ML23079A191
| ML23079A191 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/17/2022 |
| From: | NRC/RGN-III/DORS/OB |
| To: | Exelon Generation Co |
| Theodore Wingfield | |
| Shared Package | |
| ML22125A065 | List: |
| References | |
| Download: ML23079A191 (1) | |
Text
Page 1 of 14 Form 4.1-BWR Boiling-Water Reactor Examination Outline Facility: Quad Cities K/A Catalog Rev. 3 Rev. 12/09/2022 Date of Exam: 1/30/2023 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
4 3
3 3
4 3
20 4
3 7
2 1
1 1
1 1
1 6
1 2
3 Tier Totals 5
4 4
4 5
4 26 5
5 10
- 2.
Plant Systems 1
3 2
3 2
2 3
2 2
2 3
2 26 3
2 5
2 1
1 1
1 2
0 1
1 1
1 1
11 0
2 1
3 Tier Totals 4
3 4
3 4
3 3
3 3
4 3
37 5
3 8
- 3.
Generic Knowledge and Abilities Categories CO EC RC EM 6
CO EC RC EM 7
2 2
1 1
2 2
1 2
- 4. Theory Reactor Theory Thermodynamics 6
3 3
Notes: CO =
EM =
Conduct of Operations; EC = Equipment Control; RC = Radiation Control; Emergency Procedures/Plan These systems/evolutions may be eliminated from the sample when Revision 2 of the K/A catalog is used to develop the sample plan.
These systems/evolutions are only included as part of the sample (as applicable to the facility) when Revision 2 of the K/A catalog is used to develop the sample plan.
Page 2 of 14 ES-4.1-BWR BWR Examination Outline (Quad Cities)
Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)
Item #
E/APE # / Name /
Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR Q#
1 (295001) (APE 1)
PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION X
(295001AK1.03) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (APE 1) PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: (CFR: 41.8 to 41.10) Thermal limits 4.1 1
2 (295003) (APE 3)
PARTIAL OR COMPLETE LOSS OF AC POWER X
(295003AK3.06) Knowledge of the reasons for the following responses or actions as they apply to (APE 3) PARTIAL OR COMPLETE LOSS OF AC POWER: (CFR: 41.5 / 45.6)
Containment isolation 3.5 2
3 (295003) (APE 3)
PARTIAL OR COMPLETE LOSS OF AC POWER X (295003) (APE 3) PARTIAL OR COMPLETE LOSS OF AC POWER (G2.2.1) EQUIPMENT CONTROL 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) 4.4 76 4
(295004) (APE 4)
PARTIAL OR COMPLETE LOSS OF DC POWER X
(295004AA2.04) Ability to determine or interpret the following as they apply to (APE 4) PARTIAL OR COMPLETE LOSS OF DC POWER: (CFR: 41.10 / 43.5 / 45.13) System lineups 3.2 3
5 (295005) (APE 5) MAIN TURBINE GENERATOR TRIP X
(295005AA2.06) Ability to determine or interpret the following as they apply to (APE 5) MAIN TURBINE GENERATOR TRIP: (CFR: 41.10 / 43.5 / 45.13) Feedwater temperature 3.5 4
6 (295005) (APE 5) MAIN TURBINE GENERATOR TRIP X (295006) (APE 6) SCRAM (G2.4.14) EMERGENCY PROCEDURES/PLAN Knowledge of general guidelines for emergency and abnormal operating procedures usage (CFR:
41.10 / 43.1 / 45.13) 3.8 5
7 (295006) (APE 6)
SCRAM X
(295006AA2.02) Ability to determine or interpret the following as they apply to (APE 6) SCRAM: (CFR: 41.10 /
43.5 / 45.13) Control rod position 4.5 77 8
(295006) (APE 6)
SCRAM X
(295016AA2.08) Ability to determine or interpret the following as they apply to (APE 16) CONTROL ROOM ABANDONMENT: (CFR: 41.10 / 43.5 / 45.13) Successful transfer 4.3 6
9 (295016) (APE 16)
CONTROL ROOM ABANDONMENT X
(295016AA2.07) Ability to determine or interpret the following as they apply to (APE 16) CONTROL ROOM ABANDONMENT: (CFR: 41.10 / 43.5 / 45.13) Suppression chamber pressure 3.4 78 10 (295018) (APE 18)
PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER (CCW)
X (295018AK3.07) Knowledge of the reasons for the following responses or actions as they apply to (APE 18) PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER (CCW): (CFR: 41.5 / 45.6) Cross-connecting with backup systems 3.1 7
11 (295019) (APE 19)
PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR X
(295019AK2.06) Knowledge of the relationship between the (APE 19) PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the following systems or components: (CFR: 41.7 / 45.8) Offgas system 3.2 8
12 (295019) (APE 19)
PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR X (295021) (APE 21) LOSS OF SHUTDOWN COOLING (G2.2.44) EQUIPMENT CONTROL Ability to interpret control room indications to verify the status and operation of a system and understand how operator actions and directives affect plant and system conditions (CFR: 41.5 / 43.5 / 45.12) 4.2 9
13 (295021) (APE 21)
LOSS OF SHUTDOWN COOLING X (295021) (APE 21) LOSS OF SHUTDOWN COOLING (G2.1.46) CONDUCT OF OPERATIONS Ability to use integrated control systems to operate plant systems or components (CFR: 41.10/ 45.12 / 45.13) 3.3 79 14 (295023) (APE 23)
REFUELING ACCIDENTS X
(295023AA2.01) Ability to determine or interpret the following as they apply to (APE 23) REFUELING ACCIDENTS: (CFR:
41.10 / 43.5 / 45.13) Radiation levels 4.1 10 15 (295024) (EPE 1) HIGH DRYWELL PRESSURE X (295024) (EPE 1) HIGH DRYWELL PRESSURE (G2.4.39)
EMERGENCY PROCEDURES/PLAN Knowledge of RO responsibilities in emergency plan implementing procedures (CFR: 41.10 / 45.11) 3.9 11
Page 3 of 14 ES-4.1-BWR BWR Examination Outline (Quad Cities)
Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)
Item #
E/APE # / Name /
Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR Q#
16 (295025) (EPE 2) HIGH REACTOR PRESSURE X
(295025EA1.03) Ability to operate or monitor the following as they apply to (EPE 2) HIGH REACTOR PRESSURE: (CFR:
41.7 / 45.6) Safety/relief valves 4.4 12 17 (295026) (EPE 3)
SUPPRESSION POOL HIGH WATER TEMPERATURE X
(295026EK1.02) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (EPE 3) SUPPRESSION POOL HIGH WATER TEMPERATURE: (CFR: 41.8 to 41.10)
Heat capacity 4.1 13 (295027) (EPE 4) HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY)
/ 5 18 (295028) (EPE 5) HIGH DRYWELL TEMPERATURE (MARK I AND MARK II ONLY)
X (295028EK2.02) Knowledge of the relationship between the (EPE 5) HIGH DRYWELL TEMPERATURE (MARK I AND MARK II ONLY) and the following systems or components:
(CFR: 41.7 / 45.8) Components internal to the drywell 3.2 14 19 (295028) (EPE 5) HIGH DRYWELL TEMPERATURE (MARK I AND MARK II ONLY)
X (295028EA2.01) Ability to determine or interpret the following as they apply to (EPE 5) HIGH DRYWELL TEMPERATURE (MARK I AND MARK II ONLY): (CFR:
41.10 / 43.5 / 45.13) Drywell temperature 4.2 80 20 (295030) (EPE 7) LOW SUPPRESSION POOL WATER LEVEL X
(295030EK1.02) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (EPE 7) LOW SUPPRESSION POOL WATER LEVEL: (CFR: 41.8 to 41.10) Pump NPSH 3.9 15 21 (295030) (EPE 7) LOW SUPPRESSION POOL WATER LEVEL X
(295030EA2.02) Ability to determine or interpret the following as they apply to (EPE 7) LOW SUPPRESSION POOL WATER LEVEL: (CFR: 41.10 / 43.5 / 45.13)
Suppression pool temperature 3.8 81 22 (295031) (EPE 8)
REACTOR LOW WATER LEVEL X
(295031EA1.07) Ability to operate or monitor the following as they apply to (EPE 8) REACTOR LOW WATER LEVEL:
(CFR: 41.7 / 45.6) Safety/relief valves 4.1 16 23 (295031) (EPE 8)
REACTOR LOW WATER LEVEL X (295031) (EPE 8) REACTOR LOW WATER LEVEL (G2.1.8)
CONDUCT OF OPERATIONS Ability to coordinate personnel activities outside the control room (CFR:
41.10 / 43.1 / 45.5 / 45.12 / 45.13) 4.1 82 24 (295037) (EPE 14)
SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN X
(295037EK1.01) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (EPE 14) SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: (CFR: 41.8 to 41.10)
Reactor pressure effects on reactor power 4.3 17 25 (295038) (EPE 15)
HIGH OFFSITE RADIOACTIVITY RELEASE RATE X
(295038EA1.06) Ability to operate or monitor the following as they apply to (EPE 15) HIGH OFFSITE RADIOACTIVITY RELEASE RATE: (CFR: 41.7 / 45.6) Plant ventilation systems 3.6 18 26 (600000) (APE 24)
PLANT FIRE ON SITE X
(600000AK3.04) Knowledge of the reasons for the following responses or actions as they apply to (APE 24) PLANT FIRE ON SITE: (CFR: 41.5 / 41.10 / 45.6 / 45.13) Actions contained in the fire response procedures for a plant fire on site 3.6 19 27 (700000) (APE 25)
GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES X
(700000AK2.08) Knowledge of the relationship between (APE 25) GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES and the following systems or components:
(CFR: 41.4, 41.5, 41.7, 41.10 / 45.8) Main turbine generator and auxiliary systems 3.1 20 K/A Category Totals:
4 3
3 3
8 6 Group Point Total:
20 / 7
Page 4 of 14 ES-4.1-BWR BWR Examination Outline (Quad Cities)
Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)
Item #
E/APE # / Name /
Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR Q#
(295002) (APE 2)
LOSS OF MAIN CONDENSER VACUUM (295007) (APE 7) HIGH REACTOR PRESSURE
/ 3 28 (295008) (APE 8) HIGH REACTOR WATER LEVEL / 2 X (295008) (APE 8) HIGH REACTOR WATER LEVEL (G2.4.23) EMERGENCY PROCEDURES/PLAN Knowledge of the bases for prioritizing emergency operating procedures implementation (CFR: 41.10 / 43.5 / 45.13) 3.4 21 29 (295009) (APE 9) LOW REACTOR WATER LEVEL / 2 X
(295009AK1.02) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (APE 9) LOW REACTOR WATER LEVEL: (CFR: 41.8 to 41.10) Recirculation pump net positive suction head 3.4 22 30 (295010) (APE 10)
HIGH DRYWELL PRESSURE X
(295010AA2.06) Ability to determine or interpret the following as they apply to (APE 10) HIGH DRYWELL PRESSURE: (CFR: 41.10 / 43.5 / 45.13) Drywell temperature 3.8 83 (295011) (APE 11)
HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY)
/ 5 31 (295012) (APE 12)
HIGH DRYWELL TEMPERATURE / 5 X
(295012AA2.04) Ability to determine or interpret the following as they apply to (APE 12) HIGH DRYWELL TEMPERATURE: (CFR: 41.10 / 43.5 / 45.13)
System/component operating limitations 3.8 23 (295013) (APE 13)
HIGH SUPPRESSION POOL TEMPERATURE.
32 (295014) (APE 14)
INADVERTENT REACTIVITY ADDITION / 1 X
(295014AK2.11) Knowledge of the relationship between the (APE 14) INADVERTENT REACTIVITY ADDITION and the following systems or components: (CFR: 41.7 / 45.8)
Recirculation flow control 3.9 24 (295017) (APE 17)
ABNORMAL OFFSITE RELEASE RATE / 9 (295020) (APE 20)
INADVERTENT CONTAINMENT ISOLATION & 7 (295022) (APE 22)
LOSS OF CONTROL ROD DRIVE PUMPS /
1 (295029) (EPE 6) HIGH SUPPRESSION POOL WATER LEVEL / 5 33 (295032) (EPE 9) HIGH SECONDARY CONTAINMENT AREA TEMPERATURE X
(295032EK3.03) Knowledge of the reasons for the following responses or actions as they apply to (EPE 9) HIGH SECONDARY CONTAINMENT AREA TEMPERATURE:
(CFR: 41.5 / 45.6) Isolating affected systems 4.0 25 (295033) (EPE 10)
HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS
Page 5 of 14 ES-4.1-BWR BWR Examination Outline (Quad Cities)
Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)
Item #
E/APE # / Name /
Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR Q#
34 (295034) (EPE 11)
SECONDARY CONTAINMENT VENTILATION HIGH RADIATION X (295034) (EPE 11) SECONDARY CONTAINMENT VENTILATION HIGH RADIATION (G2.4.16) EMERGENCY PROCEDURES/PLAN Knowledge of emergency and abnormal operating procedures implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, or severe accident management guidelines (CFR: 41.10 / 43.5 / 45.13) 4.4 84 35 (295035) (EPE 12)
SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE X (295035) (EPE 12) SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE (G2.4.37) EMERGENCY PROCEDURES/PLAN Knowledge of the lines of authority during implementation of the emergency plan implementing procedures (CFR: 41.10 / 45.13) 4.1 85 (295036) (EPE 13)
SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL 36 (500000) (EPE 16)
HIGH CONTAINMENT HYDROGEN CONCENTRATION / 5 X
(500000EA1.01) Ability to operate or monitor the following as they apply to (EPE 16) HIGH CONTAINMENT HYDROGEN CONCENTRATION: (CFR: 41.7/45.6) Primary containment hydrogen instrumentation 3.7 26 K/A Category Totals:
1 1
1 1
2 3 Group Point Total:
6 / 3
Page 6 of 14 ES-4.1-BWR BWR Examination Outline (Quad Cities)
Plant SystemsTier 2/Group 1 (RO/SRO)
Item #
System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
37 (203000) (SF2, SF4 RHR/LPCI) RHR/LPCI:
INJECTION MODE X
(203000A3.08) Ability to monitor automatic operation of the (SF2, SF4 RHR/LPCI) RHR/LPCI:
INJECTION MODE, including:
(CFR: 41.7 / 45.7) System initiation sequence 4.0 27 (205000) (SF4 SCS)
SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) 38 (205000) (SF4 SCS)
SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE)
X (205000K3.02) Knowledge of the effect that a loss or malfunction of the (SF4 SCS) SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) will have on the following systems or system parameters: (CFR: 41.7 /
45.4) Reactor water level 3.7 29 39 (206000) (SF2, SF4 HPCI) HIGH PRESSURE COOLANT INJECTION SYSTEM X
(206000K6.10) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF2, SF4 HPCI) HIGH PRESSURE COOLANT INJECTION SYSTEM: (CFR: 41.7 /
45.7) HPCI initiation/isolation logic 4.3 30 (207000) (SF4 IC)
ISOLATION (EMERGENCY)
CONDENSER 40 (209001) (SF2, SF4 LPCS) LOW PRESSURE CORE SPRAY SYSTEM X
(209001K3.02) Knowledge of the effect that a loss or malfunction of the LOW-PRESSURE CORE SPRAY SYSTEM will have on the following systems or system parameters: (CFR: 41.7 / 45.4)
ADS logic 4.1 31 (209002) (SF2, SF4 HPCS) HIGH PRESSURE CORE SPRAY SYSTEM 41 (211000) (SF1 SLCS)
STANDBY LIQUID CONTROL SYSTEM X
(211000A4.06) Ability to manually operate and/or monitor the (SF1 SLCS) STANDBY LIQUID CONTROL SYSTEM in the control room: (CFR: 41.7 / 45.5 to 45.8)
RWCU system isolation 4.0 32 42 (212000) (SF7 RPS)
(212000A1.11) Ability to predict and/or monitor changes in parameters associated with operation of the (SF7 RPS)
REACTOR PROTECTION SYSTEM including: (CFR: 41.5 /
45.5) Lights and alarms 3.7 33 43 (212000) (SF7 RPS)
REACTOR PROTECTION SYSTEM X (212000) (SF7 RPS) REACTOR PROTECTION SYSTEM (G2.4.46)
EMERGENCY PROCEDURES/PLAN Ability to verify that the alarms are consistent with the plant conditions (CFR: 41.10 / 43.5 /
45.3 / 45.12) 4.2 86
Page 7 of 14 ES-4.1-BWR BWR Examination Outline (Quad Cities)
Plant SystemsTier 2/Group 1 (RO/SRO)
Item #
System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
44 (215003) (SF7 IRM)
INTERMEDIATE RANGE MONITOR SYSTEM X
(215003K4.01) Knowledge of (SF7 IRM) INTERMEDIATE RANGE MONITOR SYSTEM design features and/or interlocks that provide for the following: (CFR:
41.7) Rod withdrawal blocks 4.0 34 45 (215003) (SF7 IRM)
INTERMEDIATE RANGE MONITOR SYSTEM X
(215003A2.08) Ability to (a) predict the impacts of the following on the (SF7 IRM)
INTERMEDIATE RANGE MONITOR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations:
(CFR: 41.5 / 43.5 / 45.6) Improper overlap 3.5 87 46 (215004) (SF7 SRMS)
SOURCE RANGE MONITOR SYSTEM X
(215004A1.02) Ability to predict and/or monitor changes in parameters associated with operation of the (SF7 SRMS)
SOURCE RANGE MONITOR SYSTEM including: (CFR: 41.5 /
45.5) Reactor power 4.0 35 47 (215004) (SF7 SRMS)
SOURCE RANGE MONITOR SYSTEM X
(215004K6.04) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF7 SRMS) SOURCE RANGE MONITOR SYSTEM: (CFR: 41.7 /
45.7) Detectors 3.2 36 48 (215005) (SF7 PRMS)
AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR X (215005) (SF7 PRMS) AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR (G2.1.30)
CONDUCT OF OPERATIONS Ability to locate and operate components, including local controls (CFR: 41.7 / 45.7) 4.4 37 49 (215005) (SF7 PRMS)
AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR X
(215005A2.02) Ability to (a) predict the impacts of the following on the (SF7 PRMS)
AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations:
(CFR: 41.5 / 43.5 / 45.6) Upscale or downscale trips 3.9 88 50 (217000) (SF2, SF4 RCIC) REACTOR CORE ISOLATION COOLING SYSTEM X
(217000A4.03) Ability to manually operate and/or monitor the (SF2, SF4 RCIC) REACTOR CORE ISOLATION COOLING SYSTEM in the control room: (CFR: 41.7 / 45.5 to 45.8) System valves 3.8 28 51 (218000) (SF3 ADS)
AUTOMATIC DEPRESSURIZATION SYSTEM X
(218000K4.05) Knowledge of (SF3 ADS) AUTOMATIC DEPRESSURIZATION SYSTEM design features and/or interlocks that provide for the following: (CFR:
41.7) Inhibiting automatic initiation of ADS logic 4.2 38
Page 8 of 14 ES-4.1-BWR BWR Examination Outline (Quad Cities)
Plant SystemsTier 2/Group 1 (RO/SRO)
Item #
System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
52 (223002) (SF5 PCIS)
PRIMARY CONTAINMENT ISOLATION SYSTEM /
NUCLEAR STEAM SUPPLY SHUTOFF X
(223002K5.01) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF5 PCIS) PRIMARY CONTAINMENT ISOLATION SYSTEM / NUCLEAR STEAM SUPPLY SHUTOFF: (CFR: 41.5 /
45.3) Primary containment integrity 4.1 39 53 (223002) (SF5 PCIS)
PRIMARY CONTAINMENT ISOLATION SYSTEM /
NUCLEAR STEAM SUPPLY SHUTOFF X (223002) (SF5 PCIS) PRIMARY CONTAINMENT ISOLATION SYSTEM / NUCLEAR STEAM SUPPLY SHUTOFF (G2.2.6)
EQUIPMENT CONTROL Knowledge of the process for making changes to procedures (CFR: 41.10 / 43.3 / 45.13) 3.6 89 54 (239002) (SF3 SRV)
(239002K1.06) Knowledge of the physical connections and/or cause and effect relationships between the (SF3 SRV) SAFETY RELIEF VALVES and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8) Drywell instrument air/drywell pneumatics 3.6 40 55 (239002) (SF3 SRV)
(239002A2.03) Ability to (a) predict the impacts of the following on the (SF3 SRV)
SAFETY RELIEF VALVES and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations:
(CFR: 41.5 / 43.5 / 45.6) Stuck-open SRV 4.4 90 56 (259002) (SF2 RWLCS)
REACTOR WATER LEVEL CONTROL SYSTEM X
(259002K2.02) (SF2 RWLCS)
REACTOR WATER LEVEL CONTROL SYSTEM Knowledge of electrical power supplies to the following: (CFR: 41.7) Feedwater coolant injection (FWCI) initiation logic 3.4 41 57 (261000) (SF9 SGTS)
STANDBY GAS TREATMENT SYSTEM X
(261000K3.03) Knowledge of the effect that a loss or malfunction of the (SF9 SGTS) STANDBY GAS TREATMENT SYSTEM will have on the following systems or system parameters: (CFR: 41.7 / 45.6)
Primary containment pressure (Mark I and II) 3.7 42 58 (261000) (SF9 SGTS)
STANDBY GAS TREATMENT SYSTEM X
(261000K6.04) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF9 SGTS) STANDBY GAS TREATMENT SYSTEM: (CFR:
41.7 / 45.7) Radiation monitoring system 3.4 43 59 (262001) (SF6 AC) AC ELECTRICAL DISTRIBUTION X (262001) (SF6 AC) AC ELECTRICAL DISTRIBUTION (291008K1.01) COMPONENTS:
Breakers, Relays, and Disconnects Purpose for racking out breakers (deenergize components and associated control and indication circuits): (CFR: 41.7) 3.6 44
Page 9 of 14 ES-4.1-BWR BWR Examination Outline (Quad Cities)
Plant SystemsTier 2/Group 1 (RO/SRO)
Item #
System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
60 (262002) (SF6 UPS)
UNINTERRUPTABLE POWER SUPPLY (AC/DC)
X (262002A4.01) Ability to manually operate and/or monitor the (SF6 UPS) UNINTERRUPTABLE POWER SUPPLY (AC/DC) in the control room: (CFR: 41.7 / 45.5 to 45.8) Transfer of power sources 3.1 45 61 (263000) (SF6 DC) DC ELECTRICAL DISTRIBUTION X
(263000K1.01) Knowledge of the physical connections and/or cause and effect relationships between the (SF6 DC) DC ELECTRICAL DISTRIBUTION and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8) AC electrical distribution 4.0 46 62 (263000) (SF6 DC) DC ELECTRICAL DISTRIBUTION X
(263000K2.03) (SF6 DC) DC ELECTRICAL DISTRIBUTION Knowledge of electrical power supplies to the following: (CFR:
41.7) Battery chargers 3.5 47 63 (264000) (SF6 EGE)
EMERGENCY GENERATORS (DIESEL/JET)
X (264000A2.11) Ability to (a) predict the impacts of the following on the (SF6 EGE) EMERGENCY GENERATORS (DIESEL/JET) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR: 41.5 /
43.5 / 45.6) Failure of emergency generator to start/load 4.6 48 64 (300000) (SF8 IA)
INSTRUMENT AIR SYSTEM X
(300000K5.15) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF8 IA) INSTRUMENT AIR SYSTEM: (CFR: 41.5 / 45.3) High moisture content in instrument air 3.1 49 65 (400000) (SF8 CCS)
COMPONENT COOLING WATER SYSTEM X
(400000A2.09) Ability to (a) predict the impacts of the following on the (SF8 CCS) COMPONENT COOLING WATER SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR: 41.5 /
43.5 / 45.6) Loss of cooling to spent fuel pool cooling system heat exchanger 4.2 50 66 (510000) (SF4 SWS*)
SERVICE WATER SYSTEM X
(510000K1.04) Knowledge of the physical connections and/or cause and effect relationships between the (SF4 SWS*) SERVICE WATER SYSTEM and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8) Emergency generators (diesel/jet) 3.4 51 67 (510000) (SF4 SWS*)
SERVICE WATER SYSTEM X
(510000A3.02) Ability to monitor automatic operation of the (SF4 SWS*) SERVICE WATER SYSTEM, including: (CFR: 41.7 /
45.7) Valve alignment 3.3 52 K/A Category Totals:
3 2
3 2
2 3
2 5
2 3
4 Group Point Total:
26 / 5
Page 10 of 14 ES-4.1-BWR BWR Examination Outline (Quad Cities)
Plant SystemsTier 2/Group 2 (RO/SRO)
Item #
System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
68 (201001) (SF1 CRDH)
CRD HYDRAULIC SYSTEM X
(201001A2.03) Ability to (a) predict the impacts of the following on the (SF1 CRDH) CRD HYDRAULIC SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR: 41.2 / 41.5-7 /
41.10 / 45.1-6 / 41.12-13) Power supply failures 4.0 53 (201002) (SF1 RMCS)
REACTOR MANUAL CONTROL SYSTEM (201003) (SF1 CRDM)
CONTROL ROD AND DRIVE MECHANISM (201004) (SF7 RSCS)
ROD SEQUENCE CONTROL SYSTEM (201005) (SF1, SF7 RCIS) ROD CONTROL AND INFORMATION SYSTEM (201006) (SF7 RWMS)
ROD WORTH MINIMIZER SYSTEM 69 (202001) (SF1, SF4 RS) RECIRCULATION SYSTEM X
(202001A3.10) Ability to monitor automatic operation of the (SF1, SF4 RS) RECIRCULATION SYSTEM including: (CFR: 41.7 /
45.7) VFD start sequence 3.4 54 (202002) (SF1 RSCTL)
RECIRCULATION FLOW CONTROL SYSTEM 70 (204000) (SF2 RWCU)
REACTOR WATER CLEANUP SYSTEM X (204000) (SF2 RWCU) REACTOR WATER CLEANUP SYSTEM (G2.2.43) EQUIPMENT CONTROL Knowledge of the process used to track inoperable alarms (CFR:
41.10 / 43.5 / 45.13) 3.3 91 71 (214000) (SF7 RPIS)
ROD POSITION INFORMATION SYSTEM X
(214000K5.01) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF7 RPIS) ROD POSITION INFORMATION SYSTEM: (CFR:
41.5 / 45.3) Rod position indication failures 3.5 55 (215001) (SF7 TIP)
TRAVERSING IN CORE PROBE 72 (215002) (SF7 RBMS)
ROD BLOCK MONITOR SYSTEM X
(215002K4.01) Knowledge of (SF7 RBMS) ROD BLOCK MONITOR SYSTEM design features and/or interlocks that provide for the following: (CFR: 41.7) Rod withdrawal blocks 3.9 56 73 (216000) (SF7 NBI)
NUCLEAR BOILER INSTRUMENTATION X
(216000A1.02) Ability to predict and/or monitor changes in parameters associated with operation of the (SF7 NBI)
NUCLEAR BOILER INSTRUMENTATION including:
(CFR: 41.5 / 45.5) Removing or returning a sensor (transmitter) to service 3.1 57
Page 11 of 14 ES-4.1-BWR BWR Examination Outline (Quad Cities)
Plant SystemsTier 2/Group 2 (RO/SRO)
Item #
System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
(219000) (SF5 RHR SPC) RHR/LPCI:
TORUS/SUPPRESSIO N POOL COOLING MODE (223001) (SF5 PCS)
PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES 74 (226001) (SF5 RHR CSS) RHR/LPCI:
CONTAINMENT SPRAY MODE SYSTEM MODE X
(226001A4.07) Ability to manually operate and/or monitor the (SF5 RHR CSS) RHR/LPCI:
CONTAINMENT SPRAY MODE SYSTEM MODE in the control room: (CFR: 41.7 / 45.5 to 45.8)
Valve logic reset/bypass/override 3.8 58 75 (230000) (SF5 RHR SPS) RHR/LPCI:
TORUS/SUPPRESSIO N POOL SPRAY MODE X
(230000A2.07) Ability to (a) predict the impacts of the following on the (SF5 RHR SPS)
RHR/LPCI:
TORUS/SUPPRESSION POOL SPRAY MODE and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations:
(CFR: 41.5 / 43.5 / 45.6)
Emergency generator failure 3.7 92 (233000) (SF9 FPCCU)
FUEL POOL COOLING/CLEANUP 76 (234000) (SF8 FH)
FUEL HANDLING X
(234000K3.01) Knowledge of the effect that a loss or malfunction of the (SF8 FH) FUEL HANDLING will have on the following systems or system parameters: (CFR: 41.7 /
45.4) Reactor manual control system 2.8 59 (239001) (SF3, SF4 MRSS) MAIN AND REHEAT STEAM SYSTEM (239003) (SF9 MSVLCS) MAIN STEAM ISOLATION VALVE LEAKAGE CONTROL SYSTEM (241000) (SF3 RTPRS)
REACTOR/TURBINE PRESSURE REGULATING SYSTEM 77 (245000) (SF4 MTGEN)
MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS X
(245000K5.03) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF4 MTGEN) MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS: (CFR: 41.5 / 45.3)
Hydraulically operated valve operation 2.9 60 (256000) (SF2 CDS)
CONDENSATE SYSTEM
Page 12 of 14 ES-4.1-BWR BWR Examination Outline (Quad Cities)
Plant SystemsTier 2/Group 2 (RO/SRO)
Item #
System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
78 (259001) (SF2 FWS)
FEEDWATER SYSTEM X
(259001K2.01) (SF2 FWS)
FEEDWATER SYSTEM Knowledge of electrical power supplies to the following: (CFR:
41.7) Reactor feedwater pump(s):
motor-driven-only 3.8 61 (268000) (SF9 RW)
RADWASTE SYSTEM (271000) (SF9 OG)
OFFGAS SYSTEM (272000) (SF7, SF9 RMS) RADIATION MONITORING SYSTEM 79 (286000) (SF8 FPS)
FIRE PROTECTION SYSTEM X
(286000K1.12) Knowledge of the physical connections and/or cause and effect relationships between the (SF8 FPS) FIRE PROTECTION SYSTEM and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8) Emergency core cooling system 3.1 62 (288000) (SF9 PVS)
PLANT VENTILATION SYSTEMS 80 (290001) (SF5 SC)
(290001A2.08) Ability to (a) predict the impacts of the following on the (SF5 SC)
SECONDARY CONTAINMENT and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR: 41.5
/ 43.5 / 45.6) Loss of secondary containment integrity 3.9 93 (290002) (SF4 RVI)
REACTOR VESSEL INTERNALS 81 (290003) (SF9 CRV)
CONTROL ROOM VENTILATION X (290003) (SF9 CRV) CONTROL ROOM VENTILATION (G2.1.47)
CONDUCT OF OPERATIONS Ability to direct non-licensed personnel activities inside the control room (CFR: 41.10 / 43.5 /
45.5 / 45.12 / 45.13) 3.2 63 (510001) (SF8 CWS*)
CIRCULATING WATER SYSTEM K/A Category Totals:
1 1
1 1
2 0
1 3
1 1
2 Group Point Total:
11 / 3
Page 13 of 14 Form 4.1-COMMON Common Examination Outline ES-4.1-COMMON COMMON Examination Outline (Quad Cities)
Facility: Quad Cities Date of Exam: 1/30/2023 Generic Knowledge and Abilities Outline (Tier 3) (RO/SRO)
Category K/A #
Topic RO SRO-Only Item #
IR Q#
IR Q#
- 1.
Conduct of Operations G2.1.7 (G2.1.7) CONDUCT OF OPERATIONS Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation (CFR: 41.5 / 43.5 / 45.12 / 45.13) 82 4.4 64 G2.1.39 (G2.1.39) CONDUCT OF OPERATIONS Knowledge of conservative decision-making practices (CFR: 41.10 / 43.5 /
45.12) 83 3.6 65 G2.1.6 (G2.1.6) CONDUCT OF OPERATIONS Ability to manage the control room crew during plant transients (SRO Only) (CFR: 43.5 / 45.12 / 45.13) 84 4.8 94 G2.1.19 (G2.1.19) CONDUCT OF OPERATIONS Ability to use available indications to evaluate system or component status (CFR: 41.10 / 45.12) 85 3.8 95 Subtotal N/A 2
N/A 2
- 2.
Equipment Control G2.2.20 (G2.2.20) EQUIPMENT CONTROL Knowledge of the process for managing troubleshooting activities (CFR: 41.10
/ 43.5 / 45.13) 86 2.6 66 G2.2.35 (G2.2.35) EQUIPMENT CONTROL Ability to determine technical specification mode of operation (CFR: 41.7 / 41.10
/ 43.2 / 45.13) 87 3.6 67 G2.2.38 (G2.2.38) EQUIPMENT CONTROL Knowledge of conditions and limitations in the facility license (CFR:
41.7 / 41.10 / 43.1 / 45.13) 88 4.5 96 G2.2.42 (G2.2.42) EQUIPMENT CONTROL Ability to recognize system parameters that are entry-level conditions for technical specifications (CFR: 41.7 / 41.10 / 43.2 / 43.3 /
45.3) 89 4.6 97 Subtotal N/A 2
N/A 2
- 3.
Radiation Control G2.3.11 (G2.3.11) RADIATION CONTROL Ability to control radiation releases (CFR: 41.11 / 43.4 / 45.10) 90 3.8 68 G2.3.14 (G2.3.14) RADIATION CONTROL Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities, such as analysis and interpretation of radiation and activity readings as they pertain to administrative, normal, abnormal, and emergency procedures, or analysis and interpretation of coolant activity, including comparison to emergency plan or regulatory limits (SRO Only) (CFR:
43.4 / 45.10) 91 3.8 98 Subtotal N/A 1
N/A 1
- 4.
Emergency Procedures / Plan G2.4.45 (G2.4.45) EMERGENCY PROCEDURES/PLAN Ability to prioritize and interpret the significance of each annunciator or alarm (CFR: 41.10 / 43.5 / 45.3 / 45.12) 92 4.1 69 G2.4.2 (G2.4.2) EMERGENCY PROCEDURES/PLAN Knowledge of system setpoints, interlocks and automatic actions associated with emergency and abnormal operating procedure entry conditions (CFR: 41.7 / 45.7 / 45.8) 93 4.6 99 G2.4.6 (G2.4.6) EMERGENCY PROCEDURES/PLAN Knowledge of emergency and abnormal operating procedures major action categories (CFR: 41.10 / 43.5 / 45.13) 94 4.7 100 Subtotal N/A 1
N/A 2
Tier 3 Point Total N/A 6
N/A 7
Page 14 of 14 Form 4.1-COMMON Common Examination Outline ES-4.1-COMMON COMMON Examination Outline (Quad Cities)
Facility: Quad Cities Date of Exam: 1/30/2023 Theory (Tier 4) (RO)
Category K/A #
Topic RO Item #
IR Q#
Reactor Theory 292001 (292001K1.05) NEUTRONS (CFR: 41.1) Identify characteristics of good moderators 95 2.6 70 292003 (292003K1.07) REACTOR KINETICS AND NEUTRON SOURCES (CFR: 41.1) Explain prompt critical, prompt jump, and prompt drop 96 3.3 71 292004 (292004K1.10) REACTIVITY COEFFICIENTS (CFR: 41.1)
Define the void coefficient of reactivity 97 3.2 72 Subtotal 3
Thermodynamics 293007 (293007K1.12) HEAT TRANSFER (CFR: 41.14) (CORE THERMAL POWER) Define percent reactor power 98 2.7 73 293009 (293009K1.33) CORE THERMAL LIMITS (CFR: 41.14)
(PELLET-CLAD INTERACTION) Describe the purpose of the pellet to clad gap 99 2.8 74 293010 (293010K1.04) BRITTLE FRACTURE AND VESSEL THERMAL STRESS (CFR: 41.14) State how the possibility of brittle fracture is minimized by operating limitations 100 3.2 75 Subtotal 3
Tier 4 Point Total N/A 6