ML091520214
| ML091520214 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 07/07/2008 |
| From: | NRC/RGN-III |
| To: | Entergy Nuclear Palisades |
| Shared Package | |
| ML082200310 | List: |
| References | |
| Download: ML091520214 (13) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: Palisades Date of Exam: July 2008 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 4 1 4 3 3 3 18 3 3 6 Emergency
& Abnormal 2 2 1 1 N/A 1 2 N/A 2 9 2 2 4 Plant Evolutions Tier Totals 6 2 5 4 5 5 27 5 5 10 1 3 2 3 4 3 2 2 2 2 3 2 28 3 2 5 2.
Plant 2 1 0 1 1 1 1 1 1 1 1 1 10 2 1 3 Systems Tier Totals 4 2 4 5 4 3 3 3 3 4 3 38 5 3 8
- 3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 7 Categories 3 2 2 3 2 1 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 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 Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
- 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
ES-401, Page 1 of 13
ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) IR #
EK2.1 - Knowledge of the interrelations between the (Reactor Trip Recovery) and the CE/E02 Reactor Trip - Stabilization - following: Components, and functions of control and safety systems, including 1 3.3 1 Recovery / 1 instrumentation, signals, interlocks, failure modes, and automatic and manual features.
000008 Pressurizer Vapor Space AK3.04 - Knowledge of the reasons for the following responses as they apply to the 04 4.2 2 Accident / 3 Pressurizer Vapor Space Accident: RCP tripping requirements.
EA1.04 - Ability to operate and monitor the following as they apply to a small break 000009 Small Break LOCA / 3 04 3.7 3 LOCA: CVCS.
AA2.08 - Ability to determine and interpret the following as they apply to the Reactor 000015/17 RCP Malfunctions / 4 08 Coolant Pump Malfunctions (Loss of RC Flow): When to secure RCPs on high 3.4 4 bearing temperature.
G2.2.44 - Ability to interpret control room indications to verify the status and operation 000022 Loss of Rx Coolant Makeup / 2 2.2.44 of a system, and understand how operator actions and directives affect plant and 4.2 5 system conditions.
AK1.01 - Knowledge of the operational implications of the following concepts as they 000025 Loss of RHR System / 4 01 apply to Loss of Residual Heat Removal System: Loss of RHRS during all modes of 3.9 6 operation.
AK3.02 - Knowledge of the reasons for the following responses as they apply to the 000026 Loss of Component Cooling 02 Loss of Component Cooling Water: The automatic actions (alignments) within the 3.6 7 Water / 8 CCWS resulting from the actuation of the ESFAS.
AK3.03 - Knowledge of the reasons for the following responses as they apply to the 000027 Pressurizer Pressure Control 03 Pressurizer Pressure Control Malfunctions: Actions contained in EOP for PZR PCS 3.7 8 System Malfunction / 3 malfunction.
EA1.12 - Ability to operate and monitor the following as they apply to a ATWS: M/G 000029 ATWS / 1 12 4.1 9 set power supply and reactor trip breakers.
EA2.03 - Ability to determine or interpret the following as they apply to a SGTR:
000038 Steam Gen. Tube Rupture / 3 03 4.4 10 Which S/G is ruptured.
CE/E05 Steam Line Rupture - Excessive G2.4.2 - Knowledge of system set points, interlocks and automatic actions associated 2.4.2 4.5 11 Heat Transfer / 4 with EOP entry conditions.
EK1.3 - Knowledge of the operational implications of the following concepts as they CE/E06 Loss of Main Feedwater / 4 3 apply to the Loss of Feedwater: Annunciators and conditions indicating signals, and 3.2 12 remedial actions.
AK1.01 - Knowledge of the operational implications of the following concepts as they 000056 Loss of Off-site Power / 6 01 3.7 13 apply to Loss of Offsite Power: Principle of cooling by natural convection.
AK3.01 - Knowledge of the reasons for the following responses as they apply to the 000057 Loss of Vital AC Inst. Bus / 6 01 Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital ac 4.1 14 electrical instrument bus.
ES-401, Page 2 of 13
ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO) cont'd E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) IR #
AA1.01 - Ability to operate and / or monitor the following as they apply to the Loss of 000058 Loss of DC Power / 6 01 3.4 15 DC Power: Cross-tie of the affected dc bus with the alternate supply AA2.02 - Ability to determine and interpret the following as they apply to the Loss of 000062 Loss of Nuclear Svc Water / 4 02 2.9 16 Nuclear Service Water: The cause of possible SWS loss G2.1.7 - Ability to evaluate plant performance and make operational judgments based 000065 Loss of Instrument Air / 8 2.1.7 4.4 17 on operating characteristics, reactor behavior, and instrument interpretation.
000077 Generator Voltage and Electric AK1.03 - Knowledge of the operational implications of the following concepts as they 03 3.3 18 Grid Disturbances / 6 apply to Generator Voltage and Electric Grid Disturbances: Under-excitation K/A Category Point Totals: 4 1 4 3 3 3 Group Point Total: 18 ES-401, Page 3 of 13
ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)
E/APE # / Name / Safety Function K/A Topic(s) IR #
K1 K2 K3 A1 A2 G G2.1.31 - Ability to locate control room switches, controls, and indications, and to 000028 Pressurizer Level Malfunction / 2 2.1.31 4.6 19 determine that they correctly reflect the desired plant lineup.
AK1.01 - Knowledge of the operational implications of the following concepts as 000036 Fuel Handling Accident / 8 01 3.5 20 they apply to Fuel Handling Incidents: Radiation exposure hazards.
AA2.07 - Ability to determine and interpret the following as they apply to the Steam 000037 Steam Generator Tube Leak / 3 07 3.1 21 Generator Tube Leak: Flowpath for dilution of ejector exhaust air.
AK3.02 - Knowledge of the reasons for the following responses as they apply to the 000061 ARM System Alarms / 7 02 Area Radiation Monitoring (ARM) System Alarms: Guidance contained in alarm 3.4 22 response for ARM system.
AA1.06 - Ability to operate and / or monitor the following as they apply to the Plant 000067 Plant Fire On-site / 8 06 3.5 23 Fire on Site: Fire alarm.
AA2.04 - Ability to determine and interpret the following as they apply to the Control 000068 Control Room Evac. / 8 04 3.7 24 Room Evacuation: S/G pressure.
G2.4.9 - Knowledge of low power/shutdown implications in accident (e.g., loss of 000069 Loss of CTMT Integrity / 5 2.4.9 3.8 25 coolant accident or loss of residual heat removal) mitigation strategies.
AK1.2 - Knowledge of the operational implications of the following concepts as they CE/A11 RCS Overcooling - PTS / 4 2 apply to the RCS Overcooling: Normal, abnormal and emergency operating 3.0 26 procedures.
AK2.1 - Knowledge of the interrelations between the Excess RCS Leakage and the following: Components, and functions of control and safety systems, including CE/A16 Excess RCS Leakage / 2 1 3.2 27 instrumentation, signals, interlocks, failure modes, and automatic and manual features.
K/A Category Point Totals: 2 1 1 1 2 2 Group Point Total: 9 ES-401, Page 4 of 13
ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) IR #
K1.03 - Knowledge of the physical connections and/or cause-effect 003 Reactor Coolant Pump 03 relationships between the RCPS and the following systems: RCP 3.3 28 seal system.
003 Reactor Coolant Pump 01 K2.01 - Knowledge of bus power supplies to the following: RCPS. 3.1 29 K3.04 - Knowledge of the effect that a loss or malfunction of the 004 Chemical and Volume Control 04 3.7 30 CVCS will have on the following: RCPS.
K6.03 - Knowledge of the effect of a loss or malfunction on the 005 Residual Heat Removal 03 2.5 31 following will have on the RHRS: RHR heat exchanger.
K5.08 - Knowledge of the operational implications of the following 006 Emergency Core Cooling 08 2.9 32 concepts as they apply to ECCS: Operation of pumps in parallel.
K5.02 - Knowledge of the operational implications of the following 007 Pressurizer Relief/Quench Tank 02 concepts as the apply to PRTS: Method of forming a steam bubble 3.1 33 in the PZR.
A1.01 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the 007 Pressurizer Relief/Quench Tank 01 2.9 34 PRTS controls including: Maintaining quench tank water level within limits.
A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use 008 Component Cooling Water 03 3.0 35 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High/low CCW temperature.
A3.02 - Ability to monitor automatic operation of the PZR PCS, 010 Pressurizer Pressure Control 02 3.6 36 including: PZR Pressure.
A4.02 - Ability to manually operate and/or monitor in the control 010 Pressurizer Pressure Control 02 3.6 37 room: PZR heaters.
G2.2.37 - Ability to determine operability and/or availability of safety 012 Reactor Protection 2.2.37 3.6 38 related equipment.
K6.02 - Knowledge of the effect of a loss or malfunction of the 012 Reactor Protection 02 2.9 39 following will have on the RPS: Redundant channels.
013 Engineered Safety Features K2.01 - Knowledge of bus power supplies to the following:
01 3.6 40 Actuation ESFAS/safeguards equipment control.
K3.01 - Knowledge of the effect that a loss or malfunction of the 022 Containment Cooling 01 CCS will have on the following: Containment equipment subject to 2.9 41 damage by high or low temperature, humidity, and pressure.
K4.01 - Knowledge of CSS design feature(s) and/or interlock(s) 026 Containment Spray 01 which provide for the following: Source of water for CSS, including 4.2 42 recirculation phase after LOCA.
ES-401, Page 5 of 13
ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO) cont'd System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) IR #
K5.05 - Knowledge of the operational implications of the following 039 Main and Reheat Steam 05 2.7 43 concepts as the apply to the MRSS: Bases for RCS cooldown limits.
K4.18 - Knowledge of MFW design feature(s) and/or interlock(s) 059 Main Feedwater 18 which provide for the following: Automatic feedwater reduction on 2.8 44 plant trip.
A1.03 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MFW 059 Main Feedwater 03 2.7 45 controls including: Power level restrictions for operation of MFW pumps and valves.
A2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use 061 Auxiliary/Emergency Feedwater 04 procedures to correct, control, or mitigate the consequences of 3.4 46 those malfunctions or operations: pump failure or improper operation.
A3.04 - Ability to monitor automatic operation of the ac distribution 062 AC Electrical Distribution 04 system, including: Operation of inverter (e.g., precharging 2.7 47 synchronizing light, static transfer).
A4.03 - Ability to manually operate and/or monitor in the control 063 DC Electrical Distribution 03 3.0 48 room: Battery discharge rate.
G2.1.30 - Ability to locate and operate components, including local 063 DC Electrical Distribution 2.1.30 4.4 49 controls.
K1.01 - Knowledge of the physical connections and/or cause-effect 064 Emergency Diesel Generator 01 relationships between the ED/G system and the following systems: 4.1 50 AC distribution system.
A4.01 - Ability to manually operate and/or monitor in the control 073 Process Radiation Monitoring 01 3.9 51 room: Effluent release.
K3.01 - Knowledge of the effect that a loss or malfunction of the 073 Process Radiation Monitoring 01 PRM system will have on the following: Radioactive effluent 3.6 52 releases.
K4.06 - Knowledge of SWS design feature(s) and/or interlock(s) 076 Service Water 06 2.8 53 which provide for the following: Service water train separation.
K4.02 - Knowledge of IAS design feature(s) and/or interlock(s) which 078 Instrument Air 02 3.2 54 provide for the following: Cross-over to other air systems.
K1.05 - Knowledge of the physical connections and/or cause-effect 103 Containment 05 relationships between the containment system and the following 2.8 55 systems: Personnel access hatch and emergency access hatch.
K/A Category Point Totals: 3 2 3 4 3 2 2 2 2 3 2 Group Point Total: 28 ES-401, Page 6 of 13
ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) IR #
K3.01 - Knowledge of the effect that a loss or malfunction of the CRDS 001 Control Rod Drive 01 2.9 56 will have on the following: CVCS.
K4.02 - Knowledge of RCS design feature(s) and/or interlock(s) which 002 Reactor Coolant 02 3.5 57 provide for the following: Monitoring reactor vessel level.
K5.01 - Knowledge of the operational implication of the following 016 Non-nuclear 01 concepts as they apply to the NNIS: Separation of control and protection 2.7 58 Instrumentation circuits.
A1.01 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Spent Fuel Pool 033 Spent Fuel Pool Cooling 01 2.7 59 Cooling System operating the controls including: Spent fuel pool water level.
A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the S/GS: and (b) based on those predictions, use 035 Steam Generator 02 4.2 60 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Reactor trip/turbine trip.
K6.03 - Knowledge of the effect of a loss or malfunction on the following 041 Steam Dump/Turbine 03 will have on the SDS: Controller and positioners, including ICS, S/G, 2.7 61 Bypass Control CRDS.
A3.05 - Ability to monitor automatic operation of the MT/G system, 045 Main Turbine Generator 05 2.6 62 including: Electrohydraulic control.
K1.06 - Knowledge of the physical connections and/or cause-effect 055 Condenser Air Removal 06 relationships between the CARS and the following systems: PRM 2.6 63 system.
G2.1.30 - Ability to locate and operate components, including local 071 Waste Gas Disposal 2.1.30 4.4 64 controls.
A4.02 - Ability to manually operate and/or monitor in the control room:
086 Fire Protection 02 3.5 65 Fire detection panels.
K/A Category Point Totals: 1 0 1 1 1 1 1 1 1 1 1 Group Point Total: 10 ES-401, Page 7 of 13
ES-401 General Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Palisades Date of Exam: July 2008 Category K/A # Topic RO IR #
Ability to interpret reference materials, such as graphs, curves, 2.1.25 3.9 66 tables, etc.
1.
Conduct 2.1.39 Knowledge of conservative decision making practices. 3.6 67 of Operations 2.1.42 Knowledge of new and spent fuel movement procedures. 2.5 68 Subtotal 3 Ability to track Technical Specification limiting conditions for 2.2.23 3.1 69
- 2. operations.
Equipment 2.2.40 Ability to apply Technical Specifications for a system. 3.4 70 Control Subtotal 2 Ability to use radiation monitoring systems, such as fixed radiation 2.3.5 monitors and alarms, portable survey instruments, personnel 2.9 71 monitoring equipment, etc.
3.
Knowledge of radiological safety procedures pertaining to licensed Radiation operator duties, such as response to radiation monitor alarms, Control 2.3.13 3.4 72 containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
Subtotal 2 Knowledge of the operational implications of EOP warnings, 2.4.20 3.8 73 cautions, and notes.
4.
Emergency 2.4.25 Knowledge of fire protection procedures. 3.3 74 Procedures /
Plan Knowledge of annunciator alarms, indications, or response 2.4.31 4.2 75 procedures.
Subtotal 3 Tier 3 Point Total 10 ES-401, Page 8 of 13
ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)
E/APE # / Name / Safety Function K/A Topic(s) IR #
A2 G 000025 Loss of RHR System / 4 2.4.11 G2.4.11 - Knowledge of abnormal condition procedures. 4.2 1 EA2.07 - Ability to determine or interpret the following as they apply to a ATWS: Reactor trip 000029 ATWS / 1 07 4.3 2 breaker indicating lights.
CE/E06 Loss of Main Feedwater / 4 2.4.6 G2.4.6 - Knowledge of EOP mitigation strategies. 4.7 3 EA2.04 - Ability to determine or interpret the following as they apply to a Station Blackout:
000055 Station Blackout / 6 04 4.1 4 Instruments and controls operable with only dc battery power available.
G2.4.21 - Knowledge of the parameters and logic used to assess the status of safety 000056 Loss of Off-site Power / 6 2.4.21 functions, such as reactivity control, core cooling and heat removal, reactor coolant system 4.6 5 integrity, containment conditions, radioactivity release control, etc.
AA2.03 - Ability to determine and interpret the following as they apply to the Loss of Nuclear 000062 Loss of Nuclear Svc Water / 4 03 Service Water: The valve lineups necessary to restart the SWS while bypassing the portion of 2.9 6 the system causing the abnormal condition.
K/A Category Point Totals: 3 3 Group Point Total: 6 ES-401, Page 9 of 13
ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)
E/APE # / Name / Safety Function K/A Topic(s) IR #
A2 G AA2.05 - Ability to determine and interpret the following as they apply to the Continuous Rod 000001 Continuous Rod Withdrawal / 1 05 4.6 7 Withdrawal: Uncontrolled rod withdrawal, from available indications 000024 Emergency Boration / 1 2.2.38 G2.2.38 - Knowledge of conditions and limitations in the facility license. 4.5 8 AA2.10 - Ability to determine and interpret the following as they apply to the Steam Generator 000037 Steam Generator Tube Leak / 3 10 4.1 9 Tube Leak: Tech-Spec limits for RCS leakage.
G2.4.30 - Knowledge of events related to system operation/status that must be reported to 000068 Control Room Evac. / 8 2.4.30 internal organizations or external agencies, such as the State, the NRC, or the transmission 4.1 10 system operator.
K/A Category Point Totals: 2 2 Group Point Total: 4 ES-401, Page 10 of 13
ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO)
System # / Name A2 G K/A Topic(s) IR #
A2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; 026 Containment Spray 04 and (b) based on those predictions, use procedures to correct, control, or mitigate the 4.2 11 consequences of those malfunctions or operations: Failure of spray pump.
G2.2.44 - Ability to interpret control room indications to verify the status and operation of a 062 AC Electrical Distribution 2.2.44 4.4 12 system, and understand how operator actions and directives affect plant and system conditions.
A2.02 - 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, control, or mitigate the 064 Emergency Diesel Generator 02 2.9 13 consequences of those malfunctions or operations: Load, VARS, pressure on air compressor, speed droop, frequency, voltage, fuel oil level, temperatures.
G2.2.39 - Knowledge of less than or equal to one hour Technical Specification action statements 073 Process Radiation Monitoring 2.2.39 4.5 14 for systems.
A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the IAS; 078 Instrument Air 01 and (b) based on those predictions, use procedures to correct, control, or mitigate the 2.9 15 consequences of those malfunctions or operations: Air dryer and filter malfunctions K/A Category Point Totals: 3 2 Group Point Total: 5 ES-401, Page 11 of 13
ES-401 5 Form ES-401-3 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (SRO)
System # / Name A2 G K/A Topic(s) IR #
A2.08 - Ability to (a) predict the impacts of the following malfunction or operations on the CRDS- and 001 Control Rod Drive 08 (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of 3.3 16 those malfunctions or operations: Loss of CCW to CRDS A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the RCS; and 002 Reactor Coolant 03 (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of 4.3 17 those malfunctions or operations: Loss of forced circulation 015 Nuclear Instrumentation 2.1.32 G2.1.32 - Ability to explain and apply system limits and precautions. 4.0 18 K/A Category Point Totals: 2 1 Group Point Total: 3 ES-401, Page 12 of 13
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Palisades Date of Exam: July 2008 Category K/A # Topic SRO-Only IR #
Knowledge of criteria or conditions that require plant-wide 2.1.14 announcements, such as pump starts, reactor trips, mode 3.1 19
- 1. changes, etc.
Conduct of Knowledge of how to conduct system lineups, such as valves, Operations 2.1.29 4.0 20 breakers, switches, etc.
Subtotal 2
- 2. 2.2.38 Knowledge of conditions and limitations in the facility license. 4.5 21 Equipment Control Subtotal 1 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry 2.3.12 3.7 22 requirements, fuel handling responsibilities, access to locked
- 3. high-radiation areas, aligning filters, etc.
Radiation Knowledge of radiation or contamination hazards that may Control 2.3.14 arise during normal, abnormal, or emergency conditions or 3.8 23 activities.
Subtotal 2 Knowledge of system set points, interlocks and automatic 2.4.2 4.6 24
- 4. actions associated with EOP entry conditions.
Emergency Procedures / 2.4.3 Ability to identify post-accident instrumentation. 3.9 25 Plan Subtotal 2 Tier 3 Point Total 7 ES-401, Page 13 of 13