ML23215A130
| ML23215A130 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/03/2023 |
| From: | Tennessee Valley Authority |
| To: | NRC/RGN-II |
| References | |
| Download: ML23215A130 (1) | |
Text
Facility:
Sequoyah K/A Catalog Rev. 3 Rev.
3 Date of Exam:
2/1/2023 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
Total A2 G*
Total
- 1.
Emergency and Abnormal Plant Evolutions 1
3 5
3 1
3 3
18 2
2 0
1 3
1 1
8 Tier Totals 5
5 4
4 4
4 26
- 2.
Plant Systems 1
2 2
3 2
3 2
3 3
3 2
3 28 2
1 0
1 1
0 1
0 1
1 2
1 9
Tier Totals 3
2 4
3 3
3 3
4 4
4 4
37
- 3.
Generic Knowledge and Abilities Categories CO EC RC EM 6
CO EC RC EM 2
2 1
1
- 4. Theory Reactor Theory Thermodynamics 6
3 3
Notes: CO
=
EM =
Conduct of Operations; EC = Equipment Control; RC = Radiation Control; Emergency Procedures/Plan These systems/evolutions may be eliminated from the sample when Revision 2 of the K/A catalog is used to develop the sample plan.
These systems/evolutions are only included as part of the sample (as applicable to the facility) when Revision 2 of the K/A catalog is used to develop the sample plan.
ES-4.1-PWR Sequoyah Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)
Item E/APE # / Name /
Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR Q#
1 (000007) (EPE 7; BW E02 & E10; CE E02) Reactor Trip, Stabilization, Recovery X
(000007EA1.06) Ability to operate and/or monitor the following as they apply to (EPE 7) REACTOR TRIP, STABILIZATION, RECOVERY: CRDS 3.5 1
2 (000008) (APE 8)
Pressurizer Vapor Space Accident X
(000008) (APE 8) Pressurizer Vapor Space Accident (G2.4.51) EMERGENCY PROCEDURES/PLAN: Knowledge of emergency operating procedure exit conditions (e.g.,
emergency condition no longer exists or severe accident guideline entry is required) 3.0 2
3 (000009) (EPE 9)
Small Break LOCA X
(000009EA2.38) Ability to determine and/or interpret the following as they apply to (EPE 9) SMALL-Break LOCA:
Existence of head bubble 4.0 3
(000011) (EPE 11)
Large Break LOCA 4
(000015) (APE 15)
Reactor Coolant Pump Malfunctions X
(000015AK2.07) Knowledge of the relationship between (APE 15) REACTOR COOLANT Pump Malfunctions and the following systems or components: RCP seals 3.8 4
5 (000022) (APE 22)
Loss of Reactor Coolant Makeup X
(000022AK1.04) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (APE 22) LOSS OF REACTOR Coolant Makeup: Changing from manual to automatic control of charging flow valve controller 3.3 5
(000025) (APE 25)
Loss of Residual Heat Removal System (000026) (APE 26)
Loss of Component Cooling Water 6
(000027) (APE 27)
Pressurizer Pressure Control System Malfunction X
(000027AK2.13) Knowledge of the relationship between (APE 27) PRESSURIZER PRESSURE Control System Malfunction and the following systems or components: PZR master pressure controller 3.9 6
7 (000029) (EPE 29)
Anticipated Transient Without Scram X
(000029) (EPE 29) Anticipated Transient Without Scram (G2.4.12) EMERGENCY PROCEDURES/PLAN: Knowledge of operating crew responsibilities during emergency and abnormal operations 4.0 7
8 (000038) (EPE 38)
Steam Generator Tube Rupture X
(000038EK1.06) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (EPE 38) STEAM GENERATOR Tube Rupture: Initiating an RCS cooldown before isolating the ruptured S/G 4.1 8
(000040) (APE 40; BW E05; CE E05; W E12) Steam Line Rupture - Excessive Heat Transfer
9 (000054) (APE 54; CE E06) Loss of Main Feedwater X
(000054AK2.09) Knowledge of the relationship between (APE 54) LOSS OF Main Feedwater and the following systems or components: AFW 3.9 9
10 (000055) (EPE 55)
Station Blackout X
(000055EA2.08) Ability to determine and/or interpret the following as they apply to (EPE 55) Station Blackout: In-core thermocouple temperatures 3.6 10 11 (000056) (APE 56)
(000056AK2.12) Knowledge of the relationship between (APE 56) Loss of Offsite Power and the following systems or components: RCS 3.9 11 12 (000057) (APE 57)
Loss of Vital AC Instrument Bus X
(000057) (APE 57) Loss of Vital AC Instrument Bus (G2.1.2)
CONDUCT OF OPERATIONS: Knowledge of operator responsibilities during any mode of plant operation KA revised from G2.1.3 (1/3/2023) 4.1 12 13 (000058) (APE 58)
Loss of DC Power X
(000058AK2.03) Knowledge of the relationship between (APE 58) LOSS OF DC Power and the following systems or components: Battery 3.7 13 14 (000062) (APE 62)
Loss of Nuclear Service Water X
(000062AK1.01) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (APE 62) LOSS OF SERVICE WATER: Effect on loads cooled by service water 3.8 14 15 (000065) (APE 65)
Loss of Instrument Air X
(000065AK3.03) Knowledge of the reasons for the following responses and/or actions as they apply to (APE 65) LOSS OF Instrument Air: Knowing effects on plant operation of isolating certain equipment from instrument air KA revised from AK3.05 (1/3/2023) 3.6 15 16 (000077) (APE 77)
Generator Voltage and Electric Grid Disturbances X
(000077AK3.02) Knowledge of the reasons for the following responses and/or actions as they apply to (APE 77)
GENERATOR VOLTAGE AND ELECTRIC Grid Disturbances: Actions contained in AOPs for voltage and grid disturbances 3.5 16 17 (W E04) LOCA Outside Containment X
(WE04EK3.06) Knowledge of the reasons for the following responses and/or actions as they apply to (W E04) LOCA Outside Containment: Identifying and isolating the break 4.3 17 (W E11) Loss of Emergency Coolant Recirculation 18 (BW E04; W E05)
Inadequate Heat Transfer - Loss of Secondary Heat Sink X
(WE05EA2.07) Ability to determine and/or interpret the following as they apply to (W E05) Loss of Secondary Heat Sink: Condensate storage tank level 3.7 18 K/A Category Totals:
3 5
3 1
3 3
Group Point Total:
18
ES-4.1-PWR Sequoyah Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)
Item E/APE # / Name /
Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR Q#
(000001) (APE 1)
Continuous Rod Withdrawal 000003 (APE 3)
Dropped Control Rod
/ 1 (000005) (APE 5)
Inoperable/Stuck Control Rod 000024 (APE 24)
Emergency Boration
/ 1 000028 (APE 28)
Pressurizer (PZR)
Level Control Malfunction / 2 19 (000032) (APE 32)
Loss of Source Range Nuclear Instrumentation X
(000032AA2.06) Ability to determine and/or interpret the following as they apply to (APE 32) LOSS OF SOURCE RANGE Nuclear Instrumentation: Confirmation of reactor trip KA revised from AA2.07 (1/3/2023) 3.7 19 000033 (APE 33)
Loss of Intermediate Range Nuclear Instrumentation / 7 000036 (APE 36; BW/A08) Fuel-Handling Incidents /
8 000037 (APE 37)
Steam Generator Tube Leak / 3 000051 (APE 51)
Loss of Condenser Vacuum / 4 20 (000059) (APE 59)
Accidental Liquid Radwaste Release X
(000059) (APE 59) Accidental Liquid Radwaste Release (G2.1.31) CONDUCT OF OPERATIONS: Ability to locate control room switches, controls, and indications and to determine whether they correctly reflect the desired plant lineup KA revised from G2.1.4 (1/3/2023) 4.6 20 000060 (APE 60)
Accidental Gaseous Radwaste Release /
9 000061 (APE 61)
Area Radiation Monitoring System Alarms / 7 000067 (APE 67)
Plant Fire On Site / 8
000068 (APE 68; BW A06) Control Room Evacuation / 8 (000069) (APE 69; W E14) Loss of Containment Integrity (000074) (EPE 74; W E06 & E07)
Inadequate Core Cooling 000076 (APE 76)
High Reactor Coolant Activity / 9 000078 (APE 78*)
RCS Leak / 3 21 (W E01 & E02)
Rediagnosis & SI Termination X
(WE02EK3.13) Knowledge of the reasons for the following responses and/or actions as they apply to (W E02) SI TERMINATION: Initiating emergency boration (reference potential) 3.7 21 (W E13) Steam Generator Overpressure / 4 22 (W E15)
Containment Flooding X
(WE15EK1.04) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (W E15) Containment Flooding:
Design-basis flood level in containment 3.1 22 23 (W E16) High Containment Radiation X
(WE16EA1.06) Ability to operate and/or monitor the following as they apply to (W E16) HIGH Containment Radiation: ARM system 3.4 23 (BW A01) Plant Runback / 1 (BW A02 & A03)
Loss of NNI-X/Y/7 (BW A04) Turbine Trip / 4 (BW A05)
Emergency Diesel Actuation / 6 (BW A07) Flooding /
8 (BW E03)
Inadequate Subcooling Margin /
4 24 (BW E08; W E03)
LOCA Cooldown -
Depressurization X
(WE03EA1.15) Ability to operate and/or monitor the following as they apply to (W E03) LOCA COOLDOWN AND Depressurization: ECCS 3.9 24 25 (BW E09; CE A13**;
W E09 & E10)
Natural Circulation X
(WE09EK1.05) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (W E09) NATURAL CIRCULATION OPERATIONS: Loss of RCP seal cooling 3.1 25 (BW E13 & E14)
EOP Rules and Enclosures
26 (CE A11**; W E08)
RCS Overcooling -
Pressurized Thermal Shock X
(WE08EA1.16) Ability to operate and/or monitor the following as they apply to (W E08) Pressurized Thermal Shock: AFW system 3.5 26 (CE A16) Excess RCS Leakage / 2 (CE E09) Functional Recovery (CE E13*) Loss of Forced Circulation /
LOOP / Blackout / 4 K/A Category Totals:
2 0
1 3
1 1
Group Point Total:
8
ES-4.1-PWR Sequoyah Plant SystemsTier 2/Group 1 (RO/SRO)
Item System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
27 (003) (SF4P RCP)
REACTOR COOLANT PUMP SYSTEM X
(003K1.02) Knowledge of the physical connections and/or cause and effect relationships between the (SF4P RCP)
REACTOR COOLANT PUMP SYSTEM and the following systems: RCP motor cooling and ventilation 3.4 27 28 (004) (SF1; SF2 CVCS) CHEMICAL AND VOLUME CONTROL SYSTEM X
(004A1.10) Ability to predict and/or monitor changes in parameters associated with operation of the (SF1; SF2 CVCS) CHEMICAL AND VOLUME CONTROL SYSTEM, including: Reactor power 3.8 28 29 (005) (SF4P RHR)
RESIDUAL HEAT REMOVAL SYSTEM X
(005K5.04) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF4P RHR)
RESIDUAL HEAT REMOVAL SYSTEM: Heat load on the RHRS during shutdown, cooldown, and refueling operations 3.5 29 30 (006) (SF2; SF3 ECCS)
EMERGENCY CORE COOLING SYSTEM X
(006K2.02) Knowledge of electrical power supplies to the following: (SF2; SF3 ECCS)
EMERGENCY CORE COOLING SYSTEM Valve operators for safety injection tanks 3.2 30 31 (007) (SF5 PRTS)
PRESSURIZER RELIEF/QUENCH TANK SYSTEM X
(007A1.05) Ability to predict and/or monitor changes in parameters associated with operation of the (SF5 PRTS)
PRESSURIZER RELIEF/QUENCH TANK SYSTEM, including:
Containment radiation levels 3.2 31 32 (008) (SF8 CCW)
COMPONENT COOLING WATER SYSTEM X
(008K6.09) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF8 CCW) COMPONENT COOLING WATER SYSTEM:
SWS 3.8 32
33 (010) (SF3 PZR PCS)
PRESSURIZER PRESSURE CONTROL SYSTEM X
(010K4.01) Knowledge of (SF3 PZR PCS) PRESSURIZER PRESSURE CONTROL SYSTEM design features and/or interlocks that provide for the following: Spray valve warmup 2.8 33 34 (012) (SF7 RPS)
(012A4.03) Ability to manually operate and/or monitor the (SF7 RPS) REACTOR PROTECTION SYSTEM in the control room: Channel blocks and bypasses 3.8 34 35 (013) (SF2 ESFAS)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM X
(013K5.20) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF2 ESFAS)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM: Main steamline break 4.2 35 36 (022) (SF5 CCS)
CONTAINMENT COOLING SYSTEM X
(022) (SF5 CCS)
CONTAINMENT COOLING SYSTEM (G2.1.44) CONDUCT OF OPERATIONS: Knowledge of RO duties in the control room during fuel handling, such as responding to alarms from the fuel handling area, communicating with fuel handling personnel, operating systems from the control room to support fueling operations, or supporting instrumentation 3.9 36 37 (022) (SF5 CCS)
CONTAINMENT COOLING SYSTEM X
(022K2.01) Knowledge of electrical power supplies to the following: (SF5 CCS)
CONTAINMENT COOLING SYSTEM CCS fans 3.6 37 38 (025) (SF5 ICE) ICE CONDENSER SYSTEM X
(025) (SF5 ICE) ICE CONDENSER SYSTEM (191001K1.03) VALVES: The relationship of valve position to flow rate and back pressure 2.9 38 39 (026) (SF5 CSS)
CONTAINMENT SPRAY SYSTEM X
(026K1.05) Knowledge of the physical connections and/or cause and effect relationships between the (SF5 CSS)
CONTAINMENT SPRAY SYSTEM and the following systems: ESFAS 4.1 39 40 (026) (SF5 CSS)
CONTAINMENT SPRAY SYSTEM X
(026K3.01) Knowledge of the effect that a loss or malfunction of the (SF5 CSS)
CONTAINMENT SPRAY SYSTEM will have on the following systems or system parameters: CCS 3.8 40
41 (039) (SF4S MSS)
MAIN AND REHEAT STEAM SYSTEM X
(039A3.03) Ability to monitor automatic features of the (SF4S MSS) MAIN AND REHEAT STEAM SYSTEM, including: Atmospheric relief valves 3.7 41 053 (SF1; SF4P ICS*) INTEGRATED CONTROL SYSTEM 42 (059) (SF4S MFW)
MAIN FEEDWATER SYSTEM X
(059A2.12) Ability to (a) predict the impacts of the following on the (SF4S MFW) MAIN FEEDWATER SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Failure of feedwater regulating valves 3.9 42 43 (061) (SF4S AFW)
AUXILIARY /
(061A2.07) Ability to (a) predict the impacts of the following on the (SF4S AFW)
AUXILIARY/EMERGENCY FEEDWATER SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Air-operated valve, solenoid-operated valve, or motor-operated valve failure 4.0 43 44 (061) (SF4S AFW)
AUXILIARY /
(061K3.02) Knowledge of the effect that a loss or malfunction of the (SF4S AFW)
AUXILIARY/EMERGENCY FEEDWATER SYSTEM will have on the following systems or system parameters: S/G system 4.3 44 45 (062) (SF6 ED AC)
AC ELECTRICAL DISTRIBUTION SYSTEM X
(062A3.05) Ability to monitor automatic features of the (SF6 ED AC) AC ELECTRICAL DISTRIBUTION SYSTEM, including: Safety-related actuations 4.1 45 46 (062) (SF6 ED AC)
AC ELECTRICAL DISTRIBUTION SYSTEM X
(062A3.10) Ability to monitor automatic features of the (SF6 ED AC) AC ELECTRICAL DISTRIBUTION SYSTEM, including: Automatic transfer from auxiliary to reserve transformer 3.3 46
DC ELECTRICAL DISTRIBUTION SYSTEM X
(063K3.03) Knowledge of the effect that a loss or malfunction of the (SF6 ED DC) DC ELECTRICAL DISTRIBUTION SYSTEM will have on the following systems or system parameters: AC distribution system 4.0 47 48 (064) (SF6 EDG)
EMERGENCY DIESEL GENERATOR SYSTEM X
(064A4.02) Ability to manually operate and/or monitor the (SF6 EDG) EMERGENCY DIESEL GENERATOR SYSTEM in the control room:
Adjustment of exciter voltage (using voltage control switch) 3.8 48 49 (073) (SF7 PRM)
PROCESS RADIATION MONITORING SYSTEM X
(073A1.01) Ability to predict and/or monitor changes in parameters associated with operation of the (SF7 PRM)
PROCESS RADIATION MONITORING SYSTEM, including: Radiation levels 3.5 49 50 (076) (SF4S SW)
SERVICE WATER SYSTEM X
(076K4.05) Knowledge of (SF4S SW) SERVICE WATER SYSTEM design features and/or interlocks that provide for the following: Service water train flow and discharge pressure when service water flow to heat exchanger for CCW is throttled 3.3 50 51 (078) (SF8 IAS)
INSTRUMENT AIR SYSTEM X
(078A2.03) Ability to (a) predict the impacts of the following on the (SF8 IAS) INSTRUMENT AIR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations:
Cooling water malfunction 2.5 51 52 (078) (SF8 IAS)
INSTRUMENT AIR SYSTEM X
(078K5.04) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF8 IAS)
INSTRUMENT AIR SYSTEM:
High moisture content in instrument air 2.9 52 53 (103) (SF5 CNT)
CONTAINMENT SYSTEM X
(103) (SF5 CNT)
CONTAINMENT SYSTEM (G2.1.32) CONDUCT OF OPERATIONS: Ability to explain and apply system precautions, limitations, notes, or cautions 3.8 53
54 (103) (SF5 CNT)
CONTAINMENT SYSTEM X
(103K6.15) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF5 CNT)
CONTAINMENT SYSTEM:
MRSS 3.1 54 K/A Category Totals:
2 2
3 2
3 2
3 3
3 2
3 Group Point Total:
28
ES-4.1-PWR Sequoyah Plant SystemsTier 2/Group 2 (RO/SRO)
Item System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
001 (SF1 CRDS)
CONTROL ROD DRIVE SYSTEM 55 (002) (SF2; SF4P RCS) REACTOR COOLANT SYSTEM X
(002A4.04) Ability to manually operate and/or monitor the (SF2; SF4P RCS) REACTOR COOLANT SYSTEM in the control room: The filling/draining of LPI pumps during refueling 3.0 55 (011) (SF2 PZR LCS)
PRESSURIZER LEVEL CONTROL SYSTEM 56 (014) (SF1 RPI) ROD POSITION INDICATION SYSTEM X
(014A4.05) Ability to manually operate and/or monitor the (SF1 RPI) ROD POSITION INDICATION SYSTEM in the control room: RPI accuracy mode selection (W) 3.1 56 015 (SF7 NI)
NUCLEAR INSTRUMENTATION SYSTEM 016 (SF7 NNI)
NONNUCLEAR INSTRUMENTATION SYSTEM 017 (SF7 ITM) IN CORE TEMPERATURE MONITOR SYSTEM 027 (SF5 CIRS)
CONTAINMENT IODINE REMOVAL SYSTEM
(028) (SF5 HRPS)
HYDROGEN RECOMBINER AND PURGE CONTROL SYSTEM 029 (SF8 CPS)
CONTAINMENT PURGE SYSTEM 033 (SF8 SFPCS)
SPENT FUEL POOL COOLING SYSTEM 57 (034) (SF8 FHS)
FUEL HANDLING EQUIPMENT SYSTEM X
(034K1.02) Knowledge of the physical connections and/or cause and effect relationships between the (SF8 FHS) FUEL HANDLING EQUIPMENT SYSTEM and the following systems: RHRS 2.9 57 035 (SF4P SG)
STEAM GENERATOR SYSTEM 58 (041) (SF4S SDS)
STEAM DUMP/TURBINE BYPASS CONTROL SYSTEM X
(041K3.04) Knowledge of the effect that a loss or malfunction of the (SF4S SDS) STEAM DUMP/TURBINE BYPASS CONTROL SYSTEM will have on the following systems or system parameters: Reactor power 4.1 58 59 (045) (SF4S MTG)
MAIN TURBINE GENERATOR SYSTEM X
(045A2.13) Ability to (a) predict the impacts of the following on the (SF4S MTG) MAIN TURBINE GENERATOR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations:
Opening of the steam dumps at low pressure 2.9 59 (050) (SF9 CRV*)
CONTROL ROOM VENTILATION
60 (055) (SF4S CARS)
CONDENSER AIR REMOVAL SYSTEM X
(055) (SF4S CARS)
CONDENSER AIR REMOVAL SYSTEM (191006K1.14) HEAT EXCHANGERS AND CONDENSERS: Reasons for noncondensable gas removal 2.6 60 61 (056) (SF4S CDS)
CONDENSATE SYSTEM X
(056A3.09) Ability to monitor automatic features of the (SF4S CDS) CONDENSATE SYSTEM, including: Automatic protection of MFW pump low suction pressure 3.6 61 068 (SF9 LRS)
LIQUID RADWASTE SYSTEM 62 (071) (SF9 WGS)
WASTE GAS DISPOSAL SYSTEM X
(071K4.06) Knowledge of (SF9 WGS) WASTE GAS DISPOSAL SYSTEM design features and/or interlocks that provide for the following:
Sampling and monitoring of waste gas release tanks 3.0 62 072 (SF7 ARM)
AREA RADIATION MONITORING SYSTEM 075 (SF8 CW)
CIRCULATING WATER SYSTEM 079 (SF8 SAS**)
STATION AIR SYSTEM 63 (086) (SF8 FPS)
FIRE PROTECTION SYSTEM X
(086K6.01) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF8 FPS)
FIRE PROTECTION SYSTEM:
Fire pump failure 3.4 63 K/A Category Totals:
1 0
1 1
0 1
0 1
1 2
1 Group Point Total:
9
Form 4.1-COMMON Common Examination Outline ES-4.1-COMMON COMMON Examination Outline (Sequoyah)
Facility:
Sequoyah Date of Exam:
2/1/2023 Generic Knowledge and Abilities Outline (Tier 3) (RO/SRO)
Category K/A #
Topic RO SRO-Only Item #
IR Q#
IR Q#
- 1.
Conduct of Operations G2.1.15 (G2.1.15) CONDUCT OF OPERATIONS: Knowledge of administrative requirements for temporary management direction, such as standing orders, night orders, or operations memoranda 64 2.7 64 G2.1.19 (G2.1.19) CONDUCT OF OPERATIONS: Ability to use available indications to evaluate system or component status 65 3.9 65 Subtotal N/A 2
N/A
- 2.
Equipment Control G2.2.17 (G2.2.17) EQUIPMENT CONTROL: Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator 66 2.6 66 G2.2.6 (G2.2.6) EQUIPMENT CONTROL: Knowledge of the process for making changes to procedures 67 3
67 Subtotal N/A 2
N/A
- 3.
Radiation Control G2.3.5 (G2.3.5) RADIATION CONTROL: Ability to use RMSs, such as fixed radiation monitors and alarms or personnel monitoring equipment 68 2.9 68 Subtotal N/A 1
N/A
- 4.
Emergency Procedures /
Plan G2.4.42 (G2.4.42) EMERGENCY PROCEDURES/PLAN: Knowledge of emergency response facilities 69 2.6 69 Subtotal N/A 1
N/A Tier 3 Point Total N/A 6
N/A
Form 4.1-COMMON Common Examination Outline ES-4.1-COMMON COMMON Examination Outline (Sequoyah)
Facility:
Sequoyah Date of Exam:
2/1/2023 Theory (Tier 4) (RO)
Category K/A #
Topic RO Item #
IR Q#
Reactor Theory 192006 (192006K1.10) FISSION PRODUCT POISONS: Plot the curve and explain the reasoning for the reactivity insertion by xenon-135 versus time for the following: -- reactor startup with xenon-135 already present in the core 70 3.2 70 192007 (192007K1.01) FUEL DEPLETION AND BURNABLE POISONS:
Define burnable poison and state its use in the reactor 71 2.5 71 192008 (192008K1.23) REACTOR OPERATIONAL PHYSICS:
(REACTOR RESPONSE ON A TRIP) Explain the shape of a curve of reactor power versus time after a trip 72 3.1 72 Subtotal N/A 3
Thermodynamics 193003 (193003K1.17) STEAM: Define the following term: -- subcooling 73 3.2 73 193004 (193004K1.15) THERMODYNAMIC PROCESS: (THROTTLING AND THE THROTTLING PROCESS) Determine the exit conditions for a throttling process based on the use of steam and/or water 74 2.8 74 193009 (193009K1.03) CORE THERMAL LIMITS: Explain local peaking factor 75 2.7 75 Subtotal N/A 3
Tier 4 Point Total N/A 6
Form 4.1-1 Record of Rejected Knowledge and Abilities Refer to Examination Standard (ES)-4.2, Developing Written Examinations, Section B.3, for deviations from the approved written examination outline.
Tier/Group Randomly Selected K/A Reason for Rejection 1 / 1 RO (Q12) 057G2.1.3 1/3/2023 Replaced with 057G2.1.2 because both parts of original KA were not related (generic).
1 / 1 RO (Q15) 065AK3.05 1/3/2023 Replaced with 065AK3.03 because plant equipment does not support the intent of the KA.
1 / 2 RO (Q19) 032AA2.07 1/3/2023 Replaced with 032AA2.06 because surveillance does not list any allowable disagreement (unable to meet intent of KA).
1 / 2 RO (Q20) 059G2.1.4 1/3/2023 Replaced with 059G2.1.31 because both parts of original KA were not related (generic).
2 / 1 RO (Q36) 022G2.1.43 11-14-2022 Replaced with 022G2.1.44 because original KA was not conducive to writing a discriminating question for the randomly selected system.
2 / 2 RO (Q60) 055 (191006) K1.09 11-14-2022 Replaced with 055 (191006) K1.14 because original K/A was not conducive to writing a discriminating question for the randomly selected system.
Form 2.3-5 Written Examination Review Worksheet Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. K/A Use Flaws
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job Link Minutia #/Units Logic Q-K/A License Level 1
H 3
N S
Rev 0 (E)
- Revise first bullet under current conditions to state: A valid automatic reactor trip signal is generated (cueing of valid RPS trip signal)
- Revise second bullet under current conditions to state: RTB and BYA UV trip coils failed to actuate.
Rev 1 (discussion 2-21)
- Revise first half question to read: In response to the reactor trip signal, BYA will/will NOT open. (to drive cognitive level to H)
- remove due to low s/g level Rev 2
- question is SAT 2
H 3
B S
Rev 0 (procedure w/edit) (U)
- Non-discriminatory A.2/C.2 distractors, specifically with provided pressure (far above RPS trip setpoint). (LOD)
- Revise second bullet under subsequently to read: Lowest RCS pressure observed is 1900 psig
- Revise second half question/answer choices to read: In accordance with AOP-I.04, entry into E-0, Reactor Trip or Safety Injection, is/is NOT required.
- IA concept (AOP-I.04) in Question #65 Rev 1
- Potential for multiple correct answers (ref AOP-I.04 IA step 1 RNO),
revise IC: U1 in M3 with all rods in (e.g. after TS required s/d), and revise 2nd bullet to read RCS press is 1900# and continuing to lowering, A is only correct answer Rev 2
- question is SAT 3
H 3
B S
Rev 0 (procedure w/edit) (U)
- 2nd half answer cued directly by two provided indications/trend of containment pressure (also not pertinent to KA). (LOD)
- Remove bullets regarding containment pressure (0.8 psig and stable) (x2)
- Revise question stem to read: With the conditions provided above, which one of the following completes the statements below?
- Revise second half question to read: In accordance with ECA-3.1, an indication of rapidly rising pressurizer level is/is NOT due to upper head voiding.
Rev 1 (discussion 2-21)
- Higher cog with edit Rev 2
- question is SAT 4
H 3
B S
Rev 0 (U)
- Question concerns casualty affecting FCV-62-89 and downstream impact to RCP seal injection flow. As written question has no tie to RCP pump malfunction. Valid question, wrong system. (Q=K/A)
Rev 1 (discussion 2-21)
- acceptable concept to move forward on, related to RCP seals Rev 2
- question is SAT
Form 2.3-5 Written Examination Review Worksheet Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. K/A Use Flaws
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job Link Minutia #/Units Logic Q-K/A License Level 5
H 3
N S
Rev 0
- Remove bolded assumption provided by PZR lvl/% (cue)
- B identified as correct choice, yet justification identifies D as correct?
(calculation indicates B)
- What are the PZR levels associated with answer choices A, C and D and why are they plausible?
Rev 1 (discussion 2-21)
- Revised justifications for distractor choices Rev 2
- question is SAT 6
H 3
B S
Rev 0
- No comments, SAT 7
H 3
N S
Rev 0 (procedure)
- Remove the sixth bullet (2nd indented one), No RCS dilution is in progress (none provided as plant condition and not possible with provided procedure entries/casualty) (cue)
Rev 2
- question is SAT 8
H 3
B S
Rev 0 (procedure)
- No comments, SAT 9
F 3
N S
Rev 0 (procedure w/edit)
- Revise second half question to read: An automatic Main Turbine runback to ~50%/ ~72% load will occur.
- Reorder to place runback as first half and TDAFW as second half questions.
Rev 2
- question is SAT 10 F
3 N
S Rev 0
- No comments, SAT 11 F
3 N
S Rev 0 (U)
- Revise first half question to read: Immediately after the LOOP, core cooling will/ will NOT be provided by RCPs. (remove cueing)
- Revise second half question to read: One minute after the LOOP, RCPs can/ can NOT be restarted. (remove cueing)
- Justification writeup does not match actual question, revision required Rev 1 (discussion 2-21)
- Question statements revised. Immediately after LOOP and one minute after LOOP.
Rev 2
- question is SAT 12 H
3 B
S Rev 0
- No comments, SAT 13 F
3 N
S Rev 0 (procedure)
- No comments, SAT
Form 2.3-5 Written Examination Review Worksheet Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. K/A Use Flaws
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job Link Minutia #/Units Logic Q-K/A License Level 14 H
3 B
S Rev 0
- Revise answer choice A to read: A supply header has ruptured in the Yard area.
- Revise answer choice D to read: A rupture has occurred downstream of the 1A strainer.
Rev 2
- question is SAT 15 F
3 N
S Rev 0 (U)
- Remove (3) bullets and question from question stem (not needed to answer question) (focus)
- Revise question to read: WOOTF completes the statements below.
- Revise first half question to read: FCV-62-73, Letdown Orifice Isolation receives actuation air pressure from the Control/ Aux Control air header.
Rev 1 (discussion 2-21)
- Revised first half to use 62-93 vs comment above Rev 2
- question is SAT 16 H
3 N
S Rev 0 (procedure w/edit) (U)
- Revise question stem to read: In accordance with AOP-P.07, Degraded Grid or Abnormal Voltage Conditions, WOOTF
- Revise first half question to read: A reactor and main turbine trip will/ will NOT be directed. (no plausibility of EDG E-bus ties with given conditions)
- Fix spacing issues in second half answer choices
- Revise B.2/D.2 answer choices to read: exceeding analysis limits concerning speed of safety-related motors Rev 2
- question is SAT 17 F
3 N
S Rev 0
- No comments, SAT 18 F
3 N
S Rev 0 (procedure)
- No comments, SAT 19 F
3 N
S Rev 0
- Revise answer choices to include N31 Rev 2
- question is SAT 20 F
3 B
S Rev 0 (procedure)
- Revise question stem to read: concerning the required system alignment in accordance with the annunciator response procedure, 0-AR-M12-A Window E-1. (second half question cue)
Rev 2
- question is SAT 21 H
3 N
S Rev 0 (procedure, reference)
- Remove the reference clarifier (ignore effects of xenon)
Rev 2
- question is SAT
Form 2.3-5 Written Examination Review Worksheet Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. K/A Use Flaws
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job Link Minutia #/Units Logic Q-K/A License Level 22 F
3 B
SQN 2003 S
Rev 0 (procedure w/edit) (U)
- Revise answer choices A.1/D.1 to read: Lower containment sump level.
(distractor focus)
- Revise second half answer choices to read: Components needed for plant recovery could be damaged due to high water level/ water radioactivity level Rev 2
- question is SAT 23 H
3 B
S Rev 0
- Capitalize BOTH in A.1/B.1 distractors Rev 2
- question is SAT 24 H
3 B
S Rev 0 (procedure)
- No comments, SAT 25 F
3 N
S Rev 0 (procedure) (U)
- Distractor analysis does not align with as-written question, revision required.
- What is plausibility for first half question? Seal cooling is established based on the given condition (8 gpm per each pump) No clarification regarding the term established within ES-0.3.
Rev 2-21
- question is adequate, still low cog Rev 2
- question is SAT 26 H
3 N
S Rev 0 (procedure)
- Revise question stem to read: WOOTF identifies the FIRST required action in accordance with FR-P.1?
Rev 2
- question is SAT 27 F
3 B
S Rev 0
- No comments, SAT 28 H
3 B
S Rev 0
- No comments, SAT 29 H
3 B
S Rev 0
- No comments, SAT 30 F
3 B
S Rev 0
- No comments, SAT
Form 2.3-5 Written Examination Review Worksheet Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. K/A Use Flaws
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job Link Minutia #/Units Logic Q-K/A License Level 31 H
3 B
S Rev 0 (U)
- First half question can be answered with either provided answer choice.
(focus, plausibility)
- Revise given conditions to add: Annunciator PS-68-301, Pressurizer Relief Tank Press High alarm received & Maximum indication observed on 1-PI-68-301, PRT PRESS, is 77 psig
- Revise first half question to read: Containment pressure is/ is NOT expected to be increasing.
- Revise second half question to read: The RCS leakrate __(2)__
Rev 2
- question is SAT 32 H
3 B
S Rev 0 (U)
- Justification for answer choice D indicates this as a potentially correct answer choice. Revise answer choice to be specific to a component or clarify justification writeup.
Rev 2
- question is SAT 33 F
3 B
S Rev 0 (procedure)
- No comments, SAT 34 H
3 N
S Rev 0
- No comments, SAT 35 H
3 B
S Rev 0
- Two different distractor analyses for this question. Neither listed works, revision required.
- Add a new bullet before Subsequently to clarify which procedure is currently in effect (question is unclear, i.e. requires assumption as to where in EOP network crew currently is, e.g. still in/xsitioned back into E-0 or all CSFSTs are currently yellow/green, etc etc)
- Add a rate of 200# per minute of SG pressure loss to subsequently bullet Rev 2
- question is SAT 36 H
3 N
S Rev 0 (procedure)
- Remove bullet concerning 131A alarm NOT lit (not necessary to answer question)
Rev 1 (discussion 2-21)
- removed annunciator Rev 2
- question is SAT 37 F
3 N
S Rev 0
- No comments, SAT
Form 2.3-5 Written Examination Review Worksheet Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. K/A Use Flaws
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job Link Minutia #/Units Logic Q-K/A License Level 38 F
3 B
S Rev 0 (U)
- Revise answer choice A to read: Melted ice is directed away from the inlet doors by turning vanes (cueing)
- Remove parenthesis statement from second half answer
- Revise answer choice B to read: Half of the ice bays have a drain which directs (focus, cueing)
- Revise answer choice C to read: Inlet doors have proportioning springs to modulate door opening (cueing)
- Revise answer choice D to reflect the as-written justification (i.e. springs on intermediate doors) (plausibility of all ice condenser unit start for LOCA, this is a passive system)
Rev 2
- question is SAT 39 H
3 B
SQN 2003 S
Rev 0 (procedure)
- Phase B reset present in all answer choices except the correct choice.
(cueing)
- Revise answer choice C to read: Reset BOTH Train A and Train B Containment Spray signals Rev 2
- question is SAT 40 F
3 N
S Rev 0 (procedure)
- No comments, SAT 41 H
3 B
S Rev 0 (procedure, reference - Steam Tables)
- Reference use discussion Rev 2
- question is SAT 42 F
3 N
S Rev 0 (procedure)
- Remove rate of SGWL drop: #1 SG level begins lowering Rev 1 (discussion 2-21)
- Discussion occurred, no changes required Rev 2
- question is SAT 43 F
3 B
S Rev 0 (procedure)
- Is the correct component nomenclature used for this question (1-HS 51A-S vs 1-HS-51 used in procedure)?
Rev 1 (discussion 2-21)
- correct nomenclature is being used Rev 2
- question is SAT 44 H
3 B
S Rev 0
- No comments, SAT
Form 2.3-5 Written Examination Review Worksheet Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. K/A Use Flaws
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job Link Minutia #/Units Logic Q-K/A License Level 45 H
3 B
S Rev 0
- Revise second bullet to read: Vital Instrument Power Board 1-I is out of service Rev 1 (discussion 2-21)
- no changes required Rev 2
- question is SAT 46 F
3 N
S Rev 0
- Remove first bullet and subsequently from stem
- Revise remaining bullet to read: The 6900/480V transformer aligned to 480V Unit Board 1A fails.
- Revise second half question to include the appropriate procedure (i.e.
IAW 1-SO-201-5, 480V Unit Boards, Rev 2
- question is SAT 47 H
3 B
S Rev 0 (U)
- This question does not meet the intended KA (question concerns knowledge of loss/malfunction of AC on DC distribution), KA asks for knowledge of opposite) (Q=K/A)
Rev 1 (discussion 2-21)
- Need new, discussion on alternative Rev 2
- question is SAT 48 F
3 N
S Rev 0 (procedure)
- Revise B.2/D.2 distractors to read: be slightly higher than Rev 2
- question is SAT 49 H
3 B
S Rev 0
- Revise answer choice B to read: Radiation Monitor 2-RM-90-123A indication rises. Only Surge Tank vent valve 2-FCV-70-66 closes when the monitor reaches the HIGH rad setpoint.
Rev 2
- question is SAT 50 F
3 B
S Rev 0
- No comments, SAT
Form 2.3-5 Written Examination Review Worksheet Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. K/A Use Flaws
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job Link Minutia #/Units Logic Q-K/A License Level 51 H
3 N
S Rev 0 (procedure) (U)
- Answer choice A is implausible based on stem information (i.e. actively performing EA-32-2, Establishing Control and Service Air), is this distractor based on procedure revision?? May be plausible if true
- Answer choices C and D dont appear to be plausible together, there isnt anything in question stem requiring differentiation of these choices, only if ERCW parameters are appropriate (e.g. why would applicant select either of these options considering question is solely focused on ERCW)
- Question modified to read: if compressor can be started with parameters above/below 55#/85F could be valid here.
Rev 1 (discussion 2-21)
- no changes required, justification statements revision required Rev 2
- question is SAT 52 F
3 N
S Rev 0
- Misspelled accordance in question stem Rev 2
- question is SAT 53 F
3 N
S Rev 0
- No comments, SAT 54 F
3 B
S Rev 0
- No comments, SAT 55 F
3 B
S Rev 0 (procedure)
- Revise third bullet under subsequently to read: RCS water level is 6970 (redundant to first bullet information)
- Revise second half question to read: If an RHR pump exhibits..
Rev 2
- question is SAT 56 H
3 N
S Rev 0 (procedure)
- Remove bullet concerning Rod E4 (focus)
Rev 2
- question is SAT 57 F
3 N
S Rev 0 (procedure) (U)
- 15 minutes (as an answer choice) coupled with either maintenance or surveillance testing (as an answer choice) is implausible.
- Revise A.2/C.2 distractors to read: Train swapping
- Revise A.1/B.1 distractors to read: 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Rev 1
- New question substituted based on RHR interrelation with refueling cavities Rev 2
- question is SAT
Form 2.3-5 Written Examination Review Worksheet Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. K/A Use Flaws
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job Link Minutia #/Units Logic Q-K/A License Level 58 H
3 N
S Rev 0
- Revise first half question to read: When steady conditions are reached, Reactor Power will be
- Is this operationally valid? Seems that given question would result in protective action, modification of given conditions required Rev 1 (discussion 2-21)
- Added procedure to first half question, P&Ls, revised wording Rev 2
- question is SAT 59 F
3 B
S Rev 0 (procedure)
- Justification writeup requires modification to conform to as-written question (multiple writeups present)
Rev 2
- question is SAT 60 H
3 N
S Rev 0
- Misspelling in question stem: following
- Break apart last bullet for better visibility to applicant (i.e. Subsequently B pump trips
- Revise question statement to read: Condenser backpressure will __(1)__
and Condenser vacuum pump C __(2)__ immediately auto start.
Rev 2
- question is SAT 61 F
3 N
S Rev 0
- No comments, SAT 62 H
3 N
S Rev 0
- Misspelled completes in question stem Rev 2
- question is SAT 63 H
3 B
S Rev 0
- Confusing negatively worded answer choices should NOT be LIT /
ONLY
- Revise question statement and answer choices to read as positive statements: The adverse light indication(s) observed is/are Amber/ Amber
& White / Red / White & Red Rev 2
- question is SAT 64 F
3 N
S Rev 0
- No comments, SAT 65 H
3 B
S Rev 0 (U)
- C.1/D.1 distractors are not plausible, answer is provided by bullet three or stem information, IA concept overlap with Question #2 (IAs related to PORV block valves)
- Revision required Rev 2
- question is SAT 66 F
3 N
S Rev 0 (procedure)
- No comments, SAT
Form 2.3-5 Written Examination Review Worksheet Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. K/A Use Flaws
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job Link Minutia #/Units Logic Q-K/A License Level 67 F
3 N
S Rev 0 (procedure)
- No comments, SAT 68 F
3 B
SQN 2010 S
Rev 0
- Replace the word trending in answer choices A.1/B.1 with responds (or vice versa for consistency)
Rev 2
- question is SAT 69 F
3 N
S Rev 0 (procedure)
- No comments, SAT 70 H
3 B
S Rev 0
- Revise first sentence of question stem to read: A reactor startup is being performed shortly after a TRIP following a steady state 100% power history.
Rev 2
- question is SAT 71 F
3 B
S Rev 0
- No comments, SAT 72 H
3 B
S Rev 0
- No comments, SAT 73 H
3 B
S Rev 0 (reference - Steam Tables)
- Revise 1000 psia to 985 psig in first sentence.
- Answer choices have no basis for justification included in analysis, back calculating fails to reveal why these answer choices are plausible
- Revise answer choices to read: 555 psia (Tsat for 985#-65F), 566 psia (Tsat for 1000#-65F), 639 psia (Tsat for 985#-50F), 650 psia (correct, Tsat for 1000#-50F)
- Revise question to include Steam Tables as a reference Rev 2
- question is SAT 74 H
3 B
S Rev 0 (reference - Steam Tables, Mollier)
- Revise question to include Steam Tables as a reference
- Revise question statement to read: being collected in the Pressurizer Relief Tank
- convert pressures to psig Rev 2
- question is SAT 75 F
3 B
S Rev 0 (U)
- Revise answer choices A.1/C.1 to read 100 steps (plausibility of rod speed for overlap), use insertion overlap value
- Revise C.2/D.2 answer choices to read: To provide a more uniform flux distribution during rod withdrawal and insertion Rev 2
- question is SAT
Form 2.3-5 Written Examination Review Worksheet Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. K/A Use Flaws
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job Link Minutia #/Units Logic Q-K/A License Level LOK (F/H) LOD SF Cue T/F Cred.
Dist.
Par Job Link Minutia
- /units Logic Q=K/A SRO only B/M/N U/E/S Revision History 38-45 H
75 B /
10 N @
H Rev 0: Draft submittal review (received 1-13 through 2-2-2023)
Rev 1: Review discussion with facility (2-21-2023)
Rev 2: Final submittal review (3-7-2023)
RO 39 40B /
13N @ H
Form 2.3-5 Written Examination Review Worksheet Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. K/A Use Flaws
- 6. Source (B/M/N)
- 7. Status (U/E/S)
- 8. Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job Link Minutia #/Units Logic Q-K/A License Level Instructions:
Refer to ES-4.2 for the definitions of terms used in this worksheet for the written examination. Review each question (Q) as submitted and as subsequently revised and document the following in the associated worksheet columns:
- 1. Enter the level of knowledge (LOK) as either (F)undamental or (H)igher cognitive level.
- 2.
Enter the level of difficulty (LOD) from 1 (easy) to 5 (difficult); mark direct lookup questions (applicant can directly determine the answer from the provided reference) as LOD 1. A question is (U)nsatisfactory if it is LOD 1 or LOD 5.
- 3.
Check the appropriate box if a psychometric flaw is identified:
Stem Focus: The stem lacks enough focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information). This is an (U)nsatisfactory question.
Cues: The stem or one or more answer choices contains cues (e.g., clues, specific determiners, phrasing, length). This is an (U)nsatisfactory question.
T/F: All of the answer choices are a collection of unrelated true/false statements. This is an (U)nsatisfactory question.
Cred. Dist.: The distractors are not credible; single implausible distractors require (E)nhancement, and more than one noncredible distractor in the same question results in an (U)satisfactory question.
Partial: One or more distractors are partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by the stem). This is an (U)nsatisfactory question.
- 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 knowledge or ability (K/A) but, as written, is not operational in content). This is an (U)nsatisfactory question.
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). This is an (U)nsatisfactory question.
- /Units: The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
This is an (U)nsatisfactory question.
Logic: The question requires backward or reverse logic or application compared to the job requirements. This is an (U)nsatisfactory question.
- 5.
Check the first box if a K/A mismatch flaw exists. Check the second box if the question is flawed because it is written at the wrong license level. Either condition results in an (U)nsatisfactory question.
- 6.
Enter the questions source: (B)ank, (M)odified, or (N)ew. Verify that (M)odified questions meet the criteria of ES-4.2.
- 7.
Based on the review performed in steps 2-5, mark the question as (U)nsatisfactory, in need of (E)nhancement, or (S)atisfactory.
- 8.
Fully explain the reason for any (U) in column 7 (e.g., how the psychometric attributes are not being met).
Save the initial review comments and detail subsequent comment resolution so that each exam-bound question is marked by an (S) on this form.