ML22193A321

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2021 Quad-Cities Ile ES-401-1 and ES-401-3
ML22193A321
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 04/07/2021
From: Randy Baker
NRC/RGN-III/DRS/OLB
To:
Exelon Generation Co
Baker R
Shared Package
ML20139A013 List:
References
Download: ML22193A321 (16)
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Text

ES-401 1 Form ES-401-1 Facility: Quad Cities Nuclear Power Station, Units 1 and 2 Date of Exam: June 1, 2021 - June 11, 2021 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 4 4 3 20 3 4 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 5 5 4 27 5 5 10 1 2 2 2 3 2 2 3 3 2 3 2 26 3 2 5 2.

Plant 2 1 1 1 1 1 1 1 1 2 1 1 12 1 1 1 3 Systems Tier Totals 3 3 3 4 3 3 4 4 4 4 3 38 5 3 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 #

AA1.06 - Ability to operate and/or monitor the 295001 (APE 1) Partial or Complete Loss of 06 following as they apply to PARTIAL OR COMPLETE 3.3 1 Forced Core Flow Circulation / 1 & 4 LOSS OF FORCED CORE FLOW CIRCULATION:

Neutron monitoring (1)

(CFR: 41.7 /45.6)

AA2.01 - Ability to determine and/or interpret the 295003 (APE 3) Partial or Complete Loss of 01 following as they apply to PARTIAL OR COMPLETE 3.4 1 AC Power / 6 LOSS OF AC POWER: Cause of partial or complete loss of AC power. (2)

(CFR: 41.10 / 43.2 / 45.6)

G2.4.49 - Ability to perform without reference to 295004 (APE 4) Partial or Total Loss of DC 04. procedures those actions that require immediate 4.6 1 Power / 6 49 operation of system components and controls.

(CFR: 41.10 /43.5 / 45.13) (3)

AK1.03 - Knowledge of the operational implications of 295005 (APE 5) Main Turbine Generator Trip / 03 the following concepts as they apply to MAIN 3.5 1 3 TURBINE GENERATOR TRIP: Pressure effects on reactor level (4)

(CFR: 41.8 to 41.10)

AK2.03 - Knowledge of the interrelations between 295006 (APE 6) Scram / 1 03 SCRAM and the following: CRD hydraulic system 3.7 1 (CFR: 41.7 / 45.8)

(5)

AK3.02 - Knowledge of the reasons for the following 295016 (APE 16) Control Room Abandonment 02 responses as they apply to CONTROL ROOM 3.7* 1

/7 ABANDONMENT: Turbine trip.

(CFR: 41.5 / 45.6) (6)

AA1.02 - Ability to operate and/or monitor the 295018 (APE 18) Partial or Complete Loss of 02 following as they apply to PARTIAL OR COMPLETE 3.3 1 CCW / 8 LOSS OF COMPONENT COOLING WATER: System loads (7)

(CFR: 41.7 / 45.6)

AA2.01 - Ability to determine and/or interpret the 295019 (APE 19) Partial or Complete Loss of 01 following as they apply to PARTIAL OR COMPLETE 3.5 1 Instrument Air / 8 LOSS OF INSTRUMENT AIR: Instrument air system pressure. (8)

(CFR: 41.10 / 43.5 / 45.13)

G2.4.9 - Knowledge of low power/shutdown 295021 (APE 21) Loss of Shutdown Cooling / 04. implications in accident (e.g. loss of coolant accident 3.8 1 4 09 or loss of residual heat removal) mitigation strategies.

(CFR: 41.10 / 43.5 / 45.13) (9)

AK1.01 -Knowledge of the operational implications of 295023 (APE 23) Refueling Accidents / 8 01 the following concepts as they apply to REFUELING 3.6 1 ACCIDENTS: Radiation exposure hazards.

(CFR: 41.8 to 41.10) (10)

EK2.15 - Knowledge of the interrelations between 295024 High Drywell Pressure / 5 15 HIGH DRYWELL PRESSURE and the following: 3.8 1 Containment spray logic: Plant-Specific (CFR: 41.7 / 45.8) (11)

EK3.02 - Knowledge of the reasons for the following 295025 (EPE 2) High Reactor Pressure / 3 02 responses as they apply to HIGH REACTOR 3.9 1 PRESSURE: Recirculation pump trip: Plant-Specific (CFR: 41.5 / 45.6) (12)

EA1.01 - Ability to operate and/or monitor the 295026 (EPE 3) Suppression Pool High Water 01 following as they apply to SUPPRESSION POOL 4.1 1 Temperature / 5 HIGH WATER TEMPERATURE: Suppression pool cooling. (13)

(CFR: 41.7 / 45.6) 295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 EA2.03 - Ability to determine and/or interpret the 295028 (EPE 5) High Drywell Temperature 03 following as they apply to HIGH DRYWELL 3.7 1 (Mark I and Mark II only) / 5 TEMPERATURE: Reactor water level (CFR: 41.10 / 43.5 / 45.13) (14)

G2.4.1 - Knowledge of EOP entry conditions and 295030 (EPE 7) Low Suppression Pool Water 04. immediate action steps. 4.6 1 Level / 5 01 (CFR: 41.10 / 43.5 / 45.13)

(15)

EK1.01 - Knowledge of the operational implications of 295031 (EPE 8) Reactor Low Water Level / 2 01 the following concepts as they apply to REACTOR 4.6* 1 LOW WATER LEVEL: Adequate core cooling.

(CFR: 41.8 to 41.10) (16)

ES-401 3 Form ES-401-1 EK2.03 - Knowledge of the interrelations between 295037 (EPE 14) Scram Condition Present 03 SCRAM CONDITION PRESENT AND REACTOR 4.1 1 and Reactor Power Above APRM Downscale POWER ABOVE APRM DOWNSCALE OR or Unknown / 1 UNKONWN and the following: ARI/RPT/ATWS: Plant- (17)

Specific (CFR: 41.7 / 45.8)

EK3.02 - Knowledge of the reasons for the following 295038 (EPE 15) High Offsite Radioactivity 02 responses as they apply to HIGH OFF-SITE 3.9 1 Release Rate / 9 RELEASE RATE: System isolations (CFR: 41.5 / 45.6) (18)

AA1.05 - Ability to operate and/or monitor the 600000 (APE 24) Plant Fire On Site / 8 05 following as they apply to PLANT FIRE ON SITE: 3.0 1 Plant and control room ventilation systems (CFR: 41.7 / 45.5 / 45.6) (19)

AA2.09 - Ability to determine and/or interpret the 700000 (APE 25) Generator Voltage and 09 following as they apply to GENERATOR VOLTAGE 3.9 1 Electric Grid Disturbances / 6 AND ELECTRIC GRID DISTURBANCES: Operational status of emergency diesel generators (20)

(CFR: 41.5 / 43.5 / 45.5 / 45.7 / 45.8)

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

ES-401 4 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 AK2.04 - Knowledge of the interrelations between 295007 (APE 7) High Reactor Pressure / 3 1 04 HIGH REACTOR PRESSURE and the following: 3.2 LPCS (21)

(CFR: 41.7 / 45.8) 295008 (APE 8) High Reactor Water Level / 2 AK3.01 - Knowledge of the reasons for the following 295009 (APE 9) Low Reactor Water Level / 2 1 01 responses as they apply to LOW REACTOR WATER 3.2 LEVEL: Recirculation pump run back: Plant-Specific (22)

(CFR: 41.5 / 45.6)

AA1.03 - Ability to operate and/or monitor the 295010 (APE 10) High Drywell Pressure / 5 1 03 following as they apply to HIGH DRYWELL 2.6 PRESSURE: Nitrogen makeup: Plant-Specific (23)

(CFR: 41.7 / 45.6) 295011 (APE 11) High Containment 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 AA2.02 - Ability to determine and/or interpret the 295015 (APE 15) Incomplete Scram / 1 1 02 following as they apply to INCOMPLETE SCRAM: 4.1*

Control rod position (24)

(CFR: 41.10 / 43.5 / 45.13) 295017 (APE 17) Abnormal Offsite Release Rate / 9 295020 (APE 20) Inadvertent Containment Isolation / 5 & 7 G2.1.20 - Ability to interpret and execute procedure 295022 (APE 22) Loss of Control Rod Drive 1

01. steps. 4.6 Pumps / 1 (25) 20 (CFR: 41.10 / 43.5 / 45.12) 295029 (EPE 6) High Suppression Pool Water Level / 5 EK1.01 - Knowledge of the operational implications of 295032 (EPE 9) High Secondary Containment 1 01 the following concepts as they apply to HIGH 3.6 Area Temperature / 5 SECONDARY CONTAINMENT AREA (26)

TEMPERATURE: Personnel protection (CFR: 41.8 to 41.10) 295033 (EPE 10) High Secondary Containment Area Radiation Levels / 9 EK2.04 - Knowledge of the interrelations between 295034 (EPE 11) Secondary Containment 1 04 SECONDARY CONTAINMENT VENTILATION HIGH 3.9 Ventilation High Radiation / 9 RADIATION and the following: Secondary (27) containment ventilation (CFR: 41.7 / 45.8) 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: 1 2 1 1 1 1 Group Point Total: 7

ES-401 5 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) 05 A4.05 - Ability to manually operate and/or monitor 4.3* 1 in the control room: Manual initiation controls RHR/LPCI: Injection Mode (28)

(CFR: 41.7 / 45.5 to 45.8) 205000 (SF4 SCS) Shutdown Cooling 06 A2.06 - Ability to (a) predict the impacts of the 3.4 1 following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE); and (b) (29) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

SDC/RHR pump trips.

(CFR: 41.5 / 45.6) 1

02. G2.2.12 - Knowledge of surveillance procedures. 3.7 (30) 12 (CFR: 41.10 / 45.13) 206000 (SF2, SF4 HPCIS) 13 K1.13 - Knowledge of the physical connections 2.8* 1 and/or cause-effect relationship between HIGH High-Pressure Coolant Injection (31)

PRESSURE COOLANT INJECTION SYSTEM and the following: Main condenser: BWR-2,3,4 (CFR: 41.2 to 41.9 / 45.7,8) 207000 (SF4 IC) Isolation (Emergency) Condenser 209001 (SF2, SF4 LPCS) 03 K2.03 - Knowledge of electrical power supplies to 2.9* 1 the following: Initiation logic Low-Pressure Core Spray (32)

(CFR: 41.7) 209002 (SF2, SF4 HPCS)

High-Pressure Core Spray 211000 (SF1 SLCS) Standby Liquid 03 K3.03 - Knowledge of the effect that a loss or 2.6* 1 malfunction of the STANDBY LIQUID CONTROL Control (33)

SYSTEM will have on the following: Core plate differential pressure indication.

(CFR: 41.7 / 45.4) 212000 (SF7 RPS) Reactor Protection 07 K4.07 - Knowledge of REACTOR PROTECTION 4.1* 1 SYSTEM design feature(s) and/or interlocks which System (34) provide for the following: Manual system activation (trip)

(CFR: 41.7) 215003 (SF7 IRM) 01 K5.01 - Knowledge of the operational implications 2.6 1 of the following concepts as they apply to Intermediate-Range Monitor (35)

INTERMEDIATE RANGE MONITOR (IRM)

SYSTEM: Detector operation.

(CFR: 41.5 / 45.3) 04 A3.04 - Ability to monitor automatic operation of 3.5 1 the INTERMEDIATE RANGE MONITOR (IRM) (36)

SYSTEM including: Control rod block status (CFR: 41.7 / 45.7) 215004 (SF7 SRMS) Source-Range 02 K6.02 - Knowledge of the effect that a loss or 3.1 1 malfunction of the following will have on the Monitor (37)

SOURCE RANGE MONITOR (SRM) SYSTEM:

24/48 volt DC power (CFR: 41.7 / 45.7) 215005 (SF7 PRMS) Average Power 07 A1.07 - Ability to predict and/or monitor changes in 3.0 1 parameters associated with operating the Range Monitor/Local Power Range (38)

AVERAGE POWER RANGE MONITORING/

Monitor LOCAL POWER RANGE MONITORING SYSTEM controls including: APRM (gain adjustment factor).

(CFR: 41.5 / 45.5)

ES-401 6 Form ES-401-1 217000 (SF2, SF4 RCIC) Reactor 08 A2.08 - Ability to (a) predict the impacts of the 3.0 1 following on the REACTOR CORE ISOLATION Core Isolation Cooling (39)

COOLING SYSTEM (RCIC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of lube oil cooling.

(CFR: 41.5 / 45.6)

A3.02 - Ability to monitor automatic operations of 02 the REACTOR CORE ISOLATION COOLING 3.6 1 SYSTEM (RCIC) including: Turbine startup. (40)

(CFR: 41.7 / 45.7) 218000 (SF3 ADS) Automatic 04 A3.04 - Ability to monitor automatic operations of 3.7 1 the AUTOMATIC DEPRESSURIZATION SYSTEM Depressurization (41) including: Primary containment pressure (CFR: 41.7 / 45.7) 223002 (SF5 PCIS) Primary 03 A4.03 - Ability to manually operate and/or monitor 3.6 1 in the control room: Reset system isolations Containment Isolation/Nuclear Steam (42)

(CFR: 41.7 / 45.5 to 45.8)

Supply Shutoff 239002 (SF3 SRV) Safety Relief 07 A1.07 - Ability to predict and/or monitor changes in 2.9 1 parameters associated with operating the Valves (43)

RELIEF/SAFETY VALVES controls including:

Turbine load.

(CFR: 41.5 / 45.5)

G2.4.50 - Ability to verify system alarm setpoints 1

04. and operate controls identified in the alarm 4.2 (44) 50 response manual.

(CFR: 41.10 / 43.5 / 45.3) 259002 (SF2 RWLCS) Reactor Water 05 K1.05 - Knowledge of the physical connections 3.6 1 and/or cause-effect relationships between Level Control (45)

REACTOR WATER LEVEL CONTROL SYSTEM and the following: Reactor feedwater system (CFR: 41.2 to 41.9 / 45.7 to 45.8) 261000 (SF9 SGTS) Standby Gas 03 K3.03 - Knowledge of the effect that a loss or 3.2 1 malfunction of the STANDBY GAS TREATMENT Treatment (46)

SYSTEM will have on the following: Primary containment pressure: Mark-I&II (CFR: 41.7 / 45.6) 262001 (SF6 AC) AC Electrical 01 K2.01 - Knowledge of electrical power supplies to 3.3 1 the following: Off-site sources of power.

Distribution (47)

(CFR: 41.7)

K4.03 - Knowledge of AC ELECTRICAL 03 3.1 1 DISTRIBUTION design feature(s) and/or interlocks which provide for the following: Interlocks between (48) automatic bus transfer and breakers (CFR: 41.7) 262002 (SF6 UPS) Uninterruptable 01 K4.01 - Knowledge of UNINTERRUPTABLE 3.1 1 POWER SUPPLY (AC/DC) design feature(s)

Power Supply (AC/DC) (49) and/or interlocks which provide for the following:

Transfer from preferred power to alternate power (CFR: 41.7) 263000 (SF6 DC) DC Electrical 01 K5.01 - Knowledge of the operational implications 2.6 1 of the following concepts as they apply to DC Distribution (50)

ELECTRICAL DISTRIBUTION: Hydrogen generation during battery charging (CFR: 41.5 / 45.3) 264000 (SF6 EGE) Emergency 03 K6.03 - Knowledge of the effect that a loss or 3.5 1 malfunction of the following will have on the Generators (Diesel/Jet) EDG (51)

EMERGENCY GENERATORS (DIESEL/JET):

Lube oil pumps.

(CFR: 41.7 / 45.7) 300000 (SF8 IA) Instrument Air 04. G2.4.31 - Knowledge of annunciator alarms, 4.2 1 indications, or response procedures.

31 (52)

(CFR: 41.10 / 45.3)

ES-401 7 Form ES-401-1 400000 (SF8 CCS) Component 03 A1.03 - Ability to predict and/or monitor changes in 2.7 1 parameters with operating the CCWS controls Cooling Water (53) including: CCW pressure.

(CFR: 41.5 / 45.5) 510000 (SF4 SWS*) Service Water (Normal and Emergency)

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

ES-401 8 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 201002 (SF1 RMCS) Reactor Manual Control 201003 (SF1 CRDM) Control Rod and Drive A3.01 - Ability to monitor automatic operations of 1 01 the CONTROL ROD AND DRIVE MECHANISM 3.7 Mechanism including: Control rod position (54)

(CFR: 41.7 / 45.7) 201004 (SF7 RSCS) Rod Sequence Control 201005 (SF1, SF7 RCIS) Rod Control and Information 201006 (SF7 RWMS) Rod Worth Minimizer A4.05 - Ability to manually operate and/or monitor 1 05 in the control room: Rod insert error indication: plant 3.2 specific (55)

(CFR: 41.7 / 45.5 to 45.8) 202001 (SF1, SF4 RS) Recirculation 202002 (SF1 RSCTL) Recirculation Flow Control 204000 (SF2 RWCU) Reactor Water G2.4.47 - Ability to diagnose and recognize trends 1

04. in an accurate and timely manner utilizing the 4.2 Cleanup 47 appropriate control room reference material. (56)

(CFR: 41.10 / 43.5 / 45.12) 214000 (SF7 RPIS) Rod Position Information 215001 (SF7 TIP) Traversing In-Core Probe K1.01 - Knowledge of the physical connections 1 01 and/or cause-effect relationships between 2.5 TRAVERSING IN-CORE PROBE and the following: (57)

Local power range monitors (CFR: 41.2 to 41.9 / 45.7 to 45.8) 215002 (SF7 RBMS) Rod Block Monitor 216000 (SF7 NBI) Nuclear Boiler Instrumentation 219000 (SF5 RHR SPC) RHR/LPCI: K2.02 - Knowledge of electrical power supplies to 1 02 the following: Pumps 3.1*

Torus/Suppression Pool Cooling Mode (CFR: 41.7) (58) 223001 (SF5 PCS) Primary Containment and Auxiliaries 226001 (SF5 RHR CSS) RHR/LPCI: K3.03 - Knowledge of the effect that a loss or 1 03 malfunction of the RHR/LPCI: CONTAINMENT 2.9 Containment Spray Mode SPRAY SYSTEM MODE will have on the following: (59)

Containment/drywell/suppression chamber components, continued operation with elevated pressure and/or temperature and/or level.

(CFR: 41.7 / 45.4) 230000 (SF5 RHR SPS) RHR/LPCI:

Torus/Suppression Pool Spray Mode 233000 (SF9 FPCCU) Fuel Pool K4.06 - Knowledge of FUEL POOL COOLING AND 1 06 CLEAN-UP design feature(s) and/or interlocks 2.9 Cooling/Cleanup which provide for the following: Maintenance of (60) adequate pool level (CFR: 41.7) 234000 (SF8 FH) Fuel-Handling Equipment 239001 (SF3, SF4 MRSS) Main and Reheat K5.09 - Knowledge of the operational implications 1 09 of the following concepts as they apply to MAIN 3.4 Steam AND REHEAT STEAM SYSTEM: Decay heat (61) removal (CFR: 41.5 / 45.3) 239003 (SF9 MSVLCS) Main Steam Isolation Valve Leakage Control 241000 (SF3 RTPRS) Reactor/Turbine Pressure Regulating 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 256000 (SF2 CDS) Condensate

ES-401 9 Form ES-401-1 259001 (SF2 FWS) Feedwater K6.04 - Knowledge of the effect that a loss or 1 04 malfunction of the following will have on the 2.8 REACTOR FEEDWATER SYSTEM: Extraction (62) steam (CFR: 41.7 / 45.7) 268000 (SF9 RW) Radwaste 271000 (SF9 OG) Offgas 272000 (SF7, SF9 RMS) Radiation Monitoring 286000 (SF8 FPS) Fire Protection A1.05 - Ability to predict and/or monitor changes in 1 05 parameters associated with operating the FIRE 3.2 PROTECTION SYSTEM controls including: System (63) lineups (CFR: 41.5 / 45.5) 288000 (SF9 PVS) Plant Ventilation A2.04 - Ability to (a) predict the impacts of the 1 04 following on the PLANT VENTILATION SYSTEMS 3.7 and (b) based on those predictions, use procedures (64) to correct, control, or mitigate the consequences of those abnormal conditions or operations: High radiation: Plant-Specific (CFR: 41.5 / 45.6) 290001 (SF5 SC) Secondary Containment A3.01 - Ability to monitor automatic operations of 1 01 the SECONDARY CONTAINMENT including: 3.9 Secondary containment isolation (65)

(CFR: 41.7 / 45.7) 290003 (SF9 CRV) Control Room Ventilation 290002 (SF4 RVI) Reactor Vessel Internals 51001 (SF8 CWS*) Circulating Water K/A Category Point Totals: 1 1 1 1 1 1 1 1 2 1 1 Group Point Total: 12

ES-401 10 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 #

G2.4.18 - Knowledge of the specific bases for EOPs 295001 (APE 1) Partial or Complete Loss of 1

04. (CFR:41.10 / 43.1 / 45.13) 4.0 Forced Core Flow Circulation / 1 & 4 18 (76) 295003 (APE 3) Partial or Complete Loss of AC Power / 6 AA2.02 - Ability to determine and/or interpret the 295004 (APE 4) Partial or Complete Loss of 1 02 following as they apply to PARTIAL OR COMPLETE 3.9 DC Power / 6 LOSS OF DC POWER: Extent of partial or complete loss (77) of DC power (CFR: 41.10 / 43.5 / 45.13) 295005 (APE 5) Main Turbine Generator Trip /

3 295006 (APE 6) Scram / 1 G2.4.8 - Knowledge of how abnormal operating 295016 (APE 16) Control Room Abandonment 1

04. procedures are used in conjunction with EOPs 4.5

/7 08 (CFR: 41.10 / 43.5 / 45.13) (78) 295018 (APE 18) Partial or Complete Loss of CCW / 8 295019 (APE 19) Partial or Complete Loss of Instrument Air / 8 AA2.06 - Ability to determine and/or interpret the 295021 (APE 21) Loss of Shutdown Cooling / 1 06 following as they apply to LOSS OF SHUTDOWN 3.3 4 COOLING: Reactor pressure (79)

(CFR: 41.10 / 43.5 / 45.13) 295023 (APE 23) Refueling Accidents / 8 G2.4.41 - Knowledge of the emergency action level 295024 High Drywell Pressure / 5 1

04. thresholds and classifications. 4.6 41 (CFR: 41.10 / 43.5 / 45.11) (80) 295025 (EPE 2) High Reactor Pressure / 3 EA2.02 - Ability to determine and/or interpret the 295026 (EPE 3) Suppression Pool High Water 1 02 following as they apply to SUPPRESSION POOL HIGH 3.9 Temperature / 5 WATER TEMPERATURE: Suppression pool level. (81)

(CFR: 41.10 / 43.5 / 45.13) 295027 (EPE 4) High 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 295031 (EPE 8) Reactor Low Water Level / 2 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 295038 (EPE 15) High Offsite Radioactivity Release Rate / 9 600000 (APE 24) Plant Fire On Site / 8 G2.1.32 - Ability to explain and apply system limits and 700000 (APE 25) Generator Voltage and 1

01. precautions. 4.0 Electric Grid Disturbances / 6 32 (CFR: 41.10 / 43.2 / 45.12) (82)

K/A Category Totals: 0 0 0 0 3 4 Group Point Total: 7

ES-401 11 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 Vacuum / 3 295007 (APE 7) High Reactor Pressure / 3 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 Temperature (Mark III Containment only) / 5 AA2.02 - Ability to determine and/or interpret the 295012 (APE 12) High Drywell Temperature / 02 following as they apply to HIGH DRYWELL 4.1 1 5 TEMPERATURE: Drywell pressure (CFR: 41.10 / 43.5 / 45.13) (83) 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 G2.1.7 - Ability to evaluate plant performance and 295029 (EPE 6) High Suppression Pool Water 01. make operational judgements based on operating 4.7 1 Level / 5 07 characteristics, reactor behavior, and instrument interpretation. (84)

(CFR: 41.5 / 43.5 / 45.12 / 45.13) 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 295035 (EPE 12) Secondary Containment High Differential Pressure / 5 EA2.03 - Ability to determine and/or interpret the 295036 (EPE 13) Secondary Containment 03 following as they apply to SECONDARY 3.8 1 High Sump/Area Water Level / 5 CONTAINMENT HIGH SUMP/AREA WATER LEVEL: Cause of the high water level (85)

(CFR: 41.10 / 43.5 / 45.13) 500000 (EPE 16) High Containment Hydrogen Concentration / 5 K/A Category Point Totals: 0 0 0 0 2 1 Group Point Total: 3

ES-401 12 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 Coolant Injection 207000 (SF4 IC) Isolation (Emergency) Condenser 209001 (SF2, SF4 LPCS)

Low-Pressure Core Spray 209002 (SF2, SF4 HPCS)

High-Pressure Core Spray 211000 (SF1 SLCS) Standby Liquid 02 A2.02 - Ability to (a) predict the impacts of the 3.9 1 following on the STANDBY LIQUID CONTROL Control (86)

SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure of explosive valve to fire.

(CFR: 41.5 / 43.5 / 45.6) 212000 (SF7 RPS) Reactor Protection 01. G2.1.23 - Ability to perform specific system and 4.4 1 integrated plant procedures during all modes of 23 (87) plant operation.

(CFR: 41.10 / 43.5 / 45.2 / 45.6) 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 Depressurization 223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff 239002 (SF3 SRV) Safety Relief Valves 259002 (SF2 RWLCS) Reactor Water Level Control 261000 (SF9 SGTS) Standby Gas Treatment 262001 (SF6 AC) AC Electrical Distribution 262002 (SF6 UPS) Uninterruptable 01 A2.01 - Ability to (a) predict the impacts of the 2.8 1 following on the UNINTERRUPTABLE POWER Power Supply (AC/DC) (88)

SUPPLY (AC/DC), and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Under voltage.

(CFR: 41.5 / 43.5 / 45.6) 263000 (SF6 DC) DC Electrical Distribution 264000 (SF6 EGE) Emergency 02. G2.2.40 - Ability to apply Technical Specifications 4.7 1 for a system.

Generators (Diesel/Jet) EDG 40 (89)

(CFR: 41.10 / 43.2 / 43.5 / 45.3)

ES-401 13 Form ES-401-1 300000 (SF8 IA) Instrument Air 01 A2.01 - Ability to (a) predict the impacts of the 2.8 1 following on the INSTRUMENT AIR SYSTEM and (b) based on those predictions, use procedures to (90) correct, control, or mitigate the consequences of those abnormal operation: Air dryer and filter malfunctions.

(CFR: 41.5 / 43.5 / 45.6) 400000 (SF8 CCS) Component Cooling Water 510000 (SF4 SWS*) Service Water (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 14 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 201005 (SF1, SF7 RCIS) Rod Control and Information 201006 (SF7 RWMS) Rod Worth Minimizer 202001 (SF1, SF4 RS) Recirculation 202002 (SF1 RSCTL) Recirculation Flow Control 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 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 A1.03 - Ability to predict and/or monitor changes in 03 parameters associated with operating the FUEL 3.9 1 HANDLING EQUIPMENT controls including: Core (91) reactivity level.

(CFR: 41.5 / 45.5) 239001 (SF3, SF4 MRSS) Main and Reheat Steam 239003 (SF9 MSVLCS) Main Steam Isolation 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 268000 (SF9 RW) Radwaste G2.2.38 - Knowledge of conditions and limitations in

02. 4.5 1 the facility license.

38 (CFR: 41.7 / 41.10 / 43.1 / 45.13) (92) 271000 (SF9 OG) Offgas A2.04 - Ability to (a) predict the impacts of the 04 following on the OFFGAS SYSTEM and (b) based 4.1 1 on those predictions, use procedures to correct, (93) control, or mitigate the consequences of those abnormal conditions or operations: Offgas system high radiation (CFR: 41.5 / 43.5 / 45.6) 272000 (SF7, SF9 RMS) Radiation Monitoring

ES-401 15 Form ES-401-1 286000 (SF8 FPS) Fire Protection 288000 (SF9 PVS) Plant Ventilation 290001 (SF5 SC) Secondary Containment 290003 (SF9 CRV) Control Room Ventilation 290002 (SF4 RVI) Reactor Vessel Internals 51001 (SF8 CWS*) Circulating Water K/A Category Point Totals: 0 0 0 0 0 0 1 1 0 0 1 Group Point Total: 3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Quad Cities Nuclear Power Station, Units 1 and 2 Date of Exam: June 1 - 11, 2021 Category K/A # Topic RO SRO-Only IR # IR #

2.1.13 Knowledge of facility requirements for controlling vital/controlled access. 2.5 1

1. (CFR: 41.10 / 43.5 / 45.9 / 45.10) (66)

Conduct 2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, 3.6 1 of Operations and updates. (67)

(CFR: 41.10 / 45.12 / 45.13) 2.1.37 Knowledge of procedures, guidelines, or limitations associated with 4.3 1 reactivity management. (68)

(CFR: 41.1 / 43.6 / 45.6) 2.1.4 Knowledge of individual licensed operator responsibilities related to shift 3.8 1 staffing, such as medical requirements, no-solo operation, maintenance (94) of active license status, 10CFR55, etc.

(CFR: 41.10 / 43.2) 2.1.39 Knowledge of conservative decision making practices. 4.3 1 (CFR: 41.10 / 43.5 / 45.12) (95)

Subtotal 3 2 2.2.1 Ability to perform pre-startup procedures for the facility, including 4.5 1

2. operating those controls associated with plant equipment that could (69) affect reactivity.

Equipment (CFR: 41.5 / 41.10 / 43.5 / 43.6 / 45.1)

Control 2.2.14 Knowledge of the process for controlling equipment configuration or 3.9 1 status (70)

(CFR: 41.10 / 43.3 / 45.13) 2.2.35 Ability to determine Technical Specification Mode of Operation. 3.6 1 (CFR: 41.7 / 41.10 / 43.2 / 45.13) (71) 2.2.21 Knowledge of pre- and post-maintenance operability requirements. 4.1 1 (CFR: 41.10 / 43.2) (96) 2.2.43 Knowledge of the process used to track inoperable alarms 3.3 1 (CFR: 41.10 / 43.5 / 45.13) (97)

Subtotal 3 2 2.3.7 Ability to comply with radiation work permit requirements during normal 3.5 1

3. or abnormal conditions. (72)

(CFR: 41.12 / 45.10)

Radiation 2.3.13 Knowledge of radiological safety procedures pertaining to licensed 3.4 1 Control operator duties, such as response to radiation monitor alarms, (73) containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

(CFR: 41.12 / 43.4 / 45.9 / 45.10) 2.3.14 Knowledge of radiation or contamination hazards that may arise during 3.8 1 normal, abnormal, or emergency conditions or activities. (98)

(CFR: 41.12 / 43.4 / 45.10)

Subtotal 2 1 2.4.12 Knowledge of general operating crew responsibilities during emergency 4.0 1

4. operations. (74)

(CFR: 41.10 / 45.12)

Emergency 2.4.32 Knowledge of operator response to loss of all annunciators. 3.6 1 Procedures /

(CFR: 41.10 / 43.5 / 45.13) (75)

Plan 2.4.23 Knowledge of the bases for prioritizing emergency procedure 4.4 1 implementation during emergency operations. (99)

(CFR: 41.10 / 43.5 / 45.13) 2.4.38 Ability to take actions called for in the facility emergency plan, including 4.4 1 supporting or acting as emergency coordinator if required. (100)

(CFR: 41.10 / 43.5 / 45.11)

Subtotal 2 2 Tier 3 Point Total 10 7

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