhancement required.
The only procedure selection aspect to this question lies in whether the RCP has precedence or applicability after AOI entry (which the provided supporting references fail to clarify). 2-AOI-68-1A is present in all answer choices negating the procedure selection portion of this information. Supporting reference required governing RCP applicability during AOIs. This step also directs referring to 2-OI-85, which is not mentioned in the question. Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of these procedures? This is probably not SRO-Only. Refer to the flowchart in Attachment 2 of ES-401.
6/25/2018-Licensee provided updated question. Minor edits still required.
7/3/2018-Licensee made edits as required. The question is now Satisfactory.
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist Partial Job-Link Minutia
- / Units Backward Q - K/A SRO Only 77 H
1 X
X M
U K/A 295004G2.4.34 The second part question (which is the part that is SRO Only knowledge) is LOD = 1. With the reference provided and the information given in the stem, the second part answer is basically a direct lookup.
Answer choices A.1 and B.1 are implausible since there are no given conditions specified in the question stem requiring operator evaluation of 2-AOI-100-2, Control Room Abandonment, entry. Single implausible distractor (used twice due to 2x2 format) = Enhancement required.
Use of the word FUNCTIONALITY in the first half question statement cues the applicant that RCIC will remain INOPERABLE following performance of any action provided to answer the first half question. This invalidates the necessity for the two bullets under Subsequently (i.e. RCIC is guaranteed to be INOPERABLE since all second half answer choices contain snippets from the provided 3.5.3 spec). There is no procedure selection or equipment knowledge aspect to this question. Inappropriate cueing = Enhancement required.
Answer choices A.2 and B.2 are implausible based on the given conditions (i.e. HPCI tagged out for maintenance). There is no allowance in the motherhood statements or T.S. rules of usage allowing for selective Required Action entry anywhere in Technical Specifications (i.e. enter action A.2 without an AND A.1). Was it intended to test the concept of whether a tagged out HPCI results in HPCI INOPERABILITY (LOD=1)? Multiple implausible distractors = UNSAT.
7/3/2018-Licensee edited the question. All choices appear to be plausible. SRO only because the applicant must make an operability determination. Question is Satisfactory.
78 H
2 X
N U
K/A 295005AA2.07 Submitted for preliminary review.
Question is Satisfactory.
79 H
2 X
M E
K/A 295024G2.4.8 Some of the information prior to Conditions are as follows: in the question stem provides cueing of EOI entry conditions and procedure selection. What is reason for providing RWL information in the given conditions? Stem Focus = Enhancement required.
Stem can be simplified by stating. With Unit 2 at 100% RTP, an RCS leak occurred. After a non-complicated manual reactor SCRAM, the operating crew notes the following conditions: Drywell Temperature is 220F slowly rising and Drywell Pressure is 2.2 psig slowly rising.
6/4/2018-Licensee corrected issues listed above. The question is now Satisfactory.
80 H
2 X
N E
K/A 295030G2.2.42 Second half question uses negatively stated terms, an undesired method of question construction (Ref NUREG-1021, App B, Page B-10, Item 2.e). Stem Focus = Enhancement required.
What is justification for delaying operator response until exceeding a TS limit? Is this a practice normally followed on-shift? Operational validity concern.
6/4/2018-Licensee corrected issues stated above and added discussion to SRO Only justification statement to explain why this cannot be answered with RO level knowledge. Question is now Satisfactory.
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist Partial Job-Link Minutia
- / Units Backward Q - K/A SRO Only 81 H
2 X
N E
K/A 600000AA2.17 Use of the bolded word confirmed cues the UE declaration at 0915 (there is no evaluation of anything other than block 6.4-U1 for this question). This word can be removed with no impact to the question.
Cueing = Enhancement required.
The first half question is a direct lookup (comment above drives this).
Revising the question to permit applicant selection of UE vs. ALERT using EAL Bases knowledge would be an acceptable method to address this K/A. You can also give a time for a fire alarm and a different time that a fire brigade member reports a fire burning and then use 15 minutes from each of those times for answer and distractors.
6/7/2018-Licensee updated given conditions and two answer choices to correct the issues stated above. The question is now Satisfactory.
82 H
3 X
X N
U K/A 700000AA2.06 Replace the word should in the first half question with is required to.
Remove the word if in the second half question.
The knowledge being tested by the SRO portion of this question (i.e. second half question), is whether a grid frequency of 59 Hz affects only one 4.16kV s/d board (Condition G) or more than one 4.16 kV s/d board (Condition F). The knowledge required to determine the # of affected s/d boards is related to normal plant electrical alignment and does not exceed RO LOK. (Reference ES-401 Att 2, Fig 2-1)
SRO LOK credit cannot be obtained for the procedural selection portion (i.e. first half question) due to use of entry conditions and overall mitigative strategy of the provided AOPs (both of which are RO LOK).
(Reference ES-401 Att 2, Fig 2-2)
Based on the above observations this question contains a license level mismatch = UNSAT 7/3/2018-Licensee edited the second part question to ask if entry into Condition f is or is not required. Bases knowledge is required. Question is now Satisfactory.
83 H
3 M
S K/A 295009G2.2.22 Question is Satisfactory. Changing order of first part and second part questions.
84 H
2 X
X N
E K/A 295013AA2.01 Submitted for preliminary review.
Question used on 2010 BF NRC exam.
With the two classifications precisely listed in answer choices, the applicant only has to evaluate all of the conditions in 1.5-S and 1.2-G against the given conditions.
Why are the pages for the provided reference different between Questions #84 and #81?
6/7/2018-Licensee removed cues. The question is now Satisfactory.
85 F
3 X
B S
K/A 295035EA2.02 Question is Satisfactory.
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist Partial Job-Link Minutia
- / Units Backward Q - K/A SRO Only 86 F
3
?
M E?
K/A 209001A2.06 Reword the first half question to read, Given the flowrate, the 2A CS Pump __(1)__ operate continuously. Enhancement required.
Being that the low level requirement (i.e. definition) for Adequate Core Cooling (ACC) supplied by CS is 6250 gpm (IAW 2-EOI-1, Table L-3), how does the knowledge required to answer the second half question rise above the RO LOK? Is the definition of ACC interpreted to be at the RO LOK?
7/3/2018 - Licensee edited the Question. TS Bases knowledge is required to determine correct answer. The question is now Satisfactory.
87 H
3 X
M E
K/A 211000A2.07 Answer choice C is a single implausible distractor due to Mode 3 transition 6 days in advance of SLC pump OPERABLITY (disqualified by wording of TS 3.1.7 Condition C, a given reference). Single implausible requires repair = Enhancement required.
Additional answer choices can be derived by using the TS section 1.3 Completion Times criteria of multiple INOPERABILITIES (i.e. 2nd SLC pump becomes INOPERABLE and is then restored prior to 1st SLC pump being restored OPERABLE).
6/14/2018-Licensee updated question. All choices are now plausible. Question is now Satisfactory.
88 H
3 N
S K/A215003A2.06 Ensure only pages 3.3-1 through 3.3-6 are provided as reference since Table 3.3.1.1-1 provides information that could provide cues to this and other questions.
Question is Satisfactory.
89 H
2 X
X N
E K/A 261000G2.4.30 Submitted for preliminary review.
75-day Submittal The verbiage contained in the NPG document indicates that a loss of all 3 SBGTs is indeed an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> reportable IAW criteria D.2 and D.4.(C) due to loss of safety function The justification statement doesnt credit use of the phrase MOST RESTRICTIVE and would be much more clear if it did, We need to discuss.
Why are the second and third bullets of the question conditions provided? There is no significance to providing this information. LCO 3.0.3 entry is a given with merely the first bullet (RO LOK). These bullets should be removed. Stem Focus = Enhancement required.
Justification statement for answer choice A cites 3.1.B.1 (safety limit violation) and 3.1.B.3 (50.54x deviation) as a basis for plausibility. There is no information present in the question stem related to a safety limit violation or 50.54x deviation for consideration by the applicant. Single implausible requires repair = Enhancement required.
7/3/2018 - Question stem needs to be reworded because choice D does not work with the question statement.
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist Partial Job-Link Minutia
- / Units Backward Q - K/A SRO Only 90 H
3 X
?
M E
K/A 400000G2.4.2 This question has been modified from the bank question presented as the question source (listed as bank in 401-5).
EOI designation on alarm window needs to be removed.
6/7/2018-Licensee submitted question with EOI designation removed. This action is asking an immediate action required by the TRM. Based on the Technical Specification flowchart contained in Attachment 2 of ES-401, this is normally RO knowledge. Because this is an operability determination that is solely an SRO function and that this type of information is typically listed in the Technical Specification bases, the chief examiner agrees that this can be a test of SRO Only knowledge. The question is now Satisfactory.
91 H
3 X
X N
E K/A 216000G2.2.42 Question statement information at 1330 reads clunky (see below).
What does the phrase AT THIS MOMENT signify? So is time now, 1400 on March 1st? Could an applicant assume THIS MOMENT is 1400 on March 2nd? Can revise provided information to make this clearer, for example:
With Unit 2 at 95% RTP, the following sequence of events has occurred on March 1st:
At 1325, a Reactor Operator reports RPS ANALOG TRIP UNIT TROUBLE (2-9-5B, Window 23) in ALARM At 1330, the Control Room receives a field report that 2-PDIS-1-25B (xxx) is reading DOWNSCALE At 1400, a Reactor Operator discovers 2-PDIS-1-25D (xxx) is reading DOWNSCALE NO operator action has been taken.
Based on the conditions above, which ONE of the following indicates the MOST limiting application of Technical Specifications at 1400 on March 1st?
Answer choice A is cued by the verbiage of answer choice D (based on the as-written wording, the applicant has essentially been provided the information that Condition A requires entry, specifically, and the other channel can proceed under the original Condition A timeframe). This can be fixed by not providing amplifying information in the answer statements. Inappropriate cueing which leads to an implausible distractor (answer choice A) = Enhancement required, single implausible requires repair.
Answer choice C also contains inappropriate cueing (specifically, as Table xxx requires only two per Main Steam Line and there are four transmitters on each Main Steam Line). This is a form of teaching in the question. Inappropriate cueing = Enhancement required.
Why does the justification statement for answer choice C rely on interpretation of Table 3.3.5.1-1 to promote plausibility? The 3.3.5.1 spec isnt asked for in this question.
Also, one of the answer choices has a specific time while the others do not.
6/7/2018-Licensee corrected the issues stated above. The question is now Satisfactory.
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist Partial Job-Link Minutia
- / Units Backward Q - K/A SRO Only 92 H
2 X
M U*
K/A 290001A2.01 Submitted for preliminary review.
New K/A 290001A2.01 The first part question tests AOI immediate actions which is RO knowledge. The second part question (procedure selection) can be answered solely with RO systems knowledge. The question is Unsatisfactory due to not being SRO-Only. *Question not counted as Unsatisfactory for exam report purposes because it was submitted for preliminary review.
First half question relies on knowledge of AOI IMMEDIATE ACTION use to answer (RO LOK). Second half question relies on identification that Heater A1 is a HP FWH to answer (RO LOK). Knowledge of operator actions contained within 1-ARP-9-6A (which potentially could cross over to the SRO LOK) is not necessary to answer this question. Knowledge of overall mitigative strategies (RO LOK) is not required to answer this question.
License level mismatch = UNSAT.
6/7/2018-A new K/A was substituted due to not being able to write a Satisfactory SRO Only question for the condensate system. Although the question tests an immediate Technical Specification action which is normally RO knowledge in accordance with Attachment 2 of ES-401, this question requires bases knowledge of OPDRVS and secondary containment operability. The new question is Satisfactory.
93 H
3 X
N E
K/A 271000A2.08 Ensure the equipment designation nomenclature is included for the Non-Preferred Auto Transfer Sw. This information is included elsewhere for other plant components.
94 H
3 M
S K/A G2.1.25 Question is Satisfactory.
Are the graphs cited as the Reference Provided the same (paper equivalent) graphs used in the simulator/on-shift for these same determinations? Are there any differences between what is provided to the applicants and what they would actually use? (operational validity) 95 H
2 X
X M
U K/A G2.1.6 Submitted for preliminary review.
Original was question #76 on 2015 Cooper NRC exam.
I do not believe that this question tests SRO-Only knowledge. The OATC and UO are required to know their responsibilities during an uncomplicated scram and are assigned this way on the OATC and BOP Hard Cards. This is not a discriminating question at the SRO level and will also probably be tested during the scenarios. With the given conditions, choices A(1) and B(1) are also not plausible. This question is quite different from bank question that was referenced and was changed to being a modified question.
7/3/2018-Licensee submitted a new question. The question is Satisfactory.
96 H
3 B
E K/A G2.2.23 Knowledge required to answer this question is solely related to knowledge of the CREV system and implementation of LCO 3.7.3. With the reference provided this is more of a systems question.
6/4/2018-Licensee submitted question that tested generic LCO 3.0.3 knowledge that tested the K/A. The question is now Satisfactory.
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist Partial Job-Link Minutia
- / Units Backward Q - K/A SRO Only 97 F
1 X
X X?
N U
K/A G2.2.42 Reorder the question stem and 2x2 questions to reside AFTER the data table. Stem Focus = Enhancement required.
This is not a modified question (based on the provided reference question), this question is new.
Why is a reference provided for this question?
Dont understand the justification statement for answer choice A (the correct answer). The justification cites 1010 as being the entry time of LCO 3.6.1.4 Condition A, yet the temperature at 1010 is in full compliance with LCO 3.6.1.4 applicability. The actual time of LCO entry is at a point after 1010 (and before 1020), but is never provided to the applicant for an assessment. This creates a situation when addressing the first half question which relies on the concept of choosing the most correct answer choice (as opposed to a definitively correct choice). Technically, there is no correct answer to this question.
Answer choices B.1/D.1 are implausible. With the provided reference (which requires utilization of no other information apart from above-the-double line RO LOK), 150oF compliance is a given. Single implausible (2x2 format) = Enhancement required.
Answer choices C.2/D.2 are implausible when weighed against the correct answer (answer interplay). Is there any TS LCO at BFN whos specification basis is reliant solely on another LCO but not on maintaining a valid Safety Analysis? Multiple implausible distractors = UNSAT.
Additionally, based on the interplay present between answer choices, this question fails to rise above an LOD=1.
7/3/2018-Licensee edited the question. The question is Satisfactory.
98 F
3 X
X M
E K/A G2.3.14 What knowledge of radiation or contamination hazards is being tested by this question (at a plant generic level)? This appears to be a mitigation of High MSL radiation question. [Q=K/A?]
Why is the first bullet included in this question? It provides cueing/teaching of the set-point for the MSL Radiation Hi-Hi annunciator. It is much clearer to simply provide annunciator status as IN ALARM or LIT.
Stem Focus/Inappropriate cueing = Enhancement required.
The justification statement for the correct answer choice implies that the first bullet is provided to validate the necessity for directing performance of a manual Reactor SCRAM. However, this decision point isnt being tested by the as-written question (it is provided as a given in the first, and second, half question statements). Was it intended for this concept to be elicited knowledge required to successfully answer this half question?
The as-written question allows for no plausibility to be provided to the A.2/B.2 answer choices since an evaluation or statement of entry into 0-EOI-4 is not provided by the question. In other words, why would the plant operators consider 0-EOI-4 usage based on the given conditions (particularly using EOI-4 directly after ALL RODS IN report)? Single implausible (2x2 format) = Enhancement required.
The above can be corrected by providing information in the question stem that 0-EOI-4 has been entered based on offsite dose assessment. The nature of the casualty would have to be modified to accommodate, since fuel failure alone is highly unlikely to result in rad levels exceeding site boundary limits. Adding in information related to EOI-4 entry would also provide a stronger K/A tie.
7/3/2018-Licensee edited the question. The question is Satisfactory.
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist Partial Job-Link Minutia
- / Units Backward Q - K/A SRO Only 99 F
3 X
B E
K/A G2.4.49 There is significant teaching (cueing) presented in the second half answer choices. These can be re-worded and simplified to state:
A.2/C.2 ensure compliance with the SRV Tail Pipe Level Limit (Curve 4)
B.2/D.2 ensure continued usage of the Drywell to Suppression Chamber Vacuum Breakers Inappropriate cueing = Enhancement required.
6/7/2018-Licensee corrected the issues stated above. The question is now Satisfactory.
100 F
3 X
X X
M S
K/A G2.4.9 Question is Satisfactory.