ML23325A019
| ML23325A019 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 05/31/2023 |
| From: | Jack Giessner NRC/RGN-III/DORS/OB |
| To: | Constellation Energy Generation |
| Travis Iskierka-Boggs | |
| Shared Package | |
| 22122A028 | List: |
| References | |
| Download: ML23325A019 (1) | |
Text
Form 4.1-PWR Pressurized-Water Reactor Examination Outline Facility:
Byron K/A Catalog Rev. 3 Rev.
0 Date of Exam:
10/16/2023 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
3 3
3 3
3 3
18 3
3 6
2 1
1 2
2 1
1 8
2 2
4 Tier Totals 4
4 5
5 4
4 26 5
5 10
- 2.
Plant Systems 1
2 2
3 2
3 2
2 3
3 4
2 28 3
2 5
2 1
1 1
1 1
1 1
1 0
0 1
9 0
2 1
3 Tier Totals 3
3 4
3 4
3 3
4 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 = Conduct of Operations; EC = Equipment Control; RC = Radiation Control; EM = 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.
ES-4.1-PWR PWR Examination Outline (Byron)
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 (000007) (EPE 7; BW E02 & E10; CE E02) Reactor Trip, Stabilization, Recovery X
(000007EK1.06) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (EPE 7) REACTOR TRIP, STABILIZATION, RECOVERY (CFR: 41.5 / 41.7 / 45.7 /
45.8): Decay heat removal capability of AFW 3.9 1
2 (000008) (APE 8)
Pressurizer Vapor Space Accident X
(000008AK1.01) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (APE 8) PRESSURIZER VAPOR Space Accident (CFR: 41.5 / 41.7 / 45.7 / 45.8):
Thermodynamics and flow characteristics of open or leaking PZR PORV or safety valves 4.1 2
3 (000009) (EPE 9)
Small Break LOCA X
(000009EK2.05) Knowledge of the relationship between (EPE 9) SMALL-Break LOCA and the following systems or components (CFR: 41.8 / 41.10 / 45.3): RCPS 3.7 3
4 (000015) (APE 15)
Reactor Coolant Pump Malfunctions X
(000015AA1.15) Ability to operate and/or monitor the following as they apply to (APE 15) REACTOR COOLANT Pump Malfunctions (CFR: 41.5 / 41.7 / 45.5 to 45.8): High-power/low-flow reactor trip block status 3.4 4
5 (000022) (APE 22)
Loss of Reactor Coolant Makeup X
(000022AK3.03) Knowledge of the reasons for the following responses and/or actions as they apply to (APE 22) LOSS OF REACTOR Coolant Makeup (CFR: 41.5 / 41.10 / 45.6 /
45.13): Establishing excess letdown 3.3 5
6 (000025) (APE 25)
Loss of Residual Heat Removal System X
(000025AK3.01) Knowledge of the reasons for the following responses and/or actions as they apply to (APE 25) LOSS OF RESIDUAL HEAT REMOVAL SYSTEM (CFR: 41.5 /
41.10 / 45.6 / 45.13): Shift to alternate flowpath 3.8 6
7 (000029) (EPE 29)
Anticipated Transient Without Scram X
(000029EK3.11) Knowledge of the reasons for the following responses and/or actions as they apply to (EPE 29)
ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS)
(CFR: 41.5 / 41.10 / 45.6 / 45.13): Initiating emergency boration 4.3 7
8 (000038) (EPE 38)
Steam Generator Tube Rupture X
(000038EK2.15) Knowledge of the relationship between (EPE 38) STEAM GENERATOR TUBE RUPTURE and the following systems or components (CFR: 41.8 / 41.10 /
45.3): PZR PCS 3.6 8
9 (000040) (APE 40; BW E05; CE E05; W E12) Steam Line Rupture - Excessive Heat Transfer X
(000040AA2.01) Ability to determine and/or interpret the following as they apply to (APE 40) STEAM LINE RUPTURE (CFR: 41.10 / 43.5 / 45.13): Occurrence and location of a steamline rupture from pressure and flow indications 3.6 9
10 (000054) (APE 54; CE E06) Loss of Main Feedwater X
(000054) (APE 54; CE E06) Loss of Main Feedwater (G2.4.20) EMERGENCY PROCEDURES/PLAN:
Knowledge of the operational implications of emergency and abnormal operation procedures warnings, cautions, and notes (CFR: 41.10 / 43.5 / 45.13) 3.8 10 11 (000056) (APE 56)
(000056AK1.08) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (APE 56) Loss of Offsite Power (CFR: 41.5 / 41.7 / 45.7 / 45.8): Long-term spent fuel pool cooling 3.6 11 12 (000058) (APE 58)
Loss of DC Power X
(000058AK2.06) Knowledge of the relationship between (APE 58) LOSS OF DC Power and the following systems or components (CFR: 41.8 / 41.10 / 45.3): EDGs 4.1 12 13 (000062) (APE 62)
Loss of Nuclear Service Water X
(000062AA2.04) Ability to determine and/or interpret the following as they apply to (APE 62) LOSS OF SERVICE WATER (CFR: 41.10 / 43.5 / 45.13): The normal values and upper limits for the temperatures of the components cooled by SWS 3.0 13
14 (000065) (APE 65)
Loss of Instrument Air X
(000065AA1.07) Ability to operate and/or monitor the following as they apply to (APE 65) LOSS OF INSTRUMENT AIR (CFR: 41.5 / 41.7 / 45.5 to 45.8):
Instrument and/or service air compressors 3.3 14 15 (000077) (APE 77)
Generator Voltage and Electric Grid Disturbances X
(000077AA1.04) Ability to operate and/or monitor the following as they apply to (APE 77) GENERATOR VOLTAGE AND ELECTRIC Grid Disturbances (CFR: 41.5 /
41.7 / 45.5 to 45.8): Reactor controls 3.6 15 16 (W E04) LOCA Outside Containment X
(W E04) LOCA Outside Containment (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) 4.5 16 17 (W E11) Loss of Emergency Coolant Recirculation X
(W E11) Loss of Emergency Coolant Recirculation (G2.4.12) EMERGENCY PROCEDURES/PLAN:
Knowledge of operating crew responsibilities during emergency and abnormal conditions (CFR: 41.10 / 45.12) 3.8 17 18 (BW E04; W E05)
Inadequate Heat Transfer - Loss of Secondary Heat Sink X
(WE05EA2.08) Ability to determine and/or interpret the following as they apply to (W E05) Loss of Secondary Heat Sink (CFR: 41.10 / 43.5 / 45.13): CETs and/or subcooling 3.7 18 19 (000007) (EPE 7; BW E02 & E10; CE E02) Reactor Trip, Stabilization, Recovery X
(000007EA2.09) Ability to determine and/or interpret the following as they apply to (EPE 7) REACTOR TRIP, STABILIZATION, RECOVERY (CFR: 41.10 / 43.5 / 45.13):
S/G pressure 3.7 76 20 (000011) (EPE 11)
Large Break LOCA X
(000011EA2.05) Ability to determine and/or interpret the following as they apply to (EPE 11) LARGE-Break LOCA (CFR: 41.10 / 43.5 / 45.13): Significance of ECCS pump operation 4.1 77 21 (000026) (APE 26)
Loss of Component Cooling Water X
(000026AA2.04) Ability to determine and/or interpret the following as they apply to (APE 26) LOSS OF Component Cooling Water (CFR: 41.10 / 43.5 / 45.13):
The normal values and upper limits for the temperatures of the components cooled by CCW 3.3 78 22 (000027) (APE 27)
Pressurizer Pressure Control System Malfunction X
(000027) (APE 27) Pressurizer Pressure Control System Malfunction (G2.4.4) EMERGENCY PROCEDURES/PLAN: Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures (CFR: 41.10 / 43.2 / 45.6) 4.7 79 23 (000055) (EPE 55)
Station Blackout X
(000055) (EPE 55) Station Blackout (G2.1.39) CONDUCT OF OPERATIONS: Knowledge of conservative decision-making practices (CFR: 41.10 / 43.5 / 45.12) 4.3 80 24 (000057) (APE 57)
Loss of Vital AC Instrument Bus X
(000057) (APE 57) Loss of Vital AC Instrument Bus (G2.4.50) EMERGENCY PROCEDURES/PLAN: Ability to verify system alarm setpoints and operate controls identified in the alarm response procedure (CFR: 41.10
/ 43.5 / 45.3) 4.0 81 K/A Category Totals:
3 3
3 3
3/3 3/3 Group Point Total:
24
ES-4.1-PWR PWR Examination Outline (Byron)
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#
25 (000036) (APE 36; BW/A08) Fuel-Handling Incidents X
(000036) (APE 36; BW/A08) Fuel-Handling Incidents (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) 4.1 19 26 (000037) (APE 37)
Steam Generator Tube Leak X
(000037AA1.16) Ability to operate and/or monitor the following as they apply to (APE 37) Steam Generator Tube Leak: RCS (CFR: 41.7 / 41.10 / 45.5 / 45.6) 3.5 20 27 (000051) (APE 51)
(000051AK1.01) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (APE 51) LOSS OF Condenser Vacuum (CFR: 41.5 / 41.7 / 45.7 / 45.8): Relationship of condenser vacuum to circulating water, flow rate, and temperature 3.3 21 28 (000068) (APE 68; BW A06) Control Room Evacuation X
(000068AK2.16) Knowledge of the relationship between (APE 68) Control Room Evacuation and the following systems or components (CFR: 41.8 / 41.10 / 45.3):
Electrical distribution system 3.7 22 29 (000069) (APE 69; W E14) Loss of Containment Integrity X
(WE14EK3.09) Knowledge of the reasons for the following responses and/or actions as they apply to (W E14) HIGH CONTAINMENT PRESSURE (CFR: 41.5 / 41.10 / 45.6 /
45.13): Ensuring that MSLI has occurred 3.8 23 30 (000076) (APE 76)
High Reactor Coolant Activity X
(000076AK3.01) Knowledge of the reasons for the following responses and/or actions as they apply to (APE 76) HIGH REACTOR COOLANT ACTIVITY (CFR: 41.5 / 41.10 / 45.6
/ 45.13): RCS differentiating activity due to fission products and due to corrosion products from chemistry report 3.1 24 31 (W E15)
Containment Flooding X
(WE15EA1.04) Ability to operate and/or monitor the following as they apply to (W E15) Containment Flooding (CFR: 41.5 / 41.7 / 45.5 to 45.8): Service water 3.5 25 32 (BW E09; CE A13**;
W E09 & E10)
Natural Circulation X
(WE09EA2.06) Ability to determine and/or interpret the following as they apply to (W E09) NATURAL CIRCULATION OPERATIONS (CFR: 41.10 / 43.5 / 45.13):
Core exit temperatures and/or subcooling 3.7 26 33 (000001) (APE 1)
Continuous Rod Withdrawal X
(000001) (APE 1) Continuous Rod Withdrawal (G2.1.7)
CONDUCT OF OPERATIONS: Ability to evaluate plant performance and make operational judgements based on operating characteristic, reactor behavior, and instrument interpretation (CFR: 41.5 / 43.5 / 45.12 /
45.13) 4.1 82 34 (000059) (APE 59)
Accidental Liquid Radwaste Release X
(000059) (APE 59) Accidental Liquid Radwaste Release (G2.2.15) EQUIPMENT CONTROL: Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, lineups, or tagouts (reference potential)
(CFR: 41.10 / 43.3 / 45.13) 4.3 83 35 (000061) (APE 61)
Area Radiation Monitoring System Alarms X
(000061AA2.02) Ability to determine and/or interpret the following as they apply to (APE 61) AREA RADIATION MONITORING (ARM) System Alarms (CFR: 41.10 / 43.5 /
45.13): Normal operating characteristics 3.1 84 36 (000074) (EPE 74; W E06 & E07)
Inadequate Core Cooling X
(WE06EA2.06) Ability to determine and/or interpret the following as they apply to (W E06) DEGRADED CORE COOLING (CFR: 41.10 / 43.5 / 45.13): RCP No. 1 seal D/P 3.2 85 000003 (APE 3)
Dropped Control Rod
/ 1 000005 (APE 5)
Inoperable/Stuck Control Rod / 1 000024 (APE 24)
Emergency Boration
/ 1
000028 (APE 28)
Pressurizer (PZR)
Level Control Malfunction / 2 000032 (APE 32)
Loss of Source Range Nuclear Instrumentation / 7 000033 (APE 33)
Loss of Intermediate Range Nuclear Instrumentation / 7 000060 (APE 60)
Accidental Gaseous Radwaste Release /
9 000067 (APE 67)
Plant Fire On Site / 8 000078 (APE 78*)
RCS Leak / 3 (W E01 & E02)
Rediagnosis & SI Termination / 3 (W E13) Steam Generator Overpressure / 4 (W E16) High Containment Radiation /9 (BW A01) Plant Runback / 1 (BW A02 & A03)
Loss of NNI-X/Y/7 (BW A04) Turbine Trip / 4 (BW A05)
Emergency Diesel Actuation / 6 (BW A07) Flooding /
8 (BW E03)
Inadequate Subcooling Margin /
4 (BW E08; W E03)
LOCA Cooldown -
Depressurization / 4 (BW E13 & E14)
EOP Rules and Enclosures (CE A11**; W E08)
RCS Overcooling -
Pressurized Thermal Shock / 4 (CE A16) Excess RCS Leakage / 2 (CE E09) Functional Recovery (CE E13*) Loss of Forced Circulation /
LOOP / Blackout / 4 K/A Category Totals:
1 1
2 2
1/2 1/2 Group Point Total:
12
ES-4.1-PWR PWR Examination Outline (Byron)
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 (003) (SF4P RCP)
REACTOR COOLANT PUMP SYSTEM X
(003A4.08) Ability to manually operate and/or monitor the (SF4P RCP) REACTOR COOLANT PUMP SYSTEM in the control room (CFR: 41.7 /
45.5 to 45.8): RCP cooling water supplies 3.5 27 38 (003) (SF4P RCP)
REACTOR COOLANT PUMP SYSTEM X
(003K3.01) Knowledge of the effect that a loss or malfunction of the (SF4P RCP)
REACTOR COOLANT PUMP SYSTEM will have on the following systems or system parameters (CFR: 41.7 / 45.4):
RCS 4.2 28 39 (004) (SF1; SF2 CVCS) CHEMICAL AND VOLUME CONTROL SYSTEM X
(004K4.12) Knowledge of (SF1; SF2 CVCS) CHEMICAL AND VOLUME CONTROL SYSTEM design features and/or interlocks that provide for the following (CFR: 41.7):
Automatic action(s), that occur based on level of VCT 3.9 29 40 (005) (SF4P RHR)
RESIDUAL HEAT REMOVAL SYSTEM X
(005K2.01) Knowledge of electrical power supplies to the following (CFR: 41.7): (SF4P RHR) RESIDUAL HEAT REMOVAL SYSTEM RHR pumps 4.1 30 41 (006) (SF2; SF3 ECCS)
EMERGENCY CORE COOLING SYSTEM X
(006A2.02) Ability to (a) predict the impacts of the following on the (SF2; SF3 ECCS)
EMERGENCY CORE COOLING SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR:
41.5 / 45.5 / 45.3 / 45.4): Loss of Flowpath 3.9 31 42 (007) (SF5 PRTS)
PRESSURIZER RELIEF/QUENCH TANK SYSTEM X
(007K5.08) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF5 PRTS)
PRESSURIZER RELIEF/QUENCH TANK SYSTEM (CFR: 41.5 / 45.3):
Recognition of leaking PORVs/code or safety valves 4.0 32 43 (008) (SF8 CCW)
COMPONENT COOLING WATER SYSTEM X
(008A2.05) Ability to (a) predict the impacts of the following on the (SF8 CCW) 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 / 45.3 / 45.13):
Effect of loss of instrument air and control air on the position of air-operated CCW valves.
3.2 33
44 (010) (SF3 PZR PCS)
PRESSURIZER PRESSURE CONTROL SYSTEM X
(010A1.11) Ability to predict and/or monitor changes in parameters associated with operation of the (SF3 PZR PCS) PRESSURIZER PRESSURE CONTROL SYSTEM, including (CFR: 41.5
/ 45.5): PZR steam temperature 3.3 34 45 (010) (SF3 PZR PCS)
PRESSURIZER PRESSURE CONTROL SYSTEM X
(010A4.06) Ability to manually operate and/or monitor the (SF3 PZR PCS)
PRESSURIZER PRESSURE CONTROL SYSTEM in the control room (CFR: 41.7 / 45.5 to 45.8): Cycling PORVs, including PRT/quench tank parameters 3.5 35 46 (012) (SF7 RPS)
(012A3.06) Ability to monitor automatic features of the (SF7 RPS) REACTOR PROTECTION SYSTEM, including (CFR: 41.7 / 45.7):
Trip logic 4.1 36 47 (012) (SF7 RPS)
(012A4.03) Ability to manually operate and/or monitor the (SF7 RPS) REACTOR PROTECTION SYSTEM in the control room (CFR: 41.7 / 45.5 to 45.8): Channel blocks and bypasses 3.8 37 48 (013) (SF2 ESFAS)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM X
(013K6.10) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF2 ESFAS) ENGINEERED SAFETY FEATURES ACTUATION SYSTEM (CFR:
41.7 / 45.7): Feedline break 4.0 38 49 (022) (SF5 CCS)
CONTAINMENT COOLING SYSTEM X
(022K3.04) Knowledge of the effect that a loss or malfunction of the (SF5 CCS)
CONTAINMENT COOLING SYSTEM will have on the following systems or system parameters (CFR: 41.7 / 45.4):
CNT 3.9 39 50 (022) (SF5 CCS)
CONTAINMENT COOLING SYSTEM X
(022K5.05) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF5 CCS)
CONTAINMENT COOLING SYSTEM (CFR: 41.5 / 45.3):
Effects on electrical insulation 3.0 40 51 (026) (SF5 CSS)
CONTAINMENT SPRAY SYSTEM X
(026K1.06) Knowledge of the physical connections and/or cause and effect relationships between the (SF5 CSS)
CONTAINMENT SPRAY SYSTEM and the following systems (CFR: 41.2 to 41.9 /
45.7 to 45.8): RHRS 3.6 41 52 (039) (SF4S MSS)
MAIN AND REHEAT STEAM SYSTEM X
(039) (SF4S MSS) MAIN AND REHEAT STEAM SYSTEM (G2.1.34) CONDUCT OF OPERATIONS: Knowledge of RCS or balance-of-plant chemistry controls, including parameters measured and reasons for the control (CFR:
41.10 / 43.5 / 45.12) 2.7 42
53 (039) (SF4S MSS)
MAIN AND REHEAT STEAM SYSTEM X
(039K1.06) Knowledge of the physical connections and/or cause and effect relationships between the (SF4S MSS)
MAIN AND REHEAT STEAM SYSTEM and the following systems (CFR: 41.2 to 41.9 /
45.7 to 45.8): SDS 3.5 43 54 (059) (SF4S MFW)
MAIN FEEDWATER SYSTEM X
(059A4.03) Ability to manually operate and/or monitor the (SF4S MFW) MAIN FEEDWATER SYSTEM in the control room (CFR: 41.7 / 45.5 to 45.8): Feedwater control during power increase and decrease 3.6 44 55 (061) (SF4S AFW)
AUXILIARY /
(061K3.02) Knowledge of the effect that a loss or malfunction of the (SF4S AFW)
AUXILIARY/EMERGENCY FEEDWATER SYSTEM will have on the following systems or system parameters (CFR:
41.7 / 45.4): S/G system 4.3 45 56 (062) (SF6 ED AC)
AC ELECTRICAL DISTRIBUTION SYSTEM X
(062A3.07) Ability to monitor automatic features of the (SF6 ED AC) AC ELECTRICAL DISTRIBUTION SYSTEM, including (CFR: 41.7 / 45.7):
Automatic bus transfer 3.6 46 57 (062) (SF6 ED AC)
AC ELECTRICAL DISTRIBUTION SYSTEM X
(062K5.05) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF6 ED AC)
AC ELECTRICAL DISTRIBUTION SYSTEM (CFR: 41.5 / 45.3): Fault on a bus 3.5 47 58 (063) (SF6 ED DC)
DC ELECTRICAL DISTRIBUTION SYSTEM X
(063K6.06) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF6 ED DC) DC ELECTRICAL DISTRIBUTION SYSTEM (CFR: 41.7 / 45.7): Battery 4.0 48 59 (064) (SF6 EDG)
EMERGENCY DIESEL GENERATOR SYSTEM X
(064A2.29) Ability to (a) predict the impacts of the following on the (SF6 EDG) EMERGENCY DIESEL GENERATOR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR: 41.5 / 45.6): ESFAS actuation 4.3 49 60 (064) (SF6 EDG)
EMERGENCY DIESEL GENERATOR SYSTEM X
(064) (SF6 EDG)
EMERGENCY DIESEL GENERATOR SYSTEM (G2.1.45) CONDUCT OF OPERATIONS: Ability to identify and interpret diverse indications to validate the response of another indication.
(CFR: 41.7 / 43.5 / 45.4) 4.3 50
61 (073) (SF7 PRM)
PROCESS RADIATION MONITORING SYSTEM X
(073K4.02) Knowledge of (SF7 PRM) PROCESS RADIATION MONITORING SYSTEM design features and/or interlocks that provide for the following (CFR: 41.7): System actuations based on PRM signals 3.7 51 62 (076) (SF4S SW)
SERVICE WATER SYSTEM X
(076K2.07) Knowledge of electrical power supplies to the following (CFR: 41.7): (SF4S SW) SERVICE WATER SYSTEM Cooling tower fans 2.5 52 63 (078) (SF8 IAS)
INSTRUMENT AIR SYSTEM X
(078A3.05) Ability to monitor automatic features of the (SF8 IAS) INSTRUMENT AIR SYSTEM, including (CFR: 41.7
/ 45.7): Isolation of instrument air to containment 3.3 53 64 (103) (SF5 CNT)
CONTAINMENT SYSTEM X
(103A1.01) Ability to predict and/or monitor changes in parameters associated with operation of the (SF5 CNT)
CONTAINMENT SYSTEM, including (CFR: 41.5 / 45.5):
Containment pressure, temperature, and/or humidity 3.9 54 65 (004) (SF1; SF2 CVCS) CHEMICAL AND VOLUME CONTROL SYSTEM X
(004) (SF1; SF2 CVCS)
CHEMICAL AND VOLUME CONTROL SYSTEM (G2.4.4)
EMERGENCY PROCEDURES/PLAN: Ability to recognize abnormal indications for system operating parameters that are entry-level criteria for emergency and abnormal operating procedures (CFR:
41.10 / 43.5 / 45.6) 4.7 86 66 (013) (SF2 ESFAS)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM X
(013A2.06) Ability to (a) predict the impacts of the following on the (SF2 ESFAS) ENGINEERED SAFETY FEATURES ACTUATION SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR: 41.5 / 45.6):
Inadvertent ESFAS actuation 4.0 87 67 (059) (SF4S MFW)
MAIN FEEDWATER SYSTEM X
(059A2.13) Ability to (a) predict the impacts of the following on the (SF4S MFW)
MAIN FEEDWATER SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR: 41.5 / 45.6):
Loss of condensate/heater draining flow 2.8 88
68 (076) (SF4S SW)
SERVICE WATER SYSTEM X
(076A2.07) Ability to (a) predict the impacts of the following on the (SF4S SW)
SERVICE WATER SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR: 41.5 / 45.6):
Heat exchanger and condenser failure 3.2 89 69 (103) (SF5 CNT)
CONTAINMENT SYSTEM X
(103) (SF5 CNT)
CONTAINMENT SYSTEM (G2.4.3) EMERGENCY PROCEDURES/PLAN: Ability to identify post-accident instrumentation (CFR: 41.6 /
45.4) 3.9 90 025 (SF5 ICE) ICE CONDENSER SYSTEM 053 (SF1; SF4P ICS*) INTEGRATED CONTROL SYSTEM K/A Category Totals:
2 2
3 2
3 2
2 3/3 3
4 2/2 Group Point Total:
33
ES-4.1-PWR PWR Examination Outline (Byron)
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#
70 (014) (SF1 RPI) ROD POSITION INDICATION SYSTEM X
(014K5.02) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF1 RPI)
ROD POSITION INDICATION SYSTEM (CFR: 41.5 / 45.3):
RPIS independent of demand position 3.5 55 71 (017) (SF7 ITM) IN CORE TEMPERATURE MONITOR SYSTEM X
(017K3.03) Knowledge of the effect that a loss or malfunction of the (SF7 ITM) IN CORE TEMPERATURE MONITOR SYSTEM will have on the following systems or system parameters (CFR: 41.7 / 45.4):
SPDS 3.6 56 72 (029) (SF8 CPS)
CONTAINMENT PURGE SYSTEM X
(029K1.03) Knowledge of the physical connections and/or cause and effect relationships between the (SF8 CPS)
CONTAINMENT PURGE SYSTEM and the following systems (CFR: 41.2 to 41.9 /
45.7 to 45.8): ESFAS 3.5 57 73 (033) (SF8 SFPCS)
SPENT FUEL POOL COOLING SYSTEM X
(033K6.10) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF8 SFPCS) SPENT FUEL POOL COOLING SYSTEM (CFR:
41.7 / 45.7): PVS 2.5 58 74 (045) (SF4S MTG)
MAIN TURBINE GENERATOR SYSTEM X
(045) (SF4S MTG) MAIN TURBINE GENERATOR SYSTEM (G.2.2.13)
EQUIPMENT CONTROL Knowledge of the tagging and clearance process (CFR: 41.10
/ 43.1 / 45.13) 4.1 59 75 (050) (SF9 CRV*)
CONTROL ROOM VENTILATION X
(050K2.02) Knowledge of electrical power supplies to the following (CFR: 41.7): (SF9 CRV) CONTROL ROOM VENTILATION Chiller units 3.1 60 76 (055) (SF4S CARS)
CONDENSER AIR REMOVAL SYSTEM X
(055K4.02) Knowledge of (SF4S CARS) CONDENSER AIR REMOVAL SYSTEM design features and/or interlocks that provide for the following (CFR: 41.7): Effluent control and monitoring 3.3 61 77 (056) (SF4S CDS)
CONDENSATE SYSTEM X
(056A1.09) Ability to predict and/or monitor changes in parameters associated with operation of the (SF4S CDS)
CONDENSATE SYSTEM, including (CFR: 41.5 / 45.5):
Long-cycle recirculation parameters (temperature, pressure, and flow level) 2.5 62
78 (086) (SF8 FPS)
FIRE PROTECTION SYSTEM X
(086A2.05) Ability to (a) predict the impacts of the following on the (SF8 FPS) FIRE PROTECTION SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR:
41.5 / 45.6): Fire in the plant 4.0 63 79 (011) (SF2 PZR LCS)
PRESSURIZER LEVEL CONTROL SYSTEM X
(011) (SF2 PZR LCS)
PRESSURIZER LEVEL CONTROL SYSTEM (G2.1.37)
CONDUCT OF OPERATIONS:
Knowledge of procedures, guidelines, or limitations associated with reactivity management (CFR: 41.1 /
41.5 / 41.10 / 43.6 / 45.6) 4.6 91 80 035 (SF4P SG)
STEAM GENERATOR SYSTEM X
(035A2.01) Ability to (a) predict the impacts of the following on the (SF4P SG)
STEAM GENERATOR 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 / 45.3 / 45.5):
Faulted, leaking, or ruptured SG 4.4 92 81 (072) (SF7 ARM)
AREA RADIATION MONITORING SYSTEM X
(072A2.01) Ability to (a) predict the impacts of the following on the (SF7 ARM)
AREA RADIATION MONITORING SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR: 41.5 / 45.6):
ARM component failures 3.3 93 001 (SF1 CRDS)
CONTROL ROD DRIVE SYSTEM 002 (SF2; SF4P RCS) REACTOR COOLANT SYSTEM 015 (SF7 NI)
NUCLEAR INSTRUMENTATION SYSTEM 016 (SF7 NNI)
NONNUCLEAR INSTRUMENTATION SYSTEM 028 (SF5 HRPS)
HYDROGEN RECOMBINER AND PURGE CONTROL SYSTEM 034 (SF8 FHS) FUEL HANDLING EQUIPMENT SYSTEM 035 (SF4P SG)
STEAM GENERATOR SYSTEM
041 (SF4S SDS)
STEAM DUMP /
TURBINE BYPASS CONTROL SYSTEM 068 (SF9 LRS)
LIQUID RADWASTE SYSTEM 071 (SF9 WGS)
WASTE GAS DISPOSAL SYSTEM 075 (SF8 CW)
CIRCULATING WATER SYSTEM 079 (SF8 SAS**)
STATION AIR SYSTEM K/A Category Totals:
1 1
1 1
1 1
1 1/2 0
0 1/1 Group Point Total:
12
Form 4.1-COMMON Common Examination Outline ES-4.1-COMMON COMMON Examination Outline (Byron)
Facility:
Byron Date of Exam:
10/16/2023 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 G2.1.5 (G2.1.5) CONDUCT OF OPERATIONS: Ability to use procedures related to shift staffing, such as minimum crew complement or overtime limitations (reference potential) (CFR:
41.10 / 43.5 / 45.12) 82 2.9 64 G2.1.17 (G2.1.17) CONDUCT OF OPERATIONS: Ability to make accurate, clear, and concise verbal reports (CFR: 41.10 / 45.12
/ 45.13) 83 3.9 65 G2.1.40 (G2.1.30) CONDUCT OF OPERATIONS: Knowledge of refueling administrative requirements (CFR: 41.10 / 43.5 /
43.6 / 45.13) 84 3.9 94 G2.1.43 (G2.1.43) CONDUCT OF OPERATIONS: Ability to use an online power distribution monitoring system and/or procedures to determine the effects on reactivity of plant changes, such as RCS temperature, secondary plant, or fuel depletion (CFR: 41.10 / 43.6 / 45.6) 85 4.3 95 Subtotal N/A 2
N/A 2
- 2.
Equipment Control G2.2.4 (G2.2.4) EQUIPMENT CONTROL: (Multi-unit license) Ability to explain the variations in control room layouts, systems, instrumentation, and/or procedural actions between units at a facility (CFR: 41.6 / 41.7 / 41.10 / 45.1 / 45.13) 86 3.6 66 G2.2.22 (G2.2.22) EQUIPMENT CONTROL: Knowledge of limiting conditions for operation and safety limits (CFR: 41.5 / 43.2 /
45.2) 87 4
67 G2.2.5 (G2.2.5) EQUIPMENT CONTROL: Knowledge of the process for making design or operating changes to the facility, such as 10 CFR 50.59, Changes, Test and Experiments, screening and evaluation processes, administrative processes for temporary modifications, disabling annunciators, or installation of temporary equipment. (CFR: 41.10 / 43.3 / 45.13) 88 3.6 96 G2.2.14 (G2.2.14) EQUIPMENT CONTROL: Knowledge of the process for controlling equipment configuration or status (CFR: 41.10 / 43.3 / 45.13) 89 4.3 97 Subtotal N/A 2
N/A 2
- 3.
Radiation Control G2.3.5 (G2.3.5) RADIATION CONTROL: Ability to use RMSs, such as fixed radiation monitors and alarms or personnel monitoring equipment (CFR: 41.11 / 41.12 / 43.4 / 45.9) 90 2.9 68 G2.3.6 (G2.3.6) RADIATION CONTROL: Ability to approve liquid or gaseous release permits (CFR: 41.13 / 43.4 / 45.10) 91 3.8 98 Subtotal N/A 1
N/A 1
- 4.
Emergency Procedures /
Plan G2.4.34 (G2.4.34) EMERGENCY PROCEDURES/PLAN: Knowledge of RO responsibilities outside the main control room during an emergency (CFR: 41.10 / 43.5 / 45.13) 92 4.2 69 G2.4.30 (G2.4.30) EMERGENCY PROCEDURES/PLAN: Knowledge of events related to system operation/status that might be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10 / 43.5 / 45.11) 93 4.1 99 G2.4.52 (G2.4.52) EMERGENCY PROCEDURES/PLAN: Knowledge of the lines of authority during implementation of the emergency plan, emergency plan implementation procedures, emergency operating procedures, or severe accident guidelines (CFR: 41.10 / 45.13) 94 4.0 100 Subtotal N/A 1
N/A 2
Tier 3 Point Total N/A 6
N/A 7
Form 4.1-COMMON Common Examination Outline ES-4.1-COMMON COMMON Examination Outline (Byron)
Facility:
Byron Date of Exam:
10/16/2023 Theory (Tier 4) (RO)
Category K/A #
Topic RO Item #
IR Q#
Reactor Theory 192006 (192006K1.04) FISSION PRODUCT POISONS (CFR: 41.1):
Describe the removal of xenon-135 95 2.8 70 192007 (192007K1.04) FUEL DEPLETION AND BURNABLE POISONS (CFR: 41.1): Describe how and why boron concentration changes over core life 96 3.4 71 192008 (192008K1.01) REACTOR OPERATIONAL PHYSICS (CFR:
41.1): (STARTUP AND APPROACH TO CRITICALITY) List parameters that should be monitored and controlled during the approach to criticality 97 3.5 72 Subtotal N/A 3
Thermodynamics 193003 (193003K1.16) STEAM (CFR: 41.14): Define the following term: --
subcooled and compressed liquids 98 2.7 73 193004 (193004K1.15) THERMODYNAMIC PROCESS (CFR: 41.14):
(THROTTLING AND THE THROTTLING PROCESS) Determine the exit conditions for a throttling process based on the use of steam and/or water 99 2.8 74 193009 (193009K1.07) CORE THERMAL LIMITS (CFR: 41.14): Describe factors that affect peaking and hot channel factors 100 3.3 75 Subtotal N/A 3
Tier 4 Point Total N/A 6