ML060880188

WC-03-2006 - Draft - Final - Outline - Includes Rejected KAs

ML060880188
Person / Time
Site:	Wolf Creek
Issue date:	03/06/2006
From:	Operations Branch IV
To:
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Download: ML060880188 (13)

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ES-401 PWR Examination Outline Form ES-401-2 Facility: Wolf Creek Date of Exam: 3/3/2006 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4 *

1. 1 1 0 6 8 2 1 18 3 3 6 Emergency &

Abnormal 2 1 3 1 1 2 1 9 2 2 4 Plant Evolutions Tier 2 3 7 9 4 2 27 5 5 10 Totals 1 3 3 2 4 3 1 3 3 2 2 2 28 2 3 5 2.

2 0 2 1 0 1 1 1 1 2 1 0 10 1 2 3 Plant Tier 3 5 3 4 4 2 4 4 4 3 2 38 3 5 8 Systems Totals

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 7 Categories 3 2 2 3 1 2 2 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).

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

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding elimination of inappropriate K/A statements.

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

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

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

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IR) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the K/A Catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10CFR55.43 NUREG-1021 1

ES-401 Wolf Creek Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s) Imp. Q#

Emergency Procedures / Plan Knowledge of which events 008 / Pressurizer Vapor Space Accident / 3 X 2.4.30 related to system operations/status should be reported to 3.6 76 outside agencies Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of 015 / 17 / Reactor Coolant Pump Malfunctions / 4 X AA2.08 3.5 77 RC Flow): When to secure RCPs on high bearing temperature 057 / Loss of Vital AC Electrical Instrument Bus / 6 X 2.2.27 Equipment Control Knowledge of the refueling process. 3.5 78 Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water: The valve 062 / Loss of Nuclear Service. Water / 4 X AA2.03 2.9 79 lineups necessary to restart the SWS while bypassing the portion of the system causing the abnormal condition Ability to determine and interpret the following as they apply to the (Loss of Secondary Heat Sink) Adherence to E05 / Loss of Secondary Heat Sink / 4 X EA2.2 4.3 80 appropriate procedures and operation within the limitations in the facility's license and amendments.

E12 / Uncontrolled Depressurization of all Steam Emergency Procedures / Plan Knowledge of symptom X 2.4.6 4.0 81 Generators / 4 based EOP mitigation strategies Emergency Procedures / Plan Ability to perform without 007 / Reactor Trip / 1 X 2.4.49 reference to procedures those actions that require 4.0 39 immediate operation of system components and controls.

Knowledge of the reasons for the following responses as they apply to the Pressurizer Vapor Space Accident: Why 008 / Pressurizer Vapor Space Accident / 3 X AK3.02 3.6 40 PORV or code safety exit temperature is below RCS or PZR temperature Knowledge of the reasons for the following responses as 009 / Small Break LOCA / 3 X EK3.08 the apply to the small break LOCA: PTS limits on RCS 3.6 41 pressure and temperature - NC and FC Ability to operate and monitor the following as they apply 011 / Large Break LOCA / 3 X EA1.11 4.2 42 to a Large Break LOCA: Long-term cooling of core Ability to operate and / or monitor the following as they 015 / 17 / Reactor Coolant Pump Malfunctions / 4 X AA1.16 apply to the Reactor Coolant Pump Malfunctions (Loss of 3.2 43 RC Flow): Low power reactor trip block status lights Ability to operate and / or monitor the following as they 022 / Loss of Reactor Coolant Makeup / 2 X AA1.08 3.4 44 apply to the Loss of Reactor Coolant Makeup: VCT level Ability to operate and / or monitor the following as they 025 / Loss of Residual Heat Removal System / 4 X AA1.23 apply to the Loss of Residual Heat Removal System: 2.8 45 RHR heat exchangers NUREG-1021 2

ES-401 Wolf Creek Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s) Imp. Q#

Knowledge of the operational implications of the following 027 / Pressurizer Pressure Control System Malfunction /

X AK1.01 concepts as they apply to Pressurizer Pressure Control 3.1 46 3

Malfunctions: Definition of saturation temperature Knowledge of the reasons for the following responses as 029 / Anticipated Transient Without Scram (ATWS) / 1 X EK3.12 they apply to the ATWS: Actions contained in EOP for 4.4 47 ATWS Ability to operate and / or monitor the following as they apply to the Steam Line Rupture: Steam pressures and 040 / Steam Line Rupture / 4 X AA1.07 3.4 48 flow rates via computer, safety parameter display system, and other indications Ability to operate and / or monitor the following as they 056 / Loss of Off-site Power / 6 X AA1.07 3.2 49 apply to the Loss of Offsite Power: Service water pump Ability to determine and interpret the following as they 058 / Loss of DC Power / 6 X AA2 03 apply to the Loss of DC Power: DC loads lost; impact on 3.5 50 ability to operate and monitor plant systems Ability to operate and / or monitor the following as they 062 / Loss of Nuclear Service. Water / 4 X AA1.02 apply to the Loss of Nuclear Service Water: Loads on the 3.2 51 SWS in the control room Ability to determine and interpret the following as they 065 / Loss of Instrument Air / 8 X AA2.06 apply to the Loss of Instrument Air: When to trip reactor if 3.6 52 instrument air pressure is de-creasing Ability to operate and / or monitor the following as they E04 / LOCA Outside Containment / 3 X EA1.2 apply to the (LOCA Outside Containment) Operating 3.6 53 behavior characteristics of the facility.

Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary Heat Sink) Normal, E05 / Loss of Secondary Heat Sink / 4 X EK3.2 3.7 54 abnormal and emergency operating procedures associated with (Loss of Secondary Heat Sink).

Knowledge of the reasons for the following responses as they apply to the (Loss of Emergency Coolant Recirculation) RO or SRO function as a within the control E11 / Loss of Emergency Coolant Recirculation / 4 X EK3.4 room team as appropriate to the assigned position, in 3.6 55 such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

NUREG-1021 3

ES-401 Wolf Creek Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s) Imp. Q#

Knowledge of the reasons for the following responses as they apply to the (Uncontrolled Depressurization of all Steam Generators) Facility operating characteristics E12 / Uncontrolled Depressurization of all Steam X EK3.1 during transient conditions, including coolant chemistry 3.5 56 Generators / 4 and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.

K/A Category Point Totals: 1/3 1 0 6 8 2/3 Group Point Total: 18/6 NUREG-1021 4

ES-401 Wolf Creek Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s) Imp. Q#

Emergency Procedures / Plan Ability to perform without 068 / Control Room Evacuation / 8 X 2.4.49 reference to procedures those actions that require 4.0 82 immediate operation of system components and controls.

Ability to determine and interpret the following as they apply to the (Degraded Core Cooling) Facility conditions E06 / Degraded Core Cooling / 4 X EA2.1 4.2 83 and selection of appropriate procedures during abnormal and emergency operations.

Emergency Procedures / Plan Knowledge symptom E09 / Natural Circulation Operations / 4 X 2.4.6 4.0 84 based EOP mitigation strategies.

Ability to determine and interpret the following as they apply to the (SI Termination) Adherence to appropriate E02 / SI Termination / 3 X EA2.2 4.0 85 procedures and operation within the limitations in the facility's license and amendments.

Ability to operate and monitor the following as they apply 024 / Emergency Boration / 1 X AA1.07 3.3 57 to Emergency Boration: BWST level Knowledge of the operational implications of the following 037 / Steam Generator Tube Leak / 3 X AK1.02 concepts as they apply to Steam Generator Tube Leak: 3.5 58 Leak rate vs. pressure drop Ability to determine and interpret the following as they apply to the Accidental Liquid Radwaste Release: That 059 / Accidental Liquid RadWaste Release / 9 X AA2.06 3.5 59 the flow rate of the liquid being released is less than or equal to that specified on the release permit Knowledge of the interrelations between the Accidental Gaseous Radwaste Release and the following: ARM 060 / Accidental Gaseous RadWaste Release / 9 X AK2.01 2.6 60 system, including the normal radiation-level indications and the operability status Knowledge of the interrelations between the Area 061 / Area Radiation Monitoring (ARM) System Alarms /

X AK2.01 Radiation Monitoring (ARM) System Alarms and the 2.5 61 7

following: Detectors at each ARM system location Knowledge of the interrelations between the Control 068 / Control Room Evacuation / 8 X AK2.07 3.3 62 Room Evacuation and the following: EDG Ability to determine and interpret the following as they 069 / Loss of Containment Integrity / 5 X AA2.02 apply to the Loss of Containment Integrity: Verification of 3.9 63 automatic and manual means of restoring integrity Conduct of Operations: Ability to recognize indications for E09 / Natural Circulation Operations / 4 X 2.1.33 system operating parameters which are entry-level 3.4 64 conditions for technical specifications.

NUREG-1021 5

ES-401 Wolf Creek Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s) Imp. Q#

Knowledge of the reasons for the following responses as they apply to the (High Containment Pressure) RO or SRO function as a within the control room team as E14 / High Containment Pressure / 5 X EK3.4 3.3 65 appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

K/A Category Point Total: 1/2 1 3 1 1 2/2 Group Point Total: 9/4 NUREG-1021 6

ES-401 Wolf Creek Form ES-401-2 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp. Q#

Equipment Control Knowledge of limiting conditions for 008 Component Cooling Water X 2.2.22 4.1 86 operations and safety limits.

Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based 013 Engineered Safety Features X A2.03 Ability on those predictions, use procedures to correct, 4.7 87 Actuation control, or mitigate the consequences of those malfunctions or operations; Rapid depressurization Emergency Procedures / Plan Ability to recognize abnormal indications for system operating parameters 064 Emergency Diesel Generator X 2.4.4 4.3 88 which are entry conditions for emergency and abnormal operating procedures Equipment Control: Knowledge of bases in technical 005 Residual Heat Removal X 2.2.25 3.7 89 specifications for LCOs and safety limits.

Ability to (a) predict the impacts of the following malfunctions or operations on the containment system-and (b) based on those predictions, use procedures to 103 Containment X A2 04 3.6 90 correct, control, or mitigate the consequences of those malfunctions or operations Containment evacuation (including recognition of the alarm)

Knowledge of the operational implications of the following concepts as they apply to the RCPS: Effects 003 Reactor Coolant Pump K5.04 3.2 1 of RCP shutdown on secondary parameters, such as steam pressure, steam flow, and feed flow Knowledge of the operational implications of the 004 Chemical and Volume X K5.43 following concepts as they apply to the CVCS: 3.6 2 Control Saturation, subcooling, superheat in steam/water Knowledge of the effect of a loss or malfunction on the 004 Chemical and Volume X K6.17 following will have on the CVCS: Flow paths for 4.4 3 Control emergency boration Knowledge of bus power supplies to the following: RHR 005 Residual Heat Removal X K2.01 3.0 4 pumps Conduct of Operations: Knowledge of system purpose 006 Emergency Core Cooling X 2.1.27 2.8 5 and or function.

Ability to predict and/or monitor changes (to prevent 007 Pressurizer Relief/Quench exceeding design limits) associated with operating the X A1.02 2.7 6 Tank PRTS controls including: Maintaining Quench Tank Pressure Ability to predict and/or monitor changes in parameters to prevent exceeding design limits) associated with 008 Component Cooling Water X A1.02 2.9 7 operating the CCWS controls including: CCW temperature NUREG-1021 7

ES-401 Wolf Creek Form ES-401-2 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp. Q#

Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) 010 Pressurizer Pressure Control X A2.03 based on those predictions, use procedures to correct, 4.1 8 control, or mitigate the consequences of those malfunctions or operations: PORV failures Conduct of Operations: Knowledge of the purpose and 012 Reactor Protection X 2.1.28 3.2 9 function of major system components and controls.

013 Engineered Safety Features Knowledge of the effect that a loss or malfunction of the X K3.01 ESFAS will have on the following: Fuel 4.4 10 Actuation Ability to manually operate and/or monitor in the control 022 Containment Cooling X A4.01 3.6 11 room: CCS fans Knowledge of bus power supplies to the following:

026 Containment Spray X K2.02 2.7 12 MOVs Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with 026 Containment Spray X A1.03 3.5 13 operating the CSS controls including: Containment sump level Knowledge of the operational implications of the 039 Main and Reheat Steam X K5.08 following concepts s the apply to the MRSS: Effect of 3.6 14 steam removal on reactivity Knowledge of the physical connections and/or cause-059 Main Feedwater X K1.04 effect relationships between the MFW and the following 3.4 15 systems: S/GS water level control system Knowledge of MFW design feature(s) and/or interlock(s) 059 Main Feedwater X K4.14 which provide for the following: Start permissives for 3.1 16 MFW pumps 061 Auxillary/Emergency Ability to monitor automatic operation of the AFW, X A3.02 including: RCS cooldown during AFW operations 4.0 17 Feedwater Knowledge of AC Distribution design features and/or 062 AC Electrical Distribution X K4.10 interlocks which provide for the following: 3.1 18 Uninterruptible AC power sources Ability to monitor automatic operation of the dc electrical 063 DC Electrical Distribution X A3.01 system, including: Meters, annunciators, dials, 2.7 19 recorders, and indicating lights Ability to (a) predict the impacts of the following malfunctions or operations on the dc electrical systems; 063 DC Electrical Distribution X A2.01 and (b) based on those predictions, use procedures to 2.5 20 correct, control, or mitigate the consequences of those malfunctions or operations: Grounds NUREG-1021 8

ES-401 Wolf Creek Form ES-401-2 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp. Q#

Ability to manually operate and/or monitor in the control 064 Emergency Diesel Generator X A4.03 3.2 21 room: Synchroscope Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, 064 Emergency Diesel Generator X A2.16 3.3 22 control, or mitigate the consequences of those malfunctions or operations: Loss of offsite power during full-load testing of ED/G Knowledge of PRM system design feature(s) and/or 073 Process Radiation Monitoring X K4.01 interlocks which provide for the following: Release 4.0 23 termination when radiation exceeds setpoint Knowledge of bus power supplies to the following: ESF-076 Service Water X K2.08 3.1 24 actuated MOVs Knowledge of the effect that a loss or malfunction of the 078 Instrument Air X K3.01 3.1 25 IAS will have on the following: Containment air system Knowledge of the physical connections and/or cause-078 Instrument Air X K1.02 effect relationships between the IAS and the following 2.7 26 systems: Service air Knowledge of the physical connections and/or cause-103 Containment X K1.03 effect relationships between the containment system 3.1 27 and the following systems: Shield building vent system Knowledge of containment system design feature(s) 103 Containment X K4.06 and/or interlock(s) which provide for the following: 3.1 28 Containment isolation system K/A Category Point Totals: 2/3 3 3 2 4 3 1 3 3/2 2 2 Group Point Total: 28/5 NUREG-1021 9

ES-401 Wolf Creek Form ES-401-2 NRC Written Examination Outline Plant Systems - Tier 2 Group 2 System #/Name G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp. Q#

Equipment Control: Knowledge of bases in technical 015 Nuclear Instrumentation X 2.2.25 specifications for limiting conditions for operations 3.7 91 and safety limits Emergency Procedures / Plan Ability to diagnose and recognize trends in an accurate and timely 016 Non-nuclear Instrumentation X 2.4.47 3.7 92 manner utilizing the appropriate control room reference material.

Ability to (a) predict the impacts of the following malfunctions or operations on the S/GS; and (b) based on those predictions, use procedures to 035 Steam Generator X A2.01 4.6 93 correct, control, or mitigate the consequences of those malfunctions or operations: Faulted or Ruptured SGs Knowledge of the operational implications of the 011 Pressurizer Level Control X K5.12 following concepts as they apply to the PZR LCS 2.7 29 Criteria and purpose of PZR level program Knowledge of bus power supplies to the following:

015 Nuclear Instrumentation X K2.01 3.3 30 NIS channels, components, and interconnections Knowledge of the effect of a loss or malfunction of 017 In-core Temperature Monitor X K6.01 the following ITM system components: Sensors and 2.7 31 detectors Ability to predict and/or monitor changes in 028 Hydrogen Recombiner and parameter (to prevent exceeding design limits)

X A1.01 3.4 32 Purge Control associated with operating the HRPS controls including: Hydrogen concentration Ability to monitor automatic operation of the 029 Containment Purge X A3.01 3.8 33 Containment Purge System including: CPS isolation Ability to monitor automatic operation of the Spent 033 Spent Fuel Pool Cooling X A3.02 Fuel Pool Cooling System including: Spent fuel leak 2.9 34 or rupture Knowledge of bus power supplies to the following:

001 Rod Control X K2.01 2.8 35 One line diagram of power supply to M/G sets Knowledge of the effect that a loss or malfunction of 071 Waste Gas Disposal X K3.04 the Waste Gas Disposal System will have on the 2.7 36 following: Ventilation system Ability to manually operate and/or monitor in the 035 Steam Generator X A4.06 control room: S/GS isolation on steam leak or tube 4.5 37 rupture/leak NUREG-1021 10

ES-401 Wolf Creek Form ES-401-2 NRC Written Examination Outline Plant Systems - Tier 2 Group 2 System #/Name G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp. Q#

Ability to (a) predict the impacts of the following malfunctions or operations on the Fire Protection System; and (b) based on those predictions, use 086 Fire Protection X A2.04 procedures to correct, control, or mitigate the 3.3 38 consequences of those malfunctions or operations:

Failure to actuate the FPS when required, resulting in fire damage K/A Category Point Totals: 0/2 0 2 1 0 1 1 1 1/1 2 1 Group Point Total: 10/3 NUREG-1021 11

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Wolf Creek Date of Exam: 3/3/2006 RO SRO-Only Category K/A # Topic IR Q# IR Q#

Ability to locate and use procedures and directives 2.1.5 3.4 94 related to shift staffing and activities.

Ability to make accurate, clear and concise verbal 2.1.17 3.5 66 reports.

1. Ability to explain and apply all system limits and Conduct of Operations 2.1.32 3.4 67 precautions.

2.1.22 Ability to determine Mode of Operation. 2.8 68 Subtotal 3 1 Knowledge of the process for managing maintenance 2.2.17 3.5 95 activities during power operations.

Knowledge of the process for conducting tests or 2.2.7 experiments not described in the safety analysis 3.2 96

2. report.

Equipment Control Knowledge of the process for determining the internal 2.2.34 2.8 69 and external effects on core reactivity.

2.2.33 Knowledge of control rod programming. 2.5 70 Subtotal 2 2 Knowledge of the requirements for reviewing and 2.3.6 3.1 97 approving release permits.

Knowledge of radiation exposure limits and 2.3.4 contamination control, including permissible levels in 3.1 98 excess of those authorized.

3. Ability to perform procedures to reduce excessive Radiation Control 2.3.10 levels of radiation and guard against personnel 2.9 71 exposure.

2.3.2 Knowledge of facility ALARA program. 2.5 72 Subtotal 2 2 Knowledge of the process used track inoperable 2.4.33 2.8 99 alarms.

Knowledge of low power / shutdown implications in 2.4.9 accident (e.g. LOCA or loss of RHR) mitigation 3.9 100 strategies.

Knowledge of the parameters and logic used to assess the status of safety functions including: 1 Reactivity

4. 2.4.21 control 2. Core cooling and heat removal 3. Reactor 3.7 73 Emergency Procedures coolant system integrity 4. Containment conditions 5.

/ Plan Radioactivity release control.

Knowledge of RO tasks performed outside the main 2.4.34 control room during emergency operations including 3.8 74 system geography and system implications.

Knowledge of system set points, interlocks and 2.4.2 automatic actions associated with EOP entry 3.9 75 conditions.

Subtotal 3 2 Tier 3 Point Total 10 7 NUREG-1021 12

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A Selected KA topic irrelevant to the APE. Impossible to develop a 1/1 008 G2.4.36 psychometrically sound test item. Replaced with G2.4.30 Selected KA topic irrelevant to the APE. Impossible to develop a 1/1 E12 G2.2.9 psychometrically sound test item. Replaced with G2.4.6 1/1 015 AA1.19 Component does not exist at facility. Replaced with AA1.16 1/1 056 AA1.15 Component does not exist at facility. Replaced with AA1.07 1/2 E15 EA2.2 Unacceptable overlap with system item #13. Replaced with E02 EA2.2 Selected KA topic irrelevant to the APE. Impossible to develop a 2/1 008 G2.3.9 psychometrically sound test item. Replaced with G2.2.22 Selected KA topic irrelevant to the APE. Impossible to develop a 2/1 064 G2.4.38 psychometrically sound test item. Replaced with G2.4.4 2/1 005 K6.03 Unacceptable overlap with EPE/APE item #45. Replaced with 004 K6.17 2/1 059 K1.07 Component does not exist at facility. Replaced with K1.04 2/1 073 K4.02 Interlock does not exist at facility. Replaced with K4.01 Over-sample of topics related to CR Evacuation. No RO task related to 2/2 015 G2.4.34 selected system. Replaced with G2.2.25 2/2 041 K2.02 Component does not exist at facility. Replaced with 001 K2.01 2/2 079 A4.01 Unacceptable overlap with system item #26. Replaced with 035 A4.06 1/2 024 AK1.02 Unacceptable overlap, replaced with AA1.07 1/2 068 AA1.17 Unacceptable overlap, replaced with AK2.07 Topic selected would not yield a test item due to plant design. Replaced with 2/1 078 G2.2.29 005 G2.2.25 2/1 007 A4.04 Component does not exist at facility. Replaced with A1.02 2/1 039 K5.05 SRO level and unacceptable overlap. Replaced with K5.08 Impossible to develop a psychometrically sound test item for the selected 2/1 062 A4.02 topic. Replaced with K4.10 2/2 086 A2.03 Unacceptable overlap with Test Item 38. Replaced with 035 A2.01 Unable to develop psychometrically sound item. Topic has no relevance.

2/2 028 A1.02 Replaced with A1.01 NUREG-1021 13