ML21005A039

2020_401-1 and 401-3

ML21005A039
Person / Time
Site:	LaSalle
Issue date:	12/01/2020
From:	Gregory Roach Operations Branch III
To:	Exelon Generation Co, NRC/RGN-III/DRS/OLB
Roach G
Shared Package
ML19127A359	List: ML21005A020 ML21005A022 ML21005A023 ML21005A026 ML21005A039 ML21005A040 ML21005A043 ML21005A046
References
Download: ML21005A039 (13)

Text

ES-401 1 Form ES-401-1 Facility: LaSalle County Station Date of Exam: November 2020 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 1 2 1 1 1 1 7 2 1 3 Abnormal Plant Evolutions Tier Totals 4 5 4 4 5 5 27 6 4 10 1 2 2 2 2 2 3 3 3 3 2 2 26 2 3 5 2.

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

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 3 2 3 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 #

Knowledge of the interrelations between partial or complete 295001 (APE 1) Partial or Complete Loss of 02 loss of forced core flow circulation and the following: 3.2 1 Forced Core Flow Circulation / 1 & 4 Nuclear boiler instrumentation.

Knowledge of the reasons for the following responses or 295003 (APE 3) Partial or Complete Loss of 06 actions as they apply to partial or complete loss of AC 3.7 2 AC Power / 6 power: Containment isolation.

Ability to operate and/or monitor the following as they apply 295004 (APE 4) Partial or Total Loss of DC 03 to partial or complete loss of DC power: AC Electrical 3.4 3 Power / 6 Distribution.

KA change to 295004 AA1.02 (3.8)

Ability to determine and/or interpret the following as they 295005 (APE 5) Main Turbine Generator 06 apply to main turbine generator trip: Feedwater 2.6 4 Trip / 3 temperature.

Ability to recognize abnormal indications for system 295006 (APE 6) Scram / 1 4.4 operating parameters that are entry-level conditions for 4.5 5 Emergency and Abnormal Operating Procedures.

Knowledge of the interrelations between Control Room 295016 (APE 16) Control Room 01 abandonment and the following: Remote shutdown panel. 4.4 6 Abandonment / 7 Knowledge of the reasons for the following responses as 295018 (APE 18) Partial or Complete Loss 07 they apply to partial or complete loss of component cooling 3.1 7 of CCW / 8 water: Cross-connecting with backup systems.

Ability to operate and/or monitor the following as they apply 295019 (APE 19) Partial or Complete Loss 02 to a partial or complete loss of instrument air: Instrument air 3.3 8 of Instrument Air / 8 system valves.

KA change to 295019 AA1.03 (3.0)

Knowledge of the operational implications of the following 295021 (APE 21) Loss of Shutdown Cooling 01 concepts as they apply to loss of shutdown cooling: Decay 3.6 9

/4 heat.

Ability to determine and/or interpret the following as they 295023 (APE 23) Refueling Accidents / 8 03 apply to refueling accidents: Airborne contamination levels. 3.3 10 295024 High Drywell Pressure / 5 2.42 Ability to recognize system parameters that are entry-level 3.9 11 conditions for Technical Specifications.

Knowledge of the operational implications of the following 295025 (EPE 2) High Reactor Pressure / 3 06 concepts as they apply to high reactor pressure: Pressure 3.5 12 effects on reactor water level.

Knowledge of the interrelations between suppression pool 295026 (EPE 3) Suppression Pool High 02 high water temperature and the following: Suppression pool 3.6 13 Water Temperature / 5 spray.

295027 (EPE 4) High Containment Not sampled, N/A for LaSalle (Mark II Containment).

Temperature (Mark III Containment Only) / 5 Knowledge of the reasons for the following responses as 295028 (EPE 5) High Drywell Temperature 02 they apply to high drywell temperature: RPV flooding. 3.5 14 (Mark I and Mark II only) / 5 Ability to operate and/or monitor the following as they apply 295030 (EPE 7) Low Suppression Pool 03 to low suppression pool water level: HPCS. 3.4 15 Water Level / 5 Ability to determine and/or interpret the following as they 295031 (EPE 8) Reactor Low Water Level / 04 apply to reactor low water level: Adequate core cooling. 4.6 16 2

Ability to locate control room switches, controls, and 295037 (EPE 14) Scram Condition Present 1.31 indications, and to determine that they correctly reflect the 4.6 17 and Reactor Power Above APRM desired plant lineup.

Downscale or Unknown / 1 Ability to determine and/or interpret the following as they 295038 (EPE 15) High Offsite Radioactivity 04 apply to high off-site release rate: Source of off-site 4.1 18 Release Rate / 9 release.

Ability to interpret and execute procedure steps.

600000 (APE 24) Plant Fire On Site / 8 1.20 4.6 19 Knowledge of the operational implications of the following 700000 (APE 25) Generator Voltage and 02 concepts as they apply to generator voltage and electric 3.3 20 Electric Grid Disturbances / 6 grid disturbances: Over-excitation.

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 Vacuum / 3 Ability to determine and/or interpret the following as they 295007 (APE 7) High Reactor Pressure / 3 02 apply to high reactor pressure: Reactor power. 4.1 21 295008 (APE 8) High Reactor Water Level / 2 295009 (APE 9) Low Reactor Water Level / 2 295010 (APE 10) High Drywell Pressure / 5 295011 (APE 11) High Containment Not sampled, N/A for LaSalle (Mark II Containment).

Temperature (Mark III Containment only) / 5 Knowledge of the operational implications of EOP 295012 (APE 12) High Drywell Temperature / 4.20 warnings, cautions, and notes. 3.8 22 5

295013 (APE 13) High Suppression Pool Temperature / 5 Knowledge of the operational implications of the 295014 (APE 14) Inadvertent Reactivity 05 following concepts as they apply to inadvertent reactivity 3.7 23 Addition / 1 addition: Fuel thermal limits.

295015 (APE 15) Incomplete Scram / 1 295017 (APE 17) Abnormal Offsite Release Rate / 9 Knowledge of the interrelations between inadvertent 295020 (APE 20) Inadvertent Containment 01 containment isolation and the following: Main steam 3.6 24 Isolation / 5 & 7 system.

Knowledge of the interrelations between loss of CRD 295022 (APE 22) Loss of Control Rod Drive 03 pumps and the following: Accumulator pressures. 3.4 25 Pumps / 1 Knowledge of the reasons for the following responses as 295029 (EPE 6) High Suppression Pool Water 03 they apply to high suppression pool water level: Reactor 3.4 26 Level / 5 SCRAM.

295032 (EPE 9) High Secondary Containment Area Temperature / 5 295033 (EPE 10) High Secondary Containment Area Radiation Levels / 9 295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9 Ability to operate and/or monitor the following as they 295035 (EPE 12) Secondary Containment 02 apply to secondary containment high differential 3.8 27 High Differential Pressure / 5 pressure: SBGT/FRVS.

295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5 500000 (EPE 16) High Containment Hydrogen Concentration / 5 K/A Category Point Totals: 1 2 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 K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

203000 (SF2, SF4 RHR/LPCI) 2.39 Knowledge of less than or equal to one hour 3.9 28 Technical Specification action statements for RHR/LPCI: Injection Mode systems.

205000 (SF4 SCS) Shutdown Cooling 05 Knowledge of the physical connections and/or 3.1 29 cause-effect relationships between shutdown cooling system (RHR shutdown cooling mode) and the following: Component cooling water systems.

206000 (SF2, SF4 HPCIS) Not sampled, N/A for LaSalle (BWR-5).

High-Pressure Coolant Injection 207000 (SF4 IC) Isolation Not sampled, N/A for LaSalle (BWR-5).

(Emergency) Condenser 209001 (SF2, SF4 LPCS) 01 02 Knowledge of electrical power supplies to the 3.0 30 following: Pump power; Low-Pressure Core Spray Knowledge of the effect that a loss or malfunction of the following will have on the low pressure core spray system: Emergency generators.

3.8 31 209002 (SF2, SF4 HPCS) 01 04 Knowledge of the effect that a loss or malfunction 3.9 32 High-Pressure Core Spray of the high pressure core spray system will have on the following: Reactor water level; Ability to predict and/or monitor changes in 3.3 33 parameters associated with operating the high pressure core spray system controls including:

Reactor pressure.

211000 (SF1 SLCS) Standby Liquid 07 03 Knowledge of standby liquid control system design 3.8 34 feature(s) and/or interlocks which provide for the Control following: RWCU isolation; Ability to (a) predict the impacts of the following on 3.2 35 the standby liquid control system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: AC power failures.

212000 (SF7 RPS) Reactor Protection 02 05 Knowledge of the operational implications of the 3.3 36 following concepts as they apply to the reactor protection system: Specific logic arrangements; Ability to monitor automatic operations of the 3.9 37 reactor protection system including: SCRAM instrument volume level.

215003 (SF7 IRM) 05 03 Knowledge of the effect that a loss or malfunction 3.1 38 of the following will have on the intermediate Intermediate-Range Monitor range monitor system: Trip units; Ability to manually operate and/or monitor in the 3.6 39 control room: IRM range switches.

215004 (SF7 SRMS) Source-Range 03 Ability to predict and/or monitor changes in 3.4 40 parameters associated with operating the source Monitor range monitor system controls including: RPS status.

215005 (SF7 PRMS) Average Power 02 Ability to (a) predict the impacts of the following on 3.6 41 the average power range monitor/local power Range Monitor/Local Power Range range monitor system; and (b) based on those Monitor predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Upscale or downscale trips.

217000 (SF2, SF4 RCIC) Reactor 04 Ability to monitor automatic operations of the 3.6 42 reactor core isolation cooling system including:

Core Isolation Cooling System flow.

218000 (SF3 ADS) Automatic 01 Ability to manually operate and/or monitor in the 4.4 43 control room: ADS valves.

Depressurization 223002 (SF5 PCIS) Primary 1.28 Knowledge of the purpose and function of major 4.1 44 system components and controls.

Containment Isolation/Nuclear Steam Supply Shutoff 239002 (SF3 SRV) Safety Relief 01 Knowledge of electrical power supplies to the 2.8 45 following: SRV solenoids.

Valves 259002 (SF2 RWLCS) Reactor Water 15 Knowledge of the physical connections and/or 3.2 46 cause-effect relationships between Reactor Water Level Control Level Control System and the following:

Recirculation flow control system

ES-401 5 Form ES-401-1 261000 (SF9 SGTS) Standby Gas 01 Knowledge of the effect that a loss or malfunction 3.3 47 of the standby gas treatment system will have on Treatment the following: Secondary containment and environment differential pressure.

KA change to 261000 K3.03 (3.2) 262001 (SF6 AC) AC Electrical 03 Knowledge of AC electrical distribution design 3.1 48 feature(s) and/or interlocks which provide for the Distribution following: Interlocks between automatic bus transfer and breakers.

262002 (SF6 UPS) Uninterruptable 02 Knowledge of the effect that a loss or malfunction 2.8 49 of the following will have on the uninterruptable Power Supply (AC/DC) power supply (AC/DC): DC electrical power.

263000 (SF6 DC) DC Electrical 01 Knowledge of the operational implications of the 2.6 50 following concepts as they apply to DC electrical Distribution distribution: Hydrogen generation during battery charging.

264000 (SF6 EGE) Emergency 09 Ability to predict and/or monitor changes in 3.0 51 parameters associated with operating the Generators (Diesel/Jet) EDG emergency generators controls including:

Maintaining minimum load on emergency generator (to prevent reverse power).

300000 (SF8 IA) Instrument Air 01 Ability to (a) predict the impacts of the following on 2.9 52 the instrument air system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Air dryer and filter malfunctions.

400000 (SF8 CCS) Component 01 Ability to monitor automatic operations of the 3.0 53 component cooling water system including:

Cooling Water Setpoints on instrument level signals for normal operations, warnings, and trips that are applicable to the CCWS.

510000 (SF4 SWS*) Service Water Not sampled, currently in Rev. 2 of KA catalog.

(Normal and Emergency)

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

ES-401 6 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 2 (RO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

201001 (SF1 CRDH) CRD Hydraulic 02 Knowledge of the effect that a loss or malfunction 3.0 54 of the following will have on the Control Rod Drive System: Condensate storage tanks 201002 (SF1 RMCS) Reactor Manual Control Ability to manually operate and/or monitor in the 06 control room: Rod select matrix power switch. 2.8 55 KA change to 201002 A4.05 (3.1) 201003 (SF1 CRDM) Control Rod and Drive Ability to prioritize and interpret the significance 4.45 of each annunciator or alarm. 4.1 56 Mechanism 201004 (SF7 RSCS) Rod Sequence Control Not sampled, N/A for LaSalle (BWR-5).

201005 (SF1, SF7 RCIS) Rod Control and Not sampled, N/A for LaSalle (BWR-5).

Information 201006 (SF7 RWMS) Rod Worth Minimizer 202001 (SF1, SF4 RS) Recirculation 202002 (SF1 RSCTL) Recirculation Flow Control 204000 (SF2 RWCU) Reactor Water Cleanup Knowledge of the physical connections and/or 13 cause-effect relationships between the reactor 2.5 57 water cleanup system and the following: RHR system.

KA change to 204000 K1.15 (3.1) 214000 (SF7 RPIS) Rod Position Information Knowledge of the effect that a loss or malfunction 01 of the rod position information system will have 3.0 58 on the following: RWM.

215001 (SF7 TIP) Traversing In-Core Probe Knowledge of traversing in-core probe design 01 feature(s) and/or interlocks which provide for the 3.4 59 following: Primary containment isolation.

215002 (SF7 RBMS) Rod Block Monitor 216000 (SF7 NBI) Nuclear Boiler Instrumentation 219000 (SF5 RHR SPC) RHR/LPCI: Knowledge of electrical power supplies to the 02 following: Pumps. 3.1 60 Torus/Suppression Pool Cooling Mode 223001 (SF5 PCS) Primary Containment and Auxiliaries 226001 (SF5 RHR CSS) RHR/LPCI: Containment Spray Mode 230000 (SF5 RHR SPS) RHR/LPCI:

Torus/Suppression Pool Spray Mode 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup 234000 (SF8 FH) Fuel-Handling Equipment 239001 (SF3, SF4 MRSS) Main and Reheat Steam 239003 (SF9 MSVLCS) Main Steam Isolation Not sampled, N/A for LaSalle.

Valve Leakage Control 241000 (SF3 RTPRS) Reactor/Turbine Pressure Regulating 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 256000 (SF2 CDS) Condensate 259001 (SF2 FWS) Feedwater Knowledge of the operational implications of the 02 following concepts as they apply to reactor 2.5 61 feedwater system: Water hammer.

268000 (SF9 RW) Radwaste Ability to predict and/or monitor changes in 01 parameters associated with operating the 2.7 62 radwaste controls including: Radiation level 271000 (SF9 OG) Offgas 272000 (SF7, SF9 RMS) Radiation Monitoring

ES-401 7 Form ES-401-1 286000 (SF8 FPS) Fire Protection Ability to (a) predict the impacts of the following 12 on the fire protection system and (b) based on 3.1 63 those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low diesel fuel supply.

288000 (SF9 PVS) Plant Ventilation 290001 (SF5 SC) Secondary Containment Ability to monitor automatic operations of the 01 secondary containment including: Secondary 3.9 64 containment isolation.

290003 (SF9 CRV) Control Room Ventilation 290002 (SF5 RVI) Reactor Vessel Internals Knowledge of reactor vessel and internals design 05 feature(s) and/or interlocks which provide for the 3.3 65 following: Natural circulation.

51001 (SF8 CWS*) Circulating Water Not sampled, currently in Rev. 2 of KA catalog. 0 K/A Category Point Totals: 1 1 1 2 1 1 1 1 1 1 1 Group Point Total: 12

ES-401 8 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 Loss of Forced Core Flow Circulation / 1 & 4 295003 (APE 3) Partial or Complete Loss of AC Power / 6 Ability to determine and/or interpret the following as they 295004 (APE 4) Partial or Total Loss of DC 03 apply to partial or complete loss of DC power: Battery 2.9 76 Power / 6 voltage.

Ability to evaluate plant performance and make operational 295005 (APE 5) Main Turbine Generator 1.7 judgments based on operating characteristics, reactor 4.7 77 Trip / 3 behavior, and instrument interpretation.

295006 (APE 6) Scram / 1 Ability to determine and/or interpret the following as they 295016 (APE 16) Control Room 05 apply to control room abandonment: Drywell pressure. 3.9 78 Abandonment / 7 295018 (APE 18) Partial or Complete Loss of CCW / 8 Knowledge of annunciators, alarms, indications, or 295019 (APE 19) Partial or Complete Loss 4.31 response procedures. 4.1 79 of Instrument Air / 8 295021 (APE 21) Loss of Shutdown Cooling

/4 295023 (APE 23) Refueling Accidents / 8 295024 High Drywell Pressure / 5 Ability to determine and/or interpret the following as they 295025 (EPE 2) High Reactor Pressure / 3 03 apply to high reactor pressure: Suppression pool 4.1 80 temperature.

295026 (EPE 3) Suppression Pool High Water Temperature / 5 295027 (EPE 4) High Containment Not sampled, N/A for LaSalle (Mark II Containment).

Temperature (Mark III Containment Only) / 5 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only) / 5 295030 (EPE 7) Low Suppression Pool Water Level / 5 Knowledge of how abnormal operating procedures are 295031 (EPE 8) Reactor Low Water Level / 4.8 used in conjunction with EOPs. 4.5 81 2

Ability to determine and/or interpret the following as they 295037 (EPE 14) Scram Condition Present 07 apply to SCRAM condition present and reactor power 4.2 82 and Reactor Power Above APRM above APRM downscale or unknown: Containment Downscale or Unknown / 1 conditions/isolations.

295038 (EPE 15) High Offsite Radioactivity Release Rate / 9 600000 (APE 24) Plant Fire On Site / 8 700000 (APE 25) Generator Voltage and Electric Grid Disturbances / 6 K/A Category Totals: 4 3 Group Point Total: 7

ES-401 9 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 #

Ability to determine and/or interpret the following as they 295002 (APE 2) Loss of Main Condenser 02 apply to loss of main condenser vacuum: Reactor 3.3 83 Vacuum / 3 power.

295007 (APE 7) High Reactor Pressure / 3 295008 (APE 8) High Reactor Water Level / 2 295009 (APE 9) Low Reactor Water Level / 2 Ability to interpret control room indications to verify the 295010 (APE 10) High Drywell Pressure / 5 2.44 status and operation of a system, and understand how 4.4 84 operator actions and directives, affect plant and system conditions.

295011 (APE 11) High Containment Not sampled, N/A for LaSalle (BWR-5).

Temperature (Mark III Containment only) / 5 295012 (APE 12) High Drywell Temperature /

5 295013 (APE 13) High Suppression Pool Temperature. / 5 295014 (APE 14) Inadvertent Reactivity Addition / 1 295015 (APE 15) Incomplete Scram / 1 295017 (APE 17) Abnormal Offsite Release Rate / 9 295020 (APE 20) Inadvertent Containment Isolation / 5 & 7 295022 (APE 22) Loss of Control Rod Drive Pumps / 1 295029 (EPE 6) High Suppression Pool Water Level / 5 295032 (EPE 9) High Secondary Containment Area Temperature / 5 Ability to determine and/or interpret the following as they 295033 (EPE 10) High Secondary 03 apply to high secondary containment area radiation 4.2 85 Containment Area Radiation Levels / 9 levels: Cause of high area radiation.

295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9 295035 (EPE 12) Secondary Containment High Differential Pressure / 5 295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5 500000 (EPE 16) High Containment Hydrogen Concentration / 5 K/A Category Point Totals: 2 1 Group Point Total: 3

ES-401 10 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 1 (SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

203000 (SF2, SF4 RHR/LPCI) RHR/LPCI:

Injection Mode 205000 (SF4 SCS) Shutdown Cooling 206000 (SF2, SF4 HPCIS) High-Pressure Not sampled, N/A for LaSalle (BWR-5).

Coolant Injection 207000 (SF4 IC) Isolation (Emergency) Not sampled, N/A for LaSalle (BWR-5).

Condenser 209001 (SF2, SF4 LPCS) Low-Pressure 05 Ability to (a) predict the impacts of the following on 3.6 89 Core Spray the LOW 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: Core spray line break 209002 (SF2, SF4 HPCS) High-Pressure Core Spray 211000 (SF1 SLCS) Standby Liquid Control 212000 (SF7 RPS) Reactor Protection 215003 (SF7 IRM) Intermediate-Range Monitor 215004 (SF7 SRMS) Source-Range Monitor 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling 218000 (SF3 ADS) Automatic 2.25 Knowledge of the bases in the Technical 4.2 86 Depressurization Specifications for limiting conditions for operations and safety limits.

223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff 239002 (SF3 SRV) Safety Relief Valves 01 Ability to (a) predict the impacts of the following on 3.3 87 the safety relief valves and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Stuck open vacuum breakers.

259002 (SF2 RWLCS) Reactor Water Level Control 261000 (SF9 SGTS) Standby Gas Treatment 262001 (SF6 AC) AC Electrical Distribution 4.50 Ability to verify system alarm setpoints and operate 4.0 88 controls identified in the alarm response manual.

262002 (SF6 UPS) Uninterruptable Power 01 Ability to (a) predict the impacts of the following on 2.8 89 Supply (AC/DC) the uninterruptable power supply (AC/DC) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Undervoltage.

KA change to 209001 A2.05 (3.6) 263000 (SF6 DC) DC Electrical Distribution 264000 (SF6 EGE) Emergency Generators 2.40 Ability to apply Technical Specifications for a system. 4.7 90 (Diesel/Jet) EDG 300000 (SF8 IA) Instrument Air 400000 (SF8 CCS) Component Cooling Water 510000 (SF4 SWS*) Service Water (Normal Not sampled, currently in Rev. 2 of KA catalog.

and Emergency)

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

ES-401 11 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 2 (SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

201001 (SF1 CRDH) CRD Hydraulic 201002 (SF1 RMCS) Reactor Manual Control 201003 (SF1 CRDM) Control Rod and Drive Mechanism 201004 (SF7 RSCS) Rod Sequence Control Not sampled, N/A for LaSalle (BWR-5).

201005 (SF1, SF7 RCIS) Rod Control and Information Not sampled, N/A for LaSalle (BWR-5).

201006 (SF7 RWMS) Rod Worth Minimizer 202001 (SF1, SF4 RS) Recirculation 202002 (SF1 RSCTL) Recirculation Flow Control 07 Ability to (a) predict the impacts of the following 3.3 91 on recirculation flow control system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of feedwater signal inputs, 204000 (SF2 RWCU) Reactor Water Cleanup 214000 (SF7 RPIS) Rod Position Information 215001 (SF7 TIP) Traversing In-Core Probe 215002 (SF7 RBMS) Rod Block Monitor 216000 (SF7 NBI) Nuclear Boiler Instrumentation 219000 (SF5 RHR SPC) RHR/LPCI: Torus/Suppression Pool Cooling Mode 223001 (SF5 PCS) Primary Containment and Auxiliaries Ability to verify that the alarms are consistent with 4.46 the plant conditions. 4.2 92 226001 (SF5 RHR CSS) RHR/LPCI: Containment Spray Ability to verify that the alarms are consistent with Mode 4.46 the plant conditions. 4.2 92 KA change to 223001 G2.4.46 (4.2) 230000 (SF5 RHR SPS) RHR/LPCI: Torus/Suppression Pool Spray Mode 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup 234000 (SF8 FH) Fuel-Handling Equipment 239001 (SF3, SF4 MRSS) Main and Reheat Steam 239003 (SF9 MSVLCS) Main Steam Isolation Valve Not sampled, N/A for LaSalle (BWR-5).

Leakage Control 241000 (SF3 RTPRS) Reactor/Turbine Pressure Regulating 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 256000 (SF2 CDS) Condensate 259001 (SF2 FWS) Feedwater 268000 (SF9 RW) Radwaste 271000 (SF9 OG) Offgas 272000 (SF7, SF9 RMS) Radiation Monitoring 286000 (SF8 FPS) Fire Protection 288000 (SF9 PVS) Plant Ventilation 290001 (SF5 SC) Secondary Containment 290003 (SF9 CRV) Control Room Ventilation Ability to (a) predict the impacts of the following 02 on the control room HVAC and (b) based on 3.4 93 those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Extreme environmental conditions.

290002 (SF4 RVI) Reactor Vessel Internals 51001 (SF8 CWS*) Circulating Water Not sampled, currently in Rev. 2 of KA catalog.

ES-401 12 Form ES-401-1 K/A Category Point Totals: 2 1 Group Point Total: 3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: LaSalle County Station Date of Exam: November 2020 Category K/A # Topic RO SRO-only IR # IR #

Knowledge of the stations requirements for verbal communications 2.1.38 when implementing procedures. 3.7 66 Knowledge of RO duties in the control room during fuel handling such as 2.1.44 responding to alarms from the fuel handling area, communication with 3.9 67 the fuel storage facility, systems operated from the control room in support of fueling operations and supporting instrumentation.

Ability to use procedures related to shift staffing, such as minimum crew

1. Conduct of 2.1.5 complement, overtime limitations, etc. 3.9 94 Operations Ability to perform specific system and integrated plant procedures during 2.1.23 all modes of plant operation. 4.4 95 Subtotal 2 2 Knowledge of the process for controlling equipment configuration or 2.2.14 status. 3.9 68 2.2.22 Knowledge of limiting conditions for operations and safety limits. 4.0 69 Knowledge of the process used to track inoperable alarms.

2.2.43 3.0 70

2. Equipment Knowledge of the process for managing maintenance activities during 2.2.17 power operations, such as risk assessments, work prioritization, and 3.8 96 Control coordination with the transmission system operator.

2.2.21 Knowledge of pre- and post-maintenance operability requirements. 4.1 97 Subtotal 3 2 Ability to use radiation monitoring systems, such as fixed radiation 2.3.5 monitors and alarms, portable survey instruments, personnel monitoring 2.9 71 equipment, etc.

Knowledge of radiological safety principles pertaining to licensed 2.3.12 operator duties, such as containment entry requirements, fuel handling 3.2 72 responsibilities, access to locked high-radiation areas, or aligning filters.

Knowledge of radiological safety procedures pertaining to licensed 2.3.13 operator duties, such as response to radiation monitor alarms, 3.8 98

3. Radiation containment entry requirements, fuel handling responsibilities, access to Control locked high-radiation areas, aligning filters, etc.

2.3.

2.3.

2.3.

Subtotal 2 1 Knowledge of general guidelines for EOP usage.

2.4.14 3.8 73 Knowledge of RO tasks performed outside the main control room during 2.4.34 an emergency and the resultant operational effects. 4.2 74 KA change to 2.4.37 (3.0)

Knowledge of local auxiliary operator tasks during an emergency and 2.4.35 the resultant operational effects. 3.8 75

4. Emergency KA change to 2.4.12 (4.0)

Procedures/Plan Knowledge of the organization of the operating procedures network for 2.4.5 normal, abnormal, and emergency evolutions. 4.3 99 2.4.29 Knowledge of the Emergency Plan. 4.4 100 Subtotal 3 2 Tier 3 Point Total 10 7