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| number = ML090490233
| number = ML090490233
| issue date = 02/02/2009
| issue date = 02/02/2009
| title = Arkansas Nuclear One Unit 1-2009-01-Final-Outlines
| title = 2009-01-Final-Outlines
| author name =  
| author name =  
| author affiliation = NRC/RGN-IV
| author affiliation = NRC/RGN-IV
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:ES-401PWR Examination OutlineForm ES-401-2ES-401 1Form ES-401-2Facility:Arkansas Nuclear One - Unit 1Date of Exam:
{{#Wiki_filter:ES-401                                            PWR Examination Outline                                                Form ES-401-2 Facility: Arkansas Nuclear One - Unit 1                                            Date of Exam:         1/28/2009 RO K/A Category Points                                      SRO-Only Points Tier            Group K   K   K   K     K   K   A     A     A   A   G                   A2           G*         Total 1    2    3    4    5    6    1    2    3    4
1/28/2009RO K/A Category PointsSRO-Only PointsTierGroup K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G*Total A2 G*Total 10 0 00 0 0 0 3 3 6 20 0 00 0 0 0 2 2 4 1.Emergency &AbnormalPlantEvolutionsTier Totals 0 0 0N/A0 0N/A 0 0 5 5 10 10 0 0 0 0 0 0 0 0 0 0 0 3 2 5 20 0 0 0 0 0 0 0 0 0 0 0 0 2 1 3 2.PlantSystemsTier Totals 0 0 0 0 0 0 0 0 0 0 0 0 5 3 8 1 2 3 4 1 2 3 43. Generic Knowledge and AbilitiesCategories 0 0 0 0 0 2 1 2 2 7Note: 1.Ensure that at least two topics from every applicable K/A category are sampled within each tier of the ROand 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).
* Total
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.
: 1.              1          0   0   0                   0     0              0      0            3             3           6 Emergency &
3.Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not applyat the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are notincluded on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the eliminationof inappropriate K/A statements.
Abnormal              2          0    0    0        N/A        0     0     N/A      0       0           2             2           4 Plant Evolutions      Tier Totals       0    0    0                   0     0              0       0           5             5           10 1          0    0   0   0     0   0   0     0     0   0   0       0           3             2           5 2.
4.Select topics from as many systems and evolutions as possible; sample every system or evolution in the group beforeselecting a second topic for any system or evolution.5.         Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.Use the RO and SRO ratings for the RO and SRO-only portions, respectively.6.       Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
Plant              2          0    0   0   0     0   0   0     0     0   0   0       0         0     2         1           3 Systems Tier Totals       0   0   0   0     0   0   0     0     0   0   0       0           5             3           8
7.*The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topicsmust be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
: 3. Generic Knowledge and Abilities                1         2         3         4          0       1      2      3      4        7 Categories 0             0         0         0                   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).
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 totalsfor each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on theSRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicatepages for RO and SRO-only exams.
: 2. The point total for each group and tier in the proposed outline must match that specified in the table.
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.
The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.
ES-401 2Form ES-401-2ES-401 2Form ES-401-2E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)
The final RO exam must total 75 points and the SRO-only exam must total 25 points.
IR#000007 (BW/E02&E10; CE/E02) ReactorTrip - Stabilization - Recovery / 1Not selectedn/an/a000008 Pressurizer Vapor SpaceAccident / 3 XAA2.30 -Inadequate core cooling 4.7 1000009 Small Break LOCA / 3Not selectedn/an/a000011 Large Break LOCA / 3Not selectedn/an/a000015/17 RCP Malfunctions / 4Not selectedn/an/a000022 Loss of Rx Coolant Makeup / 2Not selectedn/an/a000025 Loss of RHR System / 4Not selectedn/an/a000026 Loss of Component CoolingWater / 8Not selectedn/an/a000027 Pressurizer Pressure ControlSystem Malfunction / 3Not selectedn/an/a000029 ATWS / 1Not selectedn/an/a000038 Steam Gen. Tube Rupture / 3Not selectedn/an/a000040 (BW/E05; CE/E05; W/E12)Steam Line Rupture - Excessive HeatTransfer / 4 XEA2.2 -Adherence to appropriateprocedures and operation within thelimitations in the facility's license andamendments.
: 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/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
4.0 2000054 (CE/E06) Loss of MainFeedwater / 4 XAA2.01 -Occurrence of Reactor and / orTurbine Trip.
: 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.
4.4 3000055 Station Blackout / 6 X2.4.4 -Ability to recognize abnormalindications for system operatingparameters that are entry - levelconditions for emergency and abnormaloperating procedures.
: 5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.
4.7 4000056 Loss of Off-site Power / 6Not selectedn/an/a000057 Loss of Vital AC Inst. Bus / 6Not selectedn/an/a000058 Loss of DC Power / 6 X2.2.22 -Knowledge of limiting conditionsfor operations and safety limits.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
4.7 5000062 Loss of Nuclear Svc Water / 4 X2.1.23 -Ability to perform specific systemand integrated plant procedures during allmodes of plant operation.
: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
4.4 6000065 Loss of Instrument Air / 8Not selectedn/an/aW/E04 LOCA Outside Containment / 3Not selectedn/an/aW/E11 Loss of Emergency CoolantRecirc. / 4Not selectedn/an/aBW/E04; W/E05 Inadequate HeatTransfer - Loss of Secondary Heat Sink / 4Not selectedn/an/a000077 Generator Voltage and ElectricGrid Disturbances / 6Not selectedn/an/aK/A Category Totals:
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.
3 3Group Point Total:
: 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.
6 ES-401 3Form ES-401-2ES-401 3Form ES-401-2E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)
: 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.
IR#000001 Continuous Rod Withdrawal / 1Not selectedn/an/a000003 Dropped Control Rod / 1Not selectedn/an/a000005 Inoperable/Stuck Control Rod / 1Not selectedn/an/a000024 Emergency Boration / 1Not selectedn/an/a000028 Pressurizer Level Malfunction / 2Not selectedn/an/a000032 Loss of Source Range NI / 7Not selectedn/an/a000033 Loss of Intermediate Range NI / 7 XAA2.07 -Confirmation of reactortrip.4.2 7000036 (BW/A08) Fuel Handling Accident / 8Not selectedn/an/a000037 Steam Generator Tube Leak / 3Not selectedn/an/a000051 Loss of Condenser Vacuum / 4Not selectedn/an/a000059 Accidental Liquid RadWaste Rel. / 9Not selectedn/an/a000060 Accidental Gaseous Radwaste Rel. / 9Not selectedn/an/a000061 ARM System Alarms / 7Not selectedn/an/a000067 Plant Fire On-site / 8 X2.2.40 -Ability to apply TechnicalSpecifications for a system.
ES-401                                                     1                                          Form ES-401-2
4.7 8000068 (BW/A06) Control Room Evac. / 8Not selectedn/an/a000069 (W/E14) Loss of CTMT Integrity / 5Not selectedn/an/a000074 (W/E06&E07) Inad. Core Cooling / 4Not selectedn/an/a000076 High Reactor Coolant Activity / 9 X2.4.41 -Knowledge of theEmergency Action Level thresholdsand classifications.
 
4.6 9W/EO1 & E02 Rediagnosis & SI Termination / 3Not selectedn/an/aW/E13 Steam Generator Over-pressure / 4Not selectedn/an/aW/E15 Containment Flooding / 5Not selectedn/an/aW/E16 High Containment Radiation / 9Not selectedn/an/aBW/A01 Plant Runback / 1Not selectedn/an/aBW/A02&A03 Loss of NNI-X/Y / 7Not selectedn/an/aBW/A04 Turbine Trip / 4Not selectedn/an/aBW/A05 Emergency Diesel Actuation / 6Not selectedn/an/aBW/A07 Flooding / 8Not selectedn/an/aBW/E03 Inadequate Subcooling Margin / 4Not selectedn/an/aBW/E08; W/E03 LOCA Cooldown - Depress. / 4Not selectedn/an/aBW/E09; CE/A13; W/E09&E10 Natural Circ. / 4Not selectedn/an/aBW/E13&E14 EOP Rules and Enclosures XEA2.1 -Facility conditions andselection of appropriate proceduresduring abnormal and emergencyoperations.
ES-401                                                   2                                            Form ES-401-2 E/APE # / Name / Safety Function           K K K A A G                    K/A Topic(s)                   IR   #
4.0 10CE/A11; W/E08 RCS Overcooling - PTS / 4Not selectedn/an/aCE/A16 Excess RCS Leakage / 2Not selectedn/an/aCE/E09 Functional RecoveryNot selectedn/an/aK/A Category Point Totals:0 0 0 0 2 2Group Point Total:
1 2 3 1 2 000007 (BW/E02&E10; CE/E02) Reactor                      Not selected                                  n/a  n/a Trip - Stabilization - Recovery / 1 000008 Pressurizer Vapor Space                    X    AA2.30 - Inadequate core cooling               4.7   1 Accident / 3 000009 Small Break LOCA / 3                              Not selected                                  n/a  n/a 000011 Large Break LOCA / 3                              Not selected                                  n/a  n/a 000015/17 RCP Malfunctions / 4                          Not selected                                  n/a  n/a 000022 Loss of Rx Coolant Makeup / 2                    Not selected                                  n/a  n/a 000025 Loss of RHR System / 4                            Not selected                                  n/a  n/a 000026 Loss of Component Cooling                        Not selected                                  n/a  n/a Water / 8 000027 Pressurizer Pressure Control                      Not selected                                  n/a  n/a System Malfunction / 3 000029 ATWS / 1                                          Not selected                                  n/a  n/a 000038 Steam Gen. Tube Rupture / 3                      Not selected                                  n/a  n/a 000040 (BW/E05; CE/E05; W/E12)                     X    EA2.2 - Adherence to appropriate              4.0  2 Steam Line Rupture - Excessive Heat                      procedures and operation within the Transfer / 4                                            limitations in the facilitys license and amendments.
4 ES-401 4Form ES-401-2ES-401 4Form ES-401-2 K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)
000054 (CE/E06) Loss of Main                      X    AA2.01 - Occurrence of Reactor and / or        4.4  3 Feedwater / 4                                            Turbine Trip.
IR#003 Reactor Coolant Pump X2.4.9 -Knowledge of low power /shutdown implications in accident(e.g. loss of coolant accident orloss of residual heat removal)mitigation strategies.
000055 Station Blackout / 6                         X  2.4.4 - Ability to recognize abnormal          4.7  4 indications for system operating parameters that are entry - level conditions for emergency and abnormal operating procedures.
4.2 11004 Chemical and VolumeControlNot selectedn/an/a005 Residual Heat RemovalNot selectedn/an/a006 Emergency Core Cooling X2.2.42 -Ability to recognizesystem parameters that are entry-level conditions for TechnicalSpecifications.
000056 Loss of Off-site Power / 6                        Not selected                                  n/a  n/a 000057 Loss of Vital AC Inst. Bus / 6                    Not selected                                  n/a  n/a 000058 Loss of DC Power / 6                         X  2.2.22 - Knowledge of limiting conditions      4.7  5 for operations and safety limits.
4.6 12007 Pressurizer Relief/QuenchTankNot selectedn/an/a008 Component Cooling WaterNot selectedn/an/a010 Pressurizer PressureControl XA2.02 -Spray valve failures.
000062 Loss of Nuclear Svc Water / 4                 X  2.1.23 - Ability to perform specific system    4.4  6 and integrated plant procedures during all modes of plant operation.
3.9 13012 Reactor ProtectionNot selectedn/an/a013 Engineered SafetyFeatures ActuationNot selectedn/an/a022 Containment CoolingNot selectedn/an/a025 Ice CondenserNot selectedn/an/a026 Containment SprayNot selectedn/an/a039 Main and Reheat SteamNot selectedn/an/a059 Main Feedwater XA2.04 -Feeding a dry S/G.
000065 Loss of Instrument Air / 8                        Not selected                                  n/a  n/a W/E04 LOCA Outside Containment / 3                      Not selected                                  n/a  n/a W/E11 Loss of Emergency Coolant                          Not selected                                  n/a  n/a Recirc. / 4 BW/E04; W/E05 Inadequate Heat                           Not selected                                  n/a  n/a Transfer - Loss of Secondary Heat Sink / 4 000077 Generator Voltage and Electric                    Not selected                                  n/a  n/a Grid Disturbances / 6 K/A Category Totals:                               3 3   Group Point Total:                             6 ES-401                                       2                                          Form ES-401-2
3.4 14061 Auxiliary/EmergencyFeedwaterNot selectedn/an/a062 AC Electrical DistributionNot selectedn/an/a063 DC Electrical Distribution XA2.02 -Loss of ventilation duringbattery charging.
 
3.1 15064 Emergency DieselGeneratorNot selectedn/an/a073 Process RadiationMonitoringNot selectedn/an/a076 Service WaterNot selectedn/an/a078 Instrument AirNot selectedn/an/a103 ContainmentNot selectedn/an/aK/A Category Point Totals:
ES-401                                             3                                          Form ES-401-2 E/APE # / Name / Safety Function             K K K A A G              K/A Topic(s)             IR   #
0 0 0 0 0 0 0 3 0 0 2Group Point Total:
1 2 3 1 2 000001 Continuous Rod Withdrawal / 1                      Not selected                        n/a n/a 000003 Dropped Control Rod / 1                            Not selected                        n/a n/a 000005 Inoperable/Stuck Control Rod / 1                  Not selected                        n/a n/a 000024 Emergency Boration / 1                            Not selected                        n/a n/a 000028 Pressurizer Level Malfunction / 2                  Not selected                        n/a n/a 000032 Loss of Source Range NI / 7                        Not selected                        n/a n/a 000033 Loss of Intermediate Range NI / 7             X  AA2.07 - Confirmation of reactor    4.2 7 trip.
5 ES-401 5Form ES-401-2ES-401 5Form ES-401-2System # / 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)
000036 (BW/A08) Fuel Handling Accident / 8                Not selected                        n/a n/a 000037 Steam Generator Tube Leak / 3                      Not selected                        n/a n/a 000051 Loss of Condenser Vacuum / 4                      Not selected                        n/a n/a 000059 Accidental Liquid RadWaste Rel. / 9                Not selected                        n/a n/a 000060 Accidental Gaseous Radwaste Rel. / 9              Not selected                        n/a n/a 000061 ARM System Alarms / 7                              Not selected                        n/a n/a 000067 Plant Fire On-site / 8                           X 2.2.40 - Ability to apply Technical  4.7 8 Specifications for a system.
IR#001 Control Rod DriveNot selectedn/an/a002 Reactor CoolantNot selectedn/an/a011 Pressurizer Level ControlNot selectedn/an/a014 Rod Position Indication X2.2.22 -Knowledge of limitingcondition for operations andsafety limits.
000068 (BW/A06) Control Room Evac. / 8                    Not selected                        n/a n/a 000069 (W/E14) Loss of CTMT Integrity / 5                Not selected                        n/a n/a 000074 (W/E06&E07) Inad. Core Cooling / 4                Not selected                        n/a n/a 000076 High Reactor Coolant Activity / 9               X 2.4.41 - Knowledge of the            4.6 9 Emergency Action Level thresholds and classifications.
4.7 16015 Nuclear InstrumentationNot selectedn/an/a016 Non-nuclear Instrumentation XA2.01 -Detector failure3.1* 17017 In-core Temperature MonitorNot selectedn/an/a027 Containment Iodine RemovalNot selectedn/an/a028 Hydrogen Recombinerand Purge ControlNot selectedn/an/a029 Containment PurgeNot selectedn/an/a033 Spent Fuel Pool CoolingNot selectedn/an/a034 Fuel Handling EquipmentNot selectedn/an/a035 Steam GeneratorNot selectedn/an/a041 Steam Dump/TurbineBypass ControlNot selectedn/an/a045 Main Turbine GeneratorNot selectedn/an/a055 Condenser Air RemovalNot selectedn/an/a056 Condensate XA2.04 -Loss of condensatepumps.2.8* 18068 Liquid RadwasteNot selectedn/an/a071 Waste Gas DisposalNot selectedn/an/a072 Area Radiation MonitoringNot selectedn/an/a075 Circulating WaterNot selectedn/an/a079 Station AirNot selectedn/an/a086 Fire ProtectionNot selectedn/an/aK/A Category Point Totals:
W/EO1 & E02 Rediagnosis & SI Termination / 3              Not selected                        n/a n/a W/E13 Steam Generator Over-pressure / 4                  Not selected                        n/a n/a W/E15 Containment Flooding / 5                            Not selected                        n/a n/a W/E16 High Containment Radiation / 9                      Not selected                        n/a n/a BW/A01 Plant Runback / 1                                  Not selected                        n/a n/a BW/A02&A03 Loss of NNI-X/Y / 7                            Not selected                        n/a n/a BW/A04 Turbine Trip / 4                                  Not selected                        n/a n/a BW/A05 Emergency Diesel Actuation / 6                    Not selected                        n/a n/a BW/A07 Flooding / 8                                      Not selected                        n/a n/a BW/E03 Inadequate Subcooling Margin / 4                  Not selected                        n/a n/a BW/E08; W/E03 LOCA Cooldown - Depress. / 4                Not selected                        n/a n/a BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4              Not selected                        n/a n/a BW/E13&E14 EOP Rules and Enclosures                   X  EA2.1 - Facility conditions and     4.0 10 selection of appropriate procedures during abnormal and emergency operations.
0 0 0 0 0 0 0 2 0 0 1Group Point Total:
CE/A11; W/E08 RCS Overcooling - PTS / 4                  Not selected                        n/a n/a CE/A16 Excess RCS Leakage / 2                            Not selected                        n/a n/a CE/E09 Functional Recovery                                Not selected                        n/a n/a K/A Category Point Totals:                   0 0 0 0 2 2 Group Point Total:                   4 ES-401                                       3                                    Form ES-401-2
3 ES-401Generic Knowledge and Abilities Outline (Tier 3)Form ES-401-3ES-401 6Form ES-401-2 RO SROCategoryK/A #Topic IR#IR#2.1.35Knowledge of the fuel-handling responsibilities of SROs.
 
3.9 19 2.1.36Knowledge of procedures and limitation involved in corealterations.
ES-401                                             4                                          Form ES-401-2 K K K K K K A A A A   G            K/A Topic(s)           IR   #
4.1 20 1.Conductof OperationsSubtotal 2 2.2.25Knowledge of the bases in Technical Specifications for limitingconditions for operations and safety limits.
1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump                             X 2.4.9 - Knowledge of low power /   4.2  11 shutdown implications in accident (e.g. loss of coolant accident or loss of residual heat removal) mitigation strategies.
4.2 21 2.EquipmentControlSubtotal 12.3.4Knowledge of radiation exposure limits under normal oremergency conditions.
004 Chemical and Volume                                Not selected                      n/a  n/a Control 005 Residual Heat Removal                              Not selected                      n/a  n/a 006 Emergency Core Cooling                           X 2.2.42 - Ability to recognize      4.6  12 system parameters that are entry-level conditions for Technical Specifications.
3.7 22 2.3.11Ability to control radiation releases 4.3 23 3.RadiationControlSubtotal 22.4.1Knowledge of EOP entry conditions and immediate actionssteps.4.8 24 2.4.44Knowledge of Emergency Plan protective actionrecommendations.
007 Pressurizer Relief/Quench                          Not selected                      n/a  n/a Tank 008 Component Cooling Water                            Not selected                      n/a  n/a 010 Pressurizer Pressure                    X        A2.02 - Spray valve failures.     3.9 13 Control 012 Reactor Protection                                Not selected                      n/a  n/a 013 Engineered Safety                                  Not selected                      n/a  n/a Features Actuation 022 Containment Cooling                                Not selected                      n/a  n/a 025 Ice Condenser                                      Not selected                      n/a  n/a 026 Containment Spray                                  Not selected                      n/a  n/a 039 Main and Reheat Steam                              Not selected                      n/a  n/a 059 Main Feedwater                           X        A2.04 - Feeding a dry S/G.         3.4 14 061 Auxiliary/Emergency                                Not selected                      n/a  n/a Feedwater 062 AC Electrical Distribution                        Not selected                      n/a  n/a 063 DC Electrical Distribution               X        A2.02 - Loss of ventilation during 3.1  15 battery charging.
4.4 25 4.EmergencyProcedures /
064 Emergency Diesel                                  Not selected                      n/a  n/a Generator 073 Process Radiation                                  Not selected                      n/a  n/a Monitoring 076 Service Water                                      Not selected                      n/a  n/a 078 Instrument Air                                    Not selected                      n/a  n/a 103 Containment                                        Not selected                      n/a  n/a K/A Category Point Totals:     0 0 0 0 0 0 0 3 0 0   2 Group Point Total:                 5 ES-401                                       4                                Form ES-401-2
PlanSubtotal 2Tier 3 Point Total 7
 
ES-401Record of Rejected K/AsForm ES-401-4Tier /GroupRandomlySelected K/AReason for Rejection None None None}}
ES-401                                             5                                      Form ES-401-2 System # / Name                 K K K K K K   A A A A G            K/A Topic(s)       IR #
1 2 3 4 5 6  1 2 3 4 001 Control Rod Drive                                  Not selected                  n/a  n/a 002 Reactor Coolant                                    Not selected                  n/a  n/a 011 Pressurizer Level Control                          Not selected                  n/a  n/a 014 Rod Position Indication                           X 2.2.22 - Knowledge of limiting 4.7  16 condition for operations and safety limits.
015 Nuclear Instrumentation                            Not selected                  n/a  n/a 016 Non-nuclear Instrumentation                 X      A2.01 - Detector failure      3.1* 17 017 In-core Temperature Monitor                        Not selected                  n/a  n/a 027 Containment Iodine Removal                          Not selected                  n/a  n/a 028 Hydrogen Recombiner                                Not selected                  n/a  n/a and Purge Control 029 Containment Purge                                  Not selected                  n/a  n/a 033 Spent Fuel Pool Cooling                            Not selected                  n/a  n/a 034 Fuel Handling Equipment                            Not selected                  n/a  n/a 035 Steam Generator                                    Not selected                  n/a  n/a 041 Steam Dump/Turbine                                  Not selected                  n/a  n/a Bypass Control 045 Main Turbine Generator                              Not selected                  n/a  n/a 055 Condenser Air Removal                              Not selected                  n/a  n/a 056 Condensate                                 X      A2.04 - Loss of condensate    2.8* 18 pumps.
068 Liquid Radwaste                                    Not selected                  n/a  n/a 071 Waste Gas Disposal                                  Not selected                  n/a  n/a 072 Area Radiation Monitoring                          Not selected                  n/a  n/a 075 Circulating Water                                  Not selected                  n/a  n/a 079 Station Air                                        Not selected                  n/a  n/a 086 Fire Protection                                    Not selected                  n/a  n/a K/A Category Point Totals:     0 0 0 0 0 0   0 2 0 0 1 Group Point Total:             3 ES-401                                      5                              Form ES-401-2
 
ES-401                        Generic Knowledge and Abilities Outline (Tier 3)                           Form ES-401-3 Category            K/A #                                 Topic                                 RO          SRO IR   #     IR       #
2.1.35  Knowledge of the fuel-handling responsibilities of SROs.                     3.9       19 2.1.36  Knowledge of procedures and limitation involved in core                      4.1       20 1.
alterations.
Conduct of Operations Subtotal                                                                                        2 2.2.25  Knowledge of the bases in Technical Specifications for limiting              4.2      21 conditions for operations and safety limits.
2.
Equipment Control Subtotal                                                                                        1 2.3.4    Knowledge of radiation exposure limits under normal or                      3.7       22 emergency conditions.
2.3.11  Ability to control radiation releases                                       4.3       23 3.
Radiation Control Subtotal                                                                                        2 2.4.1    Knowledge of EOP entry conditions and immediate actions                      4.8       24 steps.
4.
2.4.44  Knowledge of Emergency Plan protective action                                4.4       25 Emergency recommendations.
Procedures /
Plan Subtotal                                                                                        2 Tier 3 Point Total                                                                                                 7 ES-401                                                  6                                    Form ES-401-2
 
ES-401                  Record of Rejected K/As              Form ES-401-4 Tier /   Randomly                      Reason for Rejection Group    Selected K/A None   None           None}}

Latest revision as of 08:51, 14 November 2019

2009-01-Final-Outlines
ML090490233
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 02/02/2009
From:
NRC Region 4
To:
Entergy Operations
References
Download: ML090490233 (7)
v • d • e


Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Arkansas Nuclear One - Unit 1 Date of Exam: 1/28/2009 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

  • Total
1. 1 0 0 0 0 0 0 0 3 3 6 Emergency &

Abnormal 2 0 0 0 N/A 0 0 N/A 0 0 2 2 4 Plant Evolutions Tier Totals 0 0 0 0 0 0 0 5 5 10 1 0 0 0 0 0 0 0 0 0 0 0 0 3 2 5 2.

Plant 2 0 0 0 0 0 0 0 0 0 0 0 0 0 2 1 3 Systems Tier Totals 0 0 0 0 0 0 0 0 0 0 0 0 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 0 1 2 3 4 7 Categories 0 0 0 0 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).
2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

ES-401 1 Form ES-401-2

ES-401 2 Form ES-401-2 E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 000007 (BW/E02&E10; CE/E02) Reactor Not selected n/a n/a Trip - Stabilization - Recovery / 1 000008 Pressurizer Vapor Space X AA2.30 - Inadequate core cooling 4.7 1 Accident / 3 000009 Small Break LOCA / 3 Not selected n/a n/a 000011 Large Break LOCA / 3 Not selected n/a n/a 000015/17 RCP Malfunctions / 4 Not selected n/a n/a 000022 Loss of Rx Coolant Makeup / 2 Not selected n/a n/a 000025 Loss of RHR System / 4 Not selected n/a n/a 000026 Loss of Component Cooling Not selected n/a n/a Water / 8 000027 Pressurizer Pressure Control Not selected n/a n/a System Malfunction / 3 000029 ATWS / 1 Not selected n/a n/a 000038 Steam Gen. Tube Rupture / 3 Not selected n/a n/a 000040 (BW/E05; CE/E05; W/E12) X EA2.2 - Adherence to appropriate 4.0 2 Steam Line Rupture - Excessive Heat procedures and operation within the Transfer / 4 limitations in the facilitys license and amendments.

000054 (CE/E06) Loss of Main X AA2.01 - Occurrence of Reactor and / or 4.4 3 Feedwater / 4 Turbine Trip.

000055 Station Blackout / 6 X 2.4.4 - Ability to recognize abnormal 4.7 4 indications for system operating parameters that are entry - level conditions for emergency and abnormal operating procedures.

000056 Loss of Off-site Power / 6 Not selected n/a n/a 000057 Loss of Vital AC Inst. Bus / 6 Not selected n/a n/a 000058 Loss of DC Power / 6 X 2.2.22 - Knowledge of limiting conditions 4.7 5 for operations and safety limits.

000062 Loss of Nuclear Svc Water / 4 X 2.1.23 - Ability to perform specific system 4.4 6 and integrated plant procedures during all modes of plant operation.

000065 Loss of Instrument Air / 8 Not selected n/a n/a W/E04 LOCA Outside Containment / 3 Not selected n/a n/a W/E11 Loss of Emergency Coolant Not selected n/a n/a Recirc. / 4 BW/E04; W/E05 Inadequate Heat Not selected n/a n/a Transfer - Loss of Secondary Heat Sink / 4 000077 Generator Voltage and Electric Not selected n/a n/a Grid Disturbances / 6 K/A Category Totals: 3 3 Group Point Total: 6 ES-401 2 Form ES-401-2

ES-401 3 Form ES-401-2 E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 Not selected n/a n/a 000003 Dropped Control Rod / 1 Not selected n/a n/a 000005 Inoperable/Stuck Control Rod / 1 Not selected n/a n/a 000024 Emergency Boration / 1 Not selected n/a n/a 000028 Pressurizer Level Malfunction / 2 Not selected n/a n/a 000032 Loss of Source Range NI / 7 Not selected n/a n/a 000033 Loss of Intermediate Range NI / 7 X AA2.07 - Confirmation of reactor 4.2 7 trip.

000036 (BW/A08) Fuel Handling Accident / 8 Not selected n/a n/a 000037 Steam Generator Tube Leak / 3 Not selected n/a n/a 000051 Loss of Condenser Vacuum / 4 Not selected n/a n/a 000059 Accidental Liquid RadWaste Rel. / 9 Not selected n/a n/a 000060 Accidental Gaseous Radwaste Rel. / 9 Not selected n/a n/a 000061 ARM System Alarms / 7 Not selected n/a n/a 000067 Plant Fire On-site / 8 X 2.2.40 - Ability to apply Technical 4.7 8 Specifications for a system.

000068 (BW/A06) Control Room Evac. / 8 Not selected n/a n/a 000069 (W/E14) Loss of CTMT Integrity / 5 Not selected n/a n/a 000074 (W/E06&E07) Inad. Core Cooling / 4 Not selected n/a n/a 000076 High Reactor Coolant Activity / 9 X 2.4.41 - Knowledge of the 4.6 9 Emergency Action Level thresholds and classifications.

W/EO1 & E02 Rediagnosis & SI Termination / 3 Not selected n/a n/a W/E13 Steam Generator Over-pressure / 4 Not selected n/a n/a W/E15 Containment Flooding / 5 Not selected n/a n/a W/E16 High Containment Radiation / 9 Not selected n/a n/a BW/A01 Plant Runback / 1 Not selected n/a n/a BW/A02&A03 Loss of NNI-X/Y / 7 Not selected n/a n/a BW/A04 Turbine Trip / 4 Not selected n/a n/a BW/A05 Emergency Diesel Actuation / 6 Not selected n/a n/a BW/A07 Flooding / 8 Not selected n/a n/a BW/E03 Inadequate Subcooling Margin / 4 Not selected n/a n/a BW/E08; W/E03 LOCA Cooldown - Depress. / 4 Not selected n/a n/a BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 Not selected n/a n/a BW/E13&E14 EOP Rules and Enclosures X EA2.1 - Facility conditions and 4.0 10 selection of appropriate procedures during abnormal and emergency operations.

CE/A11; W/E08 RCS Overcooling - PTS / 4 Not selected n/a n/a CE/A16 Excess RCS Leakage / 2 Not selected n/a n/a CE/E09 Functional Recovery Not selected n/a n/a K/A Category Point Totals: 0 0 0 0 2 2 Group Point Total: 4 ES-401 3 Form ES-401-2

ES-401 4 Form ES-401-2 K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump X 2.4.9 - Knowledge of low power / 4.2 11 shutdown implications in accident (e.g. loss of coolant accident or loss of residual heat removal) mitigation strategies.

004 Chemical and Volume Not selected n/a n/a Control 005 Residual Heat Removal Not selected n/a n/a 006 Emergency Core Cooling X 2.2.42 - Ability to recognize 4.6 12 system parameters that are entry-level conditions for Technical Specifications.

007 Pressurizer Relief/Quench Not selected n/a n/a Tank 008 Component Cooling Water Not selected n/a n/a 010 Pressurizer Pressure X A2.02 - Spray valve failures. 3.9 13 Control 012 Reactor Protection Not selected n/a n/a 013 Engineered Safety Not selected n/a n/a Features Actuation 022 Containment Cooling Not selected n/a n/a 025 Ice Condenser Not selected n/a n/a 026 Containment Spray Not selected n/a n/a 039 Main and Reheat Steam Not selected n/a n/a 059 Main Feedwater X A2.04 - Feeding a dry S/G. 3.4 14 061 Auxiliary/Emergency Not selected n/a n/a Feedwater 062 AC Electrical Distribution Not selected n/a n/a 063 DC Electrical Distribution X A2.02 - Loss of ventilation during 3.1 15 battery charging.

064 Emergency Diesel Not selected n/a n/a Generator 073 Process Radiation Not selected n/a n/a Monitoring 076 Service Water Not selected n/a n/a 078 Instrument Air Not selected n/a n/a 103 Containment Not selected n/a n/a K/A Category Point Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 ES-401 4 Form ES-401-2

ES-401 5 Form ES-401-2 System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive Not selected n/a n/a 002 Reactor Coolant Not selected n/a n/a 011 Pressurizer Level Control Not selected n/a n/a 014 Rod Position Indication X 2.2.22 - Knowledge of limiting 4.7 16 condition for operations and safety limits.

015 Nuclear Instrumentation Not selected n/a n/a 016 Non-nuclear Instrumentation X A2.01 - Detector failure 3.1* 17 017 In-core Temperature Monitor Not selected n/a n/a 027 Containment Iodine Removal Not selected n/a n/a 028 Hydrogen Recombiner Not selected n/a n/a and Purge Control 029 Containment Purge Not selected n/a n/a 033 Spent Fuel Pool Cooling Not selected n/a n/a 034 Fuel Handling Equipment Not selected n/a n/a 035 Steam Generator Not selected n/a n/a 041 Steam Dump/Turbine Not selected n/a n/a Bypass Control 045 Main Turbine Generator Not selected n/a n/a 055 Condenser Air Removal Not selected n/a n/a 056 Condensate X A2.04 - Loss of condensate 2.8* 18 pumps.

068 Liquid Radwaste Not selected n/a n/a 071 Waste Gas Disposal Not selected n/a n/a 072 Area Radiation Monitoring Not selected n/a n/a 075 Circulating Water Not selected n/a n/a 079 Station Air Not selected n/a n/a 086 Fire Protection Not selected n/a n/a K/A Category Point Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 ES-401 5 Form ES-401-2

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Category K/A # Topic RO SRO IR # IR #

2.1.35 Knowledge of the fuel-handling responsibilities of SROs. 3.9 19 2.1.36 Knowledge of procedures and limitation involved in core 4.1 20 1.

alterations.

Conduct of Operations Subtotal 2 2.2.25 Knowledge of the bases in Technical Specifications for limiting 4.2 21 conditions for operations and safety limits.

2.

Equipment Control Subtotal 1 2.3.4 Knowledge of radiation exposure limits under normal or 3.7 22 emergency conditions.

2.3.11 Ability to control radiation releases 4.3 23 3.

Radiation Control Subtotal 2 2.4.1 Knowledge of EOP entry conditions and immediate actions 4.8 24 steps.

4.

2.4.44 Knowledge of Emergency Plan protective action 4.4 25 Emergency recommendations.

Procedures /

Plan Subtotal 2 Tier 3 Point Total 7 ES-401 6 Form ES-401-2

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A None None None

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