ML22193A321
| ML22193A321 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| 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) | |
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.
Emergency and Abnormal Plant Evolutions 1
3 3
3 N/A 4
4 N/A 3
20 3
4 7
2 1
2 1
1 1
1 7
2 1
3 Tier Totals 4
5 4
5 5
4 27 5
5 10
- 2.
Plant Systems 1
2 2
2 3
2 2
3 3
2 3
2 26 3
2 5
2 1
1 1
1 1
1 1
1 2
1 1
12 1
1 1
3 Tier Totals 3
3 3
4 3
3 4
4 4
4 3
38 5
3 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
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 Forced Core Flow Circulation / 1 & 4 06 AA1.06 - Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:
Neutron monitoring (CFR: 41.7 /45.6) 3.3 1
(1) 295003 (APE 3) Partial or Complete Loss of AC Power / 6 01 AA2.01 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF AC POWER: Cause of partial or complete loss of AC power.
(CFR: 41.10 / 43.2 / 45.6) 3.4 1
(2) 295004 (APE 4) Partial or Total Loss of DC Power / 6 04.
49 G2.4.49 - Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
(CFR: 41.10 /43.5 / 45.13) 4.6 1
(3) 295005 (APE 5) Main Turbine Generator Trip /
3 03 AK1.03 - Knowledge of the operational implications of the following concepts as they apply to MAIN TURBINE GENERATOR TRIP: Pressure effects on reactor level (CFR: 41.8 to 41.10) 3.5 1
(4) 295006 (APE 6) Scram / 1 03 AK2.03 - Knowledge of the interrelations between SCRAM and the following: CRD hydraulic system (CFR: 41.7 / 45.8) 3.7 1
(5) 295016 (APE 16) Control Room Abandonment
/ 7 02 AK3.02 - Knowledge of the reasons for the following responses as they apply to CONTROL ROOM ABANDONMENT: Turbine trip.
(CFR: 41.5 / 45.6) 3.7*
1 (6) 295018 (APE 18) Partial or Complete Loss of CCW / 8 02 AA1.02 - Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: System loads (CFR: 41.7 / 45.6) 3.3 1
(7) 295019 (APE 19) Partial or Complete Loss of Instrument Air / 8 01 AA2.01 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: Instrument air system pressure.
(CFR: 41.10 / 43.5 / 45.13) 3.5 1
(8) 295021 (APE 21) Loss of Shutdown Cooling /
4 04.
09 G2.4.9 - Knowledge of low power/shutdown implications in accident (e.g. loss of coolant accident or loss of residual heat removal) mitigation strategies.
(CFR: 41.10 / 43.5 / 45.13) 3.8 1
(9) 295023 (APE 23) Refueling Accidents / 8 01 AK1.01 -Knowledge of the operational implications of the following concepts as they apply to REFUELING ACCIDENTS: Radiation exposure hazards.
(CFR: 41.8 to 41.10) 3.6 1
(10) 295024 High Drywell Pressure / 5 15 EK2.15 - Knowledge of the interrelations between HIGH DRYWELL PRESSURE and the following:
Containment spray logic: Plant-Specific (CFR: 41.7 / 45.8) 3.8 1
(11) 295025 (EPE 2) High Reactor Pressure / 3 02 EK3.02 - Knowledge of the reasons for the following responses as they apply to HIGH REACTOR PRESSURE: Recirculation pump trip: Plant-Specific (CFR: 41.5 / 45.6) 3.9 1
(12) 295026 (EPE 3) Suppression Pool High Water Temperature / 5 01 EA1.01 - Ability to operate and/or monitor the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Suppression pool cooling.
(CFR: 41.7 / 45.6) 4.1 1
(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 03 EA2.03 - Ability to determine and/or interpret the following as they apply to HIGH DRYWELL TEMPERATURE: Reactor water level (CFR: 41.10 / 43.5 / 45.13) 3.7 1
(14) 295030 (EPE 7) Low Suppression Pool Water Level / 5 04.
01 G2.4.1 - Knowledge of EOP entry conditions and immediate action steps.
(CFR: 41.10 / 43.5 / 45.13) 4.6 1
(15) 295031 (EPE 8) Reactor Low Water Level / 2 01 EK1.01 - Knowledge of the operational implications of the following concepts as they apply to REACTOR LOW WATER LEVEL: Adequate core cooling.
(CFR: 41.8 to 41.10) 4.6*
1 (16)
ES-401 3
Form ES-401-1 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 03 EK2.03 - Knowledge of the interrelations between SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKONWN and the following: ARI/RPT/ATWS: Plant-Specific (CFR: 41.7 / 45.8) 4.1 1
(17) 295038 (EPE 15) High Offsite Radioactivity Release Rate / 9 02 EK3.02 - Knowledge of the reasons for the following responses as they apply to HIGH OFF-SITE RELEASE RATE: System isolations (CFR: 41.5 / 45.6) 3.9 1
(18) 600000 (APE 24) Plant Fire On Site / 8 05 AA1.05 - Ability to operate and/or monitor the following as they apply to PLANT FIRE ON SITE:
Plant and control room ventilation systems (CFR: 41.7 / 45.5 / 45.6) 3.0 1
(19) 700000 (APE 25) Generator Voltage and Electric Grid Disturbances / 6 09 AA2.09 - Ability to determine and/or interpret the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Operational status of emergency diesel generators (CFR: 41.5 / 43.5 / 45.5 / 45.7 / 45.8) 3.9 1
(20)
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 295007 (APE 7) High Reactor Pressure / 3 04 AK2.04 - Knowledge of the interrelations between HIGH REACTOR PRESSURE and the following:
LPCS (CFR: 41.7 / 45.8) 3.2 1
(21) 295008 (APE 8) High Reactor Water Level / 2 295009 (APE 9) Low Reactor Water Level / 2 01 AK3.01 - Knowledge of the reasons for the following responses as they apply to LOW REACTOR WATER LEVEL: Recirculation pump run back: Plant-Specific (CFR: 41.5 / 45.6) 3.2 1
(22) 295010 (APE 10) High Drywell Pressure / 5 03 AA1.03 - Ability to operate and/or monitor the following as they apply to HIGH DRYWELL PRESSURE: Nitrogen makeup: Plant-Specific (CFR: 41.7 / 45.6) 2.6 1
(23) 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 295015 (APE 15) Incomplete Scram / 1 02 AA2.02 - Ability to determine and/or interpret the following as they apply to INCOMPLETE SCRAM:
Control rod position (CFR: 41.10 / 43.5 / 45.13) 4.1*
1 (24) 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 01.
20 G2.1.20 - Ability to interpret and execute procedure steps.
(CFR: 41.10 / 43.5 / 45.12) 4.6 1
(25) 295029 (EPE 6) High Suppression Pool Water Level / 5 295032 (EPE 9) High Secondary Containment Area Temperature / 5 01 EK1.01 - Knowledge of the operational implications of the following concepts as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE: Personnel protection (CFR: 41.8 to 41.10) 3.6 1
(26) 295033 (EPE 10) High Secondary Containment Area Radiation Levels / 9 295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9 04 EK2.04 - Knowledge of the interrelations between SECONDARY CONTAINMENT VENTILATION HIGH RADIATION and the following: Secondary containment ventilation (CFR: 41.7 / 45.8) 3.9 1
(27) 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)
RHR/LPCI: Injection Mode 05 A4.05 - Ability to manually operate and/or monitor in the control room: Manual initiation controls (CFR: 41.7 / 45.5 to 45.8) 4.3*
1 (28) 205000 (SF4 SCS) Shutdown Cooling 06
- 02.
12 A2.06 - Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE); and (b) 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)
G2.2.12 - Knowledge of surveillance procedures.
(CFR: 41.10 / 45.13) 3.4 3.7 1
(29) 1 (30) 206000 (SF2, SF4 HPCIS)
High-Pressure Coolant Injection 13 K1.13 - Knowledge of the physical connections and/or cause-effect relationship between HIGH PRESSURE COOLANT INJECTION SYSTEM and the following: Main condenser: BWR-2,3,4 (CFR: 41.2 to 41.9 / 45.7,8) 2.8*
1 (31) 207000 (SF4 IC) Isolation (Emergency) Condenser 209001 (SF2, SF4 LPCS)
Low-Pressure Core Spray 03 K2.03 - Knowledge of electrical power supplies to the following: Initiation logic (CFR: 41.7) 2.9*
1 (32) 209002 (SF2, SF4 HPCS)
High-Pressure Core Spray 211000 (SF1 SLCS) Standby Liquid Control 03 K3.03 - Knowledge of the effect that a loss or malfunction of the STANDBY LIQUID CONTROL SYSTEM will have on the following: Core plate differential pressure indication.
(CFR: 41.7 / 45.4) 2.6*
1 (33) 212000 (SF7 RPS) Reactor Protection System 07 K4.07 - Knowledge of REACTOR PROTECTION SYSTEM design feature(s) and/or interlocks which provide for the following: Manual system activation (trip)
(CFR: 41.7) 4.1*
1 (34) 215003 (SF7 IRM)
Intermediate-Range Monitor 01 04 K5.01 - Knowledge of the operational implications of the following concepts as they apply to INTERMEDIATE RANGE MONITOR (IRM)
SYSTEM: Detector operation.
(CFR: 41.5 / 45.3)
A3.04 - Ability to monitor automatic operation of the INTERMEDIATE RANGE MONITOR (IRM)
SYSTEM including: Control rod block status (CFR: 41.7 / 45.7) 2.6 3.5 1
(35) 1 (36) 215004 (SF7 SRMS) Source-Range Monitor 02 K6.02 - Knowledge of the effect that a loss or malfunction of the following will have on the SOURCE RANGE MONITOR (SRM) SYSTEM:
24/48 volt DC power (CFR: 41.7 / 45.7) 3.1 1
(37) 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor 07 A1.07 - Ability to predict and/or monitor changes in parameters associated with operating the AVERAGE POWER RANGE MONITORING/
LOCAL POWER RANGE MONITORING SYSTEM controls including: APRM (gain adjustment factor).
(CFR: 41.5 / 45.5) 3.0 1
(38)
ES-401 6
Form ES-401-1 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling 08 02 A2.08 - Ability to (a) predict the impacts of the following on the REACTOR 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: Loss of lube oil cooling.
(CFR: 41.5 / 45.6)
A3.02 - Ability to monitor automatic operations of the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) including: Turbine startup.
(CFR: 41.7 / 45.7) 3.0 3.6 1
(39) 1 (40) 218000 (SF3 ADS) Automatic Depressurization 04 A3.04 - Ability to monitor automatic operations of the AUTOMATIC DEPRESSURIZATION SYSTEM including: Primary containment pressure (CFR: 41.7 / 45.7) 3.7 1
(41) 223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff 03 A4.03 - Ability to manually operate and/or monitor in the control room: Reset system isolations (CFR: 41.7 / 45.5 to 45.8) 3.6 1
(42) 239002 (SF3 SRV) Safety Relief Valves 07
- 04.
50 A1.07 - Ability to predict and/or monitor changes in parameters associated with operating the RELIEF/SAFETY VALVES controls including:
Turbine load.
(CFR: 41.5 / 45.5)
G2.4.50 - Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
(CFR: 41.10 / 43.5 / 45.3) 2.9 4.2 1
(43) 1 (44) 259002 (SF2 RWLCS) Reactor Water Level Control 05 K1.05 - Knowledge of the physical connections and/or cause-effect relationships between REACTOR WATER LEVEL CONTROL SYSTEM and the following: Reactor feedwater system (CFR: 41.2 to 41.9 / 45.7 to 45.8) 3.6 1
(45) 261000 (SF9 SGTS) Standby Gas Treatment 03 K3.03 - Knowledge of the effect that a loss or malfunction of the STANDBY GAS TREATMENT SYSTEM will have on the following: Primary containment pressure: Mark-I&II (CFR: 41.7 / 45.6) 3.2 1
(46) 262001 (SF6 AC) AC Electrical Distribution 01 03 K2.01 - Knowledge of electrical power supplies to the following: Off-site sources of power.
(CFR: 41.7)
K4.03 - Knowledge of AC ELECTRICAL DISTRIBUTION design feature(s) and/or interlocks which provide for the following: Interlocks between automatic bus transfer and breakers (CFR: 41.7) 3.3 3.1 1
(47) 1 (48) 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC) 01 K4.01 - Knowledge of UNINTERRUPTABLE POWER SUPPLY (AC/DC) design feature(s) and/or interlocks which provide for the following:
Transfer from preferred power to alternate power (CFR: 41.7) 3.1 1
(49) 263000 (SF6 DC) DC Electrical Distribution 01 K5.01 - Knowledge of the operational implications of the following concepts as they apply to DC ELECTRICAL DISTRIBUTION: Hydrogen generation during battery charging (CFR: 41.5 / 45.3) 2.6 1
(50) 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG 03 K6.03 - Knowledge of the effect that a loss or malfunction of the following will have on the EMERGENCY GENERATORS (DIESEL/JET):
Lube oil pumps.
(CFR: 41.7 / 45.7) 3.5 1
(51) 300000 (SF8 IA) Instrument Air
- 04.
31 G2.4.31 - Knowledge of annunciator alarms, indications, or response procedures.
(CFR: 41.10 / 45.3) 4.2 1
(52)
ES-401 7
Form ES-401-1 400000 (SF8 CCS) Component Cooling Water 03 A1.03 - Ability to predict and/or monitor changes in parameters with operating the CCWS controls including: CCW pressure.
(CFR: 41.5 / 45.5) 2.7 1
(53) 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 Mechanism 01 A3.01 - Ability to monitor automatic operations of the CONTROL ROD AND DRIVE MECHANISM including: Control rod position (CFR: 41.7 / 45.7) 3.7 1
(54) 201004 (SF7 RSCS) Rod Sequence Control 201005 (SF1, SF7 RCIS) Rod Control and Information 201006 (SF7 RWMS) Rod Worth Minimizer 05 A4.05 - Ability to manually operate and/or monitor in the control room: Rod insert error indication: plant specific (CFR: 41.7 / 45.5 to 45.8) 3.2 1
(55) 202001 (SF1, SF4 RS) Recirculation 202002 (SF1 RSCTL) Recirculation Flow Control 204000 (SF2 RWCU) Reactor Water Cleanup 04.
47 G2.4.47 - Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
(CFR: 41.10 / 43.5 / 45.12) 4.2 1
(56) 214000 (SF7 RPIS) Rod Position Information 215001 (SF7 TIP) Traversing In-Core Probe 01 K1.01 - Knowledge of the physical connections and/or cause-effect relationships between TRAVERSING IN-CORE PROBE and the following:
Local power range monitors (CFR: 41.2 to 41.9 / 45.7 to 45.8) 2.5 1
(57) 215002 (SF7 RBMS) Rod Block Monitor 216000 (SF7 NBI) Nuclear Boiler Instrumentation 219000 (SF5 RHR SPC) RHR/LPCI:
Torus/Suppression Pool Cooling Mode 02 K2.02 - Knowledge of electrical power supplies to the following: Pumps (CFR: 41.7) 3.1*
1 (58) 223001 (SF5 PCS) Primary Containment and Auxiliaries 226001 (SF5 RHR CSS) RHR/LPCI:
Containment Spray Mode 03 K3.03 - Knowledge of the effect that a loss or malfunction of the RHR/LPCI: CONTAINMENT SPRAY SYSTEM MODE will have on the following:
Containment/drywell/suppression chamber components, continued operation with elevated pressure and/or temperature and/or level.
(CFR: 41.7 / 45.4) 2.9 1
(59) 230000 (SF5 RHR SPS) RHR/LPCI:
Torus/Suppression Pool Spray Mode 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup 06 K4.06 - Knowledge of FUEL POOL COOLING AND CLEAN-UP design feature(s) and/or interlocks which provide for the following: Maintenance of adequate pool level (CFR: 41.7) 2.9 1
(60) 234000 (SF8 FH) Fuel-Handling Equipment 239001 (SF3, SF4 MRSS) Main and Reheat Steam 09 K5.09 - Knowledge of the operational implications of the following concepts as they apply to MAIN AND REHEAT STEAM SYSTEM: Decay heat removal (CFR: 41.5 / 45.3) 3.4 1
(61) 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 04 K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR FEEDWATER SYSTEM: Extraction steam (CFR: 41.7 / 45.7) 2.8 1
(62) 268000 (SF9 RW) Radwaste 271000 (SF9 OG) Offgas 272000 (SF7, SF9 RMS) Radiation Monitoring 286000 (SF8 FPS) Fire Protection 05 A1.05 - Ability to predict and/or monitor changes in parameters associated with operating the FIRE PROTECTION SYSTEM controls including: System lineups (CFR: 41.5 / 45.5) 3.2 1
(63) 288000 (SF9 PVS) Plant Ventilation 04 A2.04 - Ability to (a) predict the impacts of the following on the PLANT VENTILATION SYSTEMS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High radiation: Plant-Specific (CFR: 41.5 / 45.6) 3.7 1
(64) 290001 (SF5 SC) Secondary Containment 01 A3.01 - Ability to monitor automatic operations of the SECONDARY CONTAINMENT including:
Secondary containment isolation (CFR: 41.7 / 45.7) 3.9 1
(65) 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 295001 (APE 1) Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 04.
18 G2.4.18 - Knowledge of the specific bases for EOPs (CFR:41.10 / 43.1 / 45.13) 4.0 1
(76) 295003 (APE 3) Partial or Complete Loss of AC Power / 6 295004 (APE 4) Partial or Complete Loss of DC Power / 6 02 AA2.02 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF DC POWER: Extent of partial or complete loss of DC power (CFR: 41.10 / 43.5 / 45.13) 3.9 1
(77) 295005 (APE 5) Main Turbine Generator Trip /
3 295006 (APE 6) Scram / 1 295016 (APE 16) Control Room Abandonment
/ 7 04.
08 G2.4.8 - Knowledge of how abnormal operating procedures are used in conjunction with EOPs (CFR: 41.10 / 43.5 / 45.13) 4.5 1
(78) 295018 (APE 18) Partial or Complete Loss of CCW / 8 295019 (APE 19) Partial or Complete Loss of Instrument Air / 8 295021 (APE 21) Loss of Shutdown Cooling /
4 06 AA2.06 - Ability to determine and/or interpret the following as they apply to LOSS OF SHUTDOWN COOLING: Reactor pressure (CFR: 41.10 / 43.5 / 45.13) 3.3 1
(79) 295023 (APE 23) Refueling Accidents / 8 295024 High Drywell Pressure / 5 04.
41 G2.4.41 - Knowledge of the emergency action level thresholds and classifications.
(CFR: 41.10 / 43.5 / 45.11) 4.6 1
(80) 295025 (EPE 2) High Reactor Pressure / 3 295026 (EPE 3) Suppression Pool High Water Temperature / 5 02 EA2.02 - Ability to determine and/or interpret the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Suppression pool level.
(CFR: 41.10 / 43.5 / 45.13) 3.9 1
(81) 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 700000 (APE 25) Generator Voltage and Electric Grid Disturbances / 6 01.
32 G2.1.32 - Ability to explain and apply system limits and precautions.
(CFR: 41.10 / 43.2 / 45.12) 4.0 1
(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 295012 (APE 12) High Drywell Temperature /
5 02 AA2.02 - Ability to determine and/or interpret the following as they apply to HIGH DRYWELL TEMPERATURE: Drywell pressure (CFR: 41.10 / 43.5 / 45.13) 4.1 1
(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 295029 (EPE 6) High Suppression Pool Water Level / 5 01.
07 G2.1.7 - Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation.
(CFR: 41.5 / 43.5 / 45.12 / 45.13) 4.7 1
(84) 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 295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5 03 EA2.03 - Ability to determine and/or interpret the following as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL: Cause of the high water level (CFR: 41.10 / 43.5 / 45.13) 3.8 1
(85) 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 Control 02 A2.02 - Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL 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) 3.9 1
(86) 212000 (SF7 RPS) Reactor Protection
- 01.
23 G2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation.
(CFR: 41.10 / 43.5 / 45.2 / 45.6) 4.4 1
(87) 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 Power Supply (AC/DC) 01 A2.01 - Ability to (a) predict the impacts of the following on 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: Under voltage.
(CFR: 41.5 / 43.5 / 45.6) 2.8 1
(88) 263000 (SF6 DC) DC Electrical Distribution 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG
- 02.
40 G2.2.40 - Ability to apply Technical Specifications for a system.
(CFR: 41.10 / 43.2 / 43.5 / 45.3) 4.7 1
(89)
ES-401 13 Form ES-401-1 300000 (SF8 IA) Instrument Air 01 A2.01 - Ability to (a) predict the impacts of the following on the INSTRUMENT AIR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation: Air dryer and filter malfunctions.
(CFR: 41.5 / 43.5 / 45.6) 2.8 1
(90) 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 03 A1.03 - Ability to predict and/or monitor changes in parameters associated with operating the FUEL HANDLING EQUIPMENT controls including: Core reactivity level.
(CFR: 41.5 / 45.5) 3.9 1
(91) 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 02.
38 G2.2.38 - Knowledge of conditions and limitations in the facility license.
(CFR: 41.7 / 41.10 / 43.1 / 45.13) 4.5 1
(92) 271000 (SF9 OG) Offgas 04 A2.04 - Ability to (a) predict the impacts of the following on the OFFGAS SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Offgas system high radiation (CFR: 41.5 / 43.5 / 45.6) 4.1 1
(93) 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
- 1.
Conduct of Operations 2.1.13 Knowledge of facility requirements for controlling vital/controlled access.
(CFR: 41.10 / 43.5 / 45.9 / 45.10) 2.5 1
(66) 2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and updates.
(CFR: 41.10 / 45.12 / 45.13) 3.6 1
(67) 2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management.
(CFR: 41.1 / 43.6 / 45.6) 4.3 1
(68) 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.
(CFR: 41.10 / 43.2) 3.8 1
(94) 2.1.39 Knowledge of conservative decision making practices.
(CFR: 41.10 / 43.5 / 45.12) 4.3 1
(95)
Subtotal 3
2
- 2.
Equipment Control 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.
(CFR: 41.5 / 41.10 / 43.5 / 43.6 / 45.1) 4.5 1
(69) 2.2.14 Knowledge of the process for controlling equipment configuration or status (CFR: 41.10 / 43.3 / 45.13) 3.9 1
(70) 2.2.35 Ability to determine Technical Specification Mode of Operation.
(CFR: 41.7 / 41.10 / 43.2 / 45.13) 3.6 1
(71) 2.2.21 Knowledge of pre-and post-maintenance operability requirements.
(CFR: 41.10 / 43.2) 4.1 1
(96) 2.2.43 Knowledge of the process used to track inoperable alarms (CFR: 41.10 / 43.5 / 45.13) 3.3 1
(97)
Subtotal 3
2
- 3.
Radiation Control 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions.
(CFR: 41.12 / 45.10) 3.5 1
(72) 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
(CFR: 41.12 / 43.4 / 45.9 / 45.10) 3.4 1
(73) 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
(CFR: 41.12 / 43.4 / 45.10) 3.8 1
(98)
Subtotal 2
1
- 4.
Emergency Procedures /
Plan 2.4.12 Knowledge of general operating crew responsibilities during emergency operations.
(CFR: 41.10 / 45.12) 4.0 1
(74) 2.4.32 Knowledge of operator response to loss of all annunciators.
(CFR: 41.10 / 43.5 / 45.13) 3.6 1
(75) 2.4.23 Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.
(CFR: 41.10 / 43.5 / 45.13) 4.4 1
(99) 2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required.
(CFR: 41.10 / 43.5 / 45.11) 4.4 1
(100)
Subtotal 2
2 Tier 3 Point Total 10 7