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

RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4 *

1. 1 3 4 3 3 4 3 20 4 3 7 Emergency &

Abnormal 2 1 1 1 N/A 1 1 N/A 2 7 1 2 3 Plant Evolutions Tier Totals 4 5 4 4 5 5 27 5 5 10 1 2 2 2 3 3 3 2 2 2 2 3 26 3 2 5 2.

Plant 2 1 1 1 1 1 1 1 1 1 1 2 12 0 2 1 3 Systems Tier Totals 3 3 3 4 4 4 3 3 3 3 5 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 7 Categories 3 3 2 2 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).

Note: 2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

Note: 3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

Note: 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

Note: 5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

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

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

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

Note: 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

Note: 9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

ES-401, Page 16 of 33

ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)

K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 295001 Partial or Complete Loss of Forced 01.

18 Knowledge of system purpose and/or function. 3.9 1 Core Flow Circulation / 1 & 4 27

04. Knowledge of low power/shutdown implications in accident (e.g., loss of coolant 17 295003 Partial or Complete Loss of AC / 6 3.8 1 09 accident or loss of residual heat removal) mitigation strategies.

0 Knowledge of the interrelations between Partial or Total Loss of DC Pwr and the 20 295004 Partial or Total Loss of DC Pwr / 6 3.3 1 3 following: D.C. bus loads 01.

16 295005 Main Turbine Generator Trip / 3 Ability to use plant computers to evaluate system or component status. 3.9 1 19 0

6 295006 SCRAM / 1 Knowledge of the interrelations between SCRAM and the following: RPS 4.3 1 1

0 Ability to operate and/or monitor the following as they apply to Control Room 10 295016 Control Room Abandonment / 7 3.1 1 4 Abandonment: A.C. electrical distribution 0 Ability to determine and/or interpret the following as they apply to Partial or Total 15 295018 Partial or Total Loss of CCW / 8 2.9 1 4 Loss of CCW: System flow 0 Ability to operate and/or monitor the following as they apply to Partial or Total Loss 12 295019 Partial or Total Loss of Inst. Air / 8 3.3 1 2 of Inst. Air: Instrument air system valves: Plant-Specific 0 Ability to operate and/or monitor the following as they apply to Loss of Shutdown 11 295021 Loss of Shutdown Cooling / 4 3.5 1 2 Cooling: RHR/shutdown cooling 0 Ability to determine and/or interpret the following as they apply to Refueling 19 295023 Refueling Acc / 8 3.6 1 1 Accidents: Area radiation levels 0 Knowledge of the reasons for the following responses as they apply to High Drywell 8 295024 High Drywell Pressure / 5 3.7 1 4 Pressure: Emergency depressurization 0 Ability to determine and/or interpret the following as they apply to High Reactor 13 295025 High Reactor Pressure / 3 3.9 1 3 Pressure: Suppression pool temperature 295026 Suppression Pool High Water 0

Temp. / 5 0 Knowledge of the interrelations between High Containment Temperature and the 4 295027 High Containment Temperature / 5 3.2 1 2 following: Components internal to the containment: Mark-III 0 Knowledge of the operational implications of the following concepts as they apply to 1 295028 High Drywell Temperature / 5 3.5 1 1 High Drywell Temperature: Reactor water level measurement 0 Knowledge of the operational implications of the following concepts as they apply to 3 295030 Low Suppression Pool Wtr Lvl / 5 3.8 1 1 Low Suppression Pool Wtr Lvl: Steam condensation 0 Ability to determine and/or interpret the following as they apply to Reactor Low 14 295031 Reactor Low Water Level / 2 4.6 1 4 Water Level: Adequate core cooling 295037 SCRAM Condition Present and Knowledge of the reasons for the following responses as they apply to SCRAM 0

9 Reactor Power Above APRM Downscale or Condition Present and Reactor Power Above APRM Downscale or Unknown: 3.8 1 6 Maintaining heat sinks external to the containment Unknown / 1 0 Knowledge of the reasons for the following responses as they apply to High Off-site 7 295038 High Off-site Release Rate / 9 3.9 1 2 Release Rate: System isolations 0 Knowledge of the operational implications of the following concepts as they apply to 2 600000 Plant Fire On Site / 8 2.9 1 2 Plant Fire On Site: Fire Fighting 700000 Generator Voltage and Electric Grid 0 Knowledge of the interrelations between Generator Voltage and Electric Grid 5 3.1 1 Disturbances / 6 2 Disturbances and the following: Breakers, relays K/A Category Totals: 3 4 3 3 4 3 Group Point Total: 20 ES-401, Page 17 of 33

ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)

K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 295002 Loss of Main Condenser Vac / 3 0 0 Knowledge of the reasons for the following responses as they apply to High Reactor 23 295007 High Reactor Pressure / 3 4.0 1 4 Pressure: Safety/relief valve operation: Plant-Specific 295008 High Reactor Water Level / 2 0 295009 Low Reactor Water Level / 2 0 295010 High Drywell Pressure / 5 0 Knowledge of the parameters and logic used to assess the status of safety 04.

27 295011 High Containment Temp / 5 functions, such as reactivity control, core cooling and heat removal, reactor coolant 4.0 1 21 system integrity, containment conditions, radioactivity release control, etc.

295012 High Drywell Temperature / 5 0 0 Ability to determine and/or interpret the following as they apply to High Suppression 25 295013 High Suppression Pool Temp. / 5 3.2 1 2 Pool Temp.: Localized heating/stratification 0 Ability to operate and/or monitor the following as they apply to Inadvertent Reactivity 24 295014 Inadvertent Reactivity Addition / 1 3.9 1 5 Addition: Neutron monitoring system 295015 Incomplete SCRAM / 1 0 295017 High Off-site Release Rate / 9 0 0 Knowledge of the operational implications of the following concepts as they apply to 21 295020 Inadvertent Cont. Isolation / 5 & 7 3.3 1 5 Inadvertent Cont. Isolation: Loss of drywell/containment cooling 295022 Loss of CRD Pumps / 1 0 295029 High Suppression Pool Wtr Lvl / 5 0 295032 High Secondary Containment Area 0

Temperature / 5 295033 High Secondary Containment Area 0

Radiation Levels / 9 295034 Secondary Containment Ventilation 0

High Radiation / 9 295035 Secondary Containment High 0 Knowledge of the interrelations between Secondary Containment High Differential 22 3.3 1 Differential Pressure / 5 3 Pressure and the following: Off-site release rate 295036 Secondary Containment High 0

Sump/Area Water Level / 5

04. Ability to recognize abnormal indications for system operating parameters that are 26 500000 High CTMT Hydrogen Conc. / 5 4.5 1 04 entry-level conditions for emergency and abnormal operating procedures.

K/A Category Totals: 1 1 1 1 1 2 Group Point Total: 7 ES-401, Page 18 of 33

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

K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 0

47 203000 RHR/LPCI: Injection Mode Ability to manually operate and/or monitor in the control room: Pumps 4.3 1 1

Knowledge of the operational implications of the following concepts as they 46 0 1 2.8; 205000 Shutdown Cooling apply to Shutdown Cooling: Valve operation; Ability to manually operate and/or 2 53 2 2 monitor in the control room: Recirculation loop temperatures 3.4 206000 HPCI 0 207000 Isolation (Emergency) 0 Condenser Knowledge of LPCS design feature(s) and/or interlocks which provide for the 36 1 0 2.8; 209001 LPCS following: Testability of all operable components; Knowledge of the operational 2 50 0 5 implications of the following concepts as they apply to LPCS: System venting 2.5 0 Knowledge of electrical power supplies to the following: Initiation logic: BWR-5, 30 209002 HPCS 2.8 1 3 6 0 Ability to monitor automatic operations of the SLC including: Pump discharge 45 211000 SLC 3.5 1 1 pressure: Plant-Specific 0 Knowledge of electrical power supplies to the following: Analog trip system logic 31 212000 RPS 2.7 1 2 cabinets Knowledge of the physical connections and/or cause-effect relationships 29 0 0 215003 IRM between IRM and the following: Reactor vessel; Ability to monitor automatic 3; 3.3 2 52 7 2 operations of the IRM including: Annunciator and alarm signals 01.

48 215004 Source Range Monitor Ability to interpret reference materials, such as graphs, curves, tables, etc. 3.9 1 25 Knowledge of the operational implications of the following concepts as they 37 0 0 apply to APRM / LPRM: LPRM detector operation; Knowledge of the effect that 2.8; 215005 APRM / LPRM 2 51 1 7 a loss or malfunction of the following will have on the APRM / LPRM: Flow 3.2 converter/comparator network: Plant-Specific 0 Knowledge of the effect that a loss or malfunction of the RCIC will have on 33 217000 RCIC 3.6 1 2 following: Reactor vessel pressure Knowledge of ADS design feature(s) and/or interlocks which provide for the 35 0 04. 3.8; 218000 ADS following: ADS logic control; Knowledge of EOP entry conditions and immediate 2 49 3 01 action steps. 4.6 Knowledge of PCIS/Nuclear Steam Supply Shutoff design feature(s) and/or 223002 PCIS/Nuclear Steam Supply 0 34 interlocks which provide for the following: Automatic bypassing of selected 3.2 1 Shutoff 4 isolations during specified plant conditions 0 Knowledge of the effect that a loss or malfunction of the SRVs will have on 32 239002 SRVs 4.3 1 3 following: Ability to rapidly depressurize the reactor Ability to (a) predict the impacts of the following on the Reactor Water Level 0 Control; and (b) based on those predictions, use procedures to correct, control, 43 259002 Reactor Water Level Control 3.3 1 1 or mitigate the consequences of those abnormal conditions or operations: Loss of any number of main steam flow inputs 0 Ability to predict and/or monitor changes in parameters associated with 41 261000 SGTS 2.8 1 7 operating the SGTS controls including: SBGTS train temperature Ability to (a) predict the impacts of the following on the AC Electrical 0 Distribution; and (b) based on those predictions, use procedures to correct, 42 262001 AC Electrical Distribution 3.4 1 1 control, or mitigate the consequences of those abnormal conditions or operations: Turbine/generator trip 0 Knowledge of the effect that a loss or malfunction of the following will have on 38 262002 UPS (AC/DC) 2.8 1 2 the UPS (AC/DC): D.C. electrical power 0 Knowledge of the effect that a loss or malfunction of the following will have on 39 263000 DC Electrical Distribution 3.2 1 1 the DC Electrical Distribution: A.C. electrical distribution Ability to predict and/or monitor changes in parameters associated with 0

40 264000 EDGs operating the EDGs controls including: Operating voltages, currents, and 2.8 1 3 temperatures 04.

44 300000 Instrument Air Knowledge of abnormal condition procedures. 4.0 1 11 0 Knowledge of the physical connections and/or cause-effect relationships 28 400000 Component Cooling Water 3.2 1 1 between Component Cooling Water and the following: Service water system K/A Category Totals: 2 2 2 3 3 3 2 2 2 2 3 Group Point Total: 26 ES-401, Page 19 of 33

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

K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic 0 201002 RMCS 0 201003 Control Rod and Drive Mechanism 0 201004 RSCS 0 201005 RCIS 0 201006 RWM 0 0

63 202001 Recirculation 5 Ability to manually operate and/or monitor in the control room: Lights and alarms 3.3 1 0 Knowledge of electrical power supplies to the following: Hydraulic power unit:

64 202002 Recirculation Flow Control 2 Plant-Specific 2.6 1 0 Knowledge of the physical connections and/or cause-effect relationships 54 204000 RWCU 4 between RWCU and the following: Component cooling water systems 2.9 1 214000 RPIS 0 215001 Traversing In-core Probe 0 215002 RBM 0 216000 Nuclear Boiler Inst. 0 219000 RHR/LPCI: Torus/Pool Cooling 0 Knowledge of the effect that a loss or malfunction of the RHR/LPCI: Torus/Pool 56 1 3.9 1 Mode Cooling Mode will have on following: Suppression pool temperature control 0 Knowledge of Primary CTMT and Aux. design feature(s) and/or interlocks which 57 223001 Primary CTMT and Aux. 2 provide for the following: Contains fission products after a LOCA 3.6 1 226001 RHR/LPCI: CTMT Spray Mode 0 230000 RHR/LPCI: Torus/Pool Spray Mode 0 01.

55 233000 Fuel Pool Cooling/Cleanup Ability to locate and operate components, including local controls. 4.4 1 30 234000 Fuel Handling Equipment 0 239001 Main and Reheat Steam 0 239003 MSIV Leakage Control 0 241000 Reactor/Turbine Pressure Regulator 0 0 Knowledge of the operational implications of the following concepts as they 58 245000 Main Turbine Gen. / Aux. 7 apply to Main Turbine Gen. / Aux.: Generator operations and limitations 2.6 1 Ability to (a) predict the impacts of the following on the Reactor Condensate; 0

61 256000 Reactor Condensate 9 and (b) based on those predictions, use procedures to correct, control, or 2.8 1 mitigate the consequences of those abnormal conditions or operations: Low 0 Ability to monitor automatic operations of the Reactor Feedwater including:

62 259001 Reactor Feedwater 4 Reactor water level 3.8 1 268000 Radwaste 0 0 Ability to predict and/or monitor changes in parameters associated with 60 271000 Offgas 1 operating the Offgas controls including: Condenser vacuum 3.3 1 272000 Radiation Monitoring 0 0 Knowledge of the effect that a loss or malfunction of the following will have on 59 286000 Fire Protection 1 the Fire Protection: A.C. electrical distribution: Plant-Specific 3.1 1 02.

65 288000 Plant Ventilation Ability to apply Technical Specifications for a system. 3.4 1 40 290001 Secondary CTMT 0 290003 Control Room HVAC 0 290002 Reactor Vessel Internals 0 K/A Category Totals: 1 1 1 1 1 1 1 1 1 1 2 Group Point Total: 12 ES-401, Page 20 of 33

ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)

K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 295001 Partial or Complete Loss of Forced 0

Core Flow Circulation / 1 & 4 295003 Partial or Complete Loss of AC / 6 0 0 Ability to determine and/or interpret the following as they apply to Partial or 76 295004 Partial or Total Loss of DC Pwr / 6 3.9 1 2 Total Loss of DC Pwr: Extent of partial or complete loss of D.C. power 02.

79 295005 Main Turbine Generator Trip / 3 Knowledge of limiting conditions for operations and safety limits. 4.7 1 22 295006 SCRAM / 1 0 295016 Control Room Abandonment / 7 0 295018 Partial or Total Loss of CCW / 8 0

04. Ability to prioritize and interpret the significance of each annunciator or 80 295019 Partial or Total Loss of Inst. Air / 8 4.3 1 45 alarm.

295021 Loss of Shutdown Cooling / 4 0 0 Ability to determine and/or interpret the following as they apply to Refueling 78 295023 Refueling Acc / 8 4.1 1 4 Accidents: Occurrence of fuel handling accident 295024 High Drywell Pressure / 5 0 Ability to evaluate plant performance and make operational judgments 01.

81 295025 High Reactor Pressure / 3 based on operating characteristics, reactor behavior, and instrument 4.7 1 07 interpretation.

295026 Suppression Pool High Water 0

Temp. / 5 295027 High Containment Temperature / 5 0 0 Ability to determine and/or interpret the following as they apply to High 82 295028 High Drywell Temperature / 5 3.9 1 3 Drywell Temperature: Reactor water level 0 Ability to determine and/or interpret the following as they apply to Low 77 295030 Low Suppression Pool Wtr Lvl / 5 3.9 1 2 Suppression Pool Wtr Lvl: Suppression pool temperature 295031 Reactor Low Water Level / 2 0 295037 SCRAM Condition Present and Reactor Power Above APRM 0 Downscale or Unknown / 1 295038 High Off-site Release Rate / 9 0 600000 Plant Fire On Site / 8 0 700000 Generator Voltage and Electric Grid 0

Disturbances / 6 K/A Category Totals: 0 0 0 0 4 3 Group Point Total: 7 ES-401, Page 17 of 33

ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)

K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 01.

84 295002 Loss of Main Condenser Vac / 3 Ability to explain and apply system limits and precautions. 4.0 1 32 295007 High Reactor Pressure / 3 0 295008 High Reactor Water Level / 2 0 295009 Low Reactor Water Level / 2 0 295010 High Drywell Pressure / 5 0 295011 High Containment Temp / 5 0 0 Ability to determine and/or interpret the following as they apply to High Drywell 83 295012 High Drywell Temperature / 5 3.9 1 1 Temperature: Drywell temperature 295013 High Suppression Pool Temp. / 5 0 295014 Inadvertent Reactivity Addition / 1 0 295015 Incomplete SCRAM / 1 0 295017 High Off-site Release Rate / 9 0 295020 Inadvertent Cont. Isolation / 5 & 7 0 295022 Loss of CRD Pumps / 1 0 295029 High Suppression Pool Wtr Lvl / 5 0 Ability to interpret control room indications to verify the status and operation of a 295032 High Secondary Containment Area 02.

85 system, and understand how operator actions and directives affect plant and 4.4 1 Temperature / 5 44 system conditions.

295033 High Secondary Containment Area 0

Radiation Levels / 9 295034 Secondary Containment Ventilation 0

High Radiation / 9 295035 Secondary Containment High 0

Differential Pressure / 5 295036 Secondary Containment High 0

Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 0 K/A Category Totals: 0 0 0 0 1 2 Group Point Total: 3 ES-401, Page 18 of 33

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

K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 203000 RHR/LPCI: Injection 0 205000 Shutdown Cooling Mode 0 206000 HPCI 0 207000 Isolation (Emergency) 0 Condenser 209001 LPCS 0 209002 HPCS 0 Ability to (a) predict the impacts of the following on the SLC; and (b) based on 0

87 211000 SLC those predictions, use procedures to correct, control, or mitigate the 3.3 1 6 consequences of those abnormal conditions or operations: Valve openings 212000 RPS 0 215003 IRM 0 215004 Source Range Monitor 0 215005 APRM / LPRM 0 Ability to (a) predict the impacts of the following on the RCIC; and (b) based on 0

90 217000 RCIC those predictions, use procedures to correct, control, or mitigate the 3.3 1 5 consequences of those abnormal conditions or operations: D.C. power loss 218000 ADS 0 Ability to (a) predict the impacts of the following on the PCIS/Nuclear Steam 223002 PCIS/Nuclear Steam Supply 0 Supply Shutoff; and (b) based on those predictions, use procedures to correct, 86 3.2 1 Shutoff 6 control, or mitigate the consequences of those abnormal conditions or operations: Containment instrumentation failures 239002 SRVs 0 04.

88 259002 Reactor Water Level Control Knowledge of EOP mitigation strategies. 4.7 1 06 261000 SGTS 0 262001 AC Electrical Distribution 0

01. Ability to perform specific system and integrated plant procedures during all 89 262002 UPS (AC/DC) 4.4 1 23 modes of plant operation.

263000 DC Electrical Distribution 0 264000 EDGs 0 300000 Instrument Air 0 400000 Component Cooling Water 0 K/A Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 ES-401, Page 19 of 33

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

K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 02.

92 201001 CRD Hydraulic Knowledge of conditions and limitations in the facility license. 4.5 1 38 201002 RMCS 0 201003 Control Rod and Drive Mechanism 0 201004 RSCS 0 201005 RCIS 0 201006 RWM 0 202001 Recirculation 0 202002 Recirculation Flow Control 0 204000 RWCU 0 214000 RPIS 0 215001 Traversing In-core Probe 0 215002 RBM 0 216000 Nuclear Boiler Inst. 0 219000 RHR/LPCI: Torus/Pool Cooling 0

Mode 223001 Primary CTMT and Aux. 0 226001 RHR/LPCI: CTMT Spray Mode 0 230000 RHR/LPCI: Torus/Pool Spray Mode 0 233000 Fuel Pool Cooling/Cleanup 0 Ability to (a) predict the impacts of the following on the Fuel Handling 0

93 234000 Fuel Handling Equipment 1 Equipment; and (b) based on those predictions, use procedures to correct, 3.7 1 control or mitigate the consequences of those abnormal conditions or Ability to (a) predict the impacts of the following on the Main and Reheat Steam; 0

91 239001 Main and Reheat Steam 3 and (b) based on those predictions, use procedures to correct, control, or 4.2 1 mitigate the consequences of those abnormal conditions or operations: MSIV 239003 MSIV Leakage Control 0 241000 Reactor/Turbine Pressure Regulator 0 245000 Main Turbine Gen. / Aux. 0 256000 Reactor Condensate 0 259001 Reactor Feedwater 0 268000 Radwaste 0 271000 Offgas 0 272000 Radiation Monitoring 0 286000 Fire Protection 0 288000 Plant Ventilation 0 290001 Secondary CTMT 0 290003 Control Room HVAC 0 290002 Reactor Vessel Internals 0 K/A Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 ES-401, Page 20 of 33

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

RO SRO-Only Category K/A # Topic Q# IR # IR #

Ability to identify and interpret diverse indications to validate the response of another 66 2.1. 45 indicator. 4.3 1 4.3 Knowledge of RO duties in the control room during fuel handling such as responding to 67 2.1. 44 alarms from the fuel handling area, communication with the fuel storage facility, systems 3.9 1 3.8 operated from the control room in support of fueling operations, and supporting Ability to use procedures to determine the effects on reactivity of plant changes, such as 68

1. 2.1. 43 reactor coolant system temperature, secondary plant, fuel depletion, etc. 4.1 1 4.3 Conduct of 94 2.1. 20 Ability to interpret and execute procedure steps. 4.6 4.6 1 Operations Knowledge of individual licensed operator responsibilities related to shift staffing, such as 98 2.1. 04 medical requirements, no-solo operation, maintenance of active license status, 3.3 3.8 1 10CFR55, etc.

2.1.

Subtotal 3 2 Knowledge of the process for managing maintenance activities during power operations, 95 2.2. 17 such as risk assessments, work prioritization, and coordination with the transmission 2.6 3.8 1 system operator.

96 2.2. 23 Ability to track Technical Specification limiting conditions for operations. 3.1 4.6 1 69

2. 2.2. 35 Ability to determine Technical Specification Mode of Operation. 3.6 1 4.5 Equipment 70 2.2. 41 Ability to obtain and interpret station electrical and mechanical drawings. 3.5 1 3.9 Control Knowledge of the bases in Technical Specifications for limiting conditions for operations 71 2.2. 25 and safety limits. 3.2 1 4.2 2.2.

Subtotal 3 2 97 2.3. 11 Ability to control radiation releases. 3.8 4.3 1 2.3.

Ability to comply with radiation work permit requirements during normal or abnormal 72

3. 2.3. 07 conditions. 3.5 1 3.6 Radiation Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, 73 2.3. 15 portable survey instruments, personnel monitoring equipment, etc. 2.9 1 3.1 Control 2.3.

2.3.

Subtotal 2 1 99 2.4. 46 Ability to verify that the alarms are consistent with the plant conditions. 4.2 4.2 1 100 2.4. 18 Knowledge of the specific bases for EOPs. 3.3 4.0 1 Knowledge of facility protection requirements, including fire brigade and portable fire 74 4. 2.4. 26 fighting equipment usage. 3.1 1 3.6 Emergency Knowledge of the bases for prioritizing safety functions during abnormal/emergency 75 Procedures 2.4. 22 operations. 3.6 1 4.4

/ Plan 2.4.

2.4.

Subtotal 2 2 Tier 3 Point Total 10 7 ES-401, Page 26 of 33