ML14111A352

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2014-03-Final Outlines
ML14111A352
Person / Time
Site: River Bend Entergy icon.png
Issue date: 03/27/2014
From: Vincent Gaddy
Operations Branch IV
To:
Entergy Operations
laura hurley
References
50-458/14-003
Download: ML14111A352 (31)
v • d • e


Text

ES-401BWR Examination OutlineForm ES-401-1Facility: River Bend StationDate of Exam: March 2014TierGroupRO K/A Category PointsSRO-Only Points 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 1.Emergency &Abnormal PlantEvolutions 13 3 4N/A4 3N/A 3 20 3 4 7 21 1 21 1 1 7 2 1 3Tier Totals4 4 65 4 4 27 5 5 10 2.PlantSystems 13 2 2 2 2 2 3 2 2 3 3 26 3 2 5 22 1 1 1 1 1 1 1 1 1 1 12 2 1 3Tier Totals5 3 3 3 3 3 4 3 3 4 4 38 5 3 83. Generic Knowledge and AbilitiesCategories 1 2 3 4 10 1 2 3 4 7 3 2 2 3 2 2 1 2Note: 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).

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 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.

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.

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.

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.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 2Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO/ SRO)E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)

IR#295001 Partial or Complete Loss of ForcedCore Flow Circulation / 1 & 4 XAbility to operate and/or monitor the followingas they apply to Partial or Complete Loss ofForced Core Flow Circulation:AA1.05 Recirculation flow control systemCFR: 41.7 3.3 1295003 Partial or Complete Loss of AC / 6 X2.1.20 Ability to interpret and executeprocedure steps.CFR: 41.10 4.6 2295004 Partial or Total Loss of DC Pwr / 6 XAbility to operate and/or monitor the followingas they apply to Partial or Complete Loss ofD.C. Power:AA1.02 Systems necessary to assure safe plantshutdownCFR: 41.7 3.8 3295005 Main Turbine Generator Trip / 3 XKnowledge of the interrelations between MainTurbine Generator Trip and the following:AK2.08 A.C. electrical distribution 3.2 4295006 SCRAM / 1 XKnowledge of the following concepts as theyapply to SCRAM:AK1.03 Reactivity controlCFR: 41.8-41.10 3.7 5295016 Control Room Abandonment / 7 X2.4.34 Knowledge of RO tasks performedoutside the main control room during anemergency and the resultant operationaleffects.CFR: 41.10 4.2 6295018 Partial or Total Loss of CCW / 8 XAbility to determine and/or interpret thefollowing as they apply to Partial or CompleteLoss of Component Cooling Water:AA2.03 Cause for partial or complete lossCFR: 41.10 3.2 7295019 Partial or Total Loss of Inst. Air / 8 XKnowledge of the interrelations between Partialor Complete Loss of Instrument Air and thefollowing:AK2.02 Component cooling waterCFR: 41.7 2.9 8 295021 Loss of Shutdown Cooling / 4 XKnowledge of the reasons for the followingresponses as they apply to Loss of ShutdownCooling:AK3.05 Establishing alternate heat removalflowpaths.CFR: 41.5 3.6 9295023 Refueling Acc / 8 XKnowledge of the operational implications ofthe following concepts as they apply toRefueling Accidents:AK1.03 Inadvertent criticalityCFR: 41.8-41.10 3.7 10295024 High Drywell Pressure / 5 XKnowledge of the reasons for the followingresponses as they apply to High DrywellPressure:EK3.03 Containment venting: Mark IIICFR: 41.5 3.6 11295025 High Reactor Pressure / 3 XAbility to determine and/or interpret thefollowing as they apply to High ReactorPressure:EA2.02 Reactor powerCFR: 41.74.2* 12295026 Suppression Pool High WaterTemp. / 5 XAbility to operate and/or monitor the followingas they apply to Suppression Pool High WaterTemperature:EA1.01 Suppression pool coolingCFR: 41.7 4.1 13295027 High Containment Temperature / 5 X2.4.4 Ability to recognize abnormal indicationsfor system operating parameters that are entry-level conditions for emergency and abnormaloperating procedures.CFR: 41.10 4.5 14295028 High Drywell Temperature / 5 XKnowledge of the operational implications ofthe following concepts as they apply to HighDrywell Temperature:EK1.01 Reactor water level measurementCFR: 41.8-41.10 3.5 15295030 Low Suppression Pool Wtr Lvl / 5295031 Reactor Low Water Level / 2 XKnowledge of the reasons for the followingresponses as they apply to Reactor Low WaterLevel:EK3.01 Automatic depressurization systemactuationCFR: 41.5 3.9 16 295037 SCRAM Condition Presentand Reactor Power Above APRMDownscale or Unknown / 1 XAbility to determine and/or interpret thefollowing as they apply to Scram ConditionPresent and Reactor Power above APRMDownscale or Unknown:EA2.03 SBLC tank levelCFR: 41.104.3* 17295038 High Off-site Release Rate / 9 XKnowledge of the interrelations between HighOff-Site Release Rate and the following:EK2.04 Stack-gas monitoring system: Plant-specificCFR: 41.7 3.9 18600000 Plant Fire On Site / 8 XAbility to operate and/or monitor the followingas they apply to Plant Fire On Site:AA1.06 Fire Alarm 3.0 19700000 Generator Voltage and Electric GridDisturbances / 6 XKnowledge of the reasons for the followingresponses as they apply to Generator Voltageand Electric Grid Disturbances:AK3.01 Reactor and turbine trip criteriaCFR: 41.4, 41.5, 41.7, 41.10 3.9 20K/A Category Totals:

3 3 4 4 3 3Group Point Total:20/7 ES-401 2Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO /SRO)E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)

IR#295001 Partial or Complete Loss of ForcedCore Flow Circulation / 1 & 4 X2.1.23 Ability to perform specific system andintegrated plant procedures during all modesof plant operation.CFR: 43.5 4.4 76295003 Partial or Complete Loss of AC / 6295004 Partial or Total Loss of DC Pwr / 6295005 Main Turbine Generator Trip / 3295006 SCRAM / 1 XAbility to determine and/or interpret thefollowing as they apply to SCRAM:AA2.01 Reactor powerCFR: 43.5 4.6*77295016 Control Room Abandonment / 7 XAbility to determine and/or interpret thefollowing as they apply to CONTROL ROOMABANDONMENT:AA 2.01 Reactor Power CFR 43.5 4.1 79295018 Partial or Total Loss of CCW / 8 X2.4.45 Ability to prioritize and interpret thesignificance of each annunciator or alarm.CFR: 43.5 4.3 78295019 Partial or Total Loss of Inst. Air / 8295021 Loss of Shutdown Cooling / 4295023 Refueling Acc / 8295024 High Drywell Pressure / 5295025 High Reactor Pressure / 3 X2.4.21 Knowledge of the parameters and logicused to assess the status of safety functions,such as reactivity control, core cooling andheat removal, reactor coolant system integrity,containment conditions, radioactivity releasecontrol, etc.CFR: 43.5 4.6 80295026 Suppression Pool High WaterTemp. / 5295027 High Containment Temperature / 5295028 High Drywell Temperature / 5295030 Low Suppression Pool Wtr Lvl / 5 X2.4.50 Ability to verify system alarm setpointsand operate controls identified in the alarmresponse manual.

4.0 81 295031 Reactor Low Water Level / 2 XAbility to determine and/or interpret thefollowing as they apply to Reactor Low WaterLevel:EA2.03 Reactor pressure 4.2*82295037 SCRAM Condition Presentand Reactor Power Above APRMDownscale or Unknown / 1295038 High Off-site Release Rate / 9600000 Plant Fire On Site / 8700000 Generator Voltage and Electric GridDisturbances / 6K/A Category Totals:

3 4Group Point Total:20/7 ES-401 3Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO)E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)

IR#295002 Loss of Main Condenser Vac / 3 XKnowledge of the reasons for the followingresponses as they apply to Loss of MainCondenser Vacuum:AK3.09 Reactor power reductionCFR: 41.5 3.2 21295007 High Reactor Pressure / 3 X2.2.44 Ability to interpret control roomindications to verify the status and operation ofa system, and understand how operator actionsand directives affect plant and systemconditions.CFR: 41.5 4.2 22295008 High Reactor Water Level / 2 XKnowledge of the operational implications of thefollowing concepts as they apply to HighContainment Temperature (Mark III ContainmentOnly):AK1.01 Containment pressure: Mark IIICFR: 41.8-141.104.0* 23295009 Low Reactor Water Level / 2295010 High Drywell Pressure / 5295011 High Containment Temp / 5295012 High Drywell Temperature / 5295013 High Suppression Pool Temp. / 5295014 Inadvertent Reactivity Addition / 1295015 Incomplete SCRAM / 1 XAbility to determine and/or interpret thefollowing as they apply to Incomplete Scram:AA2.02 Control rod positionCFR: 41.104.1* 24295017 High Off-site Release Rate / 9295020 Inadvertent Cont. Isolation / 5 & 7295022 Loss of CRD Pumps / 1295029 High Suppression Pool Wtr Lvl / 5 XKnowledge of the interrelations between HighSuppression Pool Water Level and the following:EK 2.06 SRVs and discharge pipingCFR: 41.7 3.4 25295032 High Secondary ContainmentArea Temperature / 5295033 High Secondary ContainmentArea Radiation Levels / 9 295034 Secondary ContainmentVentilation High Radiation / 9295035 Secondary Containment HighDifferential Pressure / 5295036 Secondary Containment HighSump/Area Water Level / 5 XAbility to operate and/or monitor the followingas they apply to Secondary Containment HighSump/Area Water Level:EA1.03 RadwasteCFR: 41.7 2.8 26500000 High CTMT Hydrogen Conc. / 5 XKnowledge of the reasons for the followingresponses as they apply to High PrimaryContainment Hydrogen Concentrations:EK3.03 Operation of hydrogen and oxygenrecombinersCFR: 41.5 3.0 27K/A Category Point Totals:

1 1 2 1 1 1Group Point Total:

7/3 ES-401 3Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO /SRO)E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)

IR#295002 Loss of Main Condenser Vac / 3295007 High Reactor Pressure / 3295008 High Reactor Water Level / 2295009 Low Reactor Water Level / 2 X2.4.6 Knowledge of EOP mitigation strategies.CFR: 43.5 4.7 83295010 High Drywell Pressure / 5295011 High Containment Temp / 5295012 High Drywell Temperature / 5295013 High Suppression Pool Temp. / 5295014 Inadvertent Reactivity Addition / 1295015 Incomplete SCRAM / 1295017 High Off-site Release Rate / 9295020 Inadvertent Cont. Isolation / 5 & 7 XAbility to determine and/or interpret the followingas they apply to Inadvertent ContainmentIsolation:AA2.02 Drywell/containment temperatureCFR: 43.5 3.4 84295022 Loss of CRD Pumps / 1295029 High Suppression Pool Wtr Lvl / 5295032 High Secondary ContainmentArea Temperature / 5295033 High Secondary ContainmentArea Radiation Levels / 9295034 Secondary ContainmentVentilation High Radiation / 9 XAbility to determine and/or interpret the followingas they apply to Secondary ContainmentVentilation High Radiation:EA2.01 Ventilation radiation levelsCFR: 43.5 4.2 85295035 Secondary Containment HighDifferential Pressure / 5295036 Secondary Containment HighSump/Area Water Level / 5500000 High CTMT Hydrogen Conc. / 5K/A Category Point Totals:

2 1Group Point Total:

7/3 ES-401 4Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Plant Systems - Tier 2/Group 1 (RO / 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)

IR#203000 RHR/LPCI: InjectionMode XKnowledge of the operationalimplications of the following concepts asthey apply to RHR/LPCI: Injection Mode(Plant Specific):K5.02 Core cooling methodsCFR: 41.5 3.5 28205000 Shutdown Cooling XKnowledge of the electrical powersupplies to the following:K2.01 Pump motorsCFR: 41.73.1* 29206000 HPCI207000 Isolation (Emergency)Condenser209001 LPCS X XAbility to (a) predict the impacts of thefollowing on the Low Pressure CoreSpray System; and (b) based on thosepredictions, use procedures to correct,control, or mitigate the consequences ofthose abnormal conditions or operations:A2.06 Inadequate system flowCFR: 41.5Ability to manually operate and/ormonitor in the control room:A4.07 Fill pumpCFR: 41.7 3.2 2.7 30 31209002 HPCS XKnowledge of the physical connectionsand/or cause-effect relationshipsbetween High Pressure Core SpraySystem (HPCS) and the following:K1.04 HPCS diesel generator: BWR-5,6CFR: 41.2-41.9 3.8 32211000 SLC XAbility to predict and/or monitor changesin parameters associated with operatingthe Standby Liquid Control Systemcontrols including:A1.09 SBLC system lineupCFR: 41.54.0* 33 212000 RPS X XKnowledge of the effect that a loss ormalfunction of the Reactor ProtectionSystem will have on the following:K3.06 Scram air header solenoid operatedvalvesCFR: 41.72.1.28 Knowledge of the purpose andfunction of major system componentsand controls.CFR: 41.7 4.0 4.1 34 35215003 IRM XKnowledge of the operationalimplications of the following concepts asthey apply to Intermediate Range Monitor(IRM) System:K5.01 Detector operationCFR: 41.5 2.6 36215004 Source Range Monitor XKnowledge of the effect that a loss ormalfunction of the following will have onthe Source Range Monitor (SRM) System:K6.01 RPSCFR: 41.7 3.2 37215005 APRM / LPRM XKnowledge of the physical connectionsand/or cause-effect relationshipsbetween Average Power RangeMonitor/Local Power Range MonitorSystem and the following:K1.09 Reactor recirculation system:BWR-5,6CFR: 41.2-41.9 3.6 38217000 RCIC XAbility to monitor automatic operationsof the Reactor Core Isolation CoolingSystem (RCIC) including:A3.03 System pressureCFR: 41.7 3.7 39218000 ADS XKnowledge of the effect that a loss ormalfunction of the following will have onthe Automatic Depressurization System:K6.07 Primary containment instrumentationCFR: 41.7 3.4 40223002 PCIS/Nuclear SteamSupply Shutoff XKnowledge of Primary ContainmentIsolation System/Nuclear Steam SupplyShut-Off design feature(s) and/orinterlocks which provide for thefollowing:K4.08 Manual defeating of selectedisolations during specified emergencyconditions.CFR: 41.7 3.3 41 239002 SRVs XAbility to manually operate and/ormonitor in the control room:A4.02 Tail pipe temperaturesCFR: 41.7 3.6 42259002 Reactor Water LevelControl X XKnowledge of Reactor Water LevelControl System design feature(s) and/orinterlocks which provide for thefollowing:K4.10 Three element control (main steamflow, reactor feedwater flow, and reactorwater level provide input)CFR: 41.72.1.32 Ability to explain and apply systemlimits and precautions.CFR: 41.10 3.4 3.8 43 44261000 SGTS XAbility to predict and/or monitor changesin parameters associated with operatingthe Standby Gas Treatment Systemcontrols including:A1.02 Primary containment pressureCFR: 41.5 3.1 45262001 AC ElectricalDistribution XKnowledge of the effect that a loss ormalfunction of the A.C. ElectricalDistribution will have on the following:K3.01 Major system loadsCFR: 41.7 3.5 46262002 UPS (AC/DC)

XAbility to monitor automatic operationsof the Uninterruptable Power Supply(A.C./D.C.) including:A3.01 Transfer from preferred to alternatesource.CFR: 41.7 2.8 47263000 DC ElectricalDistribution X XAbility to predict and/or monitor changesin parameters associated with operatingthe D.C. Electrical Distribution controlsincluding:A1.01 Battery charging/discharging rateCFR: 41.52.4.31 Knowledge of annunciator alarms,indications, or response procedures.CFR: 41.10 2.5 4.2 48 49 264000 EDGs X XKnowledge of the physical connectionsand/or cause-effect relationshipsbetween Emergency Generators(Diesel/Jet) and the following:K1.04 Emergency generator cooling watersystem.CFR: 41.2-41.9Ability to (a) predict the impacts of thefollowing on the Emergency Generators(Diesel/Jet); and (b) based on thosepredictions, use procedures to correct,control, or mitigate the consequences ofthose abnormal conditions or operations:A2.06 Opening normal and/or alternatepower to emergency bus.CFR: 41.5 3.2 3.4 50 51300000 Instrument Air XKnowledge of the electrical powersupplies to the following:K2.02 Emergency air compressorCFR: 41.7 3.0 52400000 Component CoolingWater XAbility to manually operate and/ormonitor in the control room:A4.01 CCW indications and controlCFR: 41.7 3.1 53K/A Category Point Totals:

3 2 2 2 2 2 3 2 2 3 3Group Point Total:26/5 ES-401 4Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Plant Systems - Tier 2/Group 1 (RO /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)

IR#203000 RHR/LPCI: InjectionMode205000 Shutdown Cooling206000 HPCI207000 Isolation (Emergency)Condenser209001 LPCS209002 HPCS211000 SLC XAbility to (a) predict the impacts of thefollowing on the Standby Liquid ControlSystem; and (b) based on thosepredictions, use procedures to correct,control or mitigate the consequences ofthose abnormal conditions or operations:A2.03 A.C. power failures 3.4*86212000 RPS215003 IRM215004 Source Range Monitor215005 APRM / LPRM217000 RCIC218000 ADS X2.2.40 Ability to apply TechnicalSpecifications for a system.CFR: 43.2, 43.5 4.7 87223002 PCIS/Nuclear SteamSupply Shutoff239002 SRVs XAbility to (a) predict the impacts of thefollowing on the Relief/Safety Valves; and(b) based on those predictions, useprocedures to correct, control or mitigatethe consequences of those abnormalconditions or operations:A2.06 Reactor high pressure 4.3*88259002 Reactor Water LevelControl261000 SGTS262001 AC ElectricalDistribution 262002 UPS (AC/DC)

XAbility to (a) predict the impacts of thefollowing on the Uninterruptable PowerSupply (A.C./D.C.); and (b) based onthose predictions, use procedures tocorrect, control, or mitigate theconsequences of those abnormalconditions or operations:A2.02 Over voltage 2.7 89263000 DC ElectricalDistribution264000 EDGs300000 Instrument Air400000 Component CoolingWater X2.4.11 Knowledge of abnormal conditionprocedures.CFR: 43.5 4.2 90K/A Category Point Totals:

3 2Group Point Total:26/5 ES-401 5Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Plant Systems - Tier 2/Group 2 (RO / 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)

IR#201001 CRD Hydraulic XKnowledge of electrical powersupplies to the following:K2.05 Alternate rod insertion valvesolenoids: Plant-SpecificCFR: 41.7 4.5*54201002 RMCS201003 Control Rod and DriveMechanism201004 RSCS201005 RCIS XAbility to (a) predict the impacts ofthe following on the Rod Control andInformation System (RCIS); and (b)based on those predictions, useprocedures to correct, control, ormitigate the consequences of thoseabnormal conditions or operations:A2.12 Rod uncoupled: BWR-6CFR: 41.5 3.7 55201006 RWM202001 Recirculation202002 Recirculation Flow Control XAbility to predict and/or monitorchanges in parameters associatedwith operating the RecirculationFlow Control System controlsincluding:A1.08 Recirculation FCV position 3.4 56204000 RWCU XAbility to manually operate and/ormonitor in the control room:A4.04 Heat exchanger operationCFR: 41.7 2.8 57214000 RPIS215001 Traversing In-core Probe215002 RBM216000 Nuclear Boiler Inst.219000 RHR/LPCI: Torus/Pool Cooling Mode XAbility to monitor automaticoperations of the RHR/LPCI:Torus/Suppression Pool CoolingMode including:A3.01 Valve operationCFR: 41.7 3.3 58223001 Primary CTMT and Aux.226001 RHR/LPCI: CTMT Spray Mode230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup XKnowledge of Fuel Pool Cooling andClean-Up design feature(s) and/orinterlocks which provide for thefollowing:K4.06 Maintenance of adequate poollevel.CFR: 41.7 2.9 59234000 Fuel Handling Equipment239001 Main and Reheat Steam239003 MSIV Leakage Control241000 Reactor/Turbine PressureRegulator245000 Main Turbine Gen. / Aux.256000 Reactor Condensate XKnowledge of the effect that a lossor malfunction of the ReactorCondensate System will have on thefollowing:K3.02 CRD hydraulics systemCFR: 41.7 3.2 60259001 Reactor Feedwater268000 Radwaste271000 Offgas XKnowledge of the operationalimplications of the followingconcepts as they apply to OffgasSystem:K5.07 Radioactive decayCFR: 41.7 2.7 61272000 Radiation Monitoring286000 Fire Protection XKnowledge of the physicalconnections and/or cause-effectrelationships between FireProtection System and the following:K1.03 Reactor water levelCFR: 41.2-41.9 2.9 62288000 Plant Ventilation X2.1.30 Ability to locate and operatecomponents, including localcontrols.CFR: 41.7 4.4 63290001 Secondary CTMT XKnowledge of the effect that a lossor malfunction of the following willhave on the SecondaryContainment:K6.04 Primary containment systemCFR: 41.7 3.9 64290003 Control Room HVAC290002 Reactor Vessel Internals XKnowledge of the physicalconnections and/or cause-effectrelationships between ReactorVessel Internals and the following:K1.06 HPCS: Plant-SpecificCFR: 41.2-41.9 3.1 65 K/A Category Point Totals:

2 1 1 1 1 1 11 1 1 1Group Point Total:

12/3 ES-401 5Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Plant Systems - Tier 2/Group 2 (RO /

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)

IR#201001 CRD Hydraulic201002 RMCS201003 Control Rod and DriveMechanism XAbility to (a) predict the impacts ofthe following on the Control Rod andDrive Mechanism; and (b) based onthose predictions, use procedures tocorrect, control or mitigate theconsequences of those abnormalconditions or operations:A2.09 Low reactor pressure 3.4 91201004 RSCS201005 RCIS201006 RWM202001 Recirculation202002 Recirculation Flow Control204000 RWCU214000 RPIS215001 Traversing In-core Probe215002 RBM216000 Nuclear Boiler Inst.219000 RHR/LPCI: Torus/Pool Cooling Mode223001 Primary CTMT and Aux.

XAbility to (a) predict the impacts ofthe following on the PrimaryContainment System andAuxiliaries; and (b) based on thosepredictions, use procedures tocorrect, control, or mitigate theconsequences of those abnormalconditions or operations:A2.06 High containment pressure:Mark-III 4.1*92226001 RHR/LPCI: CTMT Spray Mode230000 RHR/LPCI: Torus/Pool Spray Mode233000 Fuel Pool Cooling/Cleanup234000 Fuel Handling Equipment239001 Main and Reheat Steam239003 MSIV Leakage Control241000 Reactor/Turbine PressureRegulator245000 Main Turbine Gen. / Aux.256000 Reactor Condensate 259001 Reactor Feedwater X2.4.46 Ability to verify that thealarms are consistent with the plantconditions.CFR: 43.5 4.2 93268000 Radwaste271000 Offgas272000 Radiation Monitoring286000 Fire Protection288000 Plant Ventilation290001 Secondary CTMT290003 Control Room HVAC290002 Reactor Vessel InternalsK/A Category Point Totals:

2 1Group Point Total:

12/3 ES-401Generic Knowledge and Abilities Outline (Tier 3)Form ES-401-3 Facility: Date of Exam:CategoryK/A #Topic ROSRO-Only IR#IR#1.Conductof Operations 2.1.2Knowledge of operator responsibilities during all modes ofplant operation.CFR: 41.10 4.1 66 2.1.15Knowledge of administrative requirements for temporarymanagement directives, such as standing orders, nightorders, operations memos, etc.CFR: 41.10 2.7 67 2.1.44Knowledge of RO duties in the control room during fuelhandling such as responding to alarms from the fuelhandling area, communication with the fuel storagefacility, systems operated from the control room insupport of fueling operations, and supportinginstrumentation.CFR: 41.10 3.9 68 2.1.4Knowledge of individual licensed operatorresponsibilities related to shift staffing, such asmedical requirements, "no-solo" operation,maintenance of active license status, 10CFR55, etc.CFR: 43.2 3.8 94 2.1.41Knowledge of the refueling process.CFR: 43.6 3.7 95Subtotal 3 2 2.EquipmentControl 2.2.6Knowledge of the process for making changes toprocedures.CFR: 41.10 3.0 69 2.2.14Knowledge of the process for controlling equipmentconfiguration or status.CFR: 41.10 3.9 70 2.2.7Knowledge of the process for conducting special orinfrequent tests.CFR: 43.3 3.6 96 2.2.20Knowledge of the process for managingtroubleshooting activities.CFR: 43.5 3.8 97Subtotal 2 2 3.Radiation 2.3.12Knowledge of radiological safety principles pertaining tolicensed operator duties, such as containment entryrequirements, fuel handling responsibilities, access tolocked high-radiation areas, aligning filters, etc.CFR: 41.12 3.2 71 Control 2.3.14Knowledge of radiation or contamination hazards thatmay arise during normal, abnormal, or emergencyconditions or activities.CFR: 41.12 3.4 72 2.3.11Ability to control radiation releases.CFR: 43.4 4.3 98Subtotal 2 1 4.EmergencyProcedures /

Plan 2.4.5Knowledge of the organization of the operatingprocedures network for normal, abnormal, andemergency evolutions.CFR: 41.10 3.7 73 2.4.13Knowledge of crew roles and responsibilities during EOPusage.CFR: 41.10 4.0 74 2.4.37Knowledge of the lines of authority during implementationof the emergency plan.CFR: 41.10 3.0 75 2.4.22Knowledge of the bases for prioritizing safetyfunctions during abnormal/emergency operations.CFR: 43.5 4.4 99 2.4.42Knowledge of emergency response facilities.

3.8 100Subtotal 3 2Tier 3 Point Total 10 7 ES-401Record of Rejected K/AsForm ES-401-4Tier /GroupRandomlySelected K/AReason for Rejection 1/1 RO295021 AK3.04This function is not performed in the off-normal procedure.Randomly reselected KA 295021 AK3.05 1/2 RO295029 EK2.05This KA is rejected because it refers to a component not used in theRiver Bend Station design. Randomly reselected KA 295029 EK2.06 1/2 RO500000 EK3.05This KA is rejected because it refers to a component not used in theRiver Bend Station design. Randomly reselected KA 500000 EK3.03 2/2 RO202002 A1.01This KA is rejected because no credible tie for this KA exists forthe system. Randomly reselected KA 202002 A1.08 2/2 RO286000 K1.05This KA is rejected because no credible tie for this KA exists forthe system. Randomly reselected KA 286000 K1.031/1 SRO 295030 G.2.4.2This KA rejected due to inability to write an SRO-only question forthis RO level knowledge KA (EOP entry conditions). Randomlyreselected KA 295030 G.2.4.502/1 SRO 400000 G.2.2.37This KA rejected because no credible tie for this KA exists for thesystem. (CCW is not safety related, therefore no operabilityrequirements).Randomly reselected 400000 G.2.4.11.1/1 SRO 295025 EA 2.06This KA rejected due to oversampling (compare with Q80).Randomly reselected 296016 AA2.01 NRCES-301Administrative Topics OutlineForm ES-301-1Facility: RIVER BEND STATIONDate of Examination: 3/24/2014Examination Level: RO SROOperating Test Number: __________Administrative Topic (see Note)Type Code*Describe activity to be performedConduct of OperationsR, M(A1) Perform Jet Pump Operability (STP-053-3001)KA 2.1.20, 2.1.25Conduct of OperationsR, N(A2) Verify Thermal Power and Loop Flow for SingleLoop Ops per GOP-0004 Steps 4.1-4.3KA 2.1.7Equipment ControlR, N(A3) Perform Hand Written Tagout for HVT-UC12Turbine Building Unit CoolerKA 2.2.13Radiation ControlR, N(A4) Determine Radiological Brief and ProtectiveClothing RequirementsKA 2.3.7Emergency Procedures/PlanNOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they areretaking only the administrative topics, when all 5 are required.* Type Codes & Criteria:(C)ontrol room, (S)imulator, or Class(R)oom(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)(N)ew or (M)odified from bank ( 1)(P)revious 2 exams ( 1; randomly selected)

NRCES-301Administrative Topics OutlineForm ES-301-1Facility: RIVER BEND STATIONDate of Examination: 3/24/2014Examination Level: RO SROOperating Test Number: __________Administrative Topic (see Note)Type Code*Describe activity to be performedConduct of OperationsR, N(A5) Determine the Heat Up Rate and the Time to Top of Active Fuel during a Loss of Shutdown CoolingKA 2.1.25Conduct of OperationsR, M(A6) Determine personnel callout availabilityKA 2.1.5Equipment ControlR, N(A7) Review manual Tagout of HVT-UC12.KA 2.2.13Radiation ControlR, N(A8) Determine if a worker is allowed to perform workwithout exceeding administrative dose limitKA 2.3.7Emergency Procedures/PlanR, N(A9) Classify an EmergencyKA 2.4.30NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they areretaking only the administrative topics, when all 5 are required.* Type Codes & Criteria:(C)ontrol room, (S)imulator, or Class(R)oom(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)(N)ew or (M)odified from bank ( 1)(P)revious 2 exams ( 1; randomly selected)

NRCES-301Control Room/In-Plant Systems OutlineForm ES-301-2Facility: RIVER BEND STATIONDate of Examination: 3/24/2014Exam Level: RO SRO-I SRO-UOperating Test No.: ______________Control Room Systems

@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)System / JPM TitleType Code*SafetyFunctiona. (S1) Initiate RCIC for level controlA,E,L,N,S 4b. (S2) Perform STP to Slow Stroke the MSIVsN,S 3c. (S3) Alternate Feedwater Level Control channelsA,N,S 2d. (S4) Parallel offsite power source to standby diesel generatorD,S 6e. (S5) Initiate Standby Liquid ControlA,E,L,N,S 1f. (S6) Emergency operation of containment coolers with Service waterD,E,S,EN 5g. (C1) Defeating Offgas high radiation isolation interlockC,D,E,L 9h. (C2) Bypass an LPRM C,D 7In-Plant Systems

@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)i. (P1) Alternating Control Building chilled water pump and chiller withinthe standby divisionD,EN 9j. (P2) Cross connecting DG air receivers within a single division N 6k. (P3) Align Instrument Air diesel air compressor backup to safetyrelief valve headerA,D,E,L,R 8@All RO and SRO-I control room (and in-plant) systems must be different and serve different safetyfunctions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions mayoverlap those tested in the control room.* Type CodesCriteria for RO / SRO-I / SRO-U(A)lternate path(C)ontrol room(D)irect from bank(E)mergency or abnormal in-plant(EN)gineered safety feature(L)ow-Power / Shutdown(N)ew or (M)odified from bank including 1(A)(P)revious 2 exams(R)CA(S)imulator4-6 / 4-6 / 2-3 4 9 / 8 / 4 6 1 / 1 / 1 5 - / - / 1 (control room system) - 1 / 1 / 1 4 2 / 2 / 1 5 3 / 3 / 2 (randomly selected) 0 1 / 1 / 1 1 NRCES-301Control Room/In-Plant Systems OutlineForm ES-301-2Facility: RIVER BEND STATIONDate of Examination: 3/24/2014Exam Level: RO SRO-I SRO-UOperating Test No.: ______________Control Room Systems

@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)System / JPM TitleType Code*SafetyFunctiona. (S1) Initiate RCIC for level controlA.E,L,N,S 4b. (S2) Perform STP to Slow Stroke the MSIVsN,S 3c. (S3) Alternate Feedwater Level Control channelsA,N,S 2Instant does not perform S4e. (S5) Initiate Standby Liquid ControlA,E,L,N,S 1f. (S6) Emergency operation of containment coolers with Service waterD,E,S,EN 5g. (C1) Defeating Offgas high radiation isolation interlockC,D,E,L 9h. (C2) Bypass an LPRM C,D 7In-Plant Systems

@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)i. (P1) Alternating Control Building chilled water pump and chiller withinthe standby divisionD,EN 9j. (P2) Cross connecting DG air receivers within a single division N 6k. (P3)Align Instrument Air diesel air compressor backup to safetyrelief valve headerA,D,E,L,R 8@All RO and SRO-I control room (and in-plant) systems must be different and serve different safetyfunctions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions mayoverlap those tested in the control room.* Type CodesCriteria for RO / SRO-I / SRO-U(A)lternate path(C)ontrol room(D)irect from bank(E)mergency or abnormal in-plant(EN)gineered safety feature(L)ow-Power / Shutdown(N)ew or (M)odified from bank including 1(A)(P)revious 2 exams(R)CA(S)imulator4-6 / 4-6 / 2-3 4 9 / 8 / 4 5 1 / 1 / 1 5 - / - / 1 (control room system) - 1 / 1 / 1 4 2 / 2 / 1 5 (3 AP) 3 / 3 / 2 (randomly selected) 0 1 / 1 / 1 1 NRCES-301Control Room/In-Plant Systems OutlineForm ES-301-2Facility: RIVER BEND STATIONDate of Examination: 3/24/2014Exam Level: RO SRO-I SRO-UOperating Test No.: ______________Control Room Systems

@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)System / JPM TitleType Code*SafetyFunction(S1) Initiate RCIC for level controlA.E,L,N,S 4(S6) Emergency operation of containment coolers with Service waterD,E,S,EN 5(C1) Defeating Offgas high radiation isolation interlockC,D,E,L 9In-Plant Systems

@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)(P2) Cross connecting DG air receivers within a single division N 6(P3) Align Instrument Air diesel air compressor backup to safety reliefvalve headerA,D,E,L,R 8@All RO and SRO-I control room (and in-plant) systems must be different and serve different safetyfunctions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions mayoverlap those tested in the control room.* Type CodesCriteria for RO / SRO-I / SRO-U(A)lternate path(C)ontrol room(D)irect from bank(E)mergency or abnormal in-plant(EN)gineered safety feature(L)ow-Power / Shutdown(N)ew or (M)odified from bank including 1(A)(P)revious 2 exams(R)CA(S)imulator4-6 / 4-6 / 2-3 2 9 / 8 / 4 3 1 / 1 / 1 4 - / - / 1 (control room system) 1 1 / 1 / 1 3 2 / 2 / 1 2 3 / 3 / 2 (randomly selected) 0 1 / 1 / 1 1 Appendix DScenario OutlineForm ES-D-1Facility: River Bend Station Scenario No.: 1IC No.: 210Examiners: Theresa BuchananOperators:_____________________________ Steve Garchow _____________________________ Mike Bloodgood _____________________________Initial Conditions: 100% reactor power. APRM B is bypassed to support I&C testingTurnover Shift priorities: 1) Perform STP-257-0201EventNo.Malf.No.EventType*EventDescription 1 NAN (SRO, BOP) Perform STP-257-0201, SBGT Operability Test 2CRDM2045C (SRO, ATC) Control Rod Drift Out, rod 20-45 (Tech Spec) 3 NMS011FI (SRO, ATC) APRM 'F' fails upscale (Tech Spec) 4GMC002AGMC001BI (BOP)Stator Cooling Water Pump A trips, B fails to auto start 5MSS005NC (SRO, BOP)R (ATC)Safety Relief Valve 51G fails open 6 NAM (ALL)Reactor scram with uncontrolled pressure drop 7FWS004BC (ATC)FW master controller output fails high (triggered 1 minute after Mode Switch) 8MSS018MSS019MSS004C (SRO, BOP)B21-AOVF022A & B21-F028A fail to closewithSteam Leak outside primary containment

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajorTotal Malfunctions (5-8) (6) Rod Drift, APRM F, Stator Cooling, SRV open, FW Master controller failure, MSIV failureMalfunctions after EOP entry (1-2) (2) FW Master controller, B21-AOVF022A & B21-AOVF028AAbnormal Events (2-4) (4) SOP-0061, AOP-0035, AOP-0001, AOP-0003Major Transients (1-2) (1) Reactor scram with uncontrolled pressure dropEOPs entered (1-2) (2) EOP-0001, EOP-0002EOP contingencies (0-2) (1) Enter EOP-0002Critical Tasks (2-3) (2) Mode switch to Shutdown by 110°F; Close Main Steam Stop Valve, B21-F098A Appendix DScenario OutlineForm ES-D-1Facility: River Bend Station Scenario No.: 2IC No.: 207Examiners: Theresa BuchananOperators:_____________________________ Steve Garchow _____________________________ Mike Bloodgood _____________________________Initial Conditions: Reactor power 70%, RCIC tagged out FWS-P1A tagged out, Feed Reg Valves B & C in service, CRD-P1A tagged out Fuel shuffle in Spent Fuel Pool ongoingTurnover Shift priorities: 1) Place 3 rd Feedwater Reg Valve in service. 2) Raise power with control rods.EventNo.Malf.No.Event Type*EventDescription 1 NAN (SRO, BOP)Place 3 rd Feedwater Regulating Valve in service.

2 NAR (ATC)Raise power with control rods.

3p601_16a:h-5LO_E22-D2-AI (SRO, BOP)E22-N654C fails upscale (CST High Level) - (Tech Spec)Manual action to align HPCS Suction to Supp Pool 4RCS002BC (SRO,ATC)Trip of Recirc Pump B (Tech Spec) 5RPS003A C(ALL)Loss of RPS A 6ED002B RPS001AM (ALL)Loss of NPS-SWG1B/Loss of FeedwaterFailure to Scram

-All Signals ARI effective 7CRD001B C (SRO)CRD Pump B trip 8HPCS005HPCS001C (SRO, BOP)HPCS suction strainer blockageHPCS pump trip (delay 1:10)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajorTotal Malfunctions (5-8) (7) CST Level Instrument Failure, Recirc Pump trip, Loss of RPS, Loss of NPS SWG1B, Failure to Scram, CRD, HPCSMalfunctions after EOP entry (1-2) (2) CRD, HPCSAbnormal Events (2-4) (4) AOP-0024, AOP-0010, AOP-0001, AOP-0002Major Transients (1-2) (1) Loss of NPS-SWGR1B/Loss of FeedEOPs entered (1-2) (1) EOP-0001EOP contingencies (0-2) (1) Alternate Level ControlCritical Tasks (2-3) (2) Initiate ARI, Emergency Depressurize Appendix DScenario OutlineForm ES-D-1Facility: River Bend Station Scenario No.: 3IC No.: 208Examiners: Theresa BuchananOperators:_____________________________ Steve Garchow _____________________________ Mike Bloodgood _____________________________Initial Conditions: Reactor power 70%. CRD-A, HDL-P1B & C, CCP-P1A & B running Accumulator Fault on Control Rod 28 Maintenance package in progressTurnover Shift priorities 1) Rotate RPCCW pumps, 2) Lower Reactor PowerEventNo.Malf.No.Event Type*EventDescription 1 NAN (SRO, BOP)Rotate RPCCW pumps.

2 NAR (ATC)Lower reactor power with control rods to 65%.

3 CCP001CCCP004BC (BOP)CCP-P1C trips; P1B fails to auto start 4ED003ADG002CC (ALL)Loss of NNS-SWGR1ADiv 3 EDG fails to start (Tech Spec) 5 CRD016C (SRO, ATC)CRD suction filter clogging and pump trip (Tech Spec) trigger initiated on CRD-P1B pump start (ramped to 97% over 2 min, 30sec){Remove Malfunction after ATWS - role play}

6 CRD014M (ALL)Anticipated Transient without Scram (Hydraulic Lock) [83%]

7TMS003C (SRO, ATC)Main Turbine High Vibration requiring a manual Turbine Trip 8AI_E51-R600-CTWC (SRO, BOP)RCIC Flow Controller Fails Low - requires manual operation.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajorTotal Malfunctions (5-8) (7) CCP Failure, Loss of NNS-A, Div 3 EDG, CRD suction filter, ATWS, Turbine Vibration, RCIC failureMalfunctions after EOP entry (1-2) (2) Turbine Vibration, RCIC flow failureAbnormal Events (2-4) (4) AOP-0011, AOP-0001, AOP-0002, AOP-0003Major Transients (1-2) (1) ATWSEOPs entered (1-2) (2) EOP-0001, EOP-0002EOP contingencies (0-2) (1) EOP-0001ACritical Tasks (2-3) (2) Terminate and prevent injection", Insert control rods
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