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{{#Wiki_filter:ES-401PWR Examination OutlineFORM ES-401-2Facility Name:Braidwood                               Date of Exam:11/10/2014 K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G  *TotalTotal 1 3 3 3 3 3 3 18 6 2 2 2 1 2 1 1 9 4Tier  Totals 5 5 4 5 4 4 27 10 1 3 2 2 3 3 2 2 3 2 3 3 28 5 2 0 1 1 1 1 1 1 1 1 1 1 10 0 1 3Tier  Totals 3 3 3 4 4 3 3 4 3 4 4 38 8 1 2 3 4 2 1 2 2Note:   1.Note:  2.Note:  3.Note:   4.Note:  5.Note:  6.Note:  7.*Note:   8.Note:  9.ES-401, 21 of 33 5The 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).
{{#Wiki_filter:ES-401                                          PWR Examination Outline                                                          FORM ES-401-2 Facility Name:Braidwood                               Date of Exam:11/10/2014 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
4 2 3 2 2 32.               Plant Systems3. Generic Knowledge and      Abilities Categories 1 7 10 2 2 3 3 21. Emergency 
* 1           3   3   3                   3   3             3         18             3            3          6
&            Abnormal Plant Evolutions 5TierGroupSRO-Only PointsRO K/A Category Points A 2 G *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.
: 1. Emergency
3 2 4 4 3 ES-401 2Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)
        &
IR#000007 Reactor Trip - Stabilization - Recovery / 1 0 5Reactor trip first-out indication3.4 1000008 Pressurizer Vapor Space Accident / 3 3 0Inadequate core cooling4.3 1000009 Small Break LOCA / 3 0
Abnormal            2           2   2   1       N/A        2   1     N/A    1           9             2            2          4 Plant Evolutions                                                                                                    5            5 Tier Totals       5   5   4                   5   4             4         27                                       10 1           3   2   2   3   3   2   2   3     2   3   3         28             3            2          5 2.
3S/Gs3.0 1000011 Large Break LOCA / 3 04.20Knowledge of the operational implications of EOP warnings, cautions, and notes.3.8 1000015 RCP Malfunctions / 4  000017 RCP Malfunctions (Loss of RC Flow) / 4 0000022 Loss of Rx Coolant Makeup / 2 02.22Knowledge of limiting conditions for operations and safety limits.4.0 1000025 Loss of RHR System / 4 0000026 Loss of Component Cooling Water / 8 0 6Control of flow rates to components cooled by the CCWS2.9 1000027 Pressurizer Pressure Control System Malfunction / 3 0 2Expansion of liquids as temperature increases2.8 1000029 ATWS / 1 0000038 Steam Gen. Tube Rupture / 3 0 4Automatic actions provided by each PRM3.9 1000040 Steam Line Rupture - Excessive Heat Transfer
2          0   1   1   1   1   1   1   1     1   1   1         10         0     1         2          3 Plant Systems Tier Totals       3   3   3   4   4     3   3     4   3   4   4         38             4            4          8 1         2         3         4                       1     2     3      4
: 3. Generic Knowledge and            Abilities 10                                        7 Categories 2          3        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-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


/ 4 0 1Valves2.6WE12 Uncontrolled Depressurization of all Steam Generators / 4000054 (CE/E06) Loss of Main Feedwater / 4 0 3AFW auxiliaries, including oil cooling water supply3.5 1000055 Station Blackout / 6 0000056 Loss of Off-site Power / 6 1 2Reactor building cooling unit3.2 1000057 Loss of Vital AC Inst. Bus / 6 04.11Knowledge of abnormal condition procedures.4.0 1000058 Loss of DC Power / 6 0 1Battery charger equipment and instrumentation2.8 1000062 Loss of Nuclear Svc Water / 4 0 6The length of time after the loss of SWS flow to a component before that component may be damaged2.8 1000065 Loss of Instrument Air / 8 0W/E04 LOCA Outside Containment / 3 0 1Components, capacity, and function of emergency systems3.5 1W/E11 Loss of Emergency Coolant Recirc. / 4 0 2Normal, abnormal and emergency operating procedures associated with Loss of Emergency Coolant Recirculation3.5 1BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 0 1Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features3.7 1000077 Generator Voltage and Electric Grid Disturbances / 6 0 1Reactor and turbine trip criteria3.9 1K/A Category Totals:
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)
3 3 3 3 3 3 18ES-401, 22 of 33Group Point Total:
K    K  K  A  A E/APE # / Name / Safety Function                                    G                            K/A Topic(s)                              IR      #
1 ES-401 3Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)
1    2  3  1  2 0
IR#000001 Continuous Rod Withdrawal / 1 03Relationship of reactivity and reactor power to rod movement3.9 1000003 Dropped Control Rod / 1 0000005 Inoperable/Stuck Control Rod / 1 02Breakers, relays, disconnects, and control room switches2.5 1000024 Emergency Boration / 1 01.20Ability to interpret and execute procedure steps.4.6 1000028 Pressurizer Level Malfunction / 2 0000032 Loss of Source Range NI / 7 01Manual restoration of power3.1 1000033 Loss of Intermediate Range NI / 7 0000036 Fuel Handling Accident / 8 02SDM3.4 1000037 Steam Generator Tube Leak / 3 0000051 Loss of Condenser Vacuum / 4 0000059 Accidental Liquid RadWaste Rel. / 9 0000060 Accidental Gaseous Radwaste Rel. / 9 0000061 ARM System Alarms / 7 02Guidance contained in alarm response for ARM system3.4 1000067 Plant Fire On-site / 8 0000068 Control Room Evac. / 8 0000069  Loss of CTMT Integrity / 5W/E14 High Containment Pressure / 5 000074 Inad. Core Cooling / 4 03AFW pump4.0W/E06 Degraded Core Cooling / 4 W/E07 Saturated Core Cooling / 4000076 High Reactor Coolant Activity / 9 0W/E01 Rediagnosis / 3 02Operating behavior characteristics of the facility3.3W/E02 SI Termination / 3W/E13 Steam Generator Over-pressure / 4 0W/E15 Containment Flooding / 5 02Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments2.9 1W/E16 High Containment Radiation / 9 0W/E03 LOCA Cooldown - Depress. / 4 0W/E09 Natural Circulation Operations / 4W/E10 Natural Circulation with Steam Voide in Vessel with/without RVLIS. / 4W/E08 RCS Overcooling - PTS / 4 0K/A Category Totals:
000007 Reactor Trip - Stabilization - Recovery / 1                            Reactor trip first-out indication                                    3.4    1 5
2 2 1 2 1 1 9ES-401, 23 of 33Group Point Total:
3 000008 Pressurizer Vapor Space Accident / 3                                    Inadequate core cooling                                              4.3    1 0
1 0 0 1 ES-401 4Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2/Group 1 (RO)System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)
0 000009 Small Break LOCA / 3                                                    S/Gs                                                                3.0    1 3
IR#003 Reactor Coolant Pump 0 8Containment isolation2.7 1004 Chemical and Volume Control 0 9Purpose of VCT divert valve2.8 1005 Residual Heat Removal 0 1 0 3RHR pumps; RHR heat exchanger3; 2.5 2006 Emergency Core Cooling 0 5Effects of pressure on a solid system3.4 1007 Pressurizer Relief/Quench Tank 0 1 0 1Maintaining quench tank water level within limits; PRT spray supply valve2.9; 2.7 2008 Component Cooling Water 0 4Requirements on and for the CCWS for different conditions of the power plant2.9 1010 Pressurizer Pressure Control 0 3Over pressure control3.8 1012 Reactor Protection 0 3 04.45SDS; Ability to prioritize and interpret the significance of each annunciator or alarm.3.1; 4.1 2013 Engineered Safety Features Actuation 1 6Avoidance of PTS3.8 1022 Containment Cooling 0 2Containment instrumentation readings3.0 1025 Ice Condenser 0026 Containment Spray 0
: 04. Knowledge of the operational implications of EOP warnings, 000011 Large Break LOCA / 3                                                                                                                        3.8    1 20  cautions, and notes.
2Failure of automatic recirculation transfer4.2 1039 Main and Reheat Steam 0 8Effect of steam removal on reactivity3.6 1059 Main Feedwater 0 3Power level restrictions for operation of MFW pumps and valves2.7 1061 Auxiliary/Emergency Feedwater 0 2 01.30MFW System; Ability to locate and operate components, including local controls.3.4; 4.4 2062 AC Electrical Distribution 0 1 0 3Types of loads that, if de-energized, would degrade or hinder plant operation; Synchroscope, including an understanding of running and incoming voltages3.4; 2.8 2063 DC Electrical Distribution 0 1Meters, annunciators, dials, recorders, and indicating lights2.7 1064 Emergency Diesel Generator 0 1 02.38Air compressor; Knowledge of conditions and limitations in the facility license.2.7; 3.6 2073 Process Radiation Monitoring 0 2Radiation intensity changes with source distance2.5 1076 Service Water 0 2Automatic start features associated with SWS pump controls2.9 1078 Instrument Air 0 4 0 1Cooling water to compressor; Pressure gauges2.6; 3.1 2103 Containment 0 4Containment evacuation (including recognition of the alarm)3.5 1 0K/A Category Totals:
000015 RCP Malfunctions / 4 0
3 2 2 3 3 2 2 3 2 3 3 28ES-401, Page 24 of 33Group Point Total:
000017 RCP Malfunctions (Loss of RC Flow) / 4 02.
ES-401 5Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2/Group 2 (RO)System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)
000022 Loss of Rx Coolant Makeup / 2                                          Knowledge of limiting conditions for operations and safety limits. 4.0    1 22 000025 Loss of RHR System / 4                                                                                                                              0 0
IR#001 Control Rod Drive 0002 Reactor Coolant 0 2 RCP3.6 1011 Pressurizer Level Control 0014 Rod Position Indication 0015 Nuclear Instrumentation 0016 Non-nuclear Instrumentation 0
000026 Loss of Component Cooling Water / 8                                    Control of flow rates to components cooled by the CCWS              2.9    1 6
1Reading of NNIS channel values outside control room2.8 1017 In-core Temperature Monitor 0
000027 Pressurizer Pressure Control System            0 Expansion of liquids as temperature increases                        2.8    1 Malfunction / 3                                        2 000029 ATWS / 1                                                                                                                                            0 0
1Indications of normal, natural, and interrupted circulation of  
000038 Steam Gen. Tube Rupture / 3                                            Automatic actions provided by each PRM                              3.9    1 4
000040 Steam Line Rupture - Excessive Heat Transfer        0 Valves                                                              2.6
/4                                                          1 1
WE12 Uncontrolled Depressurization of all Steam Generators / 4 0
000054 (CE/E06) Loss of Main Feedwater / 4                                     AFW auxiliaries, including oil cooling water supply                  3.5     1 3
000055 Station Blackout / 6                                                                                                                                 0 1
000056 Loss of Off-site Power / 6                                             Reactor building cooling unit                                        3.2     1 2
04.
000057 Loss of Vital AC Inst. Bus / 6                                         Knowledge of abnormal condition procedures.                         4.0     1 11 0
000058 Loss of DC Power / 6                                                   Battery charger equipment and instrumentation                        2.8     1 1
0       The length of time after the loss of SWS flow to a component 000062 Loss of Nuclear Svc Water / 4                                                                                                                2.8    1 6      before that component may be damaged 000065 Loss of Instrument Air / 8                                                                                                                           0 0
W/E04 LOCA Outside Containment / 3                                             Components, capacity, and function of emergency systems              3.5     1 1
0              Normal, abnormal and emergency operating procedures W/E11 Loss of Emergency Coolant Recirc. / 4                                                                                                         3.5    1 2              associated with Loss of Emergency Coolant Recirculation Components, and functions of control and safety systems, BW/E04; W/E05 Inadequate Heat Transfer - Loss of           0 including instrumentation, signals, interlocks, failure modes, and   3.7    1 Secondary Heat Sink / 4                                    1                  automatic and manual features 000077 Generator Voltage and Electric                         0 Reactor and turbine trip criteria                                    3.9     1 Grid Disturbances / 6                                         1 K/A Category Totals:                                   3   3 3   3   3   3 Group Point Total:                                                           18 ES-401, 22 of 33


RCS3.6 1027 Containment Iodine Removal 0 4Filter temperature2.8 1028 Hydrogen Recombiner and Purge Control 0029 Containment Purge 0033 Spent Fuel Pool Cooling 0034 Fuel Handling Equipment 0 3Mispositioned fuel element3.3 1035 Steam Generator 01.23Ability to perform specific system and integrated plant procedures during all modes of plant operation.4.3 1041 Steam Dump/Turbine Bypass Control 0045 Main Turbine Generator 0
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)
1Remainder of the plant2.9 1055 Condenser Air Removal 0056 Condensate 0068 Liquid Radwaste 0071 Waste Gas Disposal 0
K  K    K  A    A E/APE # / Name / Safety Function                                     G                              K/A Topic(s)                       IR   #
4Relationship of hydrogen/oxygen concentrations to flammability2.5 1072 Area Radiation Monitoring 0
1    2  3  1    2 000001 Continuous Rod Withdrawal / 1             03                        Relationship of reactivity and reactor power to rod movement  3.9    1 000003 Dropped Control Rod / 1                                                                                                                    0 000005 Inoperable/Stuck Control Rod / 1                02                    Breakers, relays, disconnects, and control room switches      2.5    1 01.
1Radiation levels3.4 1075 Circulating Water 0
000024 Emergency Boration / 1                                                Ability to interpret and execute procedure steps.              4.6    1 20 000028 Pressurizer Level Malfunction / 2                                                                                                          0 000032 Loss of Source Range NI / 7                            01            Manual restoration of power                                    3.1    1 000033 Loss of Intermediate Range NI / 7                                                                                                          0 000036 Fuel Handling Accident / 8                02                        SDM                                                            3.4    1 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                              02                Guidance contained in alarm response for ARM system            3.4   1 000067 Plant Fire On-site / 8                                                                                                                      0 000068 Control Room Evac. / 8                                                                                                                      0 000069 Loss of CTMT Integrity / 5 0
3Emergency/essential SWS pumps2.6 1079 Station Air 0086 Fire Protection 0K/A Category Totals:
W/E14 High Containment Pressure / 5 000074 Inad. Core Cooling / 4                          03                    AFW pump                                                       4.0 W/E06 Degraded Core Cooling / 4                                                                                                                    1 W/E07 Saturated Core Cooling / 4 000076 High Reactor Coolant Activity / 9                                                                                                           0 W/E01 Rediagnosis / 3                                          02            Operating behavior characteristics of the facility            3.3 1
0 1 1 1 1 1 1 1 1 1 1 10ES-401, Page 25 of 33Group Point Total:
W/E02 SI Termination / 3 W/E13 Steam Generator Over-pressure / 4                                                                                                            0 Adherence to appropriate procedures and operation within the W/E15 Containment Flooding / 5                                      02      limitations in the facility's license and amendments 2.9    1 W/E16 High Containment Radiation / 9                                                                                                              0 W/E03 LOCA Cooldown - Depress. / 4                                                                                                                 0 W/E09 Natural Circulation Operations / 4 0
ES-401 2Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)
W/E10 Natural Circulation with Steam Voide in Vessel with/without RVLIS. / 4 W/E08 RCS Overcooling - PTS / 4                                                                                                                    0 K/A Category Totals:                              2    2  1  2    1    1 Group Point Total:                                                    9 ES-401, 23 of 33
IR#000007 Reactor Trip - Stabilization - Recovery / 1 0000008 Pressurizer Vapor Space Accident / 3 0000009 Small Break LOCA / 3 0000011 Large Break LOCA / 3 0000015 RCP Malfunctions / 4 000017 RCP Malfunctions (Loss of RC Flow) / 4 0 1Cause of RCP failure3.5 1000022 Loss of Rx Coolant Makeup / 2 0000025 Loss of RHR System / 4 0 1Proper amperage of running LPI/decay heat removal/RHR pump(s)2.9 1000026 Loss of Component Cooling Water / 8 0000027 Pressurizer Pressure Control System Malfunction / 3 0000029 ATWS / 1 01.07Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.4.7 1000038 Steam Gen. Tube Rupture / 3 0000040 Steam Line Rupture - Excessive Heat Transfer


/ 4WE12 Uncontrolled Depressurization of all Steam Generators / 4 04.09Knowledge 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 / 4 0000055 Station Blackout / 6 04.06Knowledge of EOP mitigation strategies.4.7 1000056 Loss of Off-site Power / 6 0000057 Loss of Vital AC Inst. Bus / 6 0000058 Loss of DC Power / 6 0000062 Loss of Nuclear Svc Water / 4 0000065 Loss of Instrument Air / 8 0 6When to trip reactor if instrument air pressure is decreasing4.2 1W/E04 LOCA Outside Containment / 3 0W/E11 Loss of Emergency Coolant Recirc. / 4 0BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 0000077 Generator Voltage and ElectricGrid Disturbances / 6 0K/A Category Totals:
ES-401                                                          4                                                      Form ES-401-2 ES-401                                              PWR Examination Outline                                                      Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)
0 0 0 0 3 3 6ES-401, 22 of 33Group Point Total:
K K K K K K A A A A System # / Name                                                G                          K/A Topic(s)                            IR    #
1 ES-401 3Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)
1 2 3 4 5 6 1 2 3 4 0
IR#000001 Continuous Rod Withdrawal / 1 0000003 Dropped Control Rod / 1 0000005 Inoperable/Stuck Control Rod / 1 0000024 Emergency Boration / 1 0000028 Pressurizer Level Malfunction / 2 02.25Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.4.2 1000032 Loss of Source Range NI / 7 0000033 Loss of Intermediate Range NI / 7 0000036 Fuel Handling Accident / 8 0000037 Steam Generator Tube Leak / 3 0000051 Loss of Condenser Vacuum / 4 0000059 Accidental Liquid RadWaste Rel. / 9 0000060 Accidental Gaseous Radwaste Rel. / 9 0000061 ARM System Alarms / 7 0000067 Plant Fire On-site / 8 0000068 Control Room Evac. / 8 0000069  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 / 9 04.35Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.4.0 1W/E01 Rediagnosis / 3 W/E02 SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 0W/E15 Containment Flooding / 5 0W/E16 High Containment Radiation / 9 01Facility conditions and selection of appropriate procedures during abnormal and emergency operations3.3 1W/E03 LOCA Cooldown - Depress. / 4 0W/E09 Natural Circulation Operations / 4W/E10 Natural Circulation with Steam Voide in Vessel with/without RVLIS. / 4W/E08 RCS Overcooling - PTS / 4 01Facility conditions and selection of appropriate procedures during abnormal and emergency operations4.2 1K/A Category Totals:
003 Reactor Coolant Pump                                            Containment isolation                                          2.7    1 8
0 0 0 0 2 2 4ES-401, 23 of 33Group Point Total:
0 004 Chemical and Volume Control                                    Purpose of VCT divert valve                                    2.8    1 9
0 0 0 0 ES-401 4Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2/Group 1 (SRO)System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)
0        0 005 Residual Heat Removal                                          RHR pumps; RHR heat exchanger                                3; 2.5  2 1        3 0
IR#003 Reactor Coolant Pump 04.50Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.4.0 1004 Chemical and Volume Control 04.01Knowledge of EOP entry conditions and immediate action steps.4.8 1005 Residual Heat Removal 0006 Emergency Core Cooling 1 3Inadvertent SIS actuation4.2 1007 Pressurizer Relief/Quench Tank 0008 Component Cooling Water 0010 Pressurizer Pressure Control 0 1Heater failures3.6 1012 Reactor Protection 0013 Engineered Safety Features Actuation 0022 Containment Cooling 0025 Ice Condenser 0026 Containment Spray 0039 Main and Reheat Steam 0059 Main Feedwater 0061 Auxiliary/Emergency Feedwater 0062 AC Electrical Distribution 0063 DC Electrical Distribution 0064 Emergency Diesel Generator 0073 Process Radiation Monitoring 0076 Service Water 0078 Instrument Air 0103 Containment 0 3Phase A and B isolation3.8 1 0K/A Category Totals:
006 Emergency Core Cooling                                          Effects of pressure on a solid system                          3.4    1 5
0 0 0 0 0 0 0 3 0 0 2 5ES-401, Page 24 of 33Group Point Total:
0        0        Maintaining quench tank water level within limits; PRT        2.9; 007 Pressurizer Relief/Quench Tank                                                                                                        2 1        1        spray supply valve                                            2.7 0          Requirements on and for the CCWS for different conditions 008 Component Cooling Water                                                                                                        2.9    1 4          of the power plant 0
ES-401 5Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2/Group 2 (SRO)System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)
010 Pressurizer Pressure Control                                    Over pressure control                                          3.8    1 3
IR#001 Control Rod Drive 0002 Reactor Coolant 0011 Pressurizer Level Control 0014 Rod Position Indication 0015 Nuclear Instrumentation 04.08Knowledge of how abnormal operating procedures are used in conjunction with EOPs.4.5 1016 Non-nuclear Instrumentation 0017 In-core Temperature Monitor 0027 Containment Iodine Removal 0028 Hydrogen Recombiner and Purge Control 0029 Containment Purge 0033 Spent Fuel Pool Cooling 0 1Inadequate SDM3.5 1034 Fuel Handling Equipment 0035 Steam Generator 0041 Steam Dump/Turbine Bypass Control 0045 Main Turbine Generator 0055 Condenser Air Removal 0056 Condensate 0068 Liquid Radwaste 0071 Waste Gas Disposal 0072 Area Radiation Monitoring 0075 Circulating Water 0079 Station Air 04.47Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.4.2 1086 Fire Protection 0K/A Category Totals:
0                      04. SDS; Ability to prioritize and interpret the significance of  3.1; 012 Reactor Protection                                                                                                                    2 3                      45  each annunciator or alarm.                                    4.1 013 Engineered Safety Features          1 Avoidance of PTS                                              3.8    1 Actuation                                6 0
0 0 0 0 0 0 0 1 0 0 2 3ES-401, Page 25 of 33Group Point Total:}}
022 Containment Cooling                                            Containment instrumentation readings                          3.0    1 2
025 Ice Condenser                                                                                                                          0 0
026 Containment Spray                                              Failure of automatic recirculation transfer                    4.2    1 2
0 039 Main and Reheat Steam                                          Effect of steam removal on reactivity                          3.6    1 8
0                Power level restrictions for operation of MFW pumps and 059 Main Feedwater                                                                                                                2.7    1 3                valves 0                          01. MFW System; Ability to locate and operate components,          3.4; 061 Auxiliary/Emergency Feedwater                                                                                                          2 2                          30  including local controls.                                      4.4 Types of loads that, if de-energized, would degrade or 0    0                                                                      3.4; 062 AC Electrical Distribution                                      hinder plant operation; Synchroscope, including an                    2 1    3        understanding of running and incoming voltages                2.8 0
063 DC Electrical Distribution                                      Meters, annunciators, dials, recorders, and indicating lights  2.7    1 1
0                        02. Air compressor; Knowledge of conditions and limitations in    2.7; 064 Emergency Diesel Generator                                                                                                            2 1                        38  the facility license.                                          3.6 0
073 Process Radiation Monitoring                                    Radiation intensity changes with source distance              2.5    1 2
0                          Automatic start features associated with SWS pump 076 Service Water                                                                                                                  2.9    1 2                          controls 0                      0                                                                      2.6; 078 Instrument Air                                                  Cooling water to compressor; Pressure gauges                          2 4                      1                                                                      3.1 0              Containment evacuation (including recognition of the 103 Containment                                                                                                                    3.5    1 4              alarm) 0 K/A Category Totals:              3 2 2 3 3  2  2  3  2 3    3 Group Point Total:                                                      28 ES-401, Page 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  4 001 Control Rod Drive                                                                                                                        0 0
002 Reactor Coolant 2
RCP                                                              3.6    1 011 Pressurizer Level Control                                                                                                                0 014 Rod Position Indication                                                                                                                  0 015 Nuclear Instrumentation                                                                                                                  0 0
016 Non-nuclear Instrumentation 1
Reading of NNIS channel values outside control room              2.8    1 0        Indications of normal, natural, and interrupted circulation of 017 In-core Temperature Monitor 1        RCS 3.6    1 0
027 Containment Iodine Removal 4
Filter temperature                                                2.8    1 028 Hydrogen Recombiner and Purge 0
Control 029 Containment Purge                                                                                                                        0 033 Spent Fuel Pool Cooling                                                                                                                  0 0
034 Fuel Handling Equipment 3
Mispositioned fuel element                                        3.3    1
: 01. Ability to perform specific system and integrated plant 035 Steam Generator                                                                                                                    4.3    1 23 procedures during all modes of plant operation.
041 Steam Dump/Turbine Bypass Control                                                                                                        0 0
045 Main Turbine Generator 1
Remainder of the plant                                            2.9    1 055 Condenser Air Removal                                                                                                                    0 056 Condensate                                                                                                                                0 068 Liquid Radwaste                                                                                                                          0 0                      Relationship of hydrogen/oxygen concentrations to 071 Waste Gas Disposal 4                      flammability 2.5    1 0
072 Area Radiation Monitoring 1
Radiation levels                                                  3.4    1 0
075 Circulating Water 3
Emergency/essential SWS pumps                                    2.6    1 079 Station Air                                                                                                                              0 086 Fire Protection                                                                                                                          0 K/A Category Totals:                  0 1 1 1 1  1  1  1  1  1  1 Group Point Total:                                                      10 ES-401, Page 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 - Stabilization - Recovery / 1                                                                                                    0 000008 Pressurizer Vapor Space Accident / 3                                                                                                            0 000009 Small Break LOCA / 3                                                                                                                            0 000011 Large Break LOCA / 3                                                                                                                            0 000015 RCP Malfunctions / 4                                          0 Cause of RCP failure                                              3.5    1 000017 RCP Malfunctions (Loss of RC Flow) / 4                        1 000022 Loss of Rx Coolant Makeup / 2                                                                                                                  0 0      Proper amperage of running LPI/decay heat removal/RHR 000025 Loss of RHR System / 4                                                                                                                  2.9    1 1      pump(s) 000026 Loss of Component Cooling Water / 8                                                                                                            0 000027 Pressurizer Pressure Control System 0
Malfunction / 3 Ability to evaluate plant performance and make operational 01.
000029 ATWS / 1                                                              judgments based on operating characteristics, reactor behavior,  4.7    1 07  and instrument interpretation.
000038 Steam Gen. Tube Rupture / 3                                                                                                                    0 000040 Steam Line Rupture - Excessive Heat Transfer
/4 Knowledge of low power/shutdown implications in accident (e.g.,
1 WE12 Uncontrolled Depressurization of all Steam                          04.
loss of coolant accident or loss of residual heat removal)       4.2 Generators / 4                                                            09  mitigation strategies.
000054 (CE/E06) Loss of Main Feedwater / 4                                                                                                             0 04.
000055 Station Blackout / 6                                                   Knowledge of EOP mitigation strategies.                           4.7   1 06 000056 Loss of Off-site Power / 6                                                                                                                     0 000057 Loss of Vital AC Inst. Bus / 6                                                                                                                 0 000058 Loss of DC Power / 6                                                                                                                           0 000062 Loss of Nuclear Svc Water / 4                                                                                                                   0 0
000065 Loss of Instrument Air / 8                                             When to trip reactor if instrument air pressure is decreasing    4.2   1 6
W/E04 LOCA Outside Containment / 3                                                                                                                     0 W/E11 Loss of Emergency Coolant Recirc. / 4                                                                                                           0 BW/E04; W/E05 Inadequate Heat Transfer - Loss of 0
Secondary Heat Sink / 4 000077 Generator Voltage and Electric 0
Grid Disturbances / 6 K/A Category Totals:                                 0   0   0   0   3   3 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 000024 Emergency Boration / 1                                                                                                                       0
: 02. Knowledge of the bases in Technical Specifications for limiting 000028 Pressurizer Level Malfunction / 2                                                                                                      4.2    1 25  conditions for operations and safety limits.
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 000067 Plant Fire On-site / 8                                                                                                                       0 000068 Control Room Evac. / 8                                                                                                                       0 000069 Loss of CTMT Integrity / 5 0
W/E14 High Containment Pressure / 5 000074 Inad. Core Cooling / 4 W/E06 Degraded Core Cooling / 4                                                                                                                      0 W/E07 Saturated Core Cooling / 4
: 04. Knowledge of local auxiliary operator tasks during an emergency 000076 High Reactor Coolant Activity / 9                                                                                                      4.0    1 35  and the resultant operational effects.
W/E01 Rediagnosis / 3 0
W/E02 SI Termination / 3 W/E13 Steam Generator Over-pressure / 4                                                                                                             0 W/E15 Containment Flooding / 5                                                                                                                       0 Facility conditions and selection of appropriate procedures W/E16 High Containment Radiation / 9                               01      during abnormal and emergency operations 3.3   1 W/E03 LOCA Cooldown - Depress. / 4                                                                                                                   0 W/E09 Natural Circulation Operations / 4 0
W/E10 Natural Circulation with Steam Voide in Vessel with/without RVLIS. / 4 Facility conditions and selection of appropriate procedures W/E08 RCS Overcooling - PTS / 4                                   01      during abnormal and emergency operations 4.2   1 K/A Category Totals:                             0   0   0   0   2   2 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
: 04. Ability to verify system alarm setpoints and operate 003 Reactor Coolant Pump                                                                                                  4.0    1 50  controls identified in the alarm response manual.
: 04. Knowledge of EOP entry conditions and immediate action 004 Chemical and Volume Control                                                                                            4.8   1 01  steps.
005 Residual Heat Removal                                                                                                         0 1
006 Emergency Core Cooling                                       Inadvertent SIS actuation                                4.2   1 3
007 Pressurizer Relief/Quench Tank                                                                                               0 008 Component Cooling Water                                                                                                       0 0
010 Pressurizer Pressure Control                                 Heater failures                                          3.6   1 1
012 Reactor Protection                                                                                                           0 013 Engineered Safety Features 0
Actuation 022 Containment Cooling                                                                                                           0 025 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                                                                                                   0 063 DC Electrical Distribution                                                                                                   0 064 Emergency Diesel Generator                                                                                                   0 073 Process Radiation Monitoring                                                                                                 0 076 Service Water                                                                                                                 0 078 Instrument Air                                                                                                               0 0
103 Containment                                                   Phase A and B isolation                                  3.8   1 3
0 K/A Category Totals:               0 0 0 0 0 0 0   3 0 0   2 Group Point Total:                                              5 ES-401, Page 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
: 04. Knowledge of how abnormal operating procedures are used 015 Nuclear Instrumentation                                                                                                          4.5  1 08 in conjunction with EOPs.
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 0
033 Spent Fuel Pool Cooling 1
Inadequate SDM                                                  3.5   1 034 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                                                                                                                       0 071 Waste Gas Disposal                                                                                                                     0 072 Area Radiation Monitoring                                                                                                             0 075 Circulating Water                                                                                                                     0 Ability to diagnose and recognize trends in an accurate and 04.
079 Station Air                                                      timely manner utilizing the appropriate control room reference 4.2   1 47 material.
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, Page 25 of 33}}

Revision as of 18:22, 31 October 2019

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
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)
v • d • e


Text

ES-401 PWR Examination Outline FORM ES-401-2 Facility Name:Braidwood Date of Exam:11/10/2014 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 3 3 3 3 3 3 18 3 3 6
1. Emergency

&

Abnormal 2 2 2 1 N/A 2 1 N/A 1 9 2 2 4 Plant Evolutions 5 5 Tier Totals 5 5 4 5 4 4 27 10 1 3 2 2 3 3 2 2 3 2 3 3 28 3 2 5 2.

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

3. Generic Knowledge and Abilities 10 7 Categories 2 3 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-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 0

000007 Reactor Trip - Stabilization - Recovery / 1 Reactor trip first-out indication 3.4 1 5

3 000008 Pressurizer Vapor Space Accident / 3 Inadequate core cooling 4.3 1 0

0 000009 Small Break LOCA / 3 S/Gs 3.0 1 3

04. Knowledge of the operational implications of EOP warnings, 000011 Large Break LOCA / 3 3.8 1 20 cautions, and notes.

000015 RCP Malfunctions / 4 0

000017 RCP Malfunctions (Loss of RC Flow) / 4 02.

000022 Loss of Rx Coolant Makeup / 2 Knowledge of limiting conditions for operations and safety limits. 4.0 1 22 000025 Loss of RHR System / 4 0 0

000026 Loss of Component Cooling Water / 8 Control of flow rates to components cooled by the CCWS 2.9 1 6

000027 Pressurizer Pressure Control System 0 Expansion of liquids as temperature increases 2.8 1 Malfunction / 3 2 000029 ATWS / 1 0 0

000038 Steam Gen. Tube Rupture / 3 Automatic actions provided by each PRM 3.9 1 4

000040 Steam Line Rupture - Excessive Heat Transfer 0 Valves 2.6

/4 1 1

WE12 Uncontrolled Depressurization of all Steam Generators / 4 0

000054 (CE/E06) Loss of Main Feedwater / 4 AFW auxiliaries, including oil cooling water supply 3.5 1 3

000055 Station Blackout / 6 0 1

000056 Loss of Off-site Power / 6 Reactor building cooling unit 3.2 1 2

04.

000057 Loss of Vital AC Inst. Bus / 6 Knowledge of abnormal condition procedures. 4.0 1 11 0

000058 Loss of DC Power / 6 Battery charger equipment and instrumentation 2.8 1 1

0 The length of time after the loss of SWS flow to a component 000062 Loss of Nuclear Svc Water / 4 2.8 1 6 before that component may be damaged 000065 Loss of Instrument Air / 8 0 0

W/E04 LOCA Outside Containment / 3 Components, capacity, and function of emergency systems 3.5 1 1

0 Normal, abnormal and emergency operating procedures W/E11 Loss of Emergency Coolant Recirc. / 4 3.5 1 2 associated with Loss of Emergency Coolant Recirculation Components, and functions of control and safety systems, BW/E04; W/E05 Inadequate Heat Transfer - Loss of 0 including instrumentation, signals, interlocks, failure modes, and 3.7 1 Secondary Heat Sink / 4 1 automatic and manual features 000077 Generator Voltage and Electric 0 Reactor and turbine trip criteria 3.9 1 Grid Disturbances / 6 1 K/A Category Totals: 3 3 3 3 3 3 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 03 Relationship of reactivity and reactor power to rod movement 3.9 1 000003 Dropped Control Rod / 1 0 000005 Inoperable/Stuck Control Rod / 1 02 Breakers, relays, disconnects, and control room switches 2.5 1 01.

000024 Emergency Boration / 1 Ability to interpret and execute procedure steps. 4.6 1 20 000028 Pressurizer Level Malfunction / 2 0 000032 Loss of Source Range NI / 7 01 Manual restoration of power 3.1 1 000033 Loss of Intermediate Range NI / 7 0 000036 Fuel Handling Accident / 8 02 SDM 3.4 1 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 02 Guidance contained in alarm response for ARM system 3.4 1 000067 Plant Fire On-site / 8 0 000068 Control Room Evac. / 8 0 000069 Loss of CTMT Integrity / 5 0

W/E14 High Containment Pressure / 5 000074 Inad. Core Cooling / 4 03 AFW pump 4.0 W/E06 Degraded Core Cooling / 4 1 W/E07 Saturated Core Cooling / 4 000076 High Reactor Coolant Activity / 9 0 W/E01 Rediagnosis / 3 02 Operating behavior characteristics of the facility 3.3 1

W/E02 SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 0 Adherence to appropriate procedures and operation within the W/E15 Containment Flooding / 5 02 limitations in the facility's license and amendments 2.9 1 W/E16 High Containment Radiation / 9 0 W/E03 LOCA Cooldown - Depress. / 4 0 W/E09 Natural Circulation Operations / 4 0

W/E10 Natural Circulation with Steam Voide in Vessel with/without RVLIS. / 4 W/E08 RCS Overcooling - PTS / 4 0 K/A Category Totals: 2 2 1 2 1 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 0

003 Reactor Coolant Pump Containment isolation 2.7 1 8

0 004 Chemical and Volume Control Purpose of VCT divert valve 2.8 1 9

0 0 005 Residual Heat Removal RHR pumps; RHR heat exchanger 3; 2.5 2 1 3 0

006 Emergency Core Cooling Effects of pressure on a solid system 3.4 1 5

0 0 Maintaining quench tank water level within limits; PRT 2.9; 007 Pressurizer Relief/Quench Tank 2 1 1 spray supply valve 2.7 0 Requirements on and for the CCWS for different conditions 008 Component Cooling Water 2.9 1 4 of the power plant 0

010 Pressurizer Pressure Control Over pressure control 3.8 1 3

0 04. SDS; Ability to prioritize and interpret the significance of 3.1; 012 Reactor Protection 2 3 45 each annunciator or alarm. 4.1 013 Engineered Safety Features 1 Avoidance of PTS 3.8 1 Actuation 6 0

022 Containment Cooling Containment instrumentation readings 3.0 1 2

025 Ice Condenser 0 0

026 Containment Spray Failure of automatic recirculation transfer 4.2 1 2

0 039 Main and Reheat Steam Effect of steam removal on reactivity 3.6 1 8

0 Power level restrictions for operation of MFW pumps and 059 Main Feedwater 2.7 1 3 valves 0 01. MFW System; Ability to locate and operate components, 3.4; 061 Auxiliary/Emergency Feedwater 2 2 30 including local controls. 4.4 Types of loads that, if de-energized, would degrade or 0 0 3.4; 062 AC Electrical Distribution hinder plant operation; Synchroscope, including an 2 1 3 understanding of running and incoming voltages 2.8 0

063 DC Electrical Distribution Meters, annunciators, dials, recorders, and indicating lights 2.7 1 1

0 02. Air compressor; Knowledge of conditions and limitations in 2.7; 064 Emergency Diesel Generator 2 1 38 the facility license. 3.6 0

073 Process Radiation Monitoring Radiation intensity changes with source distance 2.5 1 2

0 Automatic start features associated with SWS pump 076 Service Water 2.9 1 2 controls 0 0 2.6; 078 Instrument Air Cooling water to compressor; Pressure gauges 2 4 1 3.1 0 Containment evacuation (including recognition of the 103 Containment 3.5 1 4 alarm) 0 K/A Category Totals: 3 2 2 3 3 2 2 3 2 3 3 Group Point Total: 28 ES-401, Page 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 4 001 Control Rod Drive 0 0

002 Reactor Coolant 2

RCP 3.6 1 011 Pressurizer Level Control 0 014 Rod Position Indication 0 015 Nuclear Instrumentation 0 0

016 Non-nuclear Instrumentation 1

Reading of NNIS channel values outside control room 2.8 1 0 Indications of normal, natural, and interrupted circulation of 017 In-core Temperature Monitor 1 RCS 3.6 1 0

027 Containment Iodine Removal 4

Filter temperature 2.8 1 028 Hydrogen Recombiner and Purge 0

Control 029 Containment Purge 0 033 Spent Fuel Pool Cooling 0 0

034 Fuel Handling Equipment 3

Mispositioned fuel element 3.3 1

01. Ability to perform specific system and integrated plant 035 Steam Generator 4.3 1 23 procedures during all modes of plant operation.

041 Steam Dump/Turbine Bypass Control 0 0

045 Main Turbine Generator 1

Remainder of the plant 2.9 1 055 Condenser Air Removal 0 056 Condensate 0 068 Liquid Radwaste 0 0 Relationship of hydrogen/oxygen concentrations to 071 Waste Gas Disposal 4 flammability 2.5 1 0

072 Area Radiation Monitoring 1

Radiation levels 3.4 1 0

075 Circulating Water 3

Emergency/essential SWS pumps 2.6 1 079 Station Air 0 086 Fire Protection 0 K/A Category Totals: 0 1 1 1 1 1 1 1 1 1 1 Group Point Total: 10 ES-401, Page 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 - Stabilization - Recovery / 1 0 000008 Pressurizer Vapor Space Accident / 3 0 000009 Small Break LOCA / 3 0 000011 Large Break LOCA / 3 0 000015 RCP Malfunctions / 4 0 Cause of RCP failure 3.5 1 000017 RCP Malfunctions (Loss of RC Flow) / 4 1 000022 Loss of Rx Coolant Makeup / 2 0 0 Proper amperage of running LPI/decay heat removal/RHR 000025 Loss of RHR System / 4 2.9 1 1 pump(s) 000026 Loss of Component Cooling Water / 8 0 000027 Pressurizer Pressure Control System 0

Malfunction / 3 Ability to evaluate plant performance and make operational 01.

000029 ATWS / 1 judgments based on operating characteristics, reactor behavior, 4.7 1 07 and instrument interpretation.

000038 Steam Gen. Tube Rupture / 3 0 000040 Steam Line Rupture - Excessive Heat Transfer

/4 Knowledge of low power/shutdown implications in accident (e.g.,

1 WE12 Uncontrolled Depressurization of all Steam 04.

loss of coolant accident or loss of residual heat removal) 4.2 Generators / 4 09 mitigation strategies.

000054 (CE/E06) Loss of Main Feedwater / 4 0 04.

000055 Station Blackout / 6 Knowledge of EOP mitigation strategies. 4.7 1 06 000056 Loss of Off-site Power / 6 0 000057 Loss of Vital AC Inst. Bus / 6 0 000058 Loss of DC Power / 6 0 000062 Loss of Nuclear Svc Water / 4 0 0

000065 Loss of Instrument Air / 8 When to trip reactor if instrument air pressure is decreasing 4.2 1 6

W/E04 LOCA Outside Containment / 3 0 W/E11 Loss of Emergency Coolant Recirc. / 4 0 BW/E04; W/E05 Inadequate Heat Transfer - Loss of 0

Secondary Heat Sink / 4 000077 Generator Voltage and Electric 0

Grid Disturbances / 6 K/A Category Totals: 0 0 0 0 3 3 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 000024 Emergency Boration / 1 0

02. Knowledge of the bases in Technical Specifications for limiting 000028 Pressurizer Level Malfunction / 2 4.2 1 25 conditions for operations and safety limits.

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 000067 Plant Fire On-site / 8 0 000068 Control Room Evac. / 8 0 000069 Loss of CTMT Integrity / 5 0

W/E14 High Containment Pressure / 5 000074 Inad. Core Cooling / 4 W/E06 Degraded Core Cooling / 4 0 W/E07 Saturated Core Cooling / 4

04. Knowledge of local auxiliary operator tasks during an emergency 000076 High Reactor Coolant Activity / 9 4.0 1 35 and the resultant operational effects.

W/E01 Rediagnosis / 3 0

W/E02 SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 0 W/E15 Containment Flooding / 5 0 Facility conditions and selection of appropriate procedures W/E16 High Containment Radiation / 9 01 during abnormal and emergency operations 3.3 1 W/E03 LOCA Cooldown - Depress. / 4 0 W/E09 Natural Circulation Operations / 4 0

W/E10 Natural Circulation with Steam Voide in Vessel with/without RVLIS. / 4 Facility conditions and selection of appropriate procedures W/E08 RCS Overcooling - PTS / 4 01 during abnormal and emergency operations 4.2 1 K/A Category Totals: 0 0 0 0 2 2 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

04. Ability to verify system alarm setpoints and operate 003 Reactor Coolant Pump 4.0 1 50 controls identified in the alarm response manual.
04. Knowledge of EOP entry conditions and immediate action 004 Chemical and Volume Control 4.8 1 01 steps.

005 Residual Heat Removal 0 1

006 Emergency Core Cooling Inadvertent SIS actuation 4.2 1 3

007 Pressurizer Relief/Quench Tank 0 008 Component Cooling Water 0 0

010 Pressurizer Pressure Control Heater failures 3.6 1 1

012 Reactor Protection 0 013 Engineered Safety Features 0

Actuation 022 Containment Cooling 0 025 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 0 063 DC Electrical Distribution 0 064 Emergency Diesel Generator 0 073 Process Radiation Monitoring 0 076 Service Water 0 078 Instrument Air 0 0

103 Containment Phase A and B isolation 3.8 1 3

0 K/A Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 ES-401, Page 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

04. Knowledge of how abnormal operating procedures are used 015 Nuclear Instrumentation 4.5 1 08 in conjunction with EOPs.

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 0

033 Spent Fuel Pool Cooling 1

Inadequate SDM 3.5 1 034 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 0 071 Waste Gas Disposal 0 072 Area Radiation Monitoring 0 075 Circulating Water 0 Ability to diagnose and recognize trends in an accurate and 04.

079 Station Air timely manner utilizing the appropriate control room reference 4.2 1 47 material.

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, Page 25 of 33

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