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{{#Wiki_filter:ES-401PWR Examination OutlineFORM ES-401-2Facility Name:Braidwood                                Date of Exam:11/10/2014K 1K 2K 3K 4K 5K 6A 1A 2A 3A 4G  *TotalTotal1333333186222121194Tier  Totals554544271013223322323328520111111111110013Tier  Totals3334433434438812342122Note:  1.Note:  2.Note:  3.Note:  4.Note:  5.Note:  6.Note:  7.*Note:  8.Note:  9.ES-401, 21 of 335The 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.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.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).4232232.              Plant Systems3. Generic Knowledge and      Abilities Categories1710223321. Emergency  &            Abnormal Plant Evolutions5TierGroupSRO-Only PointsRO K/A Category Points A 2G *N/AN/ASelect 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.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.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.Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.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.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.32443 ES-4012Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)E/APE # / Name / Safety FunctionK1K2K3A1A2GK/A Topic(s)IR#000007 Reactor Trip - Stabilization - Recovery / 105Reactor trip first-out indication3.41000008 Pressurizer Vapor Space Accident / 330Inadequate core cooling4.31000009 Small Break LOCA / 30 3S/Gs3.01000011 Large Break LOCA / 304.20Knowledge of the operational implications of EOP warnings, cautions, and notes.3.81000015 RCP Malfunctions / 4  000017 RCP Malfunctions (Loss of RC Flow) / 40000022 Loss of Rx Coolant Makeup / 202.22Knowledge of limiting conditions for operations and safety limits.4.01000025 Loss of RHR System / 40000026 Loss of Component Cooling Water / 806Control of flow rates to components cooled by the CCWS2.91000027 Pressurizer Pressure Control System Malfunction / 302Expansion of liquids as temperature increases2.81000029 ATWS / 10000038 Steam Gen. Tube Rupture / 304Automatic actions provided by each PRM3.91000040 Steam Line Rupture - Excessive Heat Transfer
/ 401Valves2.6WE12 Uncontrolled Depressurization of all Steam Generators / 4000054 (CE/E06) Loss of Main Feedwater / 403AFW auxiliaries, including oil cooling water supply3.51000055 Station Blackout / 60000056 Loss of Off-site Power / 612Reactor building cooling unit3.21000057 Loss of Vital AC Inst. Bus / 604.11Knowledge of abnormal condition procedures.4.01000058 Loss of DC Power / 601Battery charger equipment and instrumentation2.81000062 Loss of Nuclear Svc Water / 406The length of time after the loss of SWS flow to a component before that component may be damaged2.81000065 Loss of Instrument Air / 80W/E04 LOCA Outside Containment / 301Components, capacity, and function of emergency systems3.51W/E11 Loss of Emergency Coolant Recirc. / 402Normal, abnormal and emergency operating procedures associated with Loss of Emergency Coolant Recirculation3.51BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 401Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features3.71000077 Generator Voltage and Electric Grid Disturbances / 601Reactor and turbine trip criteria3.91K/A Category Totals:33333318ES-401, 22 of 33Group Point Total:1 ES-4013Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)E/APE # / Name / Safety FunctionK1K2K3A1A2GK/A Topic(s)IR#000001 Continuous Rod Withdrawal / 103Relationship of reactivity and reactor power to rod movement3.91000003 Dropped Control Rod / 10000005 Inoperable/Stuck Control Rod / 102Breakers, relays, disconnects, and control room switches2.51000024 Emergency Boration / 101.20Ability to interpret and execute procedure steps.4.61000028 Pressurizer Level Malfunction / 20000032 Loss of Source Range NI / 701Manual restoration of power3.11000033 Loss of Intermediate Range NI / 70000036 Fuel Handling Accident / 802SDM3.41000037 Steam Generator Tube Leak / 30000051 Loss of Condenser Vacuum / 40000059 Accidental Liquid RadWaste Rel. / 90000060 Accidental Gaseous Radwaste Rel. / 90000061 ARM System Alarms / 702Guidance contained in alarm response for ARM system3.41000067 Plant Fire On-site / 80000068 Control Room Evac. / 80000069  Loss of CTMT Integrity / 5W/E14 High Containment Pressure / 5 000074 Inad. Core Cooling / 403AFW pump4.0W/E06 Degraded Core Cooling / 4 W/E07 Saturated Core Cooling / 4000076 High Reactor Coolant Activity / 90W/E01 Rediagnosis / 302Operating behavior characteristics of the facility3.3W/E02 SI Termination / 3W/E13 Steam Generator Over-pressure / 40W/E15 Containment Flooding / 502Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments2.91W/E16 High Containment Radiation / 90W/E03 LOCA Cooldown - Depress. / 40W/E09 Natural Circulation Operations / 4W/E10 Natural Circulation with Steam Voide in Vessel with/without RVLIS. / 4W/E08 RCS Overcooling - PTS / 40K/A Category Totals:2212119ES-401, 23 of 33Group Point Total:1001 ES-4014Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2/Group 1 (RO)System # / NameK1K2K3K4K5K6A1A2A3A4GK/A Topic(s)IR#003 Reactor Coolant Pump08Containment isolation2.71004 Chemical and Volume Control09Purpose of VCT divert valve2.81005 Residual Heat Removal0103RHR pumps; RHR heat exchanger3; 2.52006 Emergency Core Cooling05Effects of pressure on a solid system3.41007 Pressurizer Relief/Quench Tank0101Maintaining quench tank water level within limits; PRT spray supply valve2.9; 2.72008 Component Cooling Water04Requirements on and for the CCWS for different conditions of the power plant2.91010 Pressurizer Pressure Control03Over pressure control3.81012 Reactor Protection0304.45SDS; Ability to prioritize and interpret the significance of each annunciator or alarm.3.1; 4.12013 Engineered Safety Features Actuation16Avoidance of PTS3.81022 Containment Cooling02Containment instrumentation readings3.01025 Ice Condenser0026 Containment Spray0 2Failure of automatic recirculation transfer4.21039 Main and Reheat Steam08Effect of steam removal on reactivity3.61059 Main Feedwater03Power level restrictions for operation of MFW pumps and valves2.71061 Auxiliary/Emergency Feedwater0201.30MFW System; Ability to locate and operate components, including local controls.3.4; 4.42062 AC Electrical Distribution0103Types of loads that, if de-energized, would degrade or hinder plant operation; Synchroscope, including an understanding of running and incoming voltages3.4; 2.82063 DC Electrical Distribution01Meters, annunciators, dials, recorders, and indicating lights2.71064 Emergency Diesel Generator0102.38Air compressor; Knowledge of conditions and limitations in the facility license.2.7; 3.62073 Process Radiation Monitoring02Radiation intensity changes with source distance2.51076 Service Water02Automatic start features associated with SWS pump controls2.91078 Instrument Air0401Cooling water to compressor; Pressure gauges2.6; 3.12103 Containment04Containment evacuation (including recognition of the alarm)3.510K/A Category Totals:3223322323328ES-401, Page 24 of 33Group Point Total:
ES-4015Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2/Group 2 (RO)System # / NameK1K2K3K4K5K6A1A2A3A4GK/A Topic(s)IR#001 Control Rod Drive0002 Reactor Coolant02RCP3.61011 Pressurizer Level Control0014 Rod Position Indication0015 Nuclear Instrumentation0016 Non-nuclear Instrumentation0 1Reading of NNIS channel values outside control room2.81017 In-core Temperature Monitor0 1Indications of normal, natural, and interrupted circulation of RCS3.61027 Containment Iodine Removal04Filter temperature2.81028 Hydrogen Recombiner and Purge Control0029 Containment Purge0033 Spent Fuel Pool Cooling0034 Fuel Handling Equipment03Mispositioned fuel element3.31035 Steam Generator01.23Ability to perform specific system and integrated plant procedures during all modes of plant operation.4.31041 Steam Dump/Turbine Bypass Control0045 Main Turbine Generator0 1Remainder of the plant2.91055 Condenser Air Removal0056 Condensate0068 Liquid Radwaste0071 Waste Gas Disposal0 4Relationship of hydrogen/oxygen concentrations to flammability2.51072 Area Radiation Monitoring0 1Radiation levels3.41075 Circulating Water0 3Emergency/essential SWS pumps2.61079 Station Air0086 Fire Protection0K/A Category Totals:0111111111110ES-401, Page 25 of 33Group Point Total:
ES-4012Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)E/APE # / Name / Safety FunctionK1K2K3A1A2GK/A Topic(s)IR#000007 Reactor Trip - Stabilization - Recovery / 10000008 Pressurizer Vapor Space Accident / 30000009 Small Break LOCA / 30000011 Large Break LOCA / 30000015 RCP Malfunctions / 4  000017 RCP Malfunctions (Loss of RC Flow) / 401Cause of RCP failure3.51000022 Loss of Rx Coolant Makeup / 20000025 Loss of RHR System / 401Proper amperage of running LPI/decay heat removal/RHR pump(s)2.91000026 Loss of Component Cooling Water / 80000027 Pressurizer Pressure Control System Malfunction / 30000029 ATWS / 101.07Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.4.71000038 Steam Gen. Tube Rupture / 30000040 Steam Line Rupture - Excessive Heat Transfer
/ 4WE12 Uncontrolled Depressurization of all Steam Generators / 404.09Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.4.2000054 (CE/E06) Loss of Main Feedwater / 40000055 Station Blackout / 604.06Knowledge of EOP mitigation strategies.4.71000056 Loss of Off-site Power / 60000057 Loss of Vital AC Inst. Bus / 60000058 Loss of DC Power / 60000062 Loss of Nuclear Svc Water / 40000065 Loss of Instrument Air / 806When to trip reactor if instrument air pressure is decreasing4.21W/E04 LOCA Outside Containment / 30W/E11 Loss of Emergency Coolant Recirc. / 40BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 40000077 Generator Voltage and ElectricGrid Disturbances / 60K/A Category Totals:0000336ES-401, 22 of 33Group Point Total:1 ES-4013Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)E/APE # / Name / Safety FunctionK1K2K3A1A2GK/A Topic(s)IR#000001 Continuous Rod Withdrawal / 10000003 Dropped Control Rod / 10000005 Inoperable/Stuck Control Rod / 10000024 Emergency Boration / 10000028 Pressurizer Level Malfunction / 202.25Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.4.21000032 Loss of Source Range NI / 70000033 Loss of Intermediate Range NI / 70000036 Fuel Handling Accident / 80000037 Steam Generator Tube Leak / 30000051 Loss of Condenser Vacuum / 40000059 Accidental Liquid RadWaste Rel. / 90000060 Accidental Gaseous Radwaste Rel. / 90000061 ARM System Alarms / 70000067 Plant Fire On-site / 80000068 Control Room Evac. / 80000069  Loss of CTMT Integrity / 5W/E14 High Containment Pressure / 5000074 Inad. Core Cooling / 4W/E06 Degraded Core Cooling / 4W/E07 Saturated Core Cooling / 4000076 High Reactor Coolant Activity / 904.35Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.4.01W/E01 Rediagnosis / 3 W/E02 SI Termination / 3 W/E13 Steam Generator Over-pressure / 40W/E15 Containment Flooding / 50W/E16 High Containment Radiation / 901Facility conditions and selection of appropriate procedures during abnormal and emergency operations3.31W/E03 LOCA Cooldown - Depress. / 40W/E09 Natural Circulation Operations / 4W/E10 Natural Circulation with Steam Voide in Vessel with/without RVLIS. / 4W/E08 RCS Overcooling - PTS / 401Facility conditions and selection of appropriate procedures during abnormal and emergency operations4.21K/A Category Totals:0000224ES-401, 23 of 33Group Point Total:0000 ES-4014Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2/Group 1 (SRO)System # / NameK1K2K3K4K5K6A1A2A3A4GK/A Topic(s)IR#003 Reactor Coolant Pump04.50Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.4.01004 Chemical and Volume Control04.01Knowledge of EOP entry conditions and immediate action steps.4.81005 Residual Heat Removal0006 Emergency Core Cooling13Inadvertent SIS actuation4.21007 Pressurizer Relief/Quench Tank0008 Component Cooling Water0010 Pressurizer Pressure Control01Heater failures3.61012 Reactor Protection0013 Engineered Safety Features Actuation0022 Containment Cooling0025 Ice Condenser0026 Containment Spray0039 Main and Reheat Steam0059 Main Feedwater0061 Auxiliary/Emergency Feedwater0062 AC Electrical Distribution0063 DC Electrical Distribution0064 Emergency Diesel Generator0073 Process Radiation Monitoring0076 Service Water0078 Instrument Air0103 Containment03Phase A and B isolation3.810K/A Category Totals:000000030025ES-401, Page 24 of 33Group Point Total:
ES-4015Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2/Group 2 (SRO)System # / NameK1K2K3K4K5K6A1A2A3A4GK/A Topic(s)IR#001 Control Rod Drive0002 Reactor Coolant0011 Pressurizer Level Control0014 Rod Position Indication0015 Nuclear Instrumentation04.08Knowledge of how abnormal operating procedures are used in conjunction with EOPs.4.51016 Non-nuclear Instrumentation0017 In-core Temperature Monitor0027 Containment Iodine Removal0028 Hydrogen Recombiner and Purge Control0029 Containment Purge0033 Spent Fuel Pool Cooling01Inadequate SDM3.51034 Fuel Handling Equipment0035 Steam Generator0041 Steam Dump/Turbine Bypass Control0045 Main Turbine Generator0055 Condenser Air Removal0056 Condensate0068 Liquid Radwaste0071 Waste Gas Disposal0072 Area Radiation Monitoring0075 Circulating Water0079 Station Air04.47Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.4.21086 Fire Protection0K/A Category Totals:000000010023ES-401, Page 25 of 33Group Point Total:}}

Revision as of 18:33, 15 June 2018

2014 Braidwood Station Initial License Examination Form ES-401-2
ML14364A376
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 11/24/2014
From: McNeil D R
NRC/RGN-III/DRS/OLB
To:
Exelon Generation Co
Shared Package
ML14344A990 List:
References
ES-401-2 50-456/OL-14, 50-457/OL-14
Download: ML14364A376 (9)
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ES-401PWR Examination OutlineFORM ES-401-2Facility Name:Braidwood Date of Exam:11/10/2014K 1K 2K 3K 4K 5K 6A 1A 2A 3A 4G *TotalTotal1333333186222121194Tier Totals554544271013223322323328520111111111110013Tier Totals3334433434438812342122Note: 1.Note: 2.Note: 3.Note: 4.Note: 5.Note: 6.Note: 7.*Note: 8.Note: 9.ES-401, 21 of 335The 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.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.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).4232232. Plant Systems3. Generic Knowledge and Abilities Categories1710223321. Emergency & Abnormal Plant Evolutions5TierGroupSRO-Only PointsRO K/A Category Points A 2G *N/AN/ASelect 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.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.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.Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.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.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.32443 ES-4012Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)E/APE # / Name / Safety FunctionK1K2K3A1A2GK/A Topic(s)IR#000007 Reactor Trip - Stabilization - Recovery / 105Reactor trip first-out indication3.41000008 Pressurizer Vapor Space Accident / 330Inadequate core cooling4.31000009 Small Break LOCA / 30 3S/Gs3.01000011 Large Break LOCA / 304.20Knowledge of the operational implications of EOP warnings, cautions, and notes.3.81000015 RCP Malfunctions / 4 000017 RCP Malfunctions (Loss of RC Flow) / 40000022 Loss of Rx Coolant Makeup / 202.22Knowledge of limiting conditions for operations and safety limits.4.01000025 Loss of RHR System / 40000026 Loss of Component Cooling Water / 806Control of flow rates to components cooled by the CCWS2.91000027 Pressurizer Pressure Control System Malfunction / 302Expansion of liquids as temperature increases2.81000029 ATWS / 10000038 Steam Gen. Tube Rupture / 304Automatic actions provided by each PRM3.91000040 Steam Line Rupture - Excessive Heat Transfer

/ 401Valves2.6WE12 Uncontrolled Depressurization of all Steam Generators / 4000054 (CE/E06) Loss of Main Feedwater / 403AFW auxiliaries, including oil cooling water supply3.51000055 Station Blackout / 60000056 Loss of Off-site Power / 612Reactor building cooling unit3.21000057 Loss of Vital AC Inst. Bus / 604.11Knowledge of abnormal condition procedures.4.01000058 Loss of DC Power / 601Battery charger equipment and instrumentation2.81000062 Loss of Nuclear Svc Water / 406The length of time after the loss of SWS flow to a component before that component may be damaged2.81000065 Loss of Instrument Air / 80W/E04 LOCA Outside Containment / 301Components, capacity, and function of emergency systems3.51W/E11 Loss of Emergency Coolant Recirc. / 402Normal, abnormal and emergency operating procedures associated with Loss of Emergency Coolant Recirculation3.51BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 401Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features3.71000077 Generator Voltage and Electric Grid Disturbances / 601Reactor and turbine trip criteria3.91K/A Category Totals:33333318ES-401, 22 of 33Group Point Total:1 ES-4013Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)E/APE # / Name / Safety FunctionK1K2K3A1A2GK/A Topic(s)IR#000001 Continuous Rod Withdrawal / 103Relationship of reactivity and reactor power to rod movement3.91000003 Dropped Control Rod / 10000005 Inoperable/Stuck Control Rod / 102Breakers, relays, disconnects, and control room switches2.51000024 Emergency Boration / 101.20Ability to interpret and execute procedure steps.4.61000028 Pressurizer Level Malfunction / 20000032 Loss of Source Range NI / 701Manual restoration of power3.11000033 Loss of Intermediate Range NI / 70000036 Fuel Handling Accident / 802SDM3.41000037 Steam Generator Tube Leak / 30000051 Loss of Condenser Vacuum / 40000059 Accidental Liquid RadWaste Rel. / 90000060 Accidental Gaseous Radwaste Rel. / 90000061 ARM System Alarms / 702Guidance contained in alarm response for ARM system3.41000067 Plant Fire On-site / 80000068 Control Room Evac. / 80000069 Loss of CTMT Integrity / 5W/E14 High Containment Pressure / 5 000074 Inad. Core Cooling / 403AFW pump4.0W/E06 Degraded Core Cooling / 4 W/E07 Saturated Core Cooling / 4000076 High Reactor Coolant Activity / 90W/E01 Rediagnosis / 302Operating behavior characteristics of the facility3.3W/E02 SI Termination / 3W/E13 Steam Generator Over-pressure / 40W/E15 Containment Flooding / 502Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments2.91W/E16 High Containment Radiation / 90W/E03 LOCA Cooldown - Depress. / 40W/E09 Natural Circulation Operations / 4W/E10 Natural Circulation with Steam Voide in Vessel with/without RVLIS. / 4W/E08 RCS Overcooling - PTS / 40K/A Category Totals:2212119ES-401, 23 of 33Group Point Total:1001 ES-4014Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2/Group 1 (RO)System # / NameK1K2K3K4K5K6A1A2A3A4GK/A Topic(s)IR#003 Reactor Coolant Pump08Containment isolation2.71004 Chemical and Volume Control09Purpose of VCT divert valve2.81005 Residual Heat Removal0103RHR pumps; RHR heat exchanger3; 2.52006 Emergency Core Cooling05Effects of pressure on a solid system3.41007 Pressurizer Relief/Quench Tank0101Maintaining quench tank water level within limits; PRT spray supply valve2.9; 2.72008 Component Cooling Water04Requirements on and for the CCWS for different conditions of the power plant2.91010 Pressurizer Pressure Control03Over pressure control3.81012 Reactor Protection0304.45SDS; Ability to prioritize and interpret the significance of each annunciator or alarm.3.1; 4.12013 Engineered Safety Features Actuation16Avoidance of PTS3.81022 Containment Cooling02Containment instrumentation readings3.01025 Ice Condenser0026 Containment Spray0 2Failure of automatic recirculation transfer4.21039 Main and Reheat Steam08Effect of steam removal on reactivity3.61059 Main Feedwater03Power level restrictions for operation of MFW pumps and valves2.71061 Auxiliary/Emergency Feedwater0201.30MFW System; Ability to locate and operate components, including local controls.3.4; 4.42062 AC Electrical Distribution0103Types of loads that, if de-energized, would degrade or hinder plant operation; Synchroscope, including an understanding of running and incoming voltages3.4; 2.82063 DC Electrical Distribution01Meters, annunciators, dials, recorders, and indicating lights2.71064 Emergency Diesel Generator0102.38Air compressor; Knowledge of conditions and limitations in the facility license.2.7; 3.62073 Process Radiation Monitoring02Radiation intensity changes with source distance2.51076 Service Water02Automatic start features associated with SWS pump controls2.91078 Instrument Air0401Cooling water to compressor; Pressure gauges2.6; 3.12103 Containment04Containment evacuation (including recognition of the alarm)3.510K/A Category Totals:3223322323328ES-401, Page 24 of 33Group Point Total:

ES-4015Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2/Group 2 (RO)System # / NameK1K2K3K4K5K6A1A2A3A4GK/A Topic(s)IR#001 Control Rod Drive0002 Reactor Coolant02RCP3.61011 Pressurizer Level Control0014 Rod Position Indication0015 Nuclear Instrumentation0016 Non-nuclear Instrumentation0 1Reading of NNIS channel values outside control room2.81017 In-core Temperature Monitor0 1Indications of normal, natural, and interrupted circulation of RCS3.61027 Containment Iodine Removal04Filter temperature2.81028 Hydrogen Recombiner and Purge Control0029 Containment Purge0033 Spent Fuel Pool Cooling0034 Fuel Handling Equipment03Mispositioned fuel element3.31035 Steam Generator01.23Ability to perform specific system and integrated plant procedures during all modes of plant operation.4.31041 Steam Dump/Turbine Bypass Control0045 Main Turbine Generator0 1Remainder of the plant2.91055 Condenser Air Removal0056 Condensate0068 Liquid Radwaste0071 Waste Gas Disposal0 4Relationship of hydrogen/oxygen concentrations to flammability2.51072 Area Radiation Monitoring0 1Radiation levels3.41075 Circulating Water0 3Emergency/essential SWS pumps2.61079 Station Air0086 Fire Protection0K/A Category Totals:0111111111110ES-401, Page 25 of 33Group Point Total:

ES-4012Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)E/APE # / Name / Safety FunctionK1K2K3A1A2GK/A Topic(s)IR#000007 Reactor Trip - Stabilization - Recovery / 10000008 Pressurizer Vapor Space Accident / 30000009 Small Break LOCA / 30000011 Large Break LOCA / 30000015 RCP Malfunctions / 4 000017 RCP Malfunctions (Loss of RC Flow) / 401Cause of RCP failure3.51000022 Loss of Rx Coolant Makeup / 20000025 Loss of RHR System / 401Proper amperage of running LPI/decay heat removal/RHR pump(s)2.91000026 Loss of Component Cooling Water / 80000027 Pressurizer Pressure Control System Malfunction / 30000029 ATWS / 101.07Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.4.71000038 Steam Gen. Tube Rupture / 30000040 Steam Line Rupture - Excessive Heat Transfer

/ 4WE12 Uncontrolled Depressurization of all Steam Generators / 404.09Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.4.2000054 (CE/E06) Loss of Main Feedwater / 40000055 Station Blackout / 604.06Knowledge of EOP mitigation strategies.4.71000056 Loss of Off-site Power / 60000057 Loss of Vital AC Inst. Bus / 60000058 Loss of DC Power / 60000062 Loss of Nuclear Svc Water / 40000065 Loss of Instrument Air / 806When to trip reactor if instrument air pressure is decreasing4.21W/E04 LOCA Outside Containment / 30W/E11 Loss of Emergency Coolant Recirc. / 40BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 40000077 Generator Voltage and ElectricGrid Disturbances / 60K/A Category Totals:0000336ES-401, 22 of 33Group Point Total:1 ES-4013Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)E/APE # / Name / Safety FunctionK1K2K3A1A2GK/A Topic(s)IR#000001 Continuous Rod Withdrawal / 10000003 Dropped Control Rod / 10000005 Inoperable/Stuck Control Rod / 10000024 Emergency Boration / 10000028 Pressurizer Level Malfunction / 202.25Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.4.21000032 Loss of Source Range NI / 70000033 Loss of Intermediate Range NI / 70000036 Fuel Handling Accident / 80000037 Steam Generator Tube Leak / 30000051 Loss of Condenser Vacuum / 40000059 Accidental Liquid RadWaste Rel. / 90000060 Accidental Gaseous Radwaste Rel. / 90000061 ARM System Alarms / 70000067 Plant Fire On-site / 80000068 Control Room Evac. / 80000069 Loss of CTMT Integrity / 5W/E14 High Containment Pressure / 5000074 Inad. Core Cooling / 4W/E06 Degraded Core Cooling / 4W/E07 Saturated Core Cooling / 4000076 High Reactor Coolant Activity / 904.35Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.4.01W/E01 Rediagnosis / 3 W/E02 SI Termination / 3 W/E13 Steam Generator Over-pressure / 40W/E15 Containment Flooding / 50W/E16 High Containment Radiation / 901Facility conditions and selection of appropriate procedures during abnormal and emergency operations3.31W/E03 LOCA Cooldown - Depress. / 40W/E09 Natural Circulation Operations / 4W/E10 Natural Circulation with Steam Voide in Vessel with/without RVLIS. / 4W/E08 RCS Overcooling - PTS / 401Facility conditions and selection of appropriate procedures during abnormal and emergency operations4.21K/A Category Totals:0000224ES-401, 23 of 33Group Point Total:0000 ES-4014Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2/Group 1 (SRO)System # / NameK1K2K3K4K5K6A1A2A3A4GK/A Topic(s)IR#003 Reactor Coolant Pump04.50Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.4.01004 Chemical and Volume Control04.01Knowledge of EOP entry conditions and immediate action steps.4.81005 Residual Heat Removal0006 Emergency Core Cooling13Inadvertent SIS actuation4.21007 Pressurizer Relief/Quench Tank0008 Component Cooling Water0010 Pressurizer Pressure Control01Heater failures3.61012 Reactor Protection0013 Engineered Safety Features Actuation0022 Containment Cooling0025 Ice Condenser0026 Containment Spray0039 Main and Reheat Steam0059 Main Feedwater0061 Auxiliary/Emergency Feedwater0062 AC Electrical Distribution0063 DC Electrical Distribution0064 Emergency Diesel Generator0073 Process Radiation Monitoring0076 Service Water0078 Instrument Air0103 Containment03Phase A and B isolation3.810K/A Category Totals:000000030025ES-401, Page 24 of 33Group Point Total:

ES-4015Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2/Group 2 (SRO)System # / NameK1K2K3K4K5K6A1A2A3A4GK/A Topic(s)IR#001 Control Rod Drive0002 Reactor Coolant0011 Pressurizer Level Control0014 Rod Position Indication0015 Nuclear Instrumentation04.08Knowledge of how abnormal operating procedures are used in conjunction with EOPs.4.51016 Non-nuclear Instrumentation0017 In-core Temperature Monitor0027 Containment Iodine Removal0028 Hydrogen Recombiner and Purge Control0029 Containment Purge0033 Spent Fuel Pool Cooling01Inadequate SDM3.51034 Fuel Handling Equipment0035 Steam Generator0041 Steam Dump/Turbine Bypass Control0045 Main Turbine Generator0055 Condenser Air Removal0056 Condensate0068 Liquid Radwaste0071 Waste Gas Disposal0072 Area Radiation Monitoring0075 Circulating Water0079 Station Air04.47Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.4.21086 Fire Protection0K/A Category Totals:000000010023ES-401, Page 25 of 33Group Point Total:

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