ML14309A501
| ML14309A501 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 04/29/2014 |
| From: | NRC/RGN-III |
| To: | Entergy Nuclear Operations |
| Reeser, D. | |
| Shared Package | |
| ML13093A491 | List: |
| References | |
| Download: ML14309A501 (10) | |
Text
ES-401 PWR Examination Outline FORM ES-401-2 Facility Name:PALISADES Date of Exam:09/19/2014 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. Emergency 1 4 2 3 4 4 1 18 4 2 6 Abnormal 2 1 2 2 N/A 1 2 N/A 1 9 3 1 4 Plant Evolutions 7 3 Tier Totals 5 4 5 5 6 2 27 10 1 2 3 4 4 1 1 3 3 2 3 2 28 3 2 5 2.
2 1 0 1 1 1 2 1 1 0 1 1 10 0 1 2 3 Plant Systems Tier Totals 3 3 5 5 2 3 4 4 2 4 3 38 4 4 8 1 2 3 4 1 2 3 4
- 3. Generic Knowledge and Abilities 10 7 Categories 2 3 3 2 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-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).
Note: 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.
Note: 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.
Note: 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.
Note: 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.
Note: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
Note: 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.
Note: 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.
Note: 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, 21 of 33
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)
K K K A A E/APE # / Name / Safety Function G K/A Topic(s) IR #
1 2 3 1 2 000007 Reactor Trip / 1 0
CE/E02 Reactor Trip Recovery / 1 AK1.01-Knowledge of the operational implications of the following concepts as they 0
000008 Pressurizer Vapor Space Accident / 3 apply to a Pressurizer Vapor Space Accident: Thermodynamics and flow 3.2 1 1 characteristics of open or leaking valves 0 EK2.03-Knowledge of the interrelations between the small break LOCA and the 000009 Small Break LOCA / 3 3.0 1 3 following: S/Gs 1 EK3.10-Knowledge of the reasons for the following responses as the apply to the 000011 Large Break LOCA / 3 3.7 1 0 Large Break LOCA: PTS limits on RCS pressure and temperature 000015 RCP Malfunctions / 4 1 AA1.14-Ability to operate and / or monitor the following as they apply to the Reactor 2.9 1 000017 RCP Malfunctions (Loss of RC Flow) / 4 4 Coolant Pump Malfunctions (Loss of RC Flow): Power range remote flux meter 0 AA2.04-Ability to determine and interpret the following as they apply to the Loss of 000022 Loss of Rx Coolant Makeup / 2 2.9 1 4 Reactor Coolant Makeup: How long PZR level can be maintained within limits AK1.01-Knowledge of the operational implications of the following concepts as they 0
000025 Loss of RHR System / 4 apply to Loss of Residual Heat Removal System: Loss of RHRS during all modes of 3.9 1 1 operation 0 AA2.01-Ability to determine and interpret the following as they apply to the Loss of 000026 Loss of Component Cooling Water / 8 2.9 1 1 Component Cooling Water: Location of a leak in the CCWS AA1.04-Ability to operate and / or monitor the following as they apply to the 000027 Pressurizer Pressure Control System 0 Pressurizer Pressure Control Malfunctions: Pressure recovery, using emergency-only 3.9 1 Malfunction / 3 4 heaters 0 EK3.09-Knowledge of the reasons for the following responses as the apply to the 000029 ATWS / 1 3.7 1 9 ATWS: Opening centrifugal charging pump suction valves from RWST 0 EK1.03-Knowledge of the operational implications of the following concepts as they 000038 Steam Gen. Tube Rupture / 3 3.9 1 3 apply to the SGTR: Natural circulation 000040 Steam Line Rupture / 4 1
EK1.3-Knowledge of the operational implications of the following concepts as they 0
CE/E05 Excessive Steam Demand / 4 apply to the (Excess Steam Demand): Annunciators and conditions indicating signals, 3.4 3 and remedial actions associated with the (Excess Steam Demand).
000054 Loss of Main Feedwater / 4 EK2.2-Knowledge of the interrelations between the (Loss of Feedwater) and the 1 0 following: Facilitys heat removal systems, including primary coolant, emergency CE/E06 Loss of Feedwater / 4 3.5 2 coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
0 EK3.02-Knowledge of the reasons for the following responses as the apply to the 000055 Station Blackout / 6 4.3 1 2 Station Blackout: Actions contained in EOP for loss of offsite and onsite power 0 AA1.07-Ability to operate and / or monitor the following as they apply to the Loss of 000056 Loss of Off-site Power / 6 3.2 1 7 Offsite Power: Service water pump 0 AA2.08-Ability to determine and interpret the following as they apply to the Loss of 000057 Loss of Vital AC Inst. Bus / 6 3.4 1 8 Vital AC Instrument Bus: Reactor power digital display and remote flux meter 04.
000058 Loss of DC Power / 6 2.4.3-Ability to identify post-accident instrumentation. 3.7 1 03 000062 Loss of Nuclear Svc Water / 4 0 0 AA2.01-Ability to determine and interpret the following as they apply to the Loss of 000065 Loss of Instrument Air / 8 2.9 1 1 Instrument Air: Cause and effect of low-pressure instrument air alarm 000077 Generator Voltage and Electric 0 AA1.03-Ability to operate and/or monitor the following as they apply to Generator 3.8 1 Grid Disturbances / 6 3 Voltage and Electric Grid Disturbances: Voltage regulator controls K/A Category Totals: 4 2 3 4 4 1 Group Point Total: 18 ES-401, 22 of 33
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)
K K K A A E/APE # / Name / Safety Function G K/A Topic(s) IR #
1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 0 000003 Dropped Control Rod / 1 0 AA2.03-Ability to determine and interpret the following as they apply to the Inoperable /
000005 Inoperable/Stuck Control Rod / 1 03 Stuck Control Rod: Required actions if more than one rod is stuck or inoperable 3.5 1 000024 Emergency Boration / 1 0 04.
000028 Pressurizer Level Malfunction / 2 2.4.45-Ability to prioritize and interpret the significance of each annunciator or alarm. 4.1 1 45 AK3.01-Knowledge of the reasons for the following responses as they apply to the Loss 000032 Loss of Source Range NI / 7 01 of Source Range Nuclear Instrumentation: Startup termination on source-range loss 3.2 1 000033 Loss of Intermediate Range NI / 7 0 AK2.02-Knowledge of the interrelations between the Fuel Handling Incidents and the 000036 Fuel Handling Accident / 8 02 following: Radiation monitoring equipment (portable and installed) 3.4 1 000037 Steam Generator Tube Leak / 3 0 000051 Loss of Condenser Vacuum / 4 0 AK1.05-Knowledge of the operational implications of the following concepts as they 000059 Accidental Liquid RadWaste Rel. / 9 05 apply to Accidental Liquid Radwaste Release: The calculation of offsite doses due to a 2.6 1 release from the power plant 000060 Accidental Gaseous Radwaste Rel. / 9 0 AK2.01-Knowledge of the interrelations between the Area Radiation Monitoring (ARM) 000061 ARM System Alarms / 7 01 System Alarms and the following: Detectors at each ARM system location 2.5 1 000067 Plant Fire On-site / 9 8 0 000068 Control Room Evac. / 8 0 000069 Loss of CTMT Integrity / 5 0 EK3.11-Knowledge of the reasons for the following responses as the apply to the 000074 Inad. Core Cooling / 4 11 Inadequate Core Cooling: Guidance contained in EOP for Inadequate Core Cooling 4.0 1 000076 High Reactor Coolant Activity / 9 0 CE/A13 Natural Circ. / 4 0 CE/A11 RCS Overcooling / 4 0 AA1.2-Ability to operate and / or monitor the following as they apply to the (Excess CE/A16 Excess RCS Leakage / 2 02 RCS Leakage): Operating behavior characteristics of the facility.
3.0 1 EA2.2-Ability to determine and interpret the following as they apply to the (Functional CE/E09 Functional Recovery 02 Recovery): Adherence to appropriate procedures and operation within the limitations in 3.5 1 the Facilitys license and amendments.
0 0
0 0
0 0
0 0
0 K/A Category Totals: 1 2 2 1 2 1 Group Point Total: 9 ES-401, 23 of 33
ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)
K K K K K K A A A A System # / Name G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 K5.05-Knowledge of the operational implications of the following concepts as 0
003 Reactor Coolant Pump they apply to the RCPS: The dependency of RCS flow rates upon the number 2.8 1 5 of operating RCPs K2.03-Knowledge of bus power supplies to the following: Charging pumps 0 0 3.3 004 Chemical and Volume Control K6.09-Knowledge of the effect of a loss or malfunction on the following CVCS 2 3 9 components: Purpose of VCT divert valve 2.8 A1.01-Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RHRS controls 0 04. 3.5 005 Residual Heat Removal including: Heatup/cooldown rates 2 1 35 2.4.35-Knowledge of local auxiliary operator tasks during an emergency and 3.8 the resultant operational effects.
A2.08-Ability to (a) predict the impacts of the following malfunctions or 0 operations on the ECCS; and (b) based on those predictions, use procedures 006 Emergency Core Cooling to correct, control, or mitigate the consequences of those malfunctions or 3.0 1 8
operations: Effect of electric power loss on valve position K4.01-Knowledge of PRTS design feature(s) and/or interlock(s) which provide 0 0 for the following: Quench tank cooling 2.6 007 Pressurizer Relief/Quench Tank A3.01-Ability to monitor automatic operation of the PRTS, including:
2 1 1 2.7 Components which discharge to the PRT A2.01-Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures 0 0 to correct, control, or mitigate the consequences of those malfunctions or 3.3 008 Component Cooling Water operations: Loss of CCW pump 2
1 3 2.7 A4.03-Ability to manually operate and/or monitor in the control room: Throttling of the CCW pump discharge valve K2.03-Knowledge of bus power supplies to the following: Indicator for PORV 0 04. position 2.8 010 Pressurizer Pressure Control 2.4.50-Ability to verify system alarm setpoints and operate controls identified in 2
3 50 4.2 the alarm response manual.
0 A4.06-Ability to manually operate and/or monitor in the control room: Reactor 012 Reactor Protection trip breakers 4.3 1 6
013 Engineered Safety Features 0 A3.01-Ability to monitor automatic operation of the ESFAS, including: Input channels and logic 3.7 1 Actuation 1 A2.04-Ability to (a) predict the impacts of the following malfunctions or 0 operations on the CCS; and (b) based on those predictions, use procedures to 022 Containment Cooling correct, control, or mitigate the consequences of those malfunctions or 2.9 1 4
operations: Loss of service water 025 Ice Condenser 0 A1.04-Ability to predict and/or monitor changes in parameters (to prevent 0
026 Containment Spray exceeding design limits) associated with operating the CSS controls including: 3.1 1 4 Containment humidity K4.02-Knowledge of MRSS design feature(s) and/or interlock(s) which provide 0
039 Main and Reheat Steam for the following: Utilization of T-ave. program control when steam dumping 3.1 1 2 through atmospheric relief/dump valves, including T-ave. limits K3.02-Knowledge of the effect that a loss or malfunction of the MFW will have 0 0 on the following: AFW System 3.6 059 Main Feedwater A4.08-Ability to manually operate and monitor in the control room: Feed 2
2 8 3 regulating valve controller K4.01-Knowledge of AFW design feature(s) and/or interlock(s) which provide for the following: Water sources and priority of use 0 0 4.1 061 Auxiliary/Emergency Feedwater A1.05-Ability to predict and/or monitor changes in parameters (to prevent 2 1 5 exceeding design limits) associated with operating the AFW controls including: 3.6 AFW flow/motor amps 0 K3.02-Knowledge of the effect that a loss or malfunction of the ac distribution 062 AC Electrical Distribution system will have on the following: ED/G 4.1 1 2
0 063 DC Electrical Distribution K2.01-Knowledge of bus power supplies to the following: Major DC loads 2.9 1 1
K1.02-Knowledge of the physical connections and/or cause-effect 0
064 Emergency Diesel Generator relationships between the ED/G system and the following systems: ED/G 3.1 1 2 cooling water system 0 K3.01-Knowledge of the effect that a loss or malfunction of the PRM system 073 Process Radiation Monitoring will have on the following: Radioactive effluent releases 3.6 1 1
0 K3.01-Knowledge of the effect that a loss or malfunction of the SWS will have 076 Service Water on the following: Closed cooling water 3.4 1 1
0 K4.01-Knowledge of IAS design feature(s) and/or interlock(s) which provide for 078 Instrument Air the following: Manual/automatic transfers of control 2.7 1 1
K1.03-Knowledge of the physical connections and/or cause-effect 0
103 Containment relationships between the containment system and the following systems: 3.1 1 3 Shield building vent system 0
K/A Category Totals: 2 3 4 4 1 1 3 3 2 3 2 Group Point Total: 28 ES-401, 24 of 33
ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO)
K K K K K K A A A A System # / Name G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 0 K1.02-Knowledge of the physical connections and/or cause-effect relationships 001 Control Rod Drive 2 between the CRDS and the following systems: CVCS 3.6 1 0 K6.04-Knowledge of the effect of a loss or malfunction on the following RCS 002 Reactor Coolant 4 components: RCS vent valves 2.5 1 0 K3.01-Knowledge of the effect that a loss or malfunction of the PZR LCS will 011 Pressurizer Level Control 1 have on the following: CVCS 3.2 1 0 K4.01-Knowledge of RPIS design feature(s) and/or interlock(s) which provide for 014 Rod Position Indication 1 the following: Upper electrical limit 2.5 1 04.
015 Nuclear Instrumentation 2.4.6-Knowledge of EOP mitigation strategies. 3.7 1 06 0 K5.01-Knowledge of the operational implication of the following concepts as they 016 Non-nuclear Instrumentation 1 apply to the NNIS: Separation of control and protection circuits 2.7 1 0 K6.01-Knowledge of the effect of a loss or malfunction of the following ITM 017 In-core Temperature Monitor 1 system components: Sensors and detectors 2.7 1 027 Containment Iodine Removal 0 028 Hydrogen Recombiner and Purge 0
Control 029 Containment Purge 0 A1.01-Ability to predict and/or monitor changes in parameters (to prevent 0
033 Spent Fuel Pool Cooling 1
exceeding design limits) associated with Spent Fuel Pool Cooling System 2.7 1 operating the controls including: Spent fuel pool water level 034 Fuel Handling Equipment 0 035 Steam Generator 0 041 Steam Dump/Turbine Bypass Control 0 045 Main Turbine Generator 0 055 Condenser Air Removal 0 056 Condensate 0 068 Liquid Radwaste 0 A2.09-Ability to (a) predict the impacts of the following malfunctions or operations 0 on the Waste Gas Disposal System ; and (b) based on those predictions, use 071 Waste Gas Disposal 9 procedures to correct, control, or mitigate the consequences of those 3.0 1 malfunctions or operations: Stuck-open relief valve 072 Area Radiation Monitoring 0 075 Circulating Water 0 0 A4.01-Ability to manually operate and/or monitor in the control room: Cross-tie 079 Station Air 1 valves with IAS 2.7 1 086 Fire Protection 0 K/A Category Totals: 1 0 1 1 1 2 1 1 0 1 1 Group Point Total: 10 ES-401, 25 of 33
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)
K K K A A E/APE # / Name / Safety Function G K/A Topic(s) IR #
1 2 3 1 2 000007 Reactor Trip / 1 0
CE/E02 Reactor Trip Recovery / 1 000008 Pressurizer Vapor Space Accident / 3 0 000009 Small Break LOCA / 3 0 000011 Large Break LOCA / 3 0 AA2.02-Ability to determine and interpret the following as they apply to the Reactor 000015 RCP Malfunctions / 4 0 Coolant Pump Malfunctions (Loss of RC Flow): Abnormalities in RCP air vent flow 3.0 1 000017 RCP Malfunctions (Loss of RC Flow) / 4 2 paths and/or oil cooling system 000022 Loss of Rx Coolant Makeup / 2 0 0 AA2.06-Ability to determine and interpret the following as they apply to the Loss of 000025 Loss of RHR System / 4 3.4 1 6 Residual Heat Removal System: Existence of proper RHR overpressure protection 000026 Loss of Component Cooling Water / 8 0 000027 Pressurizer Pressure Control System 02.
2.2.38-Knowledge of conditions and limitations in the facility license. 4.5 1 Malfunction / 3 38 000029 ATWS / 1 0 1 EA2.15-Ability to determine or interpret the following as they apply to a SGTR:
000038 Steam Gen. Tube Rupture / 3 4.4 1 5 Pressure at which to maintain RCS during S/G cooldown 000040 Steam Line Rupture / 4 1
EA2.2-Ability to determine and interpret the following as they apply to the (Excess 0
CE/E05 Excessive Steam Demand / 4 Steam Demand): Adherence to appropriate procedures and operation within the 4.2 2 limitations in the Facilitys license and amendments.
000054 Loss of Main Feedwater / 4 0
CE/E06 Loss of Feedwater / 4 000055 Station Blackout / 6 0 000056 Loss of Off-site Power / 6 0 000057 Loss of Vital AC Inst. Bus / 6 0
- 04. 2.4.8-Knowledge of how abnormal operating procedures are used in conjunction with 000058 Loss of DC Power / 6 4.5 1 08 EOPs.
000062 Loss of Nuclear Svc Water / 4 0 000065 Loss of Instrument Air / 8 0 000077 Generator Voltage and Electric 0
Grid Disturbances / 6 K/A Category Totals: 0 0 0 0 4 2 Group Point Total: 6 ES-401, 22 of 33
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)
K K K A A E/APE # / Name / Safety Function G K/A Topic(s) IR #
1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 0 000003 Dropped Control Rod / 1 0 000005 Inoperable/Stuck Control Rod / 1 0 01.
000024 Emergency Boration / 1 2.1.32-Ability to explain and apply system limits and precautions. 4.0 1 32 000028 Pressurizer Level Malfunction / 2 0 000032 Loss of Source Range NI / 7 0 000033 Loss of Intermediate Range NI / 7 0 000036 Fuel Handling Accident / 8 0 000037 Steam Generator Tube Leak / 3 0 000051 Loss of Condenser Vacuum / 4 0 000059 Accidental Liquid RadWaste Rel. / 9 0 000060 Accidental Gaseous Radwaste Rel. / 9 0 000061 ARM System Alarms / 7 0 AA2.08-Ability to determine and interpret the following as they apply to the Plant Fire 000067 Plant Fire On-site / 9 8 08 on Site: Limits of affected area 3.6 1 000068 Control Room Evac. / 8 0 000069 Loss of CTMT Integrity / 5 0 000074 Inad. Core Cooling / 4 0 AA2.06-Ability to determine and interpret the following as they apply to the High 000076 High Reactor Coolant Activity / 9 06 Reactor Coolant Activity: Response of PZR LCS to changes in the letdown flow rate 2.5 1 AA2.2-Ability to determine and interpret the following as they apply to the (Natural CE/A13 Natural Circ. / 4 02 Circulation Operations): Adherence to appropriate procedures and operation within 3.8 1 the limitations in the Facilitys license and amendments.
CE/A11 RCS Overcooling / 4 0 CE/A16 Excess RCS Leakage / 2 0 CE/E09 Functional Recovery 0 0
0 0
0 0
0 0
0 0
K/A Category Totals: 0 0 0 0 3 1 Group Point Total: 4 ES-401, 23 of 33
ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO)
K K K K K K A A A A System # / Name G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump 0 004 Chemical and Volume Control 0 005 Residual Heat Removal 0 2.4.21-Knowledge of the parameters and logic used to assess the status of
- 04. safety functions, such as reactivity control, core cooling and heat removal, 006 Emergency Core Cooling reactor coolant system integrity, containment conditions, radioactivity release 4.6 1 21 control, etc.
007 Pressurizer Relief/Quench Tank 0 008 Component Cooling Water 0 010 Pressurizer Pressure Control 0 A2.06-Ability to (a) predict the impacts of the following malfunctions or 0 operations on the RPS; and (b) based on those predictions, use procedures to 012 Reactor Protection 4.7 1 6 correct, control, or mitigate the consequences of those malfunctions or operations: Failure of RPS signal to trip the reactor 013 Engineered Safety Features 0
Actuation
- 02. 2.2.39-Knowledge of less than or equal to one hour Technical Specification 022 Containment Cooling action statements for systems.
4.5 1 39 025 Ice Condenser 0 026 Containment Spray 0 039 Main and Reheat Steam 0 059 Main Feedwater 0 061 Auxiliary/Emergency Feedwater 0 062 AC Electrical Distribution 0 A2.01-Ability to (a) predict the impacts of the following malfunctions or 0 operations on the DC electrical systems; and (b) based on those predictions, 063 DC Electrical Distribution 3.2 1 1 use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Grounds 064 Emergency Diesel Generator 0 A2.02-Ability to (a) predict the impacts of the following malfunctions or 0 operations on the PRM system; and (b) based on those predictions, use 073 Process Radiation Monitoring procedures to correct, control, or mitigate the consequences of those 3.2 1 2
malfunctions or operations: Detector failure 076 Service Water 0 078 Instrument Air 0 103 Containment 0 0
K/A Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 ES-401, 24 of 33
ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (SRO)
K K K K K K A A A A System # / Name G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive 0 002 Reactor Coolant 0 011 Pressurizer Level Control 0 014 Rod Position Indication 0 015 Nuclear Instrumentation 0 016 Non-nuclear Instrumentation 0 017 In-core Temperature Monitor 0 027 Containment Iodine Removal 0 028 Hydrogen Recombiner and Purge 0
Control 029 Containment Purge 0 033 Spent Fuel Pool Cooling 0 034 Fuel Handling Equipment 0 A2.04-Ability to (a) predict the impacts of the following malfunctions or operations 0 on the GS; and (b) based on those predictions, use procedures to correct, 035 Steam Generator 4 control, or mitigate the consequences of those malfunctions or operations:
3.8 1 Steam flow/feed mismatch 2.4.30-Knowledge of events related to system operation/status that must be 04.
041 Steam Dump/Turbine Bypass Control reported to internal organizations or external agencies, such as the State, the 4.1 1 30 NRC, or the transmission system operator.
2.4.4-Ability to recognize abnormal indications for system operating parameters 04.
045 Main Turbine Generator that are entry-level conditions for emergency and abnormal operating 4.7 1 04 procedures.
055 Condenser Air Removal 0 056 Condensate 0 068 Liquid Radwaste 0 071 Waste Gas Disposal 0 072 Area Radiation Monitoring 0 075 Circulating Water 0 079 Station Air 0 086 Fire Protection 0 K/A Category Totals: 0 0 0 0 0 0 0 1 0 0 2 Group Point Total: 3 ES-401, 25 of 33
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility Name:PALISADES Date of Exam:09/19/2014 RO SRO-Only Category K/A # Topic IR # IR #
2.1. 20 2.1.20-Ability to interpret and execute procedure steps. 4.6 1 4.6 2.1.44-Knowledge of RO duties in the control room during fuel handling such as responding to alarms from the fuel handling area, communication with the fuel storage 2.1. 44 facility, systems operated from the control room in support of fueling operations, and 3.9 1 3.8 supporting instrumentation.
- 1. 2.1.23-Ability to perform specific system and integrated plant procedures during all modes Conduct of 2.1. 23 of plant operation.
4.3 4.4 1 Operations 2.1. 42 2.1.42-Knowledge of new and spent fuel movement procedures. 2.5 3.4 1 2.1.
2.1.
Subtotal 2 2 2.2. 12 2.2.12-Knowledge of surveillance procedures. 3.7 1 4.1 2.2. 13 2.2.13-Knowledge of tagging and clearance procedures. 4.1 1 4.3 2.2.25-Knowledge of the bases in Technical Specifications for limiting conditions for
- 2. 2.2. 25 operations and safety limits.
3.2 1 4.2 Equipment Control 2.2. 19 2.2.19-Knowledge of maintenance work order requirements. 2.3 3.4 1 2.2.
2.2.
Subtotal 3 1 2.3.
2.3.7-Ability to comply with radiation work permit requirements during normal or abnormal 2.3. 07 conditions.
3.5 1 3.6 2.3.13-Knowledge of radiological safety procedures pertaining to licensed operator duties,
- 3. 2.3. 13 such as response to radiation monitor alarms, containment entry requirements, fuel 3.4 1 3.8 handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
Radiation Control 2.3.5-Ability to use radiation monitoring systems, such as fixed radiation monitors and 2.3. 05 alarms, portable survey instruments, personnel monitoring equipment, etc.
2.9 1 2.9 2.3. 04 2.3.4-Knowledge of radiation exposure limits under normal or emergency conditions. 3.2 3.7 1 2.3. 06 2.3.6-Ability to approve release permits. 2.0 3.8 1 Subtotal 3 2 2.4.9-Knowledge of low power/shutdown implications in accident (e.g., loss of coolant 2.4. 09 accident or loss of residual heat removal) mitigation strategies.
3.8 1 4.2 2.4.34-Knowledge of RO tasks performed outside the main control room during an 2.4. 34 emergency and the resultant operational effects.
4.2 1 4.1
- 4. 2.4.5-Knowledge of the organization of the operating procedures network for normal, 2.4. 05 abnormal, and emergency evolutions.
3.7 4.3 1 Emergency Procedures 2.4.47-Ability to diagnose and recognize trends in an accurate and timely manner utilizing 2.4. 47 the appropriate control room reference material.
4.2 4.2 1
/ Plan 2.4.
2.4.
Subtotal 2 2 Tier 3 Point Total 10 7 ES-401, Page 26 of 33