ML061560073
| ML061560073 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 08/22/2005 |
| From: | Gody A Operations Branch IV |
| To: | Naslund C Union Electric Co |
| References | |
| 50-483/05-301, ES-401, ES-401-2, NUREG-1021 50-483/05-301 | |
| Download: ML061560073 (11) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: Callaway Date of Exam: 8/22/2005 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 1 3 7 4 2 18 3 3 6 Emergency &
Abnormal 2 1 2 2 2 2 0 9 2 2 4 Plant Evolutions Tier 2 3 5 9 6 2 27 5 5 10 Totals 1 4 2 2 4 2 2 3 3 2 3 1 28 3 2 5 2.
2 1 2 1 0 0 1 0 0 2 1 2 10 1 2 3 Plant Tier 5 4 3 4 2 3 3 3 4 4 3 38 Systems 4 4 8 Totals
- 3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 7 Categories 2 2 2 4 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: if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-Only exam, enter it on the left side of column A2 for Tier 2, Group 2. 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 Callaway Form ES-401-2 PWR BOTH 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#
Ability to determine and interpret the following as they 008 / Pressurizer Vapor Space Accident / 3 X AA2.30 apply to the Pressurizer Vapor Space Accident: 4.7 76 Inadequate Core Cooling Equipment Control Knowledge of bases in technical 011 / Large Break LOCA / 3 X 2.2.25 specifications for limiting conditions for operations and 3.7 77 safety limits.
Ability to determine and interpret the following as they 022 / Loss of Rx Coolant Makeup / 2 X AA2.03 apply to the Loss of Reactor Coolant Makeup: Failures of 3.6 78 flow control valve or controller Conduct of Operations: Ability to explain and apply all 038 / Steam Gen. Tube Rupture / 3 X 2.1.32 3.8 79 system limits and precautions.
Emergency Procedures / Plan Ability to perform without 054 / Loss of Main Feedwater / 4 X 2.4.49 reference to procedures those actions that require 4.0 80 immediate operation of system components and controls.
Ability to determine and interpret the following as they apply to the (LOCA Outside Containment) Facility E04 / LOCA Outside Containment / 3 X EA2.1 4.3 81 conditions and selection of appropriate procedures during abnormal and emergency operations.
Ability to operate and monitor the following as they apply 007 / Reactor Trip - Stabilization - Recovery / 1 X EA1.02 3.8 39 to a reactor trip: MFW System Knowledge of the interrelations between the Pressurizer 008 / Pressurizer Vapor Space Accident / 3 X AK2.03 Vapor Space Accident and the following: Controllers and 2.5 40 positioners Knowledge of the reasons for the following responses as 009 / Small Break LOCA / 3 X EK3.12 3.4 41 they apply to the small break LOCA: Letdown isolation Conduct of Operations: Ability to perform specific system 011 / Large Break LOCA / 3 X 2.1.23 and integrated plant procedures during all modes of plant 3.9 42 operation.
Conduct of Operations: Ability to locate and operate 025 / Loss of RHR System / 4 X 2.1.30 3.9 43 components, including local controls.
Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: The 026 / Loss of Component Cooling Water / 8 X AA2.06 2.8 44 length of time after the loss of CCW flow to a component before that component may be damaged Ability to determine and interpret the following as they 027 / Pressurizer Pressure Control System Malfunction /
X AA2.04 apply to the Pressurizer Pressure Control Malfunctions: 3.7 45 3
Tech-Spec limits for RCS pressure Ability to operate and monitor the following as they apply 029 / ATWS / 1 X EA1.10 3.6 46 to a ATWS: Rod control function switch NUREG-1021 2
ES-401 Callaway Form ES-401-2 PWR BOTH 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#
Ability to operate and monitor the following as they apply 038 / Steam Gen. Tube Rupture / 3 X EA1.35 3.5 47 to a SGTR: Steam dump condenser Ability to operate and / or monitor the following as they 040 / Steam Line Rupture - Excessive Heat Transfer / 4 X AA1.05 apply to the Steam Line Rupture: Manual and automatic 4.5 48 RPS trip initiation Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW):
054 / Loss of Main Feedwater / 4 X AA2.02 4.1 49 Differentiation between loss of all MFW and trip of one MFW pump Knowledge of the operational implications of the following 056 / Loss of Off-site Power / 6 X AK1.01 concepts as they apply to Loss of Offsite Power: Principle 3.7 50 of cooling by natural convection Ability to operate and / or monitor the following as they 057 / Loss of Vital AC Inst. Bus / 6 X AA1.04 apply to the Loss of Vital AC Instrument Bus: RWST and 3.5 51 VCT valves Ability to determine and interpret the following as they apply to the Loss of DC Power: That a loss of dc power 058 / Loss of DC Power / 6 X AA2.01 3.7 52 has occurred; verification that substitute power sources have come on line Ability to operate and / or monitor the following as they apply to the Loss of Nuclear Service Water: Flow rates to 062 / Loss of Nuclear Svc. Water / 4 X AA1.07 2.9 53 the components and systems that are serviced by the CCWS; interactions among the components Knowledge of the reasons for the following responses as they apply to the (LOCA Outside Containment) Normal, E04 / LOCA Outside Containment / 3 X EK3.2 3.4 54 abnormal and emergency operating procedures associated with (LOCA Outside Containment).
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 Recirc. / 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.
Ability to operate and / or monitor the following as they apply to the (Uncontrolled Depressurization of all Steam E12 / Steam Line Rupture - Excessive Heat Transfer / 4 X EA1.3 3.4 56 Generators) Desired operating results during abnormal and emergency situations.
K/A Category Point Totals: 2/3 1 1 3 7 4/3 Group Point Total: 18/6 NUREG-1021 3
ES-401 Callaway Form ES-401-2 PWR BOTH 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#
Ability to determine and interpret the following as they apply to the Continuous Rod Withdrawal: Proper actions 001 / Continuous Rod Withdrawal / 1 X AA2.02 4.5 82 to be taken if automatic safety functions have not taken place Equipment Control Knowledge of limiting conditions for 037 / Steam Generator Tube Leak / 3 X 2.2.22 4.1 83 operations and safety limits.
Ability to determine and interpret the following as they 060 / Accidental Gaseous RadWaste Rel. / 9 X AA2.04 apply to the Accidental Gaseous Radwaste: Valve lineup 3.6 84 for release of radioactive gases Emergency Procedures / Plan Knowledge symptom E14 / Loss of CTMT Integrity / 5 X 2.4.6 4.0 85 based EOP mitigation strategies.
Ability to operate and / or monitor the following as they 036 / Fuel Handling Accident / 8 X AA1.02 3.1 57 apply to the Fuel Handling Incidents: ARM system Ability to operate and / or monitor the following as they 037 / Steam Generator Tube Leak / 3 X AA1.06 apply to the Steam Generator Tube Leak: Main steam 3.8 58 line rad monitor meters Knowledge of the operational implications of the following concepts as they apply to Accidental Liquid Radwaste Release: Biological effects on humans of various types of 059 / Accidental Liquid RadWaste Rel. / 9 X AK1.02 radiation, exposure levels that are acceptable for nuclear 2.6 59 power plant personnel, and the units used for radiation-intensity measurements and for radiation exposure levels Knowledge of the reasons for the following responses as they apply to the (Reactor Trip or Safety Injection/Rediagnosis) Facility operating characteristics E01 & E02 Rediagnosis and SI Termination / 3 X EK3.1 during transient conditions, including coolant chemistry 3.0 60 and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.
Knowledge of the reasons for the following responses as they apply to the (LOCA Cooldown and Depressurization)
E03 / LOCA Cooldown - Depress. / 4 X EK3.2 3.4 61 Normal, abnormal and emergency operating procedures associated with (LOCA Cooldown and Depressurization).
Ability to determine and interpret the following as they apply to the (Saturated Core Cooling) Adherence to E07 / Inad. Core Cooling / 4 X EA2.2 3.3 62 appropriate procedures and operation within the limitations in the facility's license and amendments.
ES-401 Callaway Form ES-401-2 PWR BOTH 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 interrelations between the (Pressurized Thermal Shock) and the following: Components, and E08 / RCS Overcooling - PTS / 4 X EK2.1 functions of control and safety systems, including 3.4 63 instrumentation, signals, interlocks, failure modes, and automatic and manual features.
Ability to determine and interpret the following as they apply to the (Natural Circulation Operations) Adherence E09 / Natural Circ. / 4 X EA2.2 3.4 64 to appropriate procedures and operation within the limitations in the facility's license and amendments.
Knowledge of the interrelations between the (High Containment Pressure) and the following: Components, E14 / Loss of CTMT Integrity / 5 X EK2.1 and functions of control and safety systems, including 3.4 65 instrumentation, signals, interlocks, failure modes, and automatic and manual features.
K/A Category Point Total: 0/2 1 2 2 2 2/2 Group Point Total: 9/4 NUREG-1021 5
ES-401 Callaway Form ES-401-2 PWR BOTH 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 ECCS; and (b) based on those predictions, use procedures to 006 Emergency Core Cooling X A2.12 4.8 86 correct, control, or mitigate the consequences of those malfunctions or operations: Conditions requiring actuation of ECCS 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 4.2 87 correct, control, or mitigate the consequences of those malfunctions or operations: PORV failures Emergency Procedures / Plan Knowledge of which 064 Emergency Diesel Generator X 2.4.30 events related to system operations/status should be 3.6 88 reported to outside agencies.
Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to 076 Service Water X A2.02 3.1 89 correct, control, or mitigate the consequences of those malfunctions or operations: Service water header pressure Conduct of Operations: Knowledge of system status 103 Containment X 2.1.14 criteria which require the notification of plant 3.3 90 personnel.
Knowledge of the physical connections and/or 003 Reactor Coolant Pump X K1.01 cause-effect relationships between the RCPS and 2.6 1 the following systems: RCP lube oil Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 003 Reactor Coolant Pump X A1.01 2.9 2 associated with operating the RCPS controls including: RCP vibration Knowledge of the effect that a loss or malfunction of 004 Chemical and Volume X K3.06 the CVCS will have on the following: RCS 3.4 3 Control temperature and pressure Knowledge of CVCS design feature(s) and/or 004 Chemical and Volume X K4.15 interlock(s) which provide for the following: Interlocks 3.0 16 Control associated with operation of orifice isolation valves Knowledge of the operational implications of the 005 Residual Heat Removal X K5.03 following concepts as they apply the RHRS: 2.9 4 Reactivity effects of RHR fill water Knowledge of ECCS design feature(s) and/or 006 Emergency Core Cooling X K4.10 interlock(s) which provide for the following: 2.9 5 Redundant pressure meters NUREG-1021 6
ES-401 Callaway Form ES-401-2 PWR BOTH 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 PRTS; and (b) 007 Pressurizer Relief/Quench based on those predictions, use procedures to X A2.02 2.6 6 Tank correct, control, or mitigate the consequences of those malfunctions or operations: Abnormal pressure in the PRT Ability to monitor automatic operation of the CCWS, including: Automatic actions associated with the 008 Component Cooling Water X A3.08 3.6 7 CCWS that occur as a result of a safety injection signal Knowledge of bus power supplies to the following:
008 Component Cooling Water X K2.02 3.0 8 CCW pump, including emergency backup Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 010 Pressurizer Pressure Control X A1.08 3.2 9 associated with operating the PZR PCS controls including: Spray nozzle DT Knowledge of the physical connections and/or 010 Pressurizer Pressure Control X K1.01 cause-effect relationships between the PZR PCS 3.9 10 and the following systems: RPS Knowledge of bus power supplies to the following:
012 Reactor Protection X K2.01 3.3 11 RPS channels, components, and interconnections Ability to monitor automatic operation of the RPS, 012 Reactor Protection X A3.06 3.7 12 including: Trip logic Knowledge of the physical connections and/or cause 013 Engineered Safety Features X K1.14 effect relationships between the ESFAS and the 3.1 13 Actuation following systems: IAS Knowledge of the operational implications of the 013 Engineered Safety Features X K5.01 following concepts as they apply to the ESFAS: 2.8 14 Actuation Definitions of safety train and ESF channel Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to 022 Containment Cooling X A2.04 2.9 15 correct, control, or mitigate the consequences of those malfunctions or operations: Loss of service water Conduct of Operations: Knowledge of operator 026 Containment Spray X 2.1.2 3.0 17 responsibilities during all modes of plant operation.
Knowledge of the effect that a loss or malfunction of 039 Main and Reheat Steam X K3.05 3.6 18 the MRSS will have on the following: RCS NUREG-1021 7
ES-401 Callaway Form ES-401-2 PWR BOTH 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 MFW; and (b) based on those predictions, use procedures to 059 Main Feedwater X A2.07 3.0 19 correct, control, or mitigate the consequences of those malfunctions or operations: Tripping of MFW pump turbine Knowledge of the effect of a loss or malfunction of 061 Auxillary/Emergency X K6.02 the following will have on the AFW components: 2.6 20 Feedwater Pumps Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 062 AC Electrical Distribution X A1.01 3.4 21 associated with operating the ac distribution system controls including: Significance of D/G load limits Knowledge of dc electrical system design feature(s) and/or interlock(s) which provide for the following:
063 DC Electrical Distribution X K4.02 2.9 22 Breaker interlocks, permissives, bypasses and cross-ties.
Ability to manually operate and/or monitor in the 063 DC Electrical Distribution X A4.01 control room: Major breakers and control power 2.8 23 fuses Knowledge of the effect of a loss or malfunction of 064 Emergency Diesel Generator X K6.08 the following will have on the ED/G system: Fuel oil 3.2 24 storage tanks Ability to manually operate and/or monitor in the 073 Process Radiation Monitoring X A4.01 3.9 25 control room: Effluent release Knowledge of the physical connections and/or 076 Service Water X K1.19 cause- effect relationships between the SWS and the 3.6 26 following systems: SWS emergency heat loads Knowledge of IAS design feature(s) and/or 078 Instrument Air X K4.01 interlock(s) which provide for the following: 2.7 27 Manual/automatic transfers of control Ability to manually operate and/or monitor in the 103 Containment X A4 04 3.5 28 control room: Phase A and phase B resets K/A Category Point Totals: 1/2 4 2 2 4 2 2 3 3/3 2 3 Group Point Total: 28/5 NUREG-1021 8
ES-401 Callaway Form ES-401-2 PWR BOTH 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#
Emergency Procedures / Plan Ability to recognize abnormal indications for system operating 001 Control Rod Drive X 2.4.4 4.3 91 parameters which are entry-level conditions for emergency and abnormal operating procedures.
Conduct of Operations: Knowledge of the purpose 002 Reactor Coolant X 2.1.28 and function of major system components and 3.3 92 controls.
Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) 011 Pressurizer Level Control X A2.03 based on those predictions, use procedures to 3.9 93 correct, control, or mitigate the consequences of those malfunctions or operations: Loss of PZR level Knowledge of bus power supplies to the following:
001 Control Rod Drive X K2.02 3.6 29 One-line diagram of power supply to trip breakers Knowledge of the effect of a loss or malfunction on 011 Pressurizer Level Control X K6.04 the following will have on the PZR LCS: Operation of 3.1 30 PZR level controllers Conduct of Operations: Knowledge of system 014 Rod Position Indication X 2.1.27 2.8 31 purpose and or function.
Knowledge of bus power supplies to the following:
015 Nuclear Instrumentation X K2.01 3.3 32 NIS channels, components, and interconnections Conduct of Operations: Knowledge of the purpose 017 In-core Temperature Monitor X 2.1.28 and function of major system components and 3.1 33 controls.
Ability to monitor automatic operation of the 029 Containment Purge X A3.01 3.8 34 Containment Purge System including: CPS isolation 041 Steam Dump/Turbine Bypass Ability to monitor automatic operation of the SDS, X A3.05 including: Main steam pressure 2.9 35 Control Knowledge of the physical connections and/or 045 Main Turbine Generator X K1.19 cause-effect relationships between the MT/G system 3.4 36 and the following systems: ESFAS Knowledge of the effect that a loss or malfunction of 071 Waste Gas Disposal X K3.05 the Waste Gas Disposal System will have on the 3.2 37 following: ARM and PRM systems Ability to manually operate and/or monitor in the 079 Station Air X A4.01 2.7 38 control room: Cross-tie valves with IAS K/A Category Point Totals: 2/2 1 2 1 0 0 1 0 0/1 2 1 Group Point Total: 10/3 NUREG-1021 9
ES-401 Generic Knowledge and Abilities Outline (Tier3) Form ES-401-3 Facility: Callaway Date of Exam: 8/22/2005 RO SRO-Only Category K/A # Topic IR Q# IR Q#
Ability to recognize indications for system operating 2.1.33 parameters which are entry-level conditions for 4.0 94 technical specifications.
- 1. Ability to make accurate, clear and concise logs, 2.1.18 2.9 66 Conduct of Operations records, status boards, and reports.
Ability to operate plant phone, paging system, and 2.1.16 2.9 67 two-way radio.
Subtotal 2 1 2.2.33 Knowledge of control rod programming. 2.9 95 Knowledge of the process for determining if the margin of safety, as defined in the basis of any technical 2.2.10 3.3 96 specification is reduced by a proposed change, test or experiment.
2.
Knowledge of bases in technical specifications for Equipment Control 2.2.25 2.5 68 limiting conditions for operations and safety limits.
Ability to manipulate the console controls as required 2.2.2 to operate the facility between shutdown and 4.0 69 designated power levels.
Subtotal 2 2 Knowledge of the process for performing a planned 2.3.8 3.2 97 gaseous radioactive release.
Ability to perform procedures to reduce excessive 2.3.10 levels of radiation and guard against personnel 3.3 98
- 3. exposure.
Radiation Control Knowledge of the process for performing a 2.3.9 2.5 70 containment purge.
2.3.11 Ability to control radiation releases. 2.7 71 Subtotal 2 2 Ability to recognize abnormal indications for system 2.4.4 operating parameters which are entry-level conditions 4.3 99 for emergency and abnormal operating procedures.
Ability to take actions called for in the facility 2.4.38 emergency plan, including (if required) supporting or 4.0 100 acting as emergency coordinator.
- 4. Knowledge of annunciators, alarms and indications, 2.4.31 3.3 72 Emergency Procedures and use of the response instructions.
/ Plan 2.4.3 Ability to identify post-accident instrumentation. 3.5 73 Knowledge of general operating crew responsibilities 2.4.12 3.4 74 during emergency operations.
2.4.29 Knowledge of the emergency plan. 2.6 75 Subtotal 4 2 Tier 3 Point Total 10 7 NUREG-1021 10
ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A The subject K/A isn't relevant at the subject facility. No pump auto start on 2/1 008 / A2.07 flow rate The subject K/A isn't relevant at the subject facility. Facility does not have 2/1 008 / A3.02 booster pumps.
It isn't possible to prepare a psychometrically sound question related to the 2/1 012 / A1.01 subject K/A. Not a task performed by operations 2/1 061 / A1.03 The subject K/A isn't relevant at the subject facility. Not multi-unit.
The subject K/A isn't relevant at the subject facility. No ability to monitor this 2/1 103 / A4.06 system and component from the control room.
2/2 027 / 2.1.27 The subject K/A isn't relevant at the subject facility. System is retired in place.
It isn't possible to prepare a psychometrically sound question related to the 2/2 017 / A2.01 subject K/A. Operating the system controls would not result in the effects stated.
The subject K/A isn't relevant at the subject facility. No heat tracing on this 2/1 006 / A2.07 system.
2/1 022 K4.03 The function required by the topic does not exist at this facility 1/2 001 AA2.02 There is no relationship between these components for this event at this facility 1/2 060 AA2.04 Could not develop a psychometrically sound SRO level test item for this topic 1/1 008 AA2.10 Could not develop a psychometrically sound SRO level test item for this topic NUREG-1021 11