ML20113F074

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Ile Forms ES-401-1 and ES-401-3
ML20113F074
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 12/11/2018
From: Chuck Zoia
Exelon Generation Co
To:
NRC/RGN-III/DRS/OLB
Zoia C
Shared Package
ML17164A411 List:
References
Download: ML20113F074 (10)
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Text

ES-401 1 Form ES-401-1 Facility: LaSalle Date of Exam: 11/16/2018 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 3 3 3 3 4 4 20 4 3 7 Emergency and N/A N/A 2 2 1 1 1 1 1 7 1 2 3 Abnormal Plant Evolutions Tier Totals 5 4 4 4 5 5 27 5 5 10 1 2 3 3 3 3 2 2 2 2 2 2 26 3 2 5 2.

Plant 2 1 1 1 1 1 2 1 1 1 1 1 12 - 1 2 3 Systems Tier Totals 3 4 4 4 4 4 3 3 3 3 3 38 4 4 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 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 outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)
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 outline. Systems or evolutions that do not apply at the facility should be deleted with justification. 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. 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 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 a category 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.

G* Generic K/As

  • These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.
    • These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.

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

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

295001 (APE 1) Partial or Complete Loss of 04 Ability to determine and/or interpret the following as they apply to 3.0 1 Forced Core Flow Circulation / 1 & 4 PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: (CFR: 41.10 / 43.5 / 45.13) Individual jet pump flows 295003 (APE 3) Partial or Complete Loss of 01- Ability to evaluate plant performance and make operational judgments 4.4 1 AC Power / 6 07 based on operating characteristics, reactor behavior, and instrument interpretation. (CFR: 41.5 / 43.5 / 45.12 / 45.13) 295004 (APE 4) Partial or Total Loss of DC 03 Knowledge of the operational implications of the following concepts as 2.9 1 Power / 6 they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER:

(CFR: 41.8 to 41.10) Electrical bus divisional separation 295005 (APE 5) Main Turbine Generator Trip 07 Knowledge of the interrelations between MAIN TURBINE 3.6 1

/3 GENERATOR TRIP and the following: (CFR: 41.7 / 45.8) Reactor pressure control 295006 (APE 6) Scram / 1 04 Knowledge of the reasons for the following responses as they apply to 3.1 1 SCRAM: (CFR: 41.5 / 45.6) Reactor water level setpoint setdown 295016 (APE 16) Control Room 07 Ability to operate and/or monitor the following as they apply to 4.2 1 Abandonment / 7 CONTROL ROOM ABANDONMENT:(CFR: 41.7 / 45.6) Control room/local control transfer mechanisms 295018 (APE 18) Partial or Complete Loss of 04 Ability to determine and/or interpret the following as they apply to 2.9 1 CCW / 8 PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: (CFR: 41.10 / 43.5 / 45.13) System flow 295019 (APE 19) Partial or Complete Loss of 04- Knowledge of local auxiliary operator tasks during an emergency and 3.8 1 Instrument Air / 8 35 the resultant operational effects. (CFR: 41.10 / 43.5 / 45.13) 295021 (APE 21) Loss of Shutdown Cooling / 01 Knowledge of the operational implications of the following concepts as 3.6 1 4 they apply to LOSS OF SHUTDOWN COOLING: (CFR: 41.8 to 41.10)

Decay heat 295023 (APE 23) Refueling Accidents / 8 05 Knowledge of the interrelations between REFUELING ACCIDENTS 3.5 1 and the following: (CFR: 41.7 / 45.8) Secondary containment ventilation 295024 High Drywell Pressure / 5 06 Knowledge of the reasons for the following responses as they apply to 4.0 1 HIGH DRYWELL PRESSURE (CFR: 41.5 / 45.6) Reactor SCRAM 295025 (EPE 2) High Reactor Pressure / 3 03 Ability to operate and/or monitor the following as they apply to HIGH 4.4 1 REACTOR PRESSURE: (CFR: 41.7 / 45.6) Safety/relief valves 295026 (EPE 3) Suppression Pool High 01 Ability to determine and/or interpret the following as they apply to 4.1 1 Water Temperature / 5 SUPPRESSION POOL HIGH WATER TEMPERATURE: (CFR: 41.10 /

43.5 / 45.13) Suppression pool water temperature 295027 (EPE 4) High Containment NOT APPLICABLE 0 Temperature (Mark III Containment Only) / 5 295028 (EPE 5) High Drywell Temperature 02- Ability to interpret control room indications to verify the status and 4.2 1 (Mark I and Mark II only) / 5 44 operation of a system, and understand how operator actions and directives affect plant and system conditions. (CFR: 41.5 / 43.5 / 45.12) 295030 (EPE 7) Low Suppression Pool 02 Knowledge of the operational implications of the following concepts as 3.5 1 Water Level / 5 they apply to LOW SUPPRESSION POOL WATER LEVEL: (CFR: 41.8 to 41.10) Pump NPSH 295031 (EPE 8) Reactor Low Water Level / 2 08 Knowledge of the interrelations between REACTOR LOW WATER 4.2 1 LEVEL and the following: (CFR: 41.7 / 45.8) Automatic depressurization system 295037 (EPE 14) Scram Condition Present 05 Knowledge of the reasons for the following responses as they apply to 3.2 1 and Reactor Power Above APRM Downscale SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE or Unknown / 1 APRM DOWNSCALE OR UNKNOWN: (CFR: 41.5 / 45.6) Cold shutdown boron weight 295038 (EPE 15) High Offsite Radioactivity 04 Ability to operate and/or monitor the following as they apply to HIGH 2.8 1 Release Rate / 9 OFF-SITE RELEASE RATE: (CFR: 41.7 / 45.6)

SPDS/ERIS/CRIDS/GDS 600000 (APE 24) Plant Fire On Site / 8 16 Ability to determine and interpret the following as they apply to PLANT 3.0 1 FIRE ON SITE: Vital equipment and control systems to be maintained and operated during a fire 700000 (APE 25) Generator Voltage and 01- Knowledge of the purpose and function of major system components 4.1 1 Electric Grid Disturbances / 6 28 and controls. (CFR: 41.7)

K/A Category Totals: 3 3 3 3 4 4 Group Point Total: 20

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

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

295002 (APE 2) Loss of Main Condenser 0 Vacuum / 3 295007 (APE 7) High Reactor Pressure / 3 0 295008 (APE 8) High Reactor Water Level / 2 0 295009 (APE 9) Low Reactor Water Level / 2 0 295010 (APE 10) High Drywell Pressure / 5 01 Knowledge of the operational implications of the following concepts as 3.0 1 they apply to HIGH DRYWELL PRESSURE: (CFR: 41.8 to 41.10)

Downcomer submergence 295011 (APE 11) High Containment NOT APPLICABLE 0 Temperature (Mark III Containment only) / 5 295012 (APE 12) High Drywell Temperature / 0 5

295013 (APE 13) High Suppression Pool 01 Knowledge of the interrelations between HIGH SUPPRESSION POOL 3.6 1 Temperature. / 5 TEMPERATURE and the following: (CFR: 41.7 / 45.8) Suppression pool cooling 295014 (APE 14) Inadvertent Reactivity 0 Addition / 1 295015 (APE 15) Incomplete Scram / 1 01 Knowledge of the reasons for the following responses as they apply to 3.4 1 INCOMPLETE SCRAM: (CFR: 41.5 / 45.6) Bypassing rod insertion blocks 295017 (APE 17) Abnormal Offsite Release 0 Rate / 9 295020 (APE 20) Inadvertent Containment 0 Isolation / 5 & 7 295022 (APE 22) Loss of Control Rod Drive 0 Pumps / 1 295029 (EPE 6) High Suppression Pool 0 Water Level / 5 295032 (EPE 9) High Secondary 02 Ability to operate and/or monitor the following as they apply to HIGH 3.4 1 Containment Area Temperature / 5 SECONDARY CONTAINMENT AREA TEMPERATURE: (CFR: 41.7 /

45.6) Leak detection system concept 295033 (EPE 10) High Secondary 0 Containment Area Radiation Levels / 9 295034 (EPE 11) Secondary Containment 01 Ability to determine and/or interpret the following as they apply to 3.8 1 Ventilation High Radiation / 9 SECONDARY CONTAINMENT VENTILATION HIGH RADIATION :

(CFR: 41.10 / 43.5 / 45.13) Ventilation radiation levels 295035 (EPE 12) Secondary Containment 02- Knowledge of conditions and limitations in the facility license. (CFR: 3.6 1 High Differential Pressure / 5 38 41.7 / 41.10 / 43.1 / 45.13) 295036 (EPE 13) Secondary Containment 02 Knowledge of the operational implications of the following concepts as 2.6 1 High Sump/Area Water Level / 5 they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL: (CFR: 41.8 to 41.10) Electrical ground/ circuit malfunction 500000 (EPE 16) High Containment 0 Hydrogen Concentration / 5 K/A Category Point Totals: 2 1 1 1 1 1 Group Point Total: 7

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

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 203000 (SF2, SF4 RHR/LPCI) RHR/LPCI: 0 01- Knowledge of electrical power supplies to the following: (CFR: 41.7) Valves 2.5 2 Injection Mode 2 27 Knowledge of system purpose and/or function. (CFR: 41.7) 3.9 205000 (SF4 SCS) Shutdown Cooling 1 0 Knowledge of the physical connections and/or cause effect relationships between 3.6 2 4 5 SHUTDOWN COOLING SYSTEM (RHR SDC MODE) and the following: (CFR: 41.2 to 41.9 / 45.7 to 45.8) Reactor temperatures (moderator, vessel, flange)

Knowledge of the effect that a loss or malfunction of the SHUTDOWN COOLING SYSTEM (RHR SDC MODE) will have on following: (CFR: 41.7 / 45.4) Fuel pool 2.6 cooling assist 206000 (SF2, SF4 HPCIS) High-Pressure Coolant NOT APPLICABLE 0 Injection 207000 (SF4 IC) Isolation (Emergency) Condenser NOT APPLICABLE 0 209001 (SF2, SF4 LPCS) Low-Pressure 0 0 Knowledge of electrical power supplies to the following: (CFR: 41.7) Valve power 2.5 2 Core Spray 2 6 Knowledge of LOW PRESSURE CORE SPRAY SYSTEM design feature(s) and/or 2.6 interlocks which provide for the following: (CFR: 41.7) Adequate pump NPSH 209002 (SF2, SF4 HPCS) High-Pressure Core 0 Ability to predict and/or monitor changes in parameters associated with operating the HIGH 2.5 1 Spray 7 PRESSURE CORE SPRAY SYSTEM (HPCS) controls including: (CFR: 41.5 / 45.5) Diesel loading 211000 (SF1 SLCS) Standby Liquid Control 0 0 Knowledge of the effect that a loss or malfunction of the SLC SYSTEM will have on 3.0 2 (SLC) 2 4 following: (CFR: 41.7 / 45.4) Core spray line break detection system Knowledge of the operational implications of the following concepts as they apply to SLC SYSTEM:(CFR: 41.5 / 45.3) Explosive valve operation 3.1 212000 (SF7 RPS) Reactor Protection 0 0 Knowledge of REACTOR PROTECTION SYSTEM design feature(s) and/or 4.2 2 8 3 interlocks which provide for the following: (CFR: 41.7) Complete control rod insertion following SCRAM signal generation Knowledge of the effect that a loss or malfunction of the following will have on the 3.5 REACTOR PROTECTION SYSTEM: CFR: 41.7 / 45.7) Nuclear boiler instrumentation 215003 (SF7 IRM) Intermediate-Range 0 Knowledge of the operational implications of the following concepts as they apply to 2.6 1 Monitor 1 INTERMEDIATE RANGE MONITOR (IRM) SYSTEM: (CFR: 41.5 / 45.3) Detector operation 215004 (SF7 SRMS) Source-Range 0 Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR 3.4 1 Monitor 2 (SRM) SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 / 45.6) SRM inop condition 215005 (SF7 PRMS) Average Power 0 Ability to monitor automatic operations of the AVERAGE POWER RANGE 3.0 1 Range Monitor (APRM) /Local Power 6 MONITOR / LOCAL POWER RANGE MONITOR SYSTEM including: (CFR: 41.7 /

Range Monitor 45.7) Maximum disagreement between flow comparator channels 217000 (SF2, SF4 RCIC) Reactor Core 0 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 3.6 1 Isolation Cooling 4 45.8) Manually initiated controls 218000 (SF3 ADS) Automatic 04- Ability to perform without reference to procedures those actions that require 4.6 1 Depressurization 49 immediate operation of system components and controls. (CFR: 41.10 / 43.2 / 45.6) 223002 (SF5 PCIS) Primary Containment 1 Knowledge of the physical connections and/or cause effect relationships between 2.5 1 Isolation/Nuclear Steam Supply Shutoff 8 PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY (NSSS) SHUT-OFF and the following: (CFR: 41.2 to 41.9 / 45.7 to 45.8) Reactor building drainage system 239002 (SF3 SRV) Safety Relief Valves 0 Knowledge of electrical power supplies to the following: (CFR: 41.7) SRV solenoids 2.8 1 1

259002 (SF2 RWLCS) Reactor Water Level 0 Knowledge of the effect that a loss or malfunction of the RWLCS will have on 2.8 1 Control 5 following: (CFR: 41.7 / 45.4), (CFR: 41.7 / 45.5 to 45.8) Recirculation flow control system 261000 (SF9 SGTS) Standby Gas 0 Knowledge of SGTS design feature(s) and/or interlocks which provide for the 2.6 1 Treatment 5 following: (CFR: 41.7) Fission product gas removal 262001 (SF6 AC) AC Electrical Distribution 0 Knowledge of the operational implications of the following concepts as they apply to 2.6 1 2 A.C. ELECTRICAL DISTRIBUTION: (CFR: 41.5 / 45.3) Breaker control 262002 (SF6 UPS) Uninterruptable Power 0 Knowledge of the effect that a loss or malfunction of the following will have on the 2.7 1 Supply (AC/DC) 3 UNINTERRUPTABLE POWER SUPPLY(AC/DC): (CFR: 41.7 / 45.7) Static inverter 263000 (SF6 DC) DC Electrical Distribution 0 Ability to predict and/or monitor changes in parameters associated with operating 2.5 1 1 the D.C. ELECTRICAL DISTRIBUTION controls including: (CFR: 41.5 / 45.5)

Battery charging/discharging rate 264000 (SF6 EGE) Emergency Generators 0 Ability to (a) predict the impacts of the following on the EDG (DIESEL/JET); and (b) 3.7 1 (Diesel/Jet) EDG 9 based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 / 45.6) Loss of A.C. power 300000 (SF8 IA) Instrument Air 0 Ability to monitor automatic operations of the INSTRUMENT AIR SYSTEM including: 2.9 1 2 (CFR: 41.7 / 45.7) Air temperature 400000 (SF8 CCS) Component Cooling 0 Ability to manually operate and / or monitor in the control room: (CFR: 41.7 / 45.5 to 3.1 1 Water (CCW) 1 45.8) CCW indications and control 510000 (SF4 SWS*) Service Water (Normal and NOT APPLICABLE 0 Emergency)

K/A Category Point Totals: 2 3 3 3 3 2 2 2 2 2 2 Group Point Total: 26

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

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 201001 (SF1 CRDH) CRD Hydraulic 0 201002 (SF1 RMCS) Reactor Manual Control 0 201003 (SF1 CRDM) Control Rod and Drive 0 Knowledge of the effect that a loss or malfunction of the following will 3.0 1 Mechanism 2 have on the CONTROL ROD AND DRIVE MECHANISM: (CFR: 41.7 /

45.7) Reactor pressure 201004 (SF7 RSCS) Rod Sequence Control NOT APPLICABLE 0 201005 (SF1, SF7 RCIS) Rod Control and Information NOT APPLICABLE 0 201006 (SF7 RWMS) Rod Worth Minimizer 0 202001 (SF1, SF4 RS) Recirculation 1 Ability to predict and/or monitor changes in parameters associated with 2.8 1 1 operating the RECIRCULATION SYSTEM controls including: (CFR: 41.5

/ 45.5) Vessel bottom head drain temperature 202002 (SF1 RSCTL) Recirculation Flow Control 0 204000 (SF2 RWCU) Reactor Water Cleanup 1 Ability to (a) predict the impacts of the following on the REACTOR 2.7 1 0 WATER CLEANUP SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 / 45.6) Valve closures 214000 (SF7 RPIS) Rod Position Information 0 215001 (SF7 TIP) Traversing In-Core Probe 0 215002 (SF7 RBMS) Rod Block Monitor 0 Ability to monitor automatic operations of the ROD BLOCK MONITOR 3.6 1 4 SYSTEM including: (CFR: 41.7 / 45.7) Verification or proper functioning/

operability 216000 (SF7 NBI) Nuclear Boiler Instrumentation 0 219000 (SF5 RHR SPC) RHR/LPCI: 1 Ability to manually operate and/or monitor in the control room: (CFR: 4.1 1 Torus/Suppression Pool Cooling Mode 2 41.7 / 45.5 to 45.8) Suppression pool temperature 223001 (SF5 PCS) Primary Containment and 0 Auxiliaries 226001 (SF5 RHR CSS) RHR/LPCI: Containment 02- Ability to explain the variations in control board/control room layouts, 3.6 1 Spray Mode 04 systems, instrumentation, and procedural actions between units at a facility. (CFR: 41.6 / 41.7 / 41.10 / 45.1 / 45.13) 230000 (SF5 RHR SPS) RHR/LPCI: 0 Torus/Suppression Pool Spray Mode 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup 0 234000 (SF8 FH) Fuel-Handling Equipment 0 239001 (SF3, SF4 MRSS) Main and Reheat Steam 2 Knowledge of the physical connections and/or cause effect relationships 2.7 1 4 between MAIN AND REHEAT STEAM SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8) Head vent 239003 (SF9 MSVLCS) Main Steam Isolation Valve NOT APPLICABLE 0 Leakage Control 241000 (SF3 RTPRS) Reactor/Turbine Pressure 0 Regulating System 245000 (SF4 MTGEN) Main Turbine 0 Knowledge of the effect that a loss or malfunction of the MAIN TURBINE 3.7 1 Generator/Auxiliary 8 GENERATOR AND AUXILIARY SYSTEMS will have on following: (CFR:

41.7 / 45.4) Reactor/turbine pressure control system 256000 (SF2 CDS) Condensate 0 Knowledge of electrical power supplies to the following: (CFR: 41.7) 2.7 1 1 System pumps 259001 (SF2 FWS) Feedwater 0 268000 (SF9 RW) Radwaste 0 271000 (SF9 OG) Offgas 0 Knowledge of OFFGAS SYSTEM design feature(s) and/or interlocks 2.6 1 2 which provide for the following: (CFR: 41.7) Prevention of the poisoning of the recombiner catalyst by the presence of water 272000 (SF7, SF9 RMS) Radiation Monitoring 0 286000 (SF8 FPS) Fire Protection 0 Knowledge of the operational implications of the following concepts as 2.6 1 7 they apply to FIRE PROTECTION SYSTEM: (CFR: 41.5 / 45.3) Smoke detection 288000 (SF9 PVS) Plant Ventilation 0 290001 (SF5 SC) Secondary Containment 0 290003 (SF9 CRV) Control Room Ventilation 0 Knowledge of the effect that a loss or malfunction of the following will 2.6 1 4 have on the CONTROL ROOM HVAC: (CFR: 41.7 / 45.7) Fire protection 290002 (SF4 RVI) Reactor Vessel Internals 0 51001 (SF8 CWS*) Circulating Water NOT APPLICABLE 0 12 K/A Category Point Totals: 1 1 1 1 1 2 1 1 1 1 1 Group Point Total:

ES-401 6 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

295001 (APE 1) Partial or Complete 0 Loss of Forced Core Flow Circulation

/1&4 295003 (APE 3) Partial or Complete 02 Ability to determine and/or interpret the following as they apply 4.3 1 Loss of AC Power / 6 to PARTIAL OR COMPLETE LOSS OF A.C. POWER: (CFR:

41.10 / 43.5 / 45.13) Reactor power / pressure / and level 295004 (APE 4) Partial or Total Loss 0 of DC Power / 6 295005 (APE 5) Main Turbine 0 Generator Trip / 3 295006 (APE 6) Scram / 1 04- Knowledge of the parameters and logic used to assess the 4.6 1 21 status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

(CFR: 41.7 / 43.5 / 45.12) 295016 (APE 16) Control Room 0 Abandonment / 7 295018 (APE 18) Partial or Complete 0 Loss of CCW / 8 295019 (APE 19) Partial or Complete 0 Loss of Instrument Air / 8 295021 (APE 21) Loss of Shutdown 03 Ability to determine and/or interpret the following as they apply 3.5 1 Cooling / 4 to LOSS OF SHUTDOWN COOLING:(CFR: 41.10/43.5/45.13)

Reactor water level 295023 (APE 23) Refueling Accidents 0

/8 295024 High Drywell Pressure / 5 01- Ability to interpret and execute procedure steps. (CFR: 41.10 / 4.6 1 20 43.5 / 45.12) 295025 (EPE 2) High Reactor 0 Pressure / 3 295026 (EPE 3) Suppression Pool 0 High Water Temperature / 5 295027 (EPE 4) High Containment NOT APPLICABLE 0 Temperature (Mark III Containment Only) / 5 295028 (EPE 5) High Drywell 06 Ability to determine and/or interpret the following as they apply 3.7 1 Temperature (Mark I and Mark II only) to HIGH DRYWELL PRESSURE: (CFR: 41.10 / 43.5 / 45.13)

/5 Torus/suppression chamber air space temperature 295030 (EPE 7) Low Suppression 0 Pool Water Level / 5 295031 (EPE 8) Reactor Low Water 0 Level / 2 295037 (EPE 14) Scram Condition 02- 2.2.25 Knowledge of the bases in Technical Specifications for 4.2 1 Present and Reactor Power Above 25 limiting conditions for operations and safety limits. (CFR: 41.5/

APRM Downscale or Unknown / 1 41.7 /43.2) 295038 (EPE 15) High Offsite 0 Radioactivity Release Rate / 9 600000 (APE 24) Plant Fire On Site / 0 8

700000 (APE 25) Generator Voltage 04 Ability to determine and/or interpret the following as they apply 3.6 1 and Electric Grid Disturbances / 6 to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: (CFR: 41.5 and 43.5 / 45.5, 45.7, and 45.8)

VARs outside capability curve K/A Category Totals: 0 0 0 0 4 3 Group Point Total: 7

ES-401 7 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

295002 (APE 2) Loss of Main Condenser 0 Vacuum / 3 295007 (APE 7) High Reactor Pressure / 3 0 295008 (APE 8) High Reactor Water Level / 2 0 295009 (APE 9) Low Reactor Water Level / 2 0 295010 (APE 10) High Drywell Pressure / 5 0 295011 (APE 11) High Containment NOT APPLICABLE 0 Temperature (Mark III Containment only) / 5 295012 (APE 12) High Drywell Temperature / 04- Ability to identify post-accident instrumentation. (CFR: 41.6 / 3.9 1 5 03 45.4) 295013 (APE 13) High Suppression Pool 0 Temperature. / 5 295014 (APE 14) Inadvertent Reactivity 0 Addition / 1 295015 (APE 15) Incomplete Scram / 1 0 295017 (APE 17) Abnormal Offsite Release 0 Rate / 9 295020 (APE 20) Inadvertent Containment 06 Ability to determine and/or interpret the following as they apply 3.8 1 Isolation / 5 & 7 to INADVERTENT CONTAINMENT ISOLATION: (CFR: 41.10

/ 43.5 / 45.13) Cause of isolation 295022 (APE 22) Loss of Control Rod Drive 0 Pumps / 1 295029 (EPE 6) High Suppression Pool 0 Water Level / 5 295032 (EPE 9) High Secondary 0 Containment Area Temperature / 5 295033 (EPE 10) High Secondary 0 Containment Area Radiation Levels / 9 295034 (EPE 11) Secondary Containment 01- Ability to explain and apply system limits and precautions. 4.0 1 Ventilation High Radiation / 9 32 (CFR: 41.10 / 43.2 / 45.12) 295035 (EPE 12) Secondary Containment 0 High Differential Pressure / 5 295036 (EPE 13) Secondary Containment 0 High Sump/Area Water Level / 5 500000 (EPE 16) High Containment 0 Hydrogen Concentration / 5 K/A Category Point Totals: 0 0 0 0 1 2 Group Point Total: 3

ES-401 8 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 1 (SRO)

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 203000 (SF2, SF4 RHR/LPCI) 0 RHR/LPCI: Injection Mode 205000 (SF4 SCS) Shutdown Cooling 0 206000 (SF2, SF4 HPCIS) NOT APPLICABLE 0 High-Pressure Coolant Injection 207000 (SF4 IC) Isolation NOT APPLICABLE 0 (Emergency) Condenser 209001 (SF2, SF4 LPCS) 0 Ability to (a) predict the impacts of the following on the LOW 3.6 1 Low-Pressure Core Spray 5 PRESSURE CORE SPRAY SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 /

45.6) Core spray line break 209002 (SF2, SF4 HPCS) 0 High-Pressure Core Spray 211000 (SF1 SLCS) Standby Liquid 0 Control (SLC) 212000 (SF7 RPS) Reactor 02- Ability to apply Technical Specifications for a system. (CFR: 41.10 / 43.2 4.7 1 Protection 40 / 43.5 / 45.3) 215003 (SF7 IRM) 0 Intermediate-Range Monitor 215004 (SF7 SRMS) Source-Range 0 Monitor 215005 (SF7 PRMS) Average Power 0 Range Monitor (APRM) /Local Power Range Monitor 217000 (SF2, SF4 RCIC) Reactor 1 Ability to (a) predict the impacts of the following on the REACTOR 3.0 1 Core Isolation Cooling 3 CORE ISOLATION COOLING SYSTEM (RCIC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 /

45.6) Loss of room cooling 218000 (SF3 ADS) Automatic 0 Depressurization 223002 (SF5 PCIS) Primary 0 Containment Isolation/Nuclear Steam Supply Shutoff (NSSS) 239002 (SF3 SRV) Safety Relief 0 Valves 259002 (SF2 RWLCS) Reactor Water 04- Ability to verify that the alarms are consistent with the plant conditions. 4.2 1 Level Control 46 (CFR: 41.10 / 43.5 / 45.3 / 45.12) 261000 (SF9 SGTS) Standby Gas 0 Treatment 262001 (SF6 AC) AC Electrical 0 Distribution 262002 (SF6 UPS) Uninterruptable 0 Power Supply (AC/DC) 263000 (SF6 DC) DC Electrical 0 Ability to (a) predict the impacts of the following on the D.C. 3.2 1 Distribution 1 ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 / 45.6) Grounds 264000 (SF6 EGE) Emergency 0 Generators (Diesel/Jet) EDG 300000 (SF8 IA) Instrument Air 0 400000 (SF8 CCS) Component 0 Cooling Water (CCW) 510000 (SF4 SWS*) Service Water NOT APPLICABLE 0 (Normal and Emergency)

K/A Category Point Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5

ES-401 9 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 2 (SRO)

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 201001 (SF1 CRDH) CRD Hydraulic 0 201002 (SF1 RMCS) Reactor Manual Control 02-22 Knowledge of limiting conditions for operations and safety 4.7 1 limits. (CFR: 41.5 / 43.2 / 45.2) 201003 (SF1 CRDM) Control Rod and Drive 0 Mechanism 201004 (SF7 RSCS) Rod Sequence Control NOT APPLICABLE 0 201005 (SF1, SF7 RCIS) Rod Control and NOT APPLICABLE 0 Information 201006 (SF7 RWMS) Rod Worth Minimizer 0 202001 (SF1, SF4 RS) Recirculation 0 202002 (SF1 RSCTL) Recirculation Flow 0 Control 204000 (SF2 RWCU) Reactor Water Cleanup 0 214000 (SF7 RPIS) Rod Position Information 0 215001 (SF7 TIP) Traversing In-Core Probe 0 215002 (SF7 RBMS) Rod Block Monitor 0 216000 (SF7 NBI) Nuclear Boiler 0 Instrumentation 219000 (SF5 RHR SPC) RHR/LPCI: 1 Ability to (a) predict the impacts of the following on the 3.2 1 Torus/Suppression Pool Cooling Mode 6 RHR/LPCI: TORUS/SUPPRESSION POOL COOLING MODE; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 / 45.6) High suppression pool level 223001 (SF5 PCS) Primary Containment and 0 Auxiliaries 226001 (SF5 RHR CSS) RHR/LPCI: 0 Containment Spray Mode 230000 (SF5 RHR SPS) RHR/LPCI: 0 Torus/Suppression Pool Spray Mode 233000 (SF9 FPCCU) Fuel Pool 0 Cooling/Cleanup 234000 (SF8 FH) Fuel-Handling Equipment 0 239001 (SF3, SF4 MRSS) Main and Reheat 0 Steam 239003 (SF9 MSVLCS) Main Steam Isolation NOT APPLICABLE 0 Valve Leakage Control 241000 (SF3 RTPRS) Reactor/Turbine 0 Pressure Regulating System 245000 (SF4 MTGEN) Main Turbine 0 Generator/Auxiliary 256000 (SF2 CDS) Condensate 0 259001 (SF2 FWS) Feedwater 0 268000 (SF9 RW) Radwaste 0 271000 (SF9 OG) Offgas 0 272000 (SF7, SF9 RMS) Radiation Monitoring 0 286000 (SF8 FPS) Fire Protection 0 288000 (SF9 PVS) Plant Ventilation 0 290001 (SF5 SC) Secondary Containment 0 290003 (SF9 CRV) Control Room Ventilation 0 290002 (SF4 RVI) Reactor Vessel Internals 04-18 Knowledge of the specific bases for EOPs. (CFR: 41.10 / 43.1 / 4.0 1 45.13) 51001 (SF8 CWS*) Circulating Water NOT APPLICABLE 0 K/A Category Point Totals: 0 0 0 0 0 0 0 1 0 0 2 Group Point Total: 3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: LaSalle Date of Exam: 11/16/2018 Category K/A # Topic RO SRO-only IR # IR #

2.1.1 Knowledge of conduct of operations requirements. (CFR: 41.10 / 45.13) 3.8 1 - -

2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as - - 3.8 1 medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc. (CFR: 41.10 / 43.2)

1. Conduct of 2.1.8 Ability to coordinate personnel activities outside the control room. (CFR: 41.10 / 45.5 / 3.4 1 - -

Operations 45.12 / 45.13) 2.1.17 Ability to make accurate, clear, and concise verbal reports. (CFR: 41.10 / 45.12 / 45.13) 3.9 1 -

  • 2.1.39 Knowledge of conservative decision making practices. (CFR: 41.10 / 43.5 / 45.12) - - 4.3 1 Subtotal 3 2 2.2.13 Knowledge of tagging and clearance procedures. (CFR: 41.10 / 45.13) 4.1 1 - -

2.2.17 Knowledge of the process for managing maintenance activities during power operations, - - 3.8 1 such as risk assessments, work prioritization, and coordination with the transmission system operator. (CFR: 41.10 / 43.5 / 45.13) 2.2.23 Ability to track Technical Specification limiting conditions for operations. (CFR: 41.10 / 3.1 1 - -

43.2 / 45.13)

2. Equipment Control 2.2.35 Ability to determine Technical Specification Mode of Operation. (CFR: 41.7 / 41.10 / 43.2 - - 4.5 1

/ 45.13) 2.2.41 Ability to obtain and interpret station electrical and mechanical drawings. (CFR: 41.10 / 3.5 1 - -

45.12 / 45.13)

Subtotal 3 2 2.3.5 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, 2.9 1 - -

portable survey instruments, personnel monitoring equipment, etc. (CFR: 41.11 / 41.12 /

43.4 / 45.9) 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as 3.2 1 - -

containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR: 41.12 / 45.9 / 45.10)

3. Radiation Control 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, - - 3.8 1 abnormal, or emergency conditions or activities. (CFR: 41.12 / 43.4 / 45.10)

Subtotal 2 1 2.4.5 Knowledge of the organization of the operating procedures network for normal, abnormal, 3.7 1 - -

and emergency evolutions. (CFR: 41.10 / 43.5 / 45.13) 2.4.11 Knowledge of abnormal condition procedures. (CFR: 41.10 / 43.5 / 45.13) - - 4.2 1

4. Emergency 2.4.25 Knowledge of fire protection procedures. (CFR: 41.10 / 43.5 / 45.13) * - 3.7 1 Procedures/Plan 2.4.42 2.4.42 Knowledge of emergency response facilities. (CFR: 41.10 / 45.11) 2.6 1 - -

Subtotal 2 2 Tier 3 Point Total 10 7

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