ML13255A059

2013 Clinton Power Station Initial License Examination Outline ES-401-1 and -3 Submittal Version

ML13255A059
Person / Time
Site:	Clinton
Issue date:	05/22/2013
From:	NRC/RGN-III
To:	Jennings T Exelon Generation Co
Dave Reeser
Shared Package
ML11354A436	List: ML13231A208 ML13231A211 ML13255A018 ML13255A040 ML13255A055 ML13255A059 ML13255A064 ML13255A071 ML13255A073 ML13255A083
References
Download: ML13255A059 (10)

Text

ES-401BWR Examination OutlineFORM ES-401-1Facility Name: Date of Exam:

K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G *TotalTotal 1 3 4 3 3 4 3 20 7 2 1 1 1 1 1 2 7 3Tier Totals 4 5 4 4 5 5 27 10 1 2 2 2 3 3 3 2 2 2 2 3 26 5 2 1 1 1 1 1 1 1 1 1 1 2 12 0 2 3Tier Totals 3 3 3 4 4 4 3 3 3 3 5 38 8 1 2 3 4 2 2 1 2Note: 1.Note: 2.Note: 3.Note: 4.Note: 5.Note: 6.Note: 7.*Note: 8.Note: 9.N/AN/AFor 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.

2 3 3ES-401, Page 16 of 33 5 2Select 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.RO K/A Category Points 7 10Ensure 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).

3The 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.3. Generic Knowledge and Abilities Categories 1 A2 2 5 4 1 5 3 2 4 2TierGroupSRO-Only Points2. Plant Systems1. Emergency & Abnormal Plant Evolutions 1

3 3 G*

ES-401 2Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)IR#18295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 01.27Knowledge of system purpose and/or function.

3.9 1 17295003 Partial or Complete Loss of AC / 6 04.09Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

3.8 1 20295004 Partial or Total Loss of DC Pwr / 6 0 3Knowledge of the interrelations between Partial or Total Loss of DC Pwr and the following: D.C. bus loads 3.3 1 16295005 Main Turbine Generator Trip / 3 01.19Ability to use plant computers to evaluate system or component status.

3.9 1 6295006 SCRAM / 1 0 1Knowledge of the interrelations between SCRAM and the following: RPS 4.3 1 10295016 Control Room Abandonment / 7 0 4Ability to operate and/or monitor the following as they apply to Control Room Abandonment: A.C. electrical distribution 3.1 1 15295018 Partial or Total Loss of CCW / 8 0 4Ability to determine and/or interpret the following as they apply to Partial or Total Loss of CCW: System flow 2.9 1 12295019 Partial or Total Loss of Inst. Air / 8 0 2Ability to operate and/or monitor the following as they apply to Partial or Total Loss of Inst. Air: Instrument air system valves: Plant-Specific 3.3 1 11295021 Loss of Shutdown Cooling / 4 0 2Ability to operate and/or monitor the following as they apply to Loss of Shutdown Cooling: RHR/shutdown cooling 3.5 1 19295023 Refueling Acc / 8 0 1Ability to determine and/or interpret the following as they apply to Refueling Accidents: Area radiation levels 3.6 1 8295024 High Drywell Pressure / 5 0 4Knowledge of the reasons for the following responses as they apply to High Drywell Pressure: Emergency depressurization 3.7 1 13295025 High Reactor Pressure / 3 0 3Ability to determine and/or interpret the following as they apply to High Reactor Pressure: Suppression pool temperature 3.9 1295026 Suppression Pool High Water Temp. / 5 0 4295027 High Containment Temperature / 5 0 2Knowledge of the interrelations between High Containment Temperature and the following: Components internal to the containment: Mark-III 3.2 1 1295028 High Drywell Temperature / 5 0 1Knowledge of the operational implications of the following concepts as they apply to High Drywell Temperature: Reactor water level measurement 3.5 1 3295030 Low Suppression Pool Wtr Lvl / 5 0 1Knowledge of the operational implications of the following concepts as they apply to Low Suppression Pool Wtr Lvl: Steam condensation 3.8 1 14295031 Reactor Low Water Level / 2 0 4Ability to determine and/or interpret the following as they apply to Reactor Low Water Level: Adequate core cooling 4.6 1 9295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 0 6Knowledge of the reasons for the following responses as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown: Maintaining heat sinks external to the containment 3.8 1 7295038 High Off-site Release Rate / 9 0 2Knowledge of the reasons for the following responses as they apply to High Off-site Release Rate: System isolations 3.9 1 2600000 Plant Fire On Site / 8 0 2Knowledge of the operational implications of the following concepts as they apply to Plant Fire On Site: Fire Fighting 2.9 1 5700000 Generator Voltage and Electric Grid Disturbances / 6 0 2Knowledge of the interrelations between Generator Voltage and Electric Grid Disturbances and the following: Breakers, relays 3.1 1K/A Category Totals:

3 4 3 3 4 3 20ES-401, Page 17 of 33Group Point Total:

ES-401 3Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)Q#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 0 23295007 High Reactor Pressure / 3 0 4Knowledge of the reasons for the following responses as they apply to High Reactor Pressure: Safety/relief valve operation: Plant-Specific 4.0 1295008 High Reactor Water Level / 2 0295009 Low Reactor Water Level / 2 0295010 High Drywell Pressure / 5 0 27295011 High Containment Temp / 5 04.21Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

4.0 1295012 High Drywell Temperature / 5 0 25295013 High Suppression Pool Temp. / 5 0 2Ability to determine and/or interpret the following as they apply to High Suppression Pool Temp.: Localized heating/stratification 3.2 1 24295014 Inadvertent Reactivity Addition / 1 0 5Ability to operate and/or monitor the following as they apply to Inadvertent Reactivity Addition: Neutron monitoring system 3.9 1295015 Incomplete SCRAM / 1 0295017 High Off-site Release Rate / 9 0 21295020 Inadvertent Cont. Isolation / 5 & 7 0 5Knowledge of the operational implications of the following concepts as they apply to Inadvertent Cont. Isolation: Loss of drywell/containment cooling 3.3 1295022 Loss of CRD Pumps / 1 0295029 High Suppression Pool Wtr Lvl / 5 0295032 High Secondary Containment Area Temperature / 5 0295033 High Secondary Containment Area Radiation Levels / 9 0295034 Secondary Containment Ventilation High Radiation / 9 0 22295035 Secondary Containment High Differential Pressure / 5 0 3Knowledge of the interrelations between Secondary Containment High Differential Pressure and the following: Off-site release rate 3.3 1295036 Secondary Containment High Sump/Area Water Level / 5 0 26500000 High CTMT Hydrogen Conc. / 5 04.04Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

4.5 1K/A Category Totals:

1 1 1 1 1 2 7ES-401, Page 18 of 33Group Point Total:

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

Q#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#47203000 RHR/LPCI: Injection Mode 0 1Ability to manually operate and/or monitor in the control room: Pumps4.3 146 53205000 Shutdown Cooling 0

2 1 2Knowledge of the operational implications of the following concepts as they apply to Shutdown Cooling: Valve operation; Ability to manually operate and/or monitor in the control room: Recirculation loop temperatures2.8; 3.4 2206000 HPCI 0207000 Isolation (Emergency) Condenser 036 50209001 LPCS 1 0 0 5Knowledge of LPCS design feature(s) and/or interlocks which provide for the following: Testability of all operable components; Knowledge of the operational implications of the following concepts as they apply to LPCS: System venting2.8; 2.5 230209002 HPCS 0 3Knowledge of electrical power supplies to the following: Initiation logic: BWR-5, 62.8 145211000 SLC 0 1Ability to monitor automatic operations of the SLC including: Pump discharge pressure: Plant-Specific3.5 131212000 RPS 0 2Knowledge of electrical power supplies to the following: Analog trip system logic cabinets2.7 129 52215003 IRM 0

7 0 2Knowledge of the physical connections and/or cause-effect relationships between IRM and the following: Reactor vessel; Ability to monitor automatic operations of the IRM including: Annunciator and alarm signals3; 3.3 248215004 Source Range Monitor01.25Ability to interpret reference materials, such as graphs, curves, tables, etc.3.9 137 51215005 APRM / LPRM 0

1 0 7Knowledge of the operational implications of the following concepts as they apply to APRM / LPRM: LPRM detector operation; Knowledge of the effect that a loss or malfunction of the following will have on the APRM / LPRM: Flow converter/comparator network: Plant-Specific2.8; 3.2 233217000 RCIC 0 2Knowledge of the effect that a loss or malfunction of the RCIC will have on following: Reactor vessel pressure3.6 135 49218000 ADS 0

304.01Knowledge of ADS design feature(s) and/or interlocks which provide for the following: ADS logic control; Knowledge of EOP entry conditions and immediate action steps.3.8; 4.6 234223002 PCIS/Nuclear Steam Supply Shutoff 0 4Knowledge of PCIS/Nuclear Steam Supply Shutoff design feature(s) and/or interlocks which provide for the following: Automatic bypassing of selected isolations during specified plant conditions3.2 132239002 SRVs 0 3Knowledge of the effect that a loss or malfunction of the SRVs will have on following: Ability to rapidly depressurize the reactor4.3 143259002 Reactor Water Level Control 0 1Ability to (a) predict the impacts of the following on the Reactor Water Level Control; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of any number of main steam flow inputs3.3 141261000 SGTS 0 7Ability to predict and/or monitor changes in parameters associated with operating the SGTS controls including: SBGTS train temperature2.8 142262001 AC Electrical Distribution 0 1Ability to (a) predict the impacts of the following on the AC Electrical Distribution; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Turbine/generator trip3.4 138262002 UPS (AC/DC) 0 2Knowledge of the effect that a loss or malfunction of the following will have on the UPS (AC/DC): D.C. electrical power2.8 139263000 DC Electrical Distribution 0 1Knowledge of the effect that a loss or malfunction of the following will have on the DC Electrical Distribution: A.C. electrical distribution3.2 140264000 EDGs 0 3Ability to predict and/or monitor changes in parameters associated with operating the EDGs controls including: Operating voltages, currents, and temperatures2.8 144300000 Instrument Air04.11Knowledge of abnormal condition procedures.4.0 128400000 Component Cooling Water 0 1Knowledge of the physical connections and/or cause-effect relationships between Component Cooling Water and the following: Service water system3.2 1K/A Category Totals:

2 2 2 3 3 3 2 2 2 2 326ES-401, Page 19 of 33Group Point Total:

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

Q#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 0201002 RMCS 0201003 Control Rod and Drive Mechanism 0201004 RSCS 0201005 RCIS 0201006 RWM 063202001 Recirculation 0 5Ability to manually operate and/or monitor in the control room: Lights and alarms3.3 164202002 Recirculation Flow Control 0

2Knowledge of electrical power supplies to the following: Hydraulic power unit: Plant-Specific2.6 154204000 RWCU 0

4Knowledge of the physical connections and/or cause-effect relationships between RWCU and the following: Component cooling water systems2.9 1214000 RPIS 0215001 Traversing In-core Probe 0215002 RBM 0216000 Nuclear Boiler Inst.

056219000 RHR/LPCI: Torus/Pool Cooling Mode 0 1Knowledge of the effect that a loss or malfunction of the RHR/LPCI: Torus/Pool Cooling Mode will have on following: Suppression pool temperature control3.9 157223001 Primary CTMT and Aux.

0 2Knowledge of Primary CTMT and Aux. design feature(s) and/or interlocks which provide for the following: Contains fission products after a LOCA3.6 1226001 RHR/LPCI: CTMT Spray Mode 0230000 RHR/LPCI: Torus/Pool Spray Mode 055233000 Fuel Pool Cooling/Cleanup 01.30Ability to locate and operate components, including local controls.4.4 1234000 Fuel Handling Equipment 0239001 Main and Reheat Steam 0239003 MSIV Leakage Control 0241000 Reactor/Turbine Pressure Regulator 058245000 Main Turbine Gen. / Aux.

0 7Knowledge of the operational implications of the following concepts as they apply to Main Turbine Gen. / Aux.: Generator operations and limitations2.6 161256000 Reactor Condensate 0

9Ability to (a) predict the impacts of the following on the Reactor Condensate; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low 2.8 162259001 Reactor Feedwater 0

4Ability to monitor automatic operations of the Reactor Feedwater including:

Reactor water level3.8 1268000 Radwaste 060271000 Offgas 0

1Ability to predict and/or monitor changes in parameters associated with operating the Offgas controls including: Condenser vacuum3.3 1272000 Radiation Monitoring 059286000 Fire Protection 0

1Knowledge of the effect that a loss or malfunction of the following will have on the Fire Protection: A.C. electrical distribution: Plant-Specific3.1 165288000 Plant Ventilation 02.40Ability to apply Technical Specifications for a system.3.4 1290001 Secondary CTMT 0290003 Control Room HVAC 0290002 Reactor Vessel Internals 0K/A Category Totals:

1 1 1 1 1 1 1 1 1 1 2 12ES-401, Page 20 of 33Group Point Total:

ES-401 2Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)Q#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 Forced Core Flow Circulation / 1 & 4 0295003 Partial or Complete Loss of AC / 6 0 76295004 Partial or Total Loss of DC Pwr / 6 0 2Ability to determine and/or interpret the following as they apply to Partial or Total Loss of DC Pwr: Extent of partial or complete loss of D.C. power3.9 1 79295005 Main Turbine Generator Trip / 3 02.22Knowledge of limiting conditions for operations and safety limits.4.7 1295006 SCRAM / 1 0295016 Control Room Abandonment / 7 0295018 Partial or Total Loss of CCW / 8 0 80295019 Partial or Total Loss of Inst. Air / 8 04.45Ability to prioritize and interpret the significance of each annunciator or alarm.4.3 1295021 Loss of Shutdown Cooling / 4 0 78295023 Refueling Acc / 8 0 4Ability to determine and/or interpret the following as they apply to Refueling Accidents: Occurrence of fuel handling accident4.1 1295024 High Drywell Pressure / 5 0 81295025 High Reactor Pressure / 3 01.07Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.4.7 1295026 Suppression Pool High Water Temp. / 5 0295027 High Containment Temperature / 5 0 82295028 High Drywell Temperature / 5 0 3Ability to determine and/or interpret the following as they apply to High Drywell Temperature: Reactor water level3.9 1 77295030 Low Suppression Pool Wtr Lvl / 5 0 2Ability to determine and/or interpret the following as they apply to Low Suppression Pool Wtr Lvl: Suppression pool temperature3.9 1295031 Reactor Low Water Level / 2 0295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 0295038 High Off-site Release Rate / 9 0600000 Plant Fire On Site / 8 0700000 Generator Voltage and Electric Grid Disturbances / 6 0K/A Category Totals:

0 0 0 0 4 3 7ES-401, Page 17 of 33Group Point Total:

ES-401 3Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)IR#84295002 Loss of Main Condenser Vac / 3 01.32Ability to explain and apply system limits and precautions.

4.0 1295007 High Reactor Pressure / 3 0295008 High Reactor Water Level / 2 0295009 Low Reactor Water Level / 2 0295010 High Drywell Pressure / 5 0295011 High Containment Temp / 5 0 83295012 High Drywell Temperature / 5 0 1Ability to determine and/or interpret the following as they apply to High Drywell Temperature: Drywell temperature 3.9 1295013 High Suppression Pool Temp. / 5 0295014 Inadvertent Reactivity Addition / 1 0295015 Incomplete SCRAM / 1 0295017 High Off-site Release Rate / 9 0295020 Inadvertent Cont. Isolation / 5 & 7 0295022 Loss of CRD Pumps / 1 0295029 High Suppression Pool Wtr Lvl / 5 0 85295032 High Secondary Containment Area Temperature / 5 02.44Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

4.4 1295033 High Secondary Containment Area Radiation Levels / 9 0295034 Secondary Containment Ventilation High Radiation / 9 0295035 Secondary Containment High Differential Pressure / 5 0295036 Secondary Containment High Sump/Area Water Level / 5 0500000 High CTMT Hydrogen Conc. / 5 0K/A Category Totals:

0 0 0 0 1 2 3ES-401, Page 18 of 33Group Point Total:

ES-401 4Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Plant Systems - Tier 2/Group 1 (SRO)Q#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: Injection 0205000 Shutdown Cooling Mode 0206000 HPCI 0207000 Isolation (Emergency) Condenser 0209001 LPCS 0209002 HPCS 0 87211000 SLC 0 6Ability to (a) predict the impacts of the following on the SLC; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Valve openings 3.3 1212000 RPS 0215003 IRM 0215004 Source Range Monitor 0215005 APRM / LPRM 0 90217000 RCIC 0 5Ability to (a) predict the impacts of the following on the RCIC; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: D.C. power loss 3.3 1218000 ADS 0 86223002 PCIS/Nuclear Steam Supply Shutoff 0 6Ability to (a) predict the impacts of the following on the PCIS/Nuclear Steam Supply Shutoff; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Containment instrumentation failures 3.2 1239002 SRVs 0 88259002 Reactor Water Level Control 04.06Knowledge of EOP mitigation strategies.

4.7 1261000 SGTS 0262001 AC Electrical Distribution 0 89262002 UPS (AC/DC) 01.23Ability to perform specific system and integrated plant procedures during all modes of plant operation.

4.4 1263000 DC Electrical Distribution 0264000 EDGs 0300000 Instrument Air 0400000 Component Cooling Water 0K/A Category Totals:

0 0 0 0 0 0 0 3 0 0 2 5ES-401, Page 19 of 33Group Point Total:

ES-401 5Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Plant Systems - Tier 2/Group 2 (SRO)

Q#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#92201001 CRD Hydraulic 02.38Knowledge of conditions and limitations in the facility license.4.5 1201002 RMCS 0201003 Control Rod and Drive Mechanism 0201004 RSCS 0201005 RCIS 0201006 RWM 0202001 Recirculation 0202002 Recirculation Flow Control 0204000 RWCU 0214000 RPIS 0215001 Traversing In-core Probe 0215002 RBM 0216000 Nuclear Boiler Inst.

0219000 RHR/LPCI: Torus/Pool Cooling Mode 0223001 Primary CTMT and Aux.

0226001 RHR/LPCI: CTMT Spray Mode 0230000 RHR/LPCI: Torus/Pool Spray Mode 0233000 Fuel Pool Cooling/Cleanup 093234000 Fuel Handling Equipment 0 1Ability to (a) predict the impacts of the following on the Fuel Handling Equipment; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or 3.7 191239001 Main and Reheat Steam 0

3Ability to (a) predict the impacts of the following on the Main and Reheat Steam; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: MSIV 4.2 1239003 MSIV Leakage Control 0241000 Reactor/Turbine Pressure Regulator 0245000 Main Turbine Gen. / Aux.

0256000 Reactor Condensate 0259001 Reactor Feedwater 0268000 Radwaste 0271000 Offgas 0272000 Radiation Monitoring 0286000 Fire Protection 0288000 Plant Ventilation 0290001 Secondary CTMT 0290003 Control Room HVAC 0290002 Reactor Vessel Internals 0K/A Category Totals:

0 0 0 0 0 0 0 2 0 0 1 3ES-401, Page 20 of 33Group Point Total:

ES-401Generic Knowledge and Abilities Outline (Tier 3)Form ES-401-3Facility Name: Date of Exam:

Q#IR#IR#662.1.45Ability to identify and interpret diverse indications to validate the response of another indicator.4.3 14.3 672.1.44Knowledge of RO duties in the control room during fuel handling such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting 3.9 13.8 682.1.43Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.4.1 14.3 942.1.20Ability to interpret and execute procedure steps.4.64.6 1 982.1.04Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.3.33.8 12.1.Subtotal 3 2 952.2.17Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.2.63.8 1 962.2.23Ability to track Technical Specification limiting conditions for operations.3.14.6 1 692.2.35Ability to determine Technical Specification Mode of Operation.3.6 14.5 702.2.41Ability to obtain and interpret station electrical and mechanical drawings.3.5 13.9 712.2.25Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.3.2 14.22.2.Subtotal 3 2 972.3.11Ability to control radiation releases.3.84.3 12.3.722.3.07Ability to comply with radiation work permit requirements during normal or abnormal conditions.3.5 13.6 732.3.15Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.2.9 13.12.3.2.3.Subtotal 2 1 992.4.46Ability to verify that the alarms are consistent with the plant conditions.4.24.2 1 1002.4.18Knowledge of the specific bases for EOPs.3.34.0 1 742.4.26Knowledge of facility protection requirements, including fire brigade and portable fire fighting equipment usage.3.1 13.6 752.4.22Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.3.6 14.42.4.2.4.Subtotal 2 2 10 7SRO-OnlyCategoryTopic1. Conduct of OperationsK/A #ES-401, Page 26 of 33Tier 3 Point Total3. Radiation Control4. Emergency Procedures / Plan2. Equipment Control RO