ML23200A236

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Form 4.1-BWR Combined Written Outline Final
ML23200A236
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 06/28/2023
From:
NRC/RGN-III/DORS/OB
To:
Detroit Edison, Co
Bryan Bergeon
Shared Package
ML22007A059 List:
References
Download: ML23200A236 (1)
v • d • e


Text

Form ES-4.1-BWR Boiling-Water Reactor Examination Outline ES 4.1 Page 1 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 Facility: Fermi Power Plant, Unit 2 Date of Exam: June 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 N/A 4

4 N/A 3

20 3

4 7

2 1

1 1

1 1

1 6

1 2

3 Tier Totals 4

4 4

5 5

4 26 4

6 10

2.

Plant Systems 1

2 2

3 2

3 2

2 2

3 2

3 26 3

2 5

2 1

2 1

1 1

1 1

1 0

1 1

11 0

1 2

3 Tier Totals 3

4 4

3 4

3 3

3 3

3 4

37 4

4 8

3.

Generic Knowledge and Abilities Categories CO EC RC EM CO EC RC EM 2

2 1

1 6

2 2

1 2

7

4.

Theory Reactor Theory Thermodynamics 3

3 6

Form 4.1-BWR BWR Examination Outline ES 4.1 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)

E/APE # / Name K1 K2 K3 A1 A2 G K/A Topic(s)

IR Page 2 295001 (APE 1) Partial or Complete Loss of Forced Core Flow Circulation X

(295001AA2.09) Ability to determine or interpret the following as they apply to (APE

1) PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:

(CFR: 41.10 / 43.5 / 45.13) Reactor pressure 3.8 1

295001 (APE 1) Partial or Complete Loss of Forced Core Flow Circulation X

(295001) (APE 1) PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION (G2.4.49) CONDUCT OF OPERATIONS Ability to perform without reference to procedures those actions that require immediate operation of system components and controls (CFR: 41.10 / 43.2

/ 45.6) 4.4 76 295003 (APE 3) Partial or Complete Loss of AC Power X

(295003AK3.01) 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 / 41.10 / 45.6 / 45.13) Manual and automatic bus transfer 3.7 2

295003 (APE 3) Partial or Complete Loss of AC Power X

(295003AA2.01) Ability to determine or interpret the following as they apply to (APE

3) PARTIAL OR COMPLETE LOSS OF AC POWER: (CFR: 41.10 / 43.5 / 45.13) Partial or complete loss of AC power 4.1 77 295004 (APE 4) Partial or Total Loss of DC Power X

(295004AK3.01) Knowledge of the reasons for the following responses or actions as they apply to (APE 4) PARTIAL OR COMPLETE LOSS OF DC POWER: (CFR:

41.5 / 41.10 / 45.6 / 45.13) Load shedding 3.9 3

295005 (APE 5) Main Turbine Generator Trip X

(295005AA2.07) Ability to determine or interpret the following as they apply to (APE

5) MAIN TURBINE GENERATOR TRIP:

(CFR: 41.10 / 43.5 / 45.13) Reactor water level 4.4 4

295006 (APE 6) Scram X

(295006AA1.02) Ability to operate or monitor the following as they apply to (APE 6)

SCRAM: (CFR: 41.5 / 41.7 / 45.5 to 45.8)

Reactor water level control system 4.2 5

295016 (APE 16) Control Room Abandonment X

(295016AA1.15) Ability to operate or monitor the following as they apply to (APE 16)

CONTROL ROOM ABANDONMENT: (CFR:

41.5 / 41.7 / 45.5 to 45.8) Emergency generators 3.8 6

295018 (APE 18) Partial or Complete Loss of CCW X

(295018AK2.06) Knowledge of the relationship between the (APE 18) PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER (CCW) and the following systems or components: (CFR: 41.8 / 41.10 /

45.3) Fuel pool cooling and cleanup system 3.8 7

295019 (APE 19) Partial or Complete Loss of Instrument Air X

(295019AK3.01) Knowledge of the reasons for the following responses or actions as they apply to (APE 19) PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR:

(CFR: 41.5 / 41.10 / 45.6 / 45.13) Alignment of backup air systems 3.6 8

295021 (APE 21) Loss of Shutdown Cooling X

(295021AA1.07) Ability to operate or monitor the following as they apply to (APE 21)

LOSS OF SHUTDOWN COOLING: (CFR:

41.5 / 41.7 / 45.5 to 45.8) Fuel pool cooling and cleanup 3.4 9

295023 (APE 23) Refueling Accidents X

(295023AK2.07) Knowledge of the relationship between the (APE 23)

REFUELING ACCIDENTS / 8 and the following systems or components: (CFR:

41.8 / 41.10 / 45.3) SGTS/FRVS 3.8 10

Form 4.1-BWR BWR Examination Outline ES 4.1 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)

E/APE # / Name K1 K2 K3 A1 A2 G K/A Topic(s)

IR Page 3 295023 (APE 23) Refueling Accidents X

(295023) (APE 23) REFUELING ACCIDENTS (G2.1.23) CONDUCT OF OPERATIONS Ability to perform general or normal operating procedures during any plant condition (CFR: 41.10 / 43.5 / 45.2 /

45.6) 4.4 78 295024 (EPE 1) High Drywell Pressure X

(295024) (EPE 1) HIGH DRYWELL PRESSURE (G2.1.19) CONDUCT OF OPERATIONS Ability to use available indications to evaluate system or component status (CFR: 41.10 / 45.12) 3.9 11 295025 (EPE 2) High Reactor Pressure X

(295025) (EPE 2) HIGH REACTOR PRESSURE (G2.4.3) EMERGENCY PROCEDURES/PLAN Ability to identify post-accident instrumentation (CFR: 41.6 /

45.4) 3.7 12 295025 (EPE 2) High Reactor Pressure X

(295025EA2.03) Ability to determine or interpret the following as they apply to (EPE

2) HIGH REACTOR PRESSURE: (CFR:

41.10 / 43.5 / 45.13) Suppression pool temperature 3.5 79 295026 (EPE 3) Suppression Pool High Water Temperature X

(295026EK1.03) 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: 41.5 / 41.7 / 45.7 /

45.8) Primary containment integrity 3.8 13 295026 (EPE 3) Suppression Pool High Water Temperature X

(295026EA2.01) Ability to determine or interpret the following as they apply to (EPE

3) SUPPRESSION POOL HIGH WATER TEMPERATURE: (CFR: 41.10 / 43.5 /

45.13) Suppression pool water temperature 4

80 295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only)

X (295028EA1.05) Ability to operate or monitor the following as they apply to (EPE 5) HIGH DRYWELL TEMPERATURE (MARK I AND MARK II ONLY): (CFR: 41.5 / 41.7 / 45.5 to 45.8) Safety relief valves 3.8 14 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only)

X (295028) (EPE 5) HIGH DRYWELL TEMPERATURE (MARK I AND MARK II ONLY) (G2.4.18) EMERGENCY PROCEDURES/PLAN Knowledge of the specific bases for emergency and abnormal procedures (CFR: 41.10 / 43.1 / 45.3) 4.0 81 295030 (EPE 7) Low Suppression Pool Water Level X

(295030EA2.03) 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) Reactor pressure 4.1 15 295031 (EPE 8) Reactor Low Water Level X

(295031) (EPE 8) REACTOR LOW WATER LEVEL (G2.4.12) EMERGENCY PROCEDURES/PLAN Knowledge of operating crew responsibilities during emergency and abnormal operations (CFR:

41.10 / 45.12) 4.0 16 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown X

(295037EA2.09) Ability to determine or interpret the following as they apply to (EPE

14) SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: (CFR: 41.10

/ 43.5 / 45.13) SCRAM air header pressure 3.5 17

Form 4.1-BWR BWR Examination Outline ES 4.1 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)

E/APE # / Name K1 K2 K3 A1 A2 G K/A Topic(s)

IR Page 4 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown X

(295037) (EPE 14) SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN (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 82 295038 (EPE 15) High Offsite Radioactivity Release Rate X

(295038EK1.06) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (EPE 15) HIGH OFFSITE RADIOACTIVITY RELEASE RATE: (CFR: 41.5 / 41.7 / 45.7 / 45.8)

Filtered vs. nonfiltered release 3.8 18 600000 (APE 24) Plant Fire On Site X

(600000AK2.09) Knowledge of the relationship between the (APE 24) PLANT FIRE ON SITE and the following systems or components: (CFR: 41.8 / 41.10 / 45.3)

Installed fire suppression systems 3.5 19 700000 (APE 25) Generator Voltage and Electric Grid Disturbances X

(700000AK1.05) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (APE 25) GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: (CFR: 41.5 / 41.7 / 45.7 /

45.8) Voltage disturbance 3.5 20 K/A Category Totals:

3 3

3 4

4/3 3/4 Group Point Total:

20/7

Form 4.1-BWR BWR Examination Outline ES 4.1 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)

E/APE # / Name K1 K2 K3 A1 A2 G K/A Topic(s)

IR Page 5 295002 (APE 2) Loss of Main Condenser Vacuum 295007 (APE 7) High Reactor Pressure 295008 (APE 8) High Reactor Water Level X

(295008) (APE 8) HIGH REACTOR WATER LEVEL (G2.1.9) CONDUCT OF OPERATIONS Ability to direct licensed personnel activities inside the control room (CFR: 43.1 / 45.5 / 45.12 / 45.13) 4.5 83 295009 (APE 9) Low Reactor Water Level X

(295009AA2.01) Ability to determine or interpret the following as they apply to (APE

9) LOW REACTOR WATER LEVEL: (CFR:

41.10 / 43.5 / 45.13) Reactor water level 4.1 21 295010 (APE 10) High Drywell Pressure 295011 (APE 11) High Containment Temperature (Mark III Containment only) 295012 (APE 12) High Drywell Temperature 295013 (APE 13) High Suppression Pool Water Temperature X

(295013) (APE 13) HIGH SUPPRESSION POOL TEMPERATURE (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 22 295014 (APE 14) Inadvertent Reactivity Addition 295015 (APE 15**) Incomplete Scram 295017 (APE 17) High Offsite Release Rate X

(295017AA2.06) Ability to determine or interpret the following as they apply to (APE

17) ABNORMAL OFFSITE RELEASE RATE: (CFR: 41.10 / 43.5 / 45.13)

Emergency plan implementation 4.3 84 295020 (APE 20) Inadvertent Containment Isolation 295022 (APE 22) Loss of Control Rod Drive Pumps X

(295022AK2.01) Knowledge of the relationship between the (APE 22) LOSS OF CONTROL ROD DRIVE PUMPS and the following systems or components:

(CFR: 41.8 / 41.10 / 45.3) Recirculation system 3.1 23 295029 (EPE 6) High Suppression Pool Water Level X

(295029EK1.02) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (EPE 6) HIGH SUPPRESSION POOL WATER LEVEL:

(CFR: 41.5 / 41.7 / 45.7 / 45.8) Venting the suppression pool (Mark I containment) 4.0 24 295032 (EPE 9) High Secondary Containment Area Temperature 295033 (EPE 10) High Secondary Containment Area Radiation Levels X

(295033EA1.01) Ability to operate or monitor the following as they apply to (EPE

10) HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS: (CFR: 41.5 /

41.7 / 45.5 to 45.8) Area radiation monitoring system 3.8 25 295034 (EPE 11) Secondary Containment Ventilation High Radiation

Form 4.1-BWR BWR Examination Outline ES 4.1 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)

E/APE # / Name K1 K2 K3 A1 A2 G K/A Topic(s)

IR Page 6 295035 (EPE 12) Secondary Containment High Differential Pressure X

(295035EK3.02) Knowledge of the reasons for the following responses or actions as they apply to (EPE 12) SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: (CFR: 41.5 / 45.6) Secondary containment ventilation alignment 3.7 26 295036 (EPE 13) Secondary Containment High Sump/Area Water Level X

(295036) (EPE 13) SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL (G2.4.5) EMERGENCY PROCEDURES/PLAN Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions (CFR: 41.10 / 43.5 /

45.13) 4.3 85 500000 (EPE 16) High Containment Hydrogen Concentration K/A Category Point Totals:

1 1

1 1 1/1 1/2 Group Point Total:

6/3

Form 4.1-BWR BWR Examination Outline ES 4.1 Plant SystemsTier 2/Group 1 (RO/SRO)

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

IR Page 7 203000 (SF2, SF4 RHR/LPCI)

RHR/LPCI: Injection Mode X

(203000A4.06) Ability to manually operate and/or monitor the (SF2, SF4 RHR/LPCI)

RHR/LPCI: INJECTION MODE in the control room: (CFR: 41.7 / 45.5 to 45.8) System reset following automatic initiation 3.6 27 203000 (SF2, SF4 RHR/LPCI)

RHR/LPCI: Injection Mode X

(203000A2.18) Ability to (a) predict the impacts of the following on the (SF2, SF4 RHR/LPCI) RHR/LPCI: INJECTION MODE and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations:

(CFR: 41.5 / 45.6) High suppression pool temperature 3.4 86 205000 (SF4 SCS) Shutdown Cooling X

(205000K2.01) (SF4 SCS) SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) Knowledge of electrical power supplies to the following: (CFR: 41.7)

Pump motors 3.6 28 206000 (SF2, SF4 HPCI) High-Pressure Coolant Injection X

(206000K3.04) Knowledge of the effect that a loss or malfunction of the (SF2, SF4 HPCI)

HIGH PRESSURE COOLANT INJECTION SYSTEM will have on the following systems or system parameters: (CFR: 41.7 / 45.4)

Reactor power 3.6 29 207000 (SF4 IC) Isolation (Emergency) Condenser 209001 (SF2, SF4 LPCS) Low-Pressure Core Spray X

(209001K5.07) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF2, SF4 LPCS) LOW PRESSURE CORE SPRAY SYSTEM: (CFR: 41.5 / 45.3)

Adequate core cooling 4.5 30 209002 (SF2, SF4 HPCS) High-Pressure Core Spray 211000 (SF1 SLCS) Standby Liquid Control X

(211000A1.01) Ability to predict and/or monitor changes in parameters associated with operation of the (SF1 SLCS) STANDBY LIQUID CONTROL SYSTEM including: (CFR:

41.5 / 45.5) Tank level 3.8 31 212000 (SF7 RPS) Reactor Protection X

(212000A3.09) Ability to monitor automatic operation of the (SF7 RPS) REACTOR PROTECTION SYSTEM including: (CFR:

41.7 / 45.7) System actuation 4.3 32 212000 (SF7 RPS) Reactor Protection X

(212000K3.03) Knowledge of the effect that a loss or malfunction of the (SF7 RPS)

REACTOR PROTECTION SYSTEM will have on the following systems or system parameters: (CFR: 41.7 / 45.4) Nuclear instrumentation 3.7 33 215003 (SF7 IRM) Intermediate-Range Monitor X

(215003K5.02) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF7 IRM) INTERMEDIATE RANGE MONITOR SYSTEM: (CFR: 41.5 / 45.3)

Gamma discrimination 2.6 34 215003 (SF7 IRM) Intermediate-Range Monitor X

(215003A2.02) 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 / 45.6) IRM inoperable condition 3.7 87 215004 (SF7 SRMS) Source-Range Monitor X

(215004K4.07) Knowledge of (SF7 SRMS)

SOURCE RANGE MONITOR SYSTEM design features and/or interlocks that provide for the following: (CFR: 41.7) SRMS channel bypass 3.4 35

Form 4.1-BWR BWR Examination Outline ES 4.1 Plant SystemsTier 2/Group 1 (RO/SRO)

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

IR Page 8 215004 (SF7 SRMS) Source-Range Monitor X

(215004A2.04) Ability to (a) predict the impacts of the following on the (SF7 SRMS)

SOURCE 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 / 45.6) Upscale and downscale trips 3.7 88 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor X

(215005) (SF7 PRMS) AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR (G2.1.37) CONDUCT OF OPERATIONS Knowledge of procedures, guidelines, or limitations associated with reactivity management (CFR: 41.1 / 41.5 /

41.10 / 43.6 / 45.6) 4.3 36 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling X

(217000K1.07) Knowledge of the physical connections and/or cause and effect relationships between the (SF2, SF4 RCIC)

REACTOR CORE ISOLATION COOLING SYSTEM and the following systems: (CFR:

41.2 to 41.9 / 45.7 to 45.8) Leak detection 3.3 37 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling X

(217000K5.10) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF2, SF4 RCIC) REACTOR CORE ISOLATION COOLING SYSTEM : (CFR: 41.5

/ 45.3) Reactor level control 4.2 38 218000 (SF3 ADS) Automatic Depressurization X

(218000K4.02) Knowledge of (SF3 ADS)

AUTOMATIC DEPRESSURIZATION SYSTEM design features and/or interlocks that provide for the following: (CFR: 41.7) Allow manual initiation of ADS logic 4.1 39 223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff X

(223002A3.01) Ability to monitor automatic operation of the (SF5 PCIS) PRIMARY CONTAINMENT ISOLATION SYSTEM /

NUCLEAR STEAM SUPPLY SHUTOFF including: (CFR: 41.7 / 45.7) System indicating lights and alarms 4.0 40 239002 (SF3 SRV) Safety Relief Valves X

(239002K6.03) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF3 SRV) SAFETY RELIEF VALVES:

(CFR: 41.7 / 45.7) AC power 3.2 41 259002 (SF2 RWLCS) Reactor Water Level Control X

(259002A3.06) Ability to monitor automatic operation of the (SF2 RWLCS) REACTOR WATER LEVEL CONTROL SYSTEM including: (CFR: 41.7 / 45.7) Reactor water level setpoint setdown following a reactor SCRAM 3.6 42 259002 (SF2 RWLCS) Reactor Water Level Control X

(259002) (SF2 RWLCS) REACTOR WATER LEVEL CONTROL SYSTEM (G2.1.27)

CONDUCT OF OPERATIONS Knowledge of system purpose and/or function (CFR: 41.7) 3.9 43 261000 (SF9 SGTS) Standby Gas Treatment X

(261000K3.04) 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 / 45.4) High-pressure coolant injection system (BWR 3, 4) 2.8 44 262001 (SF6 AC) AC Electrical Distribution X

(262001A1.04) Ability to predict and/or monitor changes in parameters associated with operation of the (SF6 AC) AC ELECTRICAL DISTRIBUTION including: (CFR: 41.5 / 45.5)

Load currents 3.2 45

Form 4.1-BWR BWR Examination Outline ES 4.1 Plant SystemsTier 2/Group 1 (RO/SRO)

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

IR Page 9 262001 (SF6 AC) AC Electrical Distribution X

(262001) (SF6 AC) AC ELECTRICAL DISTRIBUTION (G2.2.17) EQUIPMENT CONTROL Knowledge of the process for managing maintenance activities during power operations, such as risk assessment, work prioritization, and coordination with the transmission system operator (CFR: 41.10 /

43.5 / 45.13) 3.8 89 262002 (SF6 UPS)

Uninterruptable Power Supply (AC/DC)

X (262002K6.03) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF6 UPS) UNINTERRUPTABLE POWER SUPPLY (AC/DC): (CFR: 41.7 / 45.7) Static switch/inverter 3.4 46 263000 (SF6 DC) DC Electrical Distribution X

(263000A2.02) Ability to (a) predict the impacts of the following on the (SF6 DC) DC ELECTRICAL DISTRIBUTION 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 ventilation during charging 2.9 47 264000 (SF6 EGE) Emergency Generators (Diesel/Jet)

X (264000A4.04) Ability to manually operate and/or monitor the (SF6 EGE) EMERGENCY GENERATORS (DIESEL/JET) in the control room: (CFR: 41.7 / 45.5 to 45.8) 4.1 48 300000 (SF8 IA) Instrument Air X

(300000A2.01) Ability to (a) predict the impacts of the following on the (SF8 IA)

INSTRUMENT AIR 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) Air dryer and filter malfunctions 3.8 49 300000 (SF8 IA) Instrument Air X

(300000) (SF8 IA) INSTRUMENT AIR SYSTEM (G2.4.6) EMERGENCY PROCEDURES/PLAN Knowledge of emergency and abnormal operating procedures major action categories (CFR:

41.10 / 43.5 / 45.13) 4.7 90 400000 (SF8 CCW) Component Cooling Water X

(400000K1.09) Knowledge of the physical connections and/or cause and effect relationships between the (SF8 CCS)

COMPONENT COOLING WATER SYSTEM and the following systems: (CFR: 41.2 to 41.9

/ 45.7 to 45.8) Recirculation flow control system 2.8 50 400000 (SF8 CCW) Component Cooling Water Component: (291004) Pumps (Centrifugal)

X 400000 (SF8 CCW) (291004K1.03) PUMPS (CENTRIFUGAL) Consequences of air/steam binding (CFR: 41.3) 2.9 51 510000 (SF4 SWS*) Service Water X

(510000K2.02) (SF4 SWS*) SERVICE WATER SYSTEM Knowledge of electrical power supplies to the following: (CFR: 41.7)

Service water system valves (Class 1E) 3.4 52 K/A Category Point Totals:

2 2

3 2

3 2

2 2/3 3 2 3/2 Group Point Total:

26/5

Form 4.1-BWR BWR Examination Outline ES 4.1 Plant SystemsTier 2/Group 2 (RO/SRO)

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

IR Page 10 201001 (SF1 CRDH) CRD Hydraulic X

(201001K5.03) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF1 CRDH) CRD HYDRAULIC SYSTEM:

(CFR: 41.5 / 45.3) Pressure indication 3.3 53 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 X

201006K6.02 Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the Rod Worth Minimizer System: (CFR: 41.7 /

45.7) Reactor water level control input 3.0 54 202001 (SF1, SF4 RS) Recirculation 202002 (SF1 RSCTL) Recirculation Flow Control 204000 (SF2 RWCU) Reactor Water Cleanup X

(204000K2.01) (SF2 RWCU) REACTOR WATER CLEANUP SYSTEM Knowledge of electrical power supplies to the following:

(CFR: 41.7) Pumps 2.9 55 214000 (SF7 RPIS) Rod Position Information X

(214000) (SF7 RPIS) ROD POSITION INFORMATION SYSTEM (G2.1.1)

CONDUCT OF OPERATIONS Knowledge of conduct of operations requirements (CFR:

41.10 / 43.1 / 45.13) 4.2 91 215001 (SF7 TIP) Traversing In-Core Probe 215002 (SF7 RBMS) Rod Block Monitor X

(215002A4.03) Ability to manually operate and/or monitor the (SF7 RBMS) ROD BLOCK MONITOR SYSTEM in the control room:

(CFR: 41.7 / 45.5 to 45.8) Trip/channel bypasses 3.2 56 216000 (SF7 NBI) Nuclear Boiler Instrumentation 219000 (SF5 RHR SPC) RHR/LPCI:

Torus/Suppression Pool Cooling Mode X

(219000) (SF5 RHR SPC) RHR/LPCI:

TORUS/SUPPRESSION POOL COOLING MODE (G2.2.12) EQUIPMENT CONTROL Knowledge of surveillance procedures (CFR:

41.10 / 43.2 / 45.13) 4.1 92 223001 (SF5 PCS) Primary Containment and Auxiliaries X

(223001) (SF5 PCS) PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES (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) 4.2 57 226001 (SF5 RHR CSS) RHR/LPCI:

Containment Spray Mode X

(226001K2.03) (SF5 RHR CSS) RHR/LPCI:

CONTAINMENT SPRAY MODE SYSTEM MODE Knowledge of electrical power supplies to the following: (CFR: 41.7) Valve control logic 3.7 58 230000 (SF5 RHR SPS) RHR/LPCI:

Torus/Suppression Pool Spray Mode 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup

Form 4.1-BWR BWR Examination Outline ES 4.1 Plant SystemsTier 2/Group 2 (RO/SRO)

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

IR Page 11 234000 (SF8 FH) Fuel Handling Equipment 239001 (SF3, SF4 MRSS) Main and Reheat Steam X

(239001K3.06) Knowledge of the effect that a loss or malfunction of the (SF3, SF4 MRSS)

MAIN AND REHEAT STEAM SYSTEM will have on the following systems or system parameters: (CFR: 41.7 / 45.4)

Reactor/turbine pressure regulating system 3.7 59 239003 (SF9 MSIVLC) Main Steam Isolation Valve Leakage Control 241000 (SF3 RTPRS)

Reactor/Turbine Pressure Regulating 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary X

(245000A2.01) Ability to (a) predict the impacts of the following on the Main Turbine Generator and Auxiliary Systems 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) Turbine Trip 3.9 93 256000 (SF2 CDS) Condensate X

(256000K1.07) Knowledge of the physical connections and/or cause and effect relationships between the (SF2 CDS)

CONDENSATE SYSTEM and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)

SJAE condenser system 3.0 60 259001 (SF2 FWS) Feedwater 268000 (SF9 RW) Radwaste 271000 (SF9 OG) Offgas 272000 (SF7, SF9 RMS) Radiation Monitoring 286000 (SF8 FPS) Fire Protection 288000 (SF9 PVS) Plant Ventilation 290001 (SF5 SC) Secondary Containment X

(290001A1.11) Ability to predict and/or monitor changes in parameters associated with operation of the (SF5 SC) SECONDARY CONTAINMENT including: (CFR: 41.5 / 45.5)

System indicating lights and alarms 3.5 61 290002 (SF4 RVI) Reactor Vessel Internals X

(290002K4.02) Knowledge of (SF4 RVI)

REACTOR VESSEL INTERNALS design features and/or interlocks that provide for the following: (CFR: 41.7) Flow paths within the reactor vessel 3.9 62 290003 (SF9 CRV) Control Room Ventilation X

(290003A2.05) Ability to (a) predict the impacts of the following on the (SF9 CRV)

CONTROL ROOM VENTILATION 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 chillers 3.2 63 K/A Category Point Totals:

1 2

1 1

1 1

1 1/1 0 1 1/2 Group Point Total:

11/3

Form ES-4.1-COMMON Common Examination Outline ES 4.1 Page 12 Facility: Fermi Power Plant, Unit 2 Date of Exam: June 2023 Generic Knowledge and AbilitiesTier 3 (RO/SRO)

Category K/A #

Topic RO SRO-Only IR IR

1.

Conduct of Operations 2.1.14 (G2.1.14) CONDUCT OF OPERATIONS Knowledge of criteria or conditions that require plantwide announcements, such as pump starts, reactor trips, and mode changes (CFR:

41.10 / 43.5 / 45.12) 3.1 64 2.1.25 (G2.1.25) CONDUCT OF OPERATIONS Ability to interpret reference materials, such as graphs, curves, and tables (reference potential) (CFR: 41.10 / 43.5 / 45.12) 4.2 94 2.1.30 (G2.1.30) CONDUCT OF OPERATIONS Ability to locate and operate components, including local controls (CFR: 41.7

/ 45.7) 4.4 65 2.1.32 (G2.1.32) CONDUCT OF OPERATIONS Ability to explain and apply system precautions, limitations, notes, or cautions (CFR: 41.10 / 43.2 / 45.12) 4.0 95 Subtotal N/A 2

N/A 2

2.

Equipment Control 2.2.22 (G2.2.22) EQUIPMENT CONTROL Knowledge of limiting conditions for operation and safety limits (CFR: 41.5 / 43.2 /

45.2) 4.0 66 2.2.36 (G2.2.36) EQUIPMENT CONTROL Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operation (CFR: 41.10 / 43.2 / 45.13) 4.2 96 2.2.38 (G2.2.38) EQUIPMENT CONTROL Knowledge of conditions and limitations in the facility license (CFR: 41.7 / 41.10 / 43.1

/ 45.13) 4.5 97 2.2.39 (G2.2.39) EQUIPMENT CONTROL Knowledge of less than or equal to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> technical specification action statements (This K/A does not include action statements of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or less that follow the expiration of a completion time for a technical specification condition for which an action statement has already been entered.) (CFR: 41.7 / 41.10 /

43.2 / 45.13) 3.9 67 Subtotal N/A 2

N/A 2

3.

Radiation Control 2.3.5 (G2.3.5) RADIATION CONTROL Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms or personnel monitoring equipment (CFR: 41.11 /

41.12 / 43.4 / 45.9) 2.9 98 2.3.12 (G2.3.12) RADIATION CONTROL Knowledge of radiological safety principles and 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, or alignment of filters (CFR: 41.12 / 43.4 / 45.9 / 45.10) 3.2 68 Subtotal N/A 1

N/A 1

4.

Emergency Procedures/Plan 2.4.4 (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) 4.5 69 2.4.14 (G2.4.14) EMERGENCY PROCEDURES/PLAN Knowledge of general guidelines for emergency and abnormal operating procedures usage (CFR: 41.10 / 43.1 / 45.13) 4.5 99 2.4.28 (G2.4.28) EMERGENCY PROCEDURES/PLAN Knowledge of procedures relating to a security event (ensure that the test item includes no safeguards information) (CFR: 41.10 /

43.5 / 45.13) 4.1 100 Subtotal N/A 1

N/A 2

Tier 3 Point Total 6

7

Form ES-4.1-COMMON Common Examination Outline ES 4.1 Page 13 TheoryTier 4 (RO)

Category K/A #

Topic RO IR Reactor Theory 292001 K1.02 (292001K1.02) NEUTRONS (CFR: 41.1) Define prompt and delayed neutrons 3.1 70 292006 K1.01 (292006K1.01) FISSION PRODUCT POISONS (CFR: 41.1)

Define fission product poison 2.8 71 292007 K1.03 (292007K1.03) FUEL DEPLETION AND BURNABLE POISONS (CFR: 41.1) Given a curve of K-effective versus core age, state the reasons for maximum, minimum, and inflection points 2.7 72 Subtotal N/A 3

Thermodynamics 293008 K1.25 (293008K1.25) THERMAL HYDRAULICS (CFR: 41.14)

(RECIRCULATION SYSTEM) Explain the reason for forced core recirculation 3.2 73 293009 K1.33 (293009K1.33) CORE THERMAL LIMITS (CFR: 41.14) (PELLET-CLAD INTERACTION) Describe the purpose of the pellet to clad gap 2.8 74 293010 K1.05 (293010K1.05) BRITTLE FRACTURE AND VESSEL THERMAL STRESS (CFR: 41.14) State the effect of fast neutron irradiation on reactor vessel metals 2.8 75 Subtotal N/A 3

Tier 4 Point Total 6

Form ES-4.1-1 Record of Rejected Knowledge and Abilities ES 4.1 Page 14 Facility:

Date of Exam:

Refer to Examination Standard (ES)-4.2, Developing Written Examinations, Section B.3, for deviations from the approved written examination outline.

Tier/Group Randomly Selected K/A Reason for Rejection

Form 4.1-1 Record of Rejected Knowledge and Abilities Refer to Examination Standard (ES)-4.2, Developing Written Examinations, Section B.3, for deviations from the approved written examination outline.

Tier/Group Randomly Selected K/A Reason for Rejection Q54 T2/G2 201005K6.04 Replaced with:

201006K6.02 201005K6.04 Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF1, SF7 RCIS) ROD CONTROL AND INFORMATION SYSTEM:

(CFR: 41.7 / 45.7) Intermediate range monitor system.

Fermi 2 does not have RCIS. Replaced with:

201006K6.02 Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the Rod Worth Minimizer System: (CFR: 41.7 / 45.7) Reactor water level control input.

Q82 T1/G1 295037 G2.2.6 replaced with G2.4.16.

(295037) (EPE 14) SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN (G2.2.6) EQUIPMENT CONTROL Knowledge of the process for making changes to procedures (CFR: 41.10 / 43.3 / 45.13) 295037 is kept as the EPE. For G2.2.6, SRO involvement with the EOP revision process is sparse and limited to performing V&V (Verification & Validation) in the Simulator. Any SRO that performs higher-level evaluations of EOP changes (like 50.59 screening, for example) have special qualifications at Fermi. Only 2 individuals currently have that qualification, so it is not general SRO knowledge.

Replaced generic K/A with 2.4.16, 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 Q93 T2/G2 510001A2.02 Replaced with 245000A2.01 (510001A2.02) Ability to (a) predict the impacts of the following on the (SF8 CWS*) CIRCULATING 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)

Abnormal valve positions.

Nothing could be developed for this system that would satisfy the requirements to be SRO Only. For example, the Circulating Water system is limited in that it does not have related Technical Specifications, nor does it have AOPs that contain SRO-Only knowledge. Operation of the CW system is fairly generic and most questions that we attempted to develop could be answered by an RO. Replaced with:

(245001A2.01) Ability to (a) predict the impacts of the following on the Main Turbine Generator and Auxiliary Systems 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) Turbine Trip.

Q76 T1/G1 295001 G2.1.36 Replaced with 295001 G2.4.49 (295001) (APE 1) PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION (G2.1.36) CONDUCT OF OPERATIONS Knowledge of procedures and limitations involved in core alterations (CFR: 41.10 / 43.6 / 45.7)

Attempted several versions with no success. Expended excessive time and resources attempting a question at this K/A. Replaced with:

(295001) (APE 1) PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION (G2.4.49) CONDUCT OF OPERATIONS Ability to perform without reference to procedures those actions that require immediate operation of system components and controls (CFR: 41.10 / 43.2 / 45.6)

Q26 T1/G2 295035 EK3.01 Replaced with 295035 EK3.02 (295035EK3.01) Knowledge of the reasons for the following responses or actions as they apply to (EPE 12) SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: (CFR: 41.5 /

45.6) Blow-out panel operation Could not write a valid Tier 1 question for this EPE/EK combination.

No procedure references could be located where the operator is asked to verify operation of the blowout panels. Also, the blowout panels are entirely automatic, requiring no operator action or response. Replaced with:

(295035EK3.02) Knowledge of the reasons for the following responses or actions as they apply to (EPE 12) SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: (CFR: 41.5 /

45.6) Secondary containment ventilation alignment.

Q16 T1/G1 295031 G2.4.29 Replaced with 295031 G2.4.12 (295031) (EPE 8) REACTOR LOW WATER LEVEL (G2.4.29)

EMERGENCY PROCEDURES/PLAN Knowledge of the emergency plan implementing procedures (CFR: 41.10 / 43.5 /

45.11)

Could not write a question that would be accepted as RO level of knowledge and be acceptable to the NRC. Replaced with:

(295031) (EPE 8) REACTOR LOW WATER LEVEL (G2.4.12)

EMERGENCY PROCEDURES/PLAN Knowledge of operating crew responsibilities during emergency and abnormal operations (CFR:

41.10 / 45.12)

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